Sample records for reactors licensing actions

  1. 78 FR 73898 - Operator Licensing Examination Standards for Power Reactors

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-09

    ... Reactors AGENCY: Nuclear Regulatory Commission. ACTION: Draft NUREG; request for comment. SUMMARY: The U.S..., Revision 10, ``Operator Licensing Examination Standards for Power Reactors.'' DATES: Submit comments [email protected] . Both of the Office of New Reactors; or Timothy Kolb, Office of Nuclear Reactor Regulation, U...

  2. 77 FR 38742 - Non-Power Reactor License Renewal

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-06-29

    ...-0087] RIN 3150-AI96 Non-Power Reactor License Renewal AGENCY: Nuclear Regulatory Commission. ACTION... reactors. This contemplated rulemaking would also make conforming changes to address technical issues in existing non-power reactor regulations. The NRC is seeking input from the public, licensees, certificate...

  3. 76 FR 78173 - Options for Developing the Regulatory Basis for Streamlining Non-Power Reactor License Renewal...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-16

    ... Emergency Preparedness AGENCY: Nuclear Regulatory Commission. ACTION: Notice of public meeting. SUMMARY: The... non-power reactor license renewal and non-power reactor emergency preparedness. This meeting is a... potential enhancements to emergency preparedness requirements. This meeting is open to the public. DATES...

  4. 10 CFR 2.403 - Notice of proposed action on applications for operating licenses pursuant to appendix N of 10 CFR...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... operating licenses for nuclear power reactors, if the Commission has not found that a hearing is in the public interest, the Commission, the Director, Office of New Reactors or Director, Office of Nuclear... licenses pursuant to appendix N of 10 CFR part 50. 2.403 Section 2.403 Energy NUCLEAR REGULATORY COMMISSION...

  5. 10 CFR 2.403 - Notice of proposed action on applications for operating licenses pursuant to appendix N of 10 CFR...

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... this chapter for operating licenses for nuclear power reactors, if the Commission has not found that a..., Office of Nuclear Reactor Regulation, as appropriate will, prior to acting thereon, cause to be published... licenses pursuant to appendix N of 10 CFR part 50. 2.403 Section 2.403 Energy NUCLEAR REGULATORY COMMISSION...

  6. 10 CFR 2.403 - Notice of proposed action on applications for operating licenses pursuant to appendix N of 10 CFR...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... this chapter for operating licenses for nuclear power reactors, if the Commission has not found that a..., Office of Nuclear Reactor Regulation, as appropriate will, prior to acting thereon, cause to be published... licenses pursuant to appendix N of 10 CFR part 50. 2.403 Section 2.403 Energy NUCLEAR REGULATORY COMMISSION...

  7. 10 CFR 2.403 - Notice of proposed action on applications for operating licenses pursuant to appendix N of 10 CFR...

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... operating licenses for nuclear power reactors, if the Commission has not found that a hearing is in the public interest, the Commission, the Director, Office of New Reactors or Director, Office of Nuclear... licenses pursuant to appendix N of 10 CFR part 50. 2.403 Section 2.403 Energy NUCLEAR REGULATORY COMMISSION...

  8. 10 CFR 2.403 - Notice of proposed action on applications for operating licenses pursuant to appendix N of 10 CFR...

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... this chapter for operating licenses for nuclear power reactors, if the Commission has not found that a..., Office of Nuclear Reactor Regulation, as appropriate will, prior to acting thereon, cause to be published... licenses pursuant to appendix N of 10 CFR part 50. 2.403 Section 2.403 Energy NUCLEAR REGULATORY COMMISSION...

  9. 75 FR 61220 - Massachusetts Institute of Technology: Massachusetts Institute of Technology Research Reactor...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-10-04

    ... renewed Facility Operating License No. R-37, to be held by the Massachusetts Institute of Technology (MIT... Identification of the Proposed Action The proposed action would renew Facility Operating License No. R-37 for a... License No. R-37 to allow continued operation of the MITR for a period of twenty years at an increased...

  10. Nuclear Security: Action May Be Needed to Reassess the Security of NRC-Licensed Research Reactors. Report to the Ranking Member, Subcommittee on National Security and Foreign Affairs, Committee on Oversight and Government Reform, House of Representatives. GAO-08-403

    ERIC Educational Resources Information Center

    Aloise, Gene

    2008-01-01

    There are 37 research reactors in the United States, mostly located on college campuses. Of these, 33 reactors are licensed and regulated by the Nuclear Regulatory Commission (NRC). Four are operated by the Department of Energy (DOE) and are located at three national laboratories. Although less powerful than commercial nuclear power reactors,…

  11. 77 FR 37074 - License Amendment Request From the Alan J. Blotcky Reactor Facility

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-06-20

    ... the Alan J. Blotcky Reactor Facility AGENCY: Nuclear Regulatory Commission. ACTION: Notice of... section of this document. FOR FURTHER INFORMATION CONTACT: Theodore Smith, Project Manager, Reactor... provided the first time that a document is referenced. The Alan J. Blotcky Reactor Facility Decommissioning...

  12. 10 CFR 2.103 - Action on applications for byproduct, source, special nuclear material, facility and operator...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... nuclear material, facility and operator licenses. (a) If the Director, Office of Nuclear Reactor... repository operations area under parts 60 or 63 of this chapter, the Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Nuclear Material Safety and Safeguards, or...

  13. 75 FR 42469 - Firstenergy Nuclear Operating Company; Request for Licensing Action

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-07-21

    ... nuclear plant in Ohio, preventing the reactor from restarting until such time that the NRC determines... Commission's regulations. The request has been referred to the Director of the Office of Nuclear Reactor... of Nuclear Reactor Regulation. [FR Doc. 2010-17834 Filed 7-20-10; 8:45 am] BILLING CODE 7590-01-P ...

  14. 10 CFR 2.103 - Action on applications for byproduct, source, special nuclear material, facility and operator...

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... nuclear material, facility and operator licenses. (a) If the Director, Office of Nuclear Reactor... repository operations area under parts 60 or 63 of this chapter, the Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, Director, Office of Nuclear Material Safety and Safeguards, or...

  15. 10 CFR 51.121 - Status of NEPA actions.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... address inquiries to: (a) Utilization facilities: ATTN: Document Control Desk, Director, Office of Nuclear Reactor Regulation or Director, Office of New Reactors, as appropriate, U.S. Nuclear Regulatory Commission... NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL PROTECTION REGULATIONS FOR DOMESTIC LICENSING AND...

  16. 10 CFR 51.121 - Status of NEPA actions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... address inquiries to: (a) Utilization facilities: ATTN: Document Control Desk, Director, Office of Nuclear Reactor Regulation or Director, Office of New Reactors, as appropriate, U.S. Nuclear Regulatory Commission... NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL PROTECTION REGULATIONS FOR DOMESTIC LICENSING AND...

  17. 10 CFR 51.121 - Status of NEPA actions.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... address inquiries to: (a) Utilization facilities: ATTN: Document Control Desk, Director, Office of Nuclear Reactor Regulation or Director, Office of New Reactors, as appropriate, U.S. Nuclear Regulatory Commission... NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL PROTECTION REGULATIONS FOR DOMESTIC LICENSING AND...

  18. 10 CFR 2.105 - Notice of proposed action.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF ORDERS Procedure for Issuance, Amendment, Transfer, or Renewal of a License, and Standard Design Approval Hearing... within the time prescribed in the notice, the Director, Office of Nuclear Reactor Regulation, Director...

  19. 10 CFR 2.105 - Notice of proposed action.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF ORDERS Procedure for Issuance, Amendment, Transfer, or Renewal of a License, and Standard Design Approval Hearing... within the time prescribed in the notice, the Director, Office of Nuclear Reactor Regulation, Director...

  20. 10 CFR 51.53 - Postconstruction environmental reports.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... renewal of a license to operate a nuclear power plant under part 54 of this chapter shall submit with its... for a nuclear power reactor shall submit this report only in connection with the first licensing action authorizing full-power operation. In this report, the applicant shall discuss the same matters...

  1. NRC Licensing Status Summary Report for NGNP

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Moe, Wayne Leland; Kinsey, James Carl

    2014-11-01

    The Next Generation Nuclear Plant (NGNP) Project, initiated at Idaho National Laboratory (INL) by the U.S. Department of Energy (DOE) pursuant to provisions of the Energy Policy Act of 2005, is based on research and development activities supported by the Department of Energy Generation IV Nuclear Energy Systems Initiative. The principal objective of the NGNP Project is to support commercialization of high temperature gas-cooled reactor (HTGR) technology. The HTGR is a helium-cooled and graphite moderated reactor that can operate at temperatures much higher than those of conventional light water reactor (LWR) technologies. The NGNP will be licensed for construction andmore » operation by the Nuclear Regulatory Commission (NRC). However, not all elements of current regulations (and their related implementation guidance) can be applied to HTGR technology at this time. Certain policies established during past LWR licensing actions must be realigned to properly accommodate advanced HTGR technology. A strategy for licensing HTGR technology was developed and executed through the cooperative effort of DOE and the NRC through the NGNP Project. The purpose of this report is to provide a snapshot of the current status of the still evolving pre-license application regulatory framework relative to commercial HTGR technology deployment in the U.S. The following discussion focuses on (1) describing what has been accomplished by the NGNP Project up to the time of this report, and (2) providing observations and recommendations concerning actions that remain to be accomplished to enable the safe and timely licensing of a commercial HTGR facility in the U.S.« less

  2. AP1000{sup R} licensing and deployment in the United States

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Jordan, R. P.; Russ, P. A.; Filiak, P. P.

    2012-07-01

    In recent years, both domestic and foreign utilities have turned to the standardized Westinghouse AP1000 plant design in satisfying their near - and long-term - sustainable energy needs. As direct support to these actions, licensing the AP1000 design has played a significant role by providing one of the fundamental bases in clearing regulatory hurdles leading to the start of new plant construction. Within the U.S. alone, Westinghouse AP1000 licensing activities have reached unprecedented milestones with the approvals of both AP1000 Design Certification and Southern Company's combined construction permit and operating license (COL) application directly supporting the construction of two newmore » nuclear plants in Georgia. Further COL application approvals are immediately pending for an additional two AP1000 plants in South Carolina. And, across the U.S. nuclear industry spectrum, there are 10 other COL applications under regulatory review representing some 16 new plants at 10 sites. In total, these actions represent the first wave of new plant licensing under the regulatory approval process since 1978. Fundamental to the Nuclear Regulatory Commission's AP1000 Design Certification is the formal recognition of the AP1000 passive safety design through regulatory acceptance rulemaking. Through recognition and deployment of the AP1000 Design Certification, the utility licensee / operator of this reactor design are now offered an opportunity to use a simplified 'one-step' combined license process, thereby managing substantial back-end construction schedule risk from regulatory and intervention delays. Application of this regulatory philosophy represents both acceptance and encouragement of standardized reactor designs like the AP1000. With the recent AP1000 Design Certification and utility COL acceptances, the fundamental licensing processes of this philosophy have successfully proven the attainment of significant milestones with the next stage licensing actions directed towards deployment. AP1000 Design Certification and COL deployment, and management of the plant construction in accordance with the conditions within these approvals, remain as significant site and corporate responsibilities. These licensing-construction integrated activities must now focus on identifying and resolving 'as-built' departures from the standardized design as assessed against the certified AP1000 technical and licensing basis. Within this paper, significant aspects of the AP1000 U.S. licensing will be discussed, including identifying systems and processes used in ensuring compliance while deploying the standardized design. Critical licensing steps, licensing deployment actions as plant construction progresses and defining the road forward to a successful completion of licensing actions will be addressed. (authors)« less

  3. 78 FR 11688 - Notice of Issuance of Amendment to Facility License R-77 Incorporating a Decommissioning Plan for...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-02-19

    ... Reactor at the State University of New York at Buffalo AGENCY: Nuclear Regulatory Commission. ACTION... University of New York at Buffalo (UB) decommissioning plan (DP) by amendment to the Facility License R-77... in the NRC Library at http://www.nrc.gov/reading-rm/adams.html . To begin the search, select ``ADAMS...

  4. 10 CFR 171.15 - Annual fees: Reactor licenses and independent spent fuel storage licenses.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Annual fees: Reactor licenses and independent spent fuel... REACTOR LICENSES AND FUEL CYCLE LICENSES AND MATERIALS LICENSES, INCLUDING HOLDERS OF CERTIFICATES OF... NRC § 171.15 Annual fees: Reactor licenses and independent spent fuel storage licenses. (a) Each...

  5. 10 CFR 171.15 - Annual fees: Reactor licenses and independent spent fuel storage licenses.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Annual fees: Reactor licenses and independent spent fuel... REACTOR LICENSES AND FUEL CYCLE LICENSES AND MATERIALS LICENSES, INCLUDING HOLDERS OF CERTIFICATES OF... NRC § 171.15 Annual fees: Reactor licenses and independent spent fuel storage licenses. (a) Each...

  6. Operating experience feedback report: New plants, Commercial power reactors

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Dennig, R.L.; O'Reilly, P.D.

    1987-07-01

    This report documents a detailed review of the cause of unplanned events during the early months of licensed operation for plants licensed between March 1983 and April 1986. The major lessons and corrective actions that appear to have the greatest potential for improving the effectiveness of plant startups are provided for consideration through the operating experience feedback programs and activities of the industry and the NRC staff.

  7. 75 FR 73134 - Florida Power and Light Company, St. Lucie Plant, Units 1 and 2; Environmental Assessment and...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-29

    ... proposed action does not involve any physical changes to the reactor, fuel, plant, structures, support structures, water, or land at the St. Lucie Plant, Units 1 and 2, site. The proposed action is in accordance... Impact Statement for License Renewal of Nuclear Power Plants'' (GEIS). Supplement 11 of the GEIS, issued...

  8. 75 FR 48382 - Draft Regulatory Guide: Issuance, Availability

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-08-10

    ... NUCLEAR REGULATORY COMMISSION [NRC-2010-0275] Draft Regulatory Guide: Issuance, Availability AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Draft Regulatory Guide, DG-1228, ``Standard Format and Content of License Termination Plans for Nuclear Power Reactors.'' FOR FURTHER INFORMATION CONTACT: James C....

  9. 10 CFR 72.210 - General license issued.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General License for Storage of Spent Fuel at Power Reactor Sites § 72.210 General license issued. A general license is... reactor sites to persons authorized to possess or operate nuclear power reactors under 10 CFR part 50 or...

  10. 10 CFR 72.210 - General license issued.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General License for Storage of Spent Fuel at Power Reactor Sites § 72.210 General license issued. A general license is... reactor sites to persons authorized to possess or operate nuclear power reactors under 10 CFR part 50 or...

  11. 10 CFR 50.30 - Filing of application; oath or affirmation.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... Reactor Regulation, Director, Office of New Reactors, or Director, Office of Nuclear Material Safety and... Director, Office of New Reactors, or the Director, Office of Nuclear Reactor Regulation, or the Director..., operating license, early site permit, combined license, or manufacturing license for a nuclear power reactor...

  12. 10 CFR 50.30 - Filing of application; oath or affirmation.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... Reactor Regulation, Director, Office of New Reactors, or Director, Office of Nuclear Material Safety and... Director, Office of New Reactors, or the Director, Office of Nuclear Reactor Regulation, or the Director..., operating license, early site permit, combined license, or manufacturing license for a nuclear power reactor...

  13. 10 CFR 50.30 - Filing of application; oath or affirmation.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... Reactor Regulation, Director, Office of New Reactors, or Director, Office of Nuclear Material Safety and... Director, Office of New Reactors, or the Director, Office of Nuclear Reactor Regulation, or the Director..., operating license, early site permit, combined license, or manufacturing license for a nuclear power reactor...

  14. 10 CFR 50.30 - Filing of application; oath or affirmation.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... Reactor Regulation, Director, Office of New Reactors, or Director, Office of Nuclear Material Safety and... Director, Office of New Reactors, or the Director, Office of Nuclear Reactor Regulation, or the Director..., operating license, early site permit, combined license, or manufacturing license for a nuclear power reactor...

  15. 76 FR 40937 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-12

    ... Generator Water Level High-High'' instrument setpoint and associated allowable value. The proposed change is... [Pressurized-Water Reactor] PWR Operability Requirements and Actions for RCS Leakage Instrumentation''. Basis... monitor is the containment atmospheric gaseous radiation monitor. The monitoring of RCS leakage is not a...

  16. 76 FR 21917 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-04-19

    ... SGTR accident. At normal operating pressures, leakage from primary water stress corrosion cracking... PWR [pressurized- water reactor] Operability Requirements and Actions for RCS Leakage Instrumentation... water inventory can be obtained. Therefore, it is concluded that the proposed changes do not involve a...

  17. 78 FR 45984 - Yankee Atomic Electric Company, Yankee Nuclear Power Station

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-30

    ... Electric Company, Yankee Nuclear Power Station AGENCY: Nuclear Regulatory Commission. ACTION: Environmental... (YAEC) is the holder of Possession-Only License DPR-3 for the Yankee Nuclear Power Station (YNPS... on the site of any nuclear power reactor. In its Statement of Considerations (SOC) for the Final Rule...

  18. 78 FR 26811 - Dow Chemical Company, Dow TRIGA Research Reactor; License Renewal for the Dow Chemical TRIGA...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-08

    ... Research Reactor; License Renewal for the Dow Chemical TRIGA Research Reactor; Supplemental Information and... 20, 2012 (77 FR 42771), ``License Renewal for the Dow Chemical TRIGA Research Reactor,'' to inform... Chemical Company which would authorize continued operation of the Dow TRIGA Research Reactor. The notice...

  19. 77 FR 60039 - Non-Power Reactor License Renewal

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-02

    ... NUCLEAR REGULATORY COMMISSION 10 CFR Part 50 [NRC-2011-0087] RIN 3150-AI96 Non-Power Reactor... the final regulatory basis for rulemaking to streamline non-power reactor license renewal. This final... Reactor (RTR) License Renewal Process. This contemplated rulemaking also recommends conforming changes to...

  20. 76 FR 63668 - Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-13

    ... Licensing of Non-Power Reactors: Format and Content,'' for the Production of Radioisotopes and NUREG-1537, part 2, ``Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors... production facility and the Research and Test Reactor Licensing Branch (PRLB) of the Division of Policy and...

  1. 10 CFR 110.26 - General license for the export of nuclear reactor components.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false General license for the export of nuclear reactor components. 110.26 Section 110.26 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Licenses § 110.26 General license for the export of nuclear reactor...

  2. 10 CFR 110.26 - General license for the export of nuclear reactor components.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false General license for the export of nuclear reactor components. 110.26 Section 110.26 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Licenses § 110.26 General license for the export of nuclear reactor...

  3. 10 CFR 110.26 - General license for the export of nuclear reactor components.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false General license for the export of nuclear reactor components. 110.26 Section 110.26 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Licenses § 110.26 General license for the export of nuclear reactor...

  4. 10 CFR 110.26 - General license for the export of nuclear reactor components.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false General license for the export of nuclear reactor components. 110.26 Section 110.26 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Licenses § 110.26 General license for the export of nuclear reactor...

  5. 10 CFR 110.26 - General license for the export of nuclear reactor components.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false General license for the export of nuclear reactor components. 110.26 Section 110.26 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) EXPORT AND IMPORT OF NUCLEAR EQUIPMENT AND MATERIAL Licenses § 110.26 General license for the export of nuclear reactor...

  6. 76 FR 60091 - Notice of Availability of Environmental Assessment and Finding of No Significant Impact for the...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-09-28

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-407; NRC-2011-0153] Notice of Availability of Environmental Assessment and Finding of No Significant Impact for the University of Utah Nuclear Reactor Facility; Facility Operating License No. R-126 AGENCY: Nuclear Regulatory Commission. ACTION: Notice of...

  7. 10 CFR 50.72 - Immediate notification requirements for operating nuclear power reactors.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... power reactors. 50.72 Section 50.72 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... notification requirements for operating nuclear power reactors. (a) General requirements. 1 (1) Each nuclear power reactor licensee licensed under §§ 50.21(b) or 50.22 holding an operating license under this part...

  8. 10 CFR 50.72 - Immediate notification requirements for operating nuclear power reactors.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... power reactors. 50.72 Section 50.72 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... notification requirements for operating nuclear power reactors. (a) General requirements. 1 (1) Each nuclear power reactor licensee licensed under §§ 50.21(b) or 50.22 holding an operating license under this part...

  9. 10 CFR 51.107 - Public hearings in proceedings for issuance of combined licenses; limited work authorizations.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... the issuance of a combined license for a nuclear power reactor under part 52 of this chapter, the... or Director, Office of Nuclear Reactor Regulation, as appropriate. (b) If a combined license... authorization should be issued as proposed by the Director of New Reactors or the Director of Nuclear Reactor...

  10. 10 CFR 51.107 - Public hearings in proceedings for issuance of combined licenses; limited work authorizations.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... the issuance of a combined license for a nuclear power reactor under part 52 of this chapter, the... or Director, Office of Nuclear Reactor Regulation, as appropriate. (b) If a combined license... authorization should be issued as proposed by the Director of New Reactors or the Director of Nuclear Reactor...

  11. 10 CFR 51.107 - Public hearings in proceedings for issuance of combined licenses; limited work authorizations.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... the issuance of a combined license for a nuclear power reactor under part 52 of this chapter, the... or Director, Office of Nuclear Reactor Regulation, as appropriate. (b) If a combined license... authorization should be issued as proposed by the Director of New Reactors or the Director of Nuclear Reactor...

  12. 10 CFR 140.94 - Appendix D-Form of indemnity agreement with Federal agencies.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... (hereinafter referred to as the Act). Article I As used in this agreement, 1. Nuclear reactor, byproduct... irradiated or to be irradiated by, the nuclear reactor or reactors subject to the license or licenses... construction of a nuclear reactor with respect to which no operating license has been issued by the Nuclear...

  13. 10 CFR 51.107 - Public hearings in proceedings for issuance of combined licenses; limited work authorizations.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... the issuance of a combined license for a nuclear power reactor under part 52 of this chapter, the... or Director, Office of Nuclear Reactor Regulation, as appropriate. (b) If a combined license... authorization should be issued as proposed by the Director of New Reactors or the Director of Nuclear Reactor...

  14. 10 CFR 51.107 - Public hearings in proceedings for issuance of combined licenses; limited work authorizations.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... the issuance of a combined license for a nuclear power reactor under part 52 of this chapter, the... or Director, Office of Nuclear Reactor Regulation, as appropriate. (b) If a combined license... authorization should be issued as proposed by the Director of New Reactors or the Director of Nuclear Reactor...

  15. 76 FR 77023 - In the Matter of Florida Power Corporation, et al., Crystal River Unit 3 Nuclear Generating Plant...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-09

    ... the Nuclear Regulatory Commission (NRC, the Commission) consent to the proposed indirect transfer of... transfer action, FPC shall inform the Director of the Office of Nuclear Reactor Regulation in writing of... NUCLEAR REGULATORY COMMISSION [NRC-2011-0281; License No. DPR-72; Docket No. 50-302] In the Matter...

  16. Oak Ridge National Laboratory Support of Non-light Water Reactor Technologies: Capabilities Assessment for NRC Near-term Implementation Action Plans for Non-light Water Reactors

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Belles, Randy; Jain, Prashant K.; Powers, Jeffrey J.

    The Oak Ridge National Laboratory (ORNL) has a rich history of support for light water reactor (LWR) and non-LWR technologies. The ORNL history involves operation of 13 reactors at ORNL including the graphite reactor dating back to World War II, two aqueous homogeneous reactors, two molten salt reactors (MSRs), a fast-burst health physics reactor, and seven LWRs. Operation of the High Flux Isotope Reactor (HFIR) has been ongoing since 1965. Expertise exists amongst the ORNL staff to provide non-LWR training; support evaluation of non-LWR licensing and safety issues; perform modeling and simulation using advanced computational tools; run laboratory experiments usingmore » equipment such as the liquid salt component test facility; and perform in-depth fuel performance and thermal-hydraulic technology reviews using a vast suite of computer codes and tools. Summaries of this expertise are included in this paper.« less

  17. 10 CFR 72.6 - License required; types of licenses.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General... the receipt, handling, storage, and transfer of reactor-related GTCC are specific licenses. Any... hereby issued to receive title to and own spent fuel, high-level radioactive waste, or reactor-related...

  18. 10 CFR 72.6 - License required; types of licenses.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General... the receipt, handling, storage, and transfer of reactor-related GTCC are specific licenses. Any... hereby issued to receive title to and own spent fuel, high-level radioactive waste, or reactor-related...

  19. 10 CFR 72.218 - Termination of licenses.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General License for Storage of Spent Fuel at Power Reactor Sites § 72.218 Termination of licenses. (a) The notification regarding the program for the management of spent fuel at the reactor required by § 50.54(bb) of...

  20. 10 CFR 72.218 - Termination of licenses.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General License for Storage of Spent Fuel at Power Reactor Sites § 72.218 Termination of licenses. (a) The notification regarding the program for the management of spent fuel at the reactor required by § 50.54(bb) of...

  1. Interim Status Report for Risk Management for SFRs

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Jankovsky, Zachary Kyle; Denman, Matthew R.; Groth, Katrina

    2015-10-01

    Accident management is an important component to maintaining risk at acceptable levels for all complex systems, such as nuclear power plants. With the introduction of passive, or inherently safe, reactor designs the focus has shifted from management by operators to allowing the system's design to take advantage of natural phenomena to manage the accident. Inherently and passively safe designs are laudable, but nonetheless extreme boundary conditions can interfere with the design attributes which facilitate inherent safety, thus resulting in unanticipated and undesirable end states. This report examines an inherently safe and small sodium fast reactor experiencing a variety of beyondmore » design basis events with the intent of exploring the utility of a Dynamic Bayesian Network to infer the state of the reactor to inform the operator's corrective actions. These inferences also serve to identify the instruments most critical to informing an operator's actions as candidates for hardening against radiation and other extreme environmental conditions that may exist in an accident. This reduction in uncertainty serves to inform ongoing discussions of how small sodium reactors would be licensed and may serve to reduce regulatory risk and cost for such reactors.« less

  2. Advanced Reactor Technologies - Regulatory Technology Development Plan (RTDP)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Moe, Wayne L.

    This DOE-NE Advanced Small Modular Reactor (AdvSMR) regulatory technology development plan (RTDP) will link critical DOE nuclear reactor technology development programs to important regulatory and policy-related issues likely to impact a “critical path” for establishing a viable commercial AdvSMR presence in the domestic energy market. Accordingly, the regulatory considerations that are set forth in the AdvSMR RTDP will not be limited to any one particular type or subset of advanced reactor technology(s) but rather broadly consider potential regulatory approaches and the licensing implications that accompany all DOE-sponsored research and technology development activity that deal with commercial non-light water reactors. However,more » it is also important to remember that certain “minimum” levels of design and safety approach knowledge concerning these technology(s) must be defined and available to an extent that supports appropriate pre-licensing regulatory analysis within the RTDP. Final resolution to advanced reactor licensing issues is most often predicated on the detailed design information and specific safety approach as documented in a facility license application and submitted for licensing review. Because the AdvSMR RTDP is focused on identifying and assessing the potential regulatory implications of DOE-sponsored reactor technology research very early in the pre-license application development phase, the information necessary to support a comprehensive regulatory analysis of a new reactor technology, and the resolution of resulting issues, will generally not be available. As such, the regulatory considerations documented in the RTDP should be considered an initial “first step” in the licensing process which will continue until a license is issued to build and operate the said nuclear facility. Because a facility license application relies heavily on the data and information generated by technology development studies, the anticipated regulatory importance of key DOE reactor research initiatives should be assessed early in the technology development process. Quality assurance requirements supportive of later licensing activities must also be attached to important research activities to ensure resulting data is usable in that context. Early regulatory analysis and licensing approach planning thus provides a significant benefit to the formulation of research plans and also enables the planning and development of a compatible AdvSMR licensing framework, should significant modification be required.« less

  3. Advanced Reactor Technology -- Regulatory Technology Development Plan (RTDP)

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Moe, Wayne Leland

    This DOE-NE Advanced Small Modular Reactor (AdvSMR) regulatory technology development plan (RTDP) will link critical DOE nuclear reactor technology development programs to important regulatory and policy-related issues likely to impact a “critical path” for establishing a viable commercial AdvSMR presence in the domestic energy market. Accordingly, the regulatory considerations that are set forth in the AdvSMR RTDP will not be limited to any one particular type or subset of advanced reactor technology(s) but rather broadly consider potential regulatory approaches and the licensing implications that accompany all DOE-sponsored research and technology development activity that deal with commercial non-light water reactors. However,more » it is also important to remember that certain “minimum” levels of design and safety approach knowledge concerning these technology(s) must be defined and available to an extent that supports appropriate pre-licensing regulatory analysis within the RTDP. Final resolution to advanced reactor licensing issues is most often predicated on the detailed design information and specific safety approach as documented in a facility license application and submitted for licensing review. Because the AdvSMR RTDP is focused on identifying and assessing the potential regulatory implications of DOE-sponsored reactor technology research very early in the pre-license application development phase, the information necessary to support a comprehensive regulatory analysis of a new reactor technology, and the resolution of resulting issues, will generally not be available. As such, the regulatory considerations documented in the RTDP should be considered an initial “first step” in the licensing process which will continue until a license is issued to build and operate the said nuclear facility. Because a facility license application relies heavily on the data and information generated by technology development studies, the anticipated regulatory importance of key DOE reactor research initiatives should be assessed early in the technology development process. Quality assurance requirements supportive of later licensing activities must also be attached to important research activities to ensure resulting data is usable in that context. Early regulatory analysis and licensing approach planning thus provides a significant benefit to the formulation of research plans and also enables the planning and development of a compatible AdvSMR licensing framework, should significant modification be required.« less

  4. 77 FR 26321 - Reed College, Reed Research Nuclear Reactor, Renewed Facility Operating License No. R-112

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-03

    ... Nuclear Reactor, Renewed Facility Operating License No. R-112 AGENCY: Nuclear Regulatory Commission... Commission (NRC or the Commission) has issued renewed Facility Operating License No. R- 112, held by Reed... License No. R-112 will expire 20 years from its date of issuance. The renewed facility operating license...

  5. 76 FR 16842 - Request for a License To Export Reactor Components

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-03-25

    ... NUCLEAR REGULATORY COMMISSION Request for a License To Export Reactor Components Pursuant to 10.... Mechanical Corporation. coolant pump 1000 (design) maintenance, and systems, related reactors. operation of AP- equipment, and 1000 (design) spare parts. nuclear reactors. February 10, 2011 February 23, 2011...

  6. 78 FR 5840 - Notice of License Termination for University of Illinois Advanced TRIGA Reactor, License No. R-115

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-28

    ... University of Illinois Advanced TRIGA Reactor, License No. R-115 The U.S. Nuclear Regulatory Commission (NRC) is noticing the termination of Facility Operating License No. R-115, for the University of Illinois... Operating License No. R-115 is terminated. The above referenced documents may be examined, and/or copied for...

  7. 10 CFR Appendix N to Part 52 - Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate...

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... Designs: Combined Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple... construct and operate nuclear power reactors of identical design (“common design”) to be located at multiple...

  8. 76 FR 68514 - Request for a License To Export Reactor Components

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-04

    ... NUCLEAR REGULATORY COMMISSION Request for a License To Export Reactor Components Pursuant to 10.../docket Number Westinghouse Electric Company Complete reactor 12 Perform seismic China. LLC, August 18... qualification equipment. of AP1000 (design) nuclear reactors. For the Nuclear Regulatory Commission. Dated this...

  9. 10 CFR 50.72 - Immediate notification requirements for operating nuclear power reactors.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... power reactors. 50.72 Section 50.72 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... notification requirements for operating nuclear power reactors. (a) General requirements. 1 (1) Each nuclear... requirements for immediate notification of the NRC by licensed operating nuclear power reactors are contained...

  10. 10 CFR 50.36 - Technical specifications.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... nuclear reactors are limits upon important process variables that are found to be necessary to reasonably... Commission terminates the license for the reactor, except for nuclear power reactors licensed under § 50.21(b... for nuclear reactors are settings for automatic protective devices related to those variables having...

  11. 10 CFR 50.36 - Technical specifications.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... nuclear reactors are limits upon important process variables that are found to be necessary to reasonably... Commission terminates the license for the reactor, except for nuclear power reactors licensed under § 50.21(b... for nuclear reactors are settings for automatic protective devices related to those variables having...

  12. 10 CFR 50.36 - Technical specifications.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... nuclear reactors are limits upon important process variables that are found to be necessary to reasonably... Commission terminates the license for the reactor, except for nuclear power reactors licensed under § 50.21(b... for nuclear reactors are settings for automatic protective devices related to those variables having...

  13. 10 CFR Appendix A to Part 110 - Illustrative List of Nuclear Reactor Equipment Under NRC Export Licensing Authority

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Illustrative List of Nuclear Reactor Equipment Under NRC... List of Nuclear Reactor Equipment Under NRC Export Licensing Authority Note—A nuclear reactor basically includes the items within or attached directly to the reactor vessel, the equipment which controls the...

  14. 10 CFR Appendix A to Part 110 - Illustrative List of Nuclear Reactor Equipment Under NRC Export Licensing Authority

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Illustrative List of Nuclear Reactor Equipment Under NRC... List of Nuclear Reactor Equipment Under NRC Export Licensing Authority Note—A nuclear reactor basically includes the items within or attached directly to the reactor vessel, the equipment which controls the...

  15. 10 CFR Appendix A to Part 110 - Illustrative List of Nuclear Reactor Equipment Under NRC Export Licensing Authority

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Illustrative List of Nuclear Reactor Equipment Under NRC... List of Nuclear Reactor Equipment Under NRC Export Licensing Authority Note: A nuclear reactor... core of a nuclear reactor and capable of withstanding the operating pressure of the primary coolant. (2...

  16. 78 FR 57904 - Request for a License To Export; Reactor Components

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-20

    ... NUCLEAR REGULATORY COMMISSION Request for a License To Export; Reactor Components Pursuant to 10..., systems, related reactors. operation of AP- XR177, 11006121. equipment, and 1000 (design) spare parts. nuclear reactors. Dated this 16th day of September 2013 in Rockville, Maryland. For The Nuclear Regulatory...

  17. 10 CFR 2.1115 - Designation of issues for adjudicatory hearing.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... at Civilian Nuclear Power Reactors § 2.1115 Designation of issues for adjudicatory hearing. (a) After... reactor already licensed to operate at the site, or any civilian nuclear power reactor for which a... the issuance of a construction permit or operating license for a civilian nuclear power reactor at...

  18. 75 FR 70042 - In the Matter of All Power Reactor Licensees and Research Reactor Licensees Who Transport Spent...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-16

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos (Redacted), License Nos (Redacted), EA (Redacted); NRC- 2010-0351] In the Matter of All Power Reactor Licensees and Research Reactor Licensees Who Transport Spent Nuclear Fuel; Order Modifying License (Effective Immediately) I. The licensees identified in...

  19. 75 FR 79423 - In the Matter of All Power Reactor Licensees and Research Reactor Licensees Who Transport Spent...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-20

    ... NUCLEAR REGULATORY COMMISSION [Docket Nos. (Redacted), License Nos.: (Redacted), EA (Redacted); NRC- 2010-0351] In the Matter of All Power Reactor Licensees and Research Reactor Licensees Who Transport Spent Nuclear Fuel; Order Modifying License (Effective Immediately) I The licensees identified in...

  20. 10 CFR 2.501 - Notice of hearing on application under subpart F of 10 CFR part 52 for a license to manufacture...

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... part 52 for a license to manufacture nuclear power reactors. 2.501 Section 2.501 Energy NUCLEAR... Procedures Applicable to Proceedings for the Issuance of Licenses To Manufacture Nuclear Power Reactors To Be... power reactors. (a) In the case of an application under subpart F of part 52 of this chapter for a...

  1. 10 CFR 2.501 - Notice of hearing on application under subpart F of 10 CFR part 52 for a license to manufacture...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... part 52 for a license to manufacture nuclear power reactors. 2.501 Section 2.501 Energy NUCLEAR... Procedures Applicable to Proceedings for the Issuance of Licenses To Manufacture Nuclear Power Reactors To Be... power reactors. (a) In the case of an application under subpart F of part 52 of this chapter for a...

  2. 10 CFR Appendix N to Part 50 - Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate...

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites Section 101... nuclear power reactors of essentially the same design to be located at different sites. 1 1 If the design...

  3. 10 CFR Appendix N to Part 50 - Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate...

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites Section 101... nuclear power reactors of essentially the same design to be located at different sites. 1 1 If the design...

  4. 10 CFR Appendix N to Part 50 - Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites Section 101... nuclear power reactors of essentially the same design to be located at different sites. 1 1 If the design...

  5. 10 CFR Appendix A to Part 110 - Illustrative List of Nuclear Reactor Equipment Under NRC Export Licensing Authority

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Illustrative List of Nuclear Reactor Equipment Under NRC... List of Nuclear Reactor Equipment Under NRC Export Licensing Authority Note—A nuclear reactor basically... nuclear reactor and capable of withstanding the operating pressure of the primary coolant. (2) On-line (e...

  6. 10 CFR Appendix A to Part 110 - Illustrative List of Nuclear Reactor Equipment Under NRC Export Licensing Authority

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Illustrative List of Nuclear Reactor Equipment Under NRC... List of Nuclear Reactor Equipment Under NRC Export Licensing Authority Note—A nuclear reactor basically... nuclear reactor and capable of withstanding the operating pressure of the primary coolant. (2) On-line (e...

  7. Function of university reactors in operator licensing training for nuclear utilities

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Wicks, F.

    1985-11-01

    The director of the Division of the US Nuclear Regulatory Commission in generic letter 84-10, dated April 26, 1984, spoke the requirement that applicants for senior reactor operator licenses for power reactors shall have performed then reactor startups. Simulator startups were not acknowledged. Startups performed on a university reactor are acceptable. The content and results of a five-day program combining instruction and experiments with the Rensselaer reactor are summarized.

  8. 75 FR 30451 - Duke Energy Carolinas, LLC; Duke Energy Carolinas, LLC; William States Lee III Combined License...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-06-01

    ... Energy Carolinas, LLC; William States Lee III Combined License Application; Notice of Intent To Conduct a... environmental review of the William States Lee III Nuclear Station, Units 1 and 2 combined licenses application...-licensing/col/lee.html '' to `` http://www.nrc.gov/reactors/new-reactors/col/lee.html ''. Dated at Rockville...

  9. 10 CFR 52.171 - Finality of manufacturing licenses; information requests.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... required for issuance of a construction permit, operating license, combined license, in any hearing under... manufactured reactor, the costs and benefits of severe accident mitigation design alternatives, and the bases for not incorporating severe accident mitigation design alternatives into the design of the reactor to...

  10. 77 FR 7613 - Dow Chemical Company; Dow Chemical TRIGA Research Reactor; Facility Operating License No. R-108

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-02-13

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-264; NRC-2012-0026] Dow Chemical Company; Dow Chemical TRIGA Research Reactor; Facility Operating License No. R-108 AGENCY: Nuclear Regulatory Commission... Facility Operating License No. R-108 (``Application''), which currently authorizes the Dow Chemical Company...

  11. BWR Anticipated Transients Without Scram Leading to Instability

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cheng L. Y.; Baek J.; Cuadra, A.

    2013-11-10

    Anticipated transients without scram (ATWS) in aboiling water reactor (BWR) were simulated in order to understand reactor response and determine the effectiveness of automatic and operator actions to mitigate this beyond-design-basis accident. The events of interest herein are initiated by a turbine trip when the reactor is operating in the expanded operating domainMELLLA+ [maximum extended load line limit plus]. In these events the reactor may initially be at up to 120% of the original licensed thermal power (OLTP) and at flow rates as low as 80% of rated.For these (and similar) ATWS events the concern isthat when the reactor powermore » decreases in response to a dual recirculation pump trip, the core will become unstable and large amplitude oscillations will begin. The occurrence of these power oscillations, if left unmitigated, may result in fuel damage, and the amplitude of the poweroscillations may hamper the effectiveness of the injection of dissolved neutron absorber through the standby liquid control system (SLCS).« less

  12. 77 FR 58419 - Guidelines for Preparing and Reviewing Licensing Applications for Instrumentation and Control...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-20

    ... Applications for Instrumentation and Control Upgrades for Non-Power Reactors AGENCY: Nuclear Regulatory...-Power Reactors: Format and Content,'' for instrumentation and control upgrades and NUREG-1537, Part 2, ``Guidelines for Preparing and Reviewing Applications for the Licensing of Non-Power Reactors: Standard Review...

  13. 77 FR 39521 - Application for a License To Export Nuclear Reactor Major Components and Equipment

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-07-03

    ... LLC reactor coolant equipment for four constructing four plant May 14, 2012 pumps with motors, APR1400... Emirates. XR176 monitoring and plant in Braka. 110060011 control equipment, auxiliary equipment and... NUCLEAR REGULATORY COMMISSION Application for a License To Export Nuclear Reactor Major Components...

  14. 75 FR 12311 - FirstEnergy Nuclear Operating Company; Notice of Consideration of Issuance of Amendment to...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-15

    ... INFORMATION CONTACT: Michael Mahoney, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission... Licensing Branch III-2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR... NUCLEAR REGULATORY COMMISSION [Docket No. 50-346] FirstEnergy Nuclear Operating Company; Notice of...

  15. 10 CFR 72.220 - Violations.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ..., HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General License for Storage of Spent Fuel at Power Reactor Sites § 72.220 Violations. This general license is subject to the...

  16. 10 CFR 72.220 - Violations.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ..., HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General License for Storage of Spent Fuel at Power Reactor Sites § 72.220 Violations. This general license is subject to the...

  17. 75 FR 36126 - Office of New Reactors; Proposed Revision to Standard Review Plan Section 13.6.1, Revision 1 on...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-06-24

    ... NUCLEAR REGULATORY COMMISSION [NRC-2010-0228] Office of New Reactors; Proposed Revision to Standard Review Plan Section 13.6.1, Revision 1 on Physical Security--Combined License and Operating...), Section 13.6.1 on ``Physical Security--Combined License and Operating Reactors,'' (Agencywide Documents...

  18. 77 FR 40092 - License Amendment To Increase the Maximum Reactor Power Level, Florida Power & Light Company, St...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-07-06

    ... Increase the Maximum Reactor Power Level, Florida Power & Light Company, St. Lucie, Units 1 and 2 AGENCY... amendment for Renewed Facility Operating License Nos. DPR-67 and NPF-16, issued to Florida Power & Light... St. Lucie County, Florida. The proposed license amendment would increase the maximum thermal power...

  19. 75 FR 13 - Alternate Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-04

    ...The Nuclear Regulatory Commission (NRC) is amending its regulations to provide alternate fracture toughness requirements for protection against pressurized thermal shock (PTS) events for pressurized water reactor (PWR) pressure vessels. This final rule provides alternate PTS requirements based on updated analysis methods. This action is desirable because the existing requirements are based on unnecessarily conservative probabilistic fracture mechanics analyses. This action reduces regulatory burden for those PWR licensees who expect to exceed the existing requirements before the expiration of their licenses, while maintaining adequate safety, and may choose to comply with the final rule as an alternative to complying with the existing requirements.

  20. 10 CFR 70.20b - General license for carriers of transient shipments of formula quantities of strategic special...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... significance, special nuclear material of low strategic significance, and irradiated reactor fuel. 70.20b..., special nuclear material of low strategic significance, and irradiated reactor fuel. (a) A general license... requirements of § 73.67 of this chapter. (3) Irradiated reactor fuel of the type and quantity subject to the...

  1. 10 CFR 70.20b - General license for carriers of transient shipments of formula quantities of strategic special...

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... significance, special nuclear material of low strategic significance, and irradiated reactor fuel. 70.20b..., special nuclear material of low strategic significance, and irradiated reactor fuel. (a) A general license... requirements of § 73.67 of this chapter. (3) Irradiated reactor fuel of the type and quantity subject to the...

  2. 10 CFR 52.93 - Exemptions and variances.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... referencing a nuclear power reactor manufactured under a manufacturing license issued under subpart F of this... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS..., site parameters, terms and conditions, or approved design of the manufactured reactor. The Commission...

  3. 10 CFR 52.155 - Filing of applications.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... file an application for a manufacturing license under this subpart with the Director of New Reactors or the Director of Nuclear Reactor Regulation, as appropriate. (b) The application must comply with the... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS...

  4. 10 CFR 52.155 - Filing of applications.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... file an application for a manufacturing license under this subpart with the Director of New Reactors or the Director of Nuclear Reactor Regulation, as appropriate. (b) The application must comply with the... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS...

  5. 10 CFR 52.155 - Filing of applications.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... file an application for a manufacturing license under this subpart with the Director of New Reactors or the Director of Nuclear Reactor Regulation, as appropriate. (b) The application must comply with the... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS...

  6. 10 CFR 52.155 - Filing of applications.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... file an application for a manufacturing license under this subpart with the Director of New Reactors or the Director of Nuclear Reactor Regulation, as appropriate. (b) The application must comply with the... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS...

  7. 10 CFR 52.155 - Filing of applications.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... file an application for a manufacturing license under this subpart with the Director of New Reactors or the Director of Nuclear Reactor Regulation, as appropriate. (b) The application must comply with the... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS...

  8. A Potential NASA Research Reactor to Support NTR Development

    NASA Technical Reports Server (NTRS)

    Eades, Michael; Gerrish, Harold; Hardin, Leroy

    2013-01-01

    In support of efforts for research into the design and development of a man rated Nuclear Thermal Rocket (NTR) engine, the National Aeronautics and Space Administration (NASA), Marshall Space Flight Center (MSFC), is evaluating the potential for building a Nuclear Regulatory Commission (NRC) licensed research reactor. The proposed reactor would be licensed by NASA and operated jointly by NASA and university partners. The purpose of this reactor would be to perform further research into the technologies and systems needed for a successful NTR project and promote nuclear training and education.

  9. 10 CFR 2.500 - Scope of subpart.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... Procedures Applicable to Proceedings for the Issuance of Licenses To Manufacture Nuclear Power Reactors To Be... consideration in separate hearings of an application for a license to manufacture nuclear power reactors under... 10 Energy 1 2010-01-01 2010-01-01 false Scope of subpart. 2.500 Section 2.500 Energy NUCLEAR...

  10. 78 FR 26812 - University of California, Irvine; License Renewal for University of California, Irvine Nuclear...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-08

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-326; NRC-2010-0217] University of California, Irvine; License Renewal for University of California, Irvine Nuclear Reactor Facility; Supplemental Information... Renewal for University of California, Irvine Nuclear Reactor Facility,'' to inform the public that the NRC...

  11. 10 CFR 51.105a - Public hearings in proceedings for issuance of manufacturing licenses.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... should be issued as proposed by the NRC's Director, Office of New Reactors or Director, Office of Nuclear Reactor Regulation, as appropriate. [73 FR 5724, Jan. 31, 2008] ... manufacturing licenses. 51.105a Section 51.105a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL...

  12. 78 FR 9745 - Kewaunee Power Station; Application for Amendment to Facility Operating License

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-02-11

    ... FURTHER INFORMATION CONTACT: Karl Feintuch, Project Manager, Office of Nuclear Reactor Regulation, U.S... Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2013-03037 Filed 2-8-13; 8:45 am] BILLING CODE... NUCLEAR REGULATORY COMMISSION [Docket No. 50-305; NRC-2013-0028] Kewaunee Power Station...

  13. 10 CFR 51.105a - Public hearings in proceedings for issuance of manufacturing licenses.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... should be issued as proposed by the NRC's Director, Office of New Reactors or Director, Office of Nuclear Reactor Regulation, as appropriate. [73 FR 5724, Jan. 31, 2008] ... manufacturing licenses. 51.105a Section 51.105a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL...

  14. 10 CFR 51.105a - Public hearings in proceedings for issuance of manufacturing licenses.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... should be issued as proposed by the NRC's Director, Office of New Reactors or Director, Office of Nuclear Reactor Regulation, as appropriate. [73 FR 5724, Jan. 31, 2008] ... manufacturing licenses. 51.105a Section 51.105a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL...

  15. 10 CFR 51.105a - Public hearings in proceedings for issuance of manufacturing licenses.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... should be issued as proposed by the NRC's Director, Office of New Reactors or Director, Office of Nuclear Reactor Regulation, as appropriate. [73 FR 5724, Jan. 31, 2008] ... manufacturing licenses. 51.105a Section 51.105a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL...

  16. 10 CFR 51.105a - Public hearings in proceedings for issuance of manufacturing licenses.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... should be issued as proposed by the NRC's Director, Office of New Reactors or Director, Office of Nuclear Reactor Regulation, as appropriate. [73 FR 5724, Jan. 31, 2008] ... manufacturing licenses. 51.105a Section 51.105a Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL...

  17. 10 CFR 171.3 - Scope.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... holding an operating license for a power reactor, test reactor or research reactor issued under part 50 of... authorizes operation of a power reactor. The regulations in this part also apply to any person holding a...

  18. 76 FR 23339 - Notice of Issuance of License Amendment Regarding Decommission Plan Approval; University of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-04-26

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-113; NRC-2009-0549] Notice of Issuance of License Amendment Regarding Decommission Plan Approval; University of Arizona Research Reactor The U.S. Nuclear... located within the University of Arizona Nuclear Reactor Laboratory (NRL) on the 325-acre campus of the...

  19. 75 FR 58447 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Plant...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-24

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Plant License Renewal The ACRS Subcommittee on Plant License Renewal will hold a meeting on..., ``Generic Aging Lessons Learned (GALL) Report.'' The Subcommittee will hear presentations by and hold...

  20. 10 CFR 50.43 - Additional standards and provisions affecting class 103 licenses and certifications for...

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Additional standards and provisions affecting class 103... Regulatory Approvals § 50.43 Additional standards and provisions affecting class 103 licenses and... propose nuclear reactor designs which differ significantly from light-water reactor designs that were...

  1. 10 CFR 50.43 - Additional standards and provisions affecting class 103 licenses and certifications for...

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Additional standards and provisions affecting class 103... Regulatory Approvals § 50.43 Additional standards and provisions affecting class 103 licenses and... propose nuclear reactor designs which differ significantly from light-water reactor designs that were...

  2. 10 CFR 50.43 - Additional standards and provisions affecting class 103 licenses and certifications for...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 1 2013-01-01 2013-01-01 false Additional standards and provisions affecting class 103... Regulatory Approvals § 50.43 Additional standards and provisions affecting class 103 licenses and... propose nuclear reactor designs which differ significantly from light-water reactor designs that were...

  3. 10 CFR 50.43 - Additional standards and provisions affecting class 103 licenses and certifications for...

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Additional standards and provisions affecting class 103... Regulatory Approvals § 50.43 Additional standards and provisions affecting class 103 licenses and... propose nuclear reactor designs which differ significantly from light-water reactor designs that were...

  4. 10 CFR 52.91 - Authorization to conduct limited work authorization activities.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... determination required by 10 CFR 50.10(e), and the Director of New Reactors or the Director of Nuclear Reactor... activities. 52.91 Section 52.91 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Combined Licenses § 52.91 Authorization to conduct limited work...

  5. 76 FR 62095 - Exelon Generation Company, LLC; Notice of Withdrawal of Application for Amendment to Facility...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-06

    ... Licensing Branch III-2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-373 and 50-374; NRC-2011-0234] Exelon Generation.... Nuclear Regulatory Commission (NRC, the Commission) has granted the request of Exelon Generation Company...

  6. 10 CFR 52.91 - Authorization to conduct limited work authorization activities.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... determination required by 10 CFR 50.10(e), and the Director of New Reactors or the Director of Nuclear Reactor... activities. 52.91 Section 52.91 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Combined Licenses § 52.91 Authorization to conduct limited work...

  7. 10 CFR 52.91 - Authorization to conduct limited work authorization activities.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... determination required by 10 CFR 50.10(e), and the Director of New Reactors or the Director of Nuclear Reactor... activities. 52.91 Section 52.91 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Combined Licenses § 52.91 Authorization to conduct limited work...

  8. 10 CFR 52.91 - Authorization to conduct limited work authorization activities.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... determination required by 10 CFR 50.10(e), and the Director of New Reactors or the Director of Nuclear Reactor... activities. 52.91 Section 52.91 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Combined Licenses § 52.91 Authorization to conduct limited work...

  9. 10 CFR 52.91 - Authorization to conduct limited work authorization activities.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... determination required by 10 CFR 50.10(e), and the Director of New Reactors or the Director of Nuclear Reactor... activities. 52.91 Section 52.91 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Combined Licenses § 52.91 Authorization to conduct limited work...

  10. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Soubies, B.; Henry, J.Y.; Le Meur, M.

    1300 MWe pressurised water reactors (PWRs), like the 1400 MWe reactors, operate with microprocessor-based safety systems. This is particularly the case for the Digital Integrated Protection System (SPIN), which trips the reactor in an emergency and sets in action the safeguard functions. The softwares used in these systems must therefore be highly dependable in the execution of their functions. In the case of SPIN, three players are working at different levels to achieve this goal: the protection system manufacturer, Merlin Gerin; the designer of the nuclear steam supply system, Framatome; the operator of the nuclear power plants, Electricite de Francemore » (EDF), which is also responsible for the safety of its installations. Regulatory licenses are issued by the French safety authority, the Nuclear Installations Safety Directorate (French abbreviation DSIN), subsequent to a successful examination of the technical provisions adopted by the operator. This examination is carried out by the IPSN and the standing group on nuclear reactors. This communication sets out: the methods used by the manufacturer to develop SPIN software for the 1400 MWe PWRs (N4 series); the approach adopted by the IPSN to evaluate the safety software of the protection system for the N4 series of reactors.« less

  11. 10 CFR 52.167 - Issuance of manufacturing license.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... proposed reactor(s) can be incorporated into a nuclear power plant and operated at sites having... design and manufacture the proposed nuclear power reactor(s); (5) The proposed inspections, tests... the construction of a nuclear power facility using the manufactured reactor(s). (2) A holder of a...

  12. Disposition of Chicago Pile 5 (CP-5) Converter Tubes in the 10-160B Cask

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Pancake, Daniel C.; Rock, Cynthia

    This paper will focus on the unique characterization, packaging, and transportation issues associated with the disposition of the two CP-5 Converter Tube assemblies from Argonne National Laboratory. The converter tubes were constructed of combinations of HEU and alloys of zirconium, and were part of the original research facilities attached to the CP-5 reactor during operating evolutions. These assemblies were heavily irradiated during their operational lifetime, and were segregated from the balance of irradiated test specimens when the reactor was deactivated and slated for Decontamination and Demolition (D&D). In addition, the substantial contribution of fissile material to the assemblies’ inventory mademore » the potential disposition pathways extremely challenging. As a result, these items became part of Argonne’s legacy “nuclear footprint”, and were added to the Nuclear Footprint Reduction Project scope for disposition. The Project was responsible for the size reduction and characterization of these items, as well as the ultimate disposition. After negotiating a disposal pathway for these tubes, there were significant transportation issues that required a small team to overcome, in order to successfully ship these items to the Nevada National Security Site (NNSS). The Project team at Argonne, technical support from transportation specialists, licensing support from the 10-160B license owner, the Savanah River National Lab (SRNL) Packaging Certification Team (PCT, and the DOE EM-33 staff contributed to license and safety analysis report amendments that eventually authorized the shipment of the material. The paper will identify the organizations, and the specific actions, required to successfully make three “one of a kind” shipments of irradiated test specimen material. This will include the unique packaging configurations, contents modification for the cask license (via the Amendment process), criticality evaluations, and associated review and approval processes.« less

  13. 77 FR 39521 - Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-07-03

    ... Methodology for Boiling Water Reactors, June 2011. To support use of Topical Report ANP-10307PA, Revision 0... the NRC's E-Filing system does not support unlisted software, and the NRC Meta System Help Desk will... Water Reactors with AREVA Topical Report ANP- 10307PA, Revision 0, ``AREVA MCPR Safety Limit Methodology...

  14. 77 FR 58590 - Determining Technical Adequacy of Probabilistic Risk Assessment for Risk-Informed License...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-09-21

    ... reactors or for activities associated with review of applications for early site permits and combined licenses (COL) for the Office of New Reactors (NRO). DATES: The effective date of this SRP update is... Rulemaking Web Site: Go to http://www.regulations.gov and search for Docket ID NRC-2010-0138. Address...

  15. 10 CFR 2.621 - Acceptance and docketing of application for early review of site suitability issues in a combined...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF ORDERS Additional... Issuance of Limited Work Authorizations Early Partial Decisions on Site Suitability-Combined License Under... Director of the Office of New Reactors or the Director of the Office of Nuclear Reactor Regulation, as...

  16. 77 FR 27487 - License Amendment Request From The State University of New York, University of Buffalo Reactor...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-10

    ... State University of New York, University of Buffalo Reactor Facility AGENCY: Nuclear Regulatory... staff at 1-800-397-4209, 301-415- 4737, or by email to [email protected] . The University of Buffalo... license amendment application from the State University of New York, University of Buffalo requesting...

  17. 10 CFR 2.629 - Finality of partial decision on site suitability issues in a combined license proceeding.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... complete and acceptable for docketing under § 2.101(a)(3), the Director of the Office of New Reactors or the Director of the Office of Nuclear Reactor Regulation, as appropriate, shall determine whether the... a combined license proceeding. 2.629 Section 2.629 Energy NUCLEAR REGULATORY COMMISSION RULES OF...

  18. 10 CFR 2.629 - Finality of partial decision on site suitability issues in a combined license proceeding.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... complete and acceptable for docketing under § 2.101(a)(3), the Director of the Office of New Reactors or the Director of the Office of Nuclear Reactor Regulation, as appropriate, shall determine whether the... a combined license proceeding. 2.629 Section 2.629 Energy NUCLEAR REGULATORY COMMISSION RULES OF...

  19. Code qualification of structural materials for AFCI advanced recycling reactors.

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Natesan, K.; Li, M.; Majumdar, S.

    2012-05-31

    This report summarizes the further findings from the assessments of current status and future needs in code qualification and licensing of reference structural materials and new advanced alloys for advanced recycling reactors (ARRs) in support of Advanced Fuel Cycle Initiative (AFCI). The work is a combined effort between Argonne National Laboratory (ANL) and Oak Ridge National Laboratory (ORNL) with ANL as the technical lead, as part of Advanced Structural Materials Program for AFCI Reactor Campaign. The report is the second deliverable in FY08 (M505011401) under the work package 'Advanced Materials Code Qualification'. The overall objective of the Advanced Materials Codemore » Qualification project is to evaluate key requirements for the ASME Code qualification and the Nuclear Regulatory Commission (NRC) approval of structural materials in support of the design and licensing of the ARR. Advanced materials are a critical element in the development of sodium reactor technologies. Enhanced materials performance not only improves safety margins and provides design flexibility, but also is essential for the economics of future advanced sodium reactors. Code qualification and licensing of advanced materials are prominent needs for developing and implementing advanced sodium reactor technologies. Nuclear structural component design in the U.S. must comply with the ASME Boiler and Pressure Vessel Code Section III (Rules for Construction of Nuclear Facility Components) and the NRC grants the operational license. As the ARR will operate at higher temperatures than the current light water reactors (LWRs), the design of elevated-temperature components must comply with ASME Subsection NH (Class 1 Components in Elevated Temperature Service). However, the NRC has not approved the use of Subsection NH for reactor components, and this puts additional burdens on materials qualification of the ARR. In the past licensing review for the Clinch River Breeder Reactor Project (CRBRP) and the Power Reactor Innovative Small Module (PRISM), the NRC/Advisory Committee on Reactor Safeguards (ACRS) raised numerous safety-related issues regarding elevated-temperature structural integrity criteria. Most of these issues remained unresolved today. These critical licensing reviews provide a basis for the evaluation of underlying technical issues for future advanced sodium-cooled reactors. Major materials performance issues and high temperature design methodology issues pertinent to the ARR are addressed in the report. The report is organized as follows: the ARR reference design concepts proposed by the Argonne National Laboratory and four industrial consortia were reviewed first, followed by a summary of the major code qualification and licensing issues for the ARR structural materials. The available database is presented for the ASME Code-qualified structural alloys (e.g. 304, 316 stainless steels, 2.25Cr-1Mo, and mod.9Cr-1Mo), including physical properties, tensile properties, impact properties and fracture toughness, creep, fatigue, creep-fatigue interaction, microstructural stability during long-term thermal aging, material degradation in sodium environments and effects of neutron irradiation for both base metals and weld metals. An assessment of modified versions of Type 316 SS, i.e. Type 316LN and its Japanese version, 316FR, was conducted to provide a perspective for codification of 316LN or 316FR in Subsection NH. Current status and data availability of four new advanced alloys, i.e. NF616, NF616+TMT, NF709, and HT-UPS, are also addressed to identify the R&D needs for their code qualification for ARR applications. For both conventional and new alloys, issues related to high temperature design methodology are described to address the needs for improvements for the ARR design and licensing. Assessments have shown that there are significant data gaps for the full qualification and licensing of the ARR structural materials. Development and evaluation of structural materials require a variety of experimental facilities that have been seriously degraded in the past. The availability and additional needs for the key experimental facilities are summarized at the end of the report. Detailed information covered in each Chapter is given.« less

  20. 78 FR 35990 - All Operating Boiling-Water Reactor Licensees With Mark I And Mark II Containments; Docket Nos...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-14

    ... NUCLEAR REGULATORY COMMISSION [NRC-2013-0128] All Operating Boiling-Water Reactor Licensees With Mark I And Mark II Containments; Docket Nos. (As Shown In Attachment 1), License Nos. (As Shown In Attachment 1), EA-13-109; Order Modifying Licenses With Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident...

  1. 10 CFR 2.629 - Finality of partial decision on site suitability issues in a combined license proceeding.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ...), the Director of the Office of New Reactors or the Director of the Office of Nuclear Reactor Regulation... 10 Energy 1 2014-01-01 2014-01-01 false Finality of partial decision on site suitability issues in a combined license proceeding. 2.629 Section 2.629 Energy NUCLEAR REGULATORY COMMISSION AGENCY RULES...

  2. 10 CFR 2.629 - Finality of partial decision on site suitability issues in a combined license proceeding.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ...), the Director of the Office of New Reactors or the Director of the Office of Nuclear Reactor Regulation... 10 Energy 1 2013-01-01 2013-01-01 false Finality of partial decision on site suitability issues in a combined license proceeding. 2.629 Section 2.629 Energy NUCLEAR REGULATORY COMMISSION AGENCY RULES...

  3. 10 CFR 52.98 - Finality of combined licenses; information requests.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... condition of the combined license, the design of the facility, the inspections, tests, analyses, and acceptance criteria contained in the license which are not derived from a referenced standard design... chapter, as applicable. (b) If the combined license does not reference a design certification or a reactor...

  4. 10 CFR 52.98 - Finality of combined licenses; information requests.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... condition of the combined license, the design of the facility, the inspections, tests, analyses, and acceptance criteria contained in the license which are not derived from a referenced standard design... chapter, as applicable. (b) If the combined license does not reference a design certification or a reactor...

  5. 10 CFR 52.98 - Finality of combined licenses; information requests.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... condition of the combined license, the design of the facility, the inspections, tests, analyses, and acceptance criteria contained in the license which are not derived from a referenced standard design... chapter, as applicable. (b) If the combined license does not reference a design certification or a reactor...

  6. 10 CFR 52.98 - Finality of combined licenses; information requests.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... condition of the combined license, the design of the facility, the inspections, tests, analyses, and acceptance criteria contained in the license which are not derived from a referenced standard design... chapter, as applicable. (b) If the combined license does not reference a design certification or a reactor...

  7. 10 CFR 52.98 - Finality of combined licenses; information requests.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... condition of the combined license, the design of the facility, the inspections, tests, analyses, and acceptance criteria contained in the license which are not derived from a referenced standard design... chapter, as applicable. (b) If the combined license does not reference a design certification or a reactor...

  8. 10 CFR 2.1327 - Application for a stay of the effectiveness of NRC staff action on license transfer.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... action on license transfer. 2.1327 Section 2.1327 Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF ORDERS Procedures for Hearings on License Transfer Applications § 2.1327 Application for a stay of the effectiveness of NRC staff action on license transfer. (a...

  9. 10 CFR 2.1327 - Application for a stay of the effectiveness of NRC staff action on license transfer.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... action on license transfer. 2.1327 Section 2.1327 Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF ORDERS Procedures for Hearings on License Transfer Applications § 2.1327 Application for a stay of the effectiveness of NRC staff action on license transfer. (a...

  10. 10 CFR 100.3 - Definitions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... COMMISSION (CONTINUED) REACTOR SITE CRITERIA § 100.3 Definitions. As used in this part: Combined license... power facilities. Exclusion area means that area surrounding the reactor, in which the reactor licensee.... Activities unrelated to operation of the reactor may be permitted in an exclusion area under appropriate...

  11. 10 CFR 100.3 - Definitions.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... COMMISSION (CONTINUED) REACTOR SITE CRITERIA § 100.3 Definitions. As used in this part: Combined license... power facilities. Exclusion area means that area surrounding the reactor, in which the reactor licensee.... Activities unrelated to operation of the reactor may be permitted in an exclusion area under appropriate...

  12. 5 CFR 5801.102 - Prohibited securities.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... licenses for facilities which generate electric energy by means of a nuclear reactor; (2) State or local... reactor or a low-level waste facility; (3) Entities manufacturing or selling nuclear power or test reactors; (4) Architectural-engineering companies providing services relating to a nuclear power reactor...

  13. 5 CFR 5801.102 - Prohibited securities.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... licenses for facilities which generate electric energy by means of a nuclear reactor; (2) State or local... reactor or a low-level waste facility; (3) Entities manufacturing or selling nuclear power or test reactors; (4) Architectural-engineering companies providing services relating to a nuclear power reactor...

  14. Implementation Plan for Qualification of Sodium-Cooled Fast Reactor Technology Information

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Moe, Wayne; Honma, George

    This document identifies and discusses implementation elements that can be used to facilitate consistent and systematic evaluation processes relating to quality attributes of technical information (with focus on SFR technology) that will be used to support licensing of advanced reactor designs. Information may include, but is not limited to, design documents for SFRs, research-and-development (R&D) data and associated documents, test plans and associated protocols, operations and test data, international research data, technical reports, and information associated with past U.S. Nuclear Regulatory Commission (NRC) reviews of SFR designs. The approach for determining acceptability of test data, analysis, and/or other technical informationmore » is based on guidance provided in INL/EXT-15-35805, “Guidance on Evaluating Historic Technology Information for Use in Advanced Reactor Licensing.” The implementation plan can be adopted into a working procedure at each of the national laboratories performing data qualification, or by applicants seeking future license application for advanced reactor technology.« less

  15. 10 CFR 73.60 - Additional requirements for physical protection at nonpower reactors.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... nonpower reactors. 73.60 Section 73.60 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION... requirements for physical protection at nonpower reactors. Each nonpower reactor licensee who, pursuant to the... nonpower reactors licensed to operate at or above a power level of 2 megawatts thermal. [38 FR 35430, Dec...

  16. 10 CFR 73.60 - Additional requirements for physical protection at nonpower reactors.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... nonpower reactors. 73.60 Section 73.60 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION... requirements for physical protection at nonpower reactors. Each nonpower reactor licensee who, pursuant to the... nonpower reactors licensed to operate at or above a power level of 2 megawatts thermal. [38 FR 35430, Dec...

  17. A summary of the results from the DOE advanced gas reactor (AGR) fuel development and qualification program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Petti, David Andrew

    2017-04-01

    Modular high temperature gas-cooled reactor (HTGR) designs were developed to provide natural safety, which prevents core damage under all licensing basis events. The principle that guides their design concepts is to passively maintain core temperatures below fission product release thresholds under all accident scenarios. The required level of fuel performance and fission product retention reduces the radioactive source term by many orders of magnitude relative to source terms for other reactor types and allows a graded approach to emergency planning and the potential elimination of the need for evacuation and sheltering beyond a small exclusion area. Achieving this level, however,more » is predicated on exceptionally high coated-particle fuel fabrication quality and excellent performance under normal operation and accident conditions. The design goal of modular HTGRs is to meet the Environmental Protection Agency (EPA) Protective Action Guides (PAGs) for offsite dose at the Exclusion Area Boundary (EAB). To achieve this, the reactor design concepts require a level of fuel integrity that is far better than that achieved for all prior U.S.-manufactured tristructural isotropic (TRISO) coated particle fuel.« less

  18. 10 CFR 140.11 - Amounts of financial protection for certain reactors.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ...,000,000 for each nuclear reactor he is authorized to operate at a thermal power level not exceeding ten kilowatts; (2) In the amount of $1,500,000 for each nuclear reactor he is authorized to operate at... amount of $2,500,000 for each nuclear reactor other than a testing reactor or a reactor licensed under...

  19. 10 CFR 140.11 - Amounts of financial protection for certain reactors.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ...,000,000 for each nuclear reactor he is authorized to operate at a thermal power level not exceeding ten kilowatts; (2) In the amount of $1,500,000 for each nuclear reactor he is authorized to operate at... amount of $2,500,000 for each nuclear reactor other than a testing reactor or a reactor licensed under...

  20. 10 CFR 140.11 - Amounts of financial protection for certain reactors.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ...,000,000 for each nuclear reactor he is authorized to operate at a thermal power level not exceeding ten kilowatts; (2) In the amount of $1,500,000 for each nuclear reactor he is authorized to operate at... amount of $2,500,000 for each nuclear reactor other than a testing reactor or a reactor licensed under...

  1. 77 FR 63897 - Notice of License Terminations for National Aeronautics and Space Administration; Plum Brook...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-17

    ... test reactor, constructed to perform irradiation testing of fueled and unfueled experiments for space... constructed to test ``mock-up'' irradiation components for the Plum Brook Reactor. The reactors operated from...

  2. 10 CFR 171.21 - [Reserved

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false [Reserved] 171.21 Section 171.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) ANNUAL FEES FOR REACTOR LICENSES AND FUEL CYCLE LICENSES AND MATERIALS LICENSES, INCLUDING HOLDERS OF CERTIFICATES OF COMPLIANCE, REGISTRATIONS, AND QUALITY ASSURANCE PROGRAM APPROVALS AND...

  3. 78 FR 71675 - Update of the Office of Nuclear Reactor Regulation's Electronic Operating Reactor Correspondence

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-11-29

    ... correspondence to addressees and subscribers through a computer-based email distribution system. Since then, the... Electronic Operating Reactor Correspondence The U.S. Nuclear Regulatory Commission (NRC) is issuing this... available operating reactor licensing correspondence, effective December 9, 2013. Official agency records...

  4. 10 CFR 73.58 - Safety/security interface requirements for nuclear power reactors.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Safety/security interface requirements for nuclear power reactors. 73.58 Section 73.58 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF... requirements for nuclear power reactors. (a) Each operating nuclear power reactor licensee with a license...

  5. 10 CFR 73.58 - Safety/security interface requirements for nuclear power reactors.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Safety/security interface requirements for nuclear power reactors. 73.58 Section 73.58 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF... requirements for nuclear power reactors. (a) Each operating nuclear power reactor licensee with a license...

  6. 10 CFR 73.58 - Safety/security interface requirements for nuclear power reactors.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Safety/security interface requirements for nuclear power reactors. 73.58 Section 73.58 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF... requirements for nuclear power reactors. (a) Each operating nuclear power reactor licensee with a license...

  7. 10 CFR 73.58 - Safety/security interface requirements for nuclear power reactors.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Safety/security interface requirements for nuclear power reactors. 73.58 Section 73.58 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF... requirements for nuclear power reactors. (a) Each operating nuclear power reactor licensee with a license...

  8. 10 CFR 73.58 - Safety/security interface requirements for nuclear power reactors.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Safety/security interface requirements for nuclear power reactors. 73.58 Section 73.58 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) PHYSICAL PROTECTION OF... requirements for nuclear power reactors. (a) Each operating nuclear power reactor licensee with a license...

  9. 10 CFR 140.72 - Indemnity agreements.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... (issued pursuant to part 50 of this chapter) authorizing the licensee to operate the nuclear reactor... the licensee to possess and store special nuclear material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after issuance of an operating license for the reactor...

  10. 10 CFR 140.72 - Indemnity agreements.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... (issued pursuant to part 50 of this chapter) authorizing the licensee to operate the nuclear reactor... the licensee to possess and store special nuclear material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after issuance of an operating license for the reactor...

  11. 10 CFR 171.9 - Communications.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Communications. 171.9 Section 171.9 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) ANNUAL FEES FOR REACTOR LICENSES AND FUEL CYCLE LICENSES AND MATERIALS... APPROVALS AND GOVERNMENT AGENCIES LICENSED BY THE NRC § 171.9 Communications. All communications concerning...

  12. 10 CFR 171.9 - Communications.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Communications. 171.9 Section 171.9 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) ANNUAL FEES FOR REACTOR LICENSES AND FUEL CYCLE LICENSES AND MATERIALS... APPROVALS AND GOVERNMENT AGENCIES LICENSED BY THE NRC § 171.9 Communications. All communications concerning...

  13. 10 CFR 171.9 - Communications.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Communications. 171.9 Section 171.9 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) ANNUAL FEES FOR REACTOR LICENSES AND FUEL CYCLE LICENSES AND MATERIALS... APPROVALS AND GOVERNMENT AGENCIES LICENSED BY THE NRC § 171.9 Communications. All communications concerning...

  14. 10 CFR 52.171 - Finality of manufacturing licenses; information requests.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Finality of manufacturing licenses; information requests. 52.171 Section 52.171 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND... manufactured reactor, the costs and benefits of severe accident mitigation design alternatives, and the bases...

  15. 10 CFR 52.171 - Finality of manufacturing licenses; information requests.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Finality of manufacturing licenses; information requests. 52.171 Section 52.171 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND... manufactured reactor, the costs and benefits of severe accident mitigation design alternatives, and the bases...

  16. 10 CFR 52.171 - Finality of manufacturing licenses; information requests.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Finality of manufacturing licenses; information requests. 52.171 Section 52.171 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND... manufactured reactor, the costs and benefits of severe accident mitigation design alternatives, and the bases...

  17. 10 CFR 52.171 - Finality of manufacturing licenses; information requests.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Finality of manufacturing licenses; information requests. 52.171 Section 52.171 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND... manufactured reactor, the costs and benefits of severe accident mitigation design alternatives, and the bases...

  18. ReactorHealth Physics operations at the NIST center for neutron research.

    PubMed

    Johnston, Thomas P

    2015-02-01

    Performing health physics and radiation safety functions under a special nuclear material license and a research and test reactor license at a major government research and development laboratory encompasses many elements not encountered by industrial, general, or broad scope licenses. This article reviews elements of the health physics and radiation safety program at the NIST Center for Neutron Research, including the early history and discovery of the neutron, applications of neutron research, reactor overview, safety and security of radiation sources and radioactive material, and general health physics procedures. These comprise precautions and control of tritium, training program, neutron beam sample processing, laboratory audits, inventory and leak tests, meter calibration, repair and evaluation, radioactive waste management, and emergency response. In addition, the radiation monitoring systems will be reviewed including confinement building monitoring, ventilation filter radiation monitors, secondary coolant monitors, gaseous fission product monitors, gas monitors, ventilation tritium monitor, and the plant effluent monitor systems.

  19. 10 CFR 50.36a - Technical specifications on effluents from nuclear power reactors.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... reactors. 50.36a Section 50.36a Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND...; Ineligibility of Certain Applicants § 50.36a Technical specifications on effluents from nuclear power reactors..., including expected occurrences, as low as is reasonably achievable, each licensee of a nuclear power reactor...

  20. 10 CFR 1.44 - Office of New Reactors.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Office of New Reactors. 1.44 Section 1.44 Energy NUCLEAR... Office of New Reactors. The Office of New Reactors— (a) Develops, promulgates and implements regulations... safeguarding of nuclear reactor facilities licensed under part 52 of this chapter prior to initial commencement...

  1. 10 CFR 50.36a - Technical specifications on effluents from nuclear power reactors.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... reactors. 50.36a Section 50.36a Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND...; Ineligibility of Certain Applicants § 50.36a Technical specifications on effluents from nuclear power reactors..., including expected occurrences, as low as is reasonably achievable, each licensee of a nuclear power reactor...

  2. 10 CFR 1.44 - Office of New Reactors.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Office of New Reactors. 1.44 Section 1.44 Energy NUCLEAR... Office of New Reactors. The Office of New Reactors— (a) Develops, promulgates and implements regulations... safeguarding of nuclear reactor facilities licensed under part 52 of this chapter prior to initial commencement...

  3. 10 CFR 50.36a - Technical specifications on effluents from nuclear power reactors.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... reactors. 50.36a Section 50.36a Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND...; Ineligibility of Certain Applicants § 50.36a Technical specifications on effluents from nuclear power reactors..., including expected occurrences, as low as is reasonably achievable, each licensee of a nuclear power reactor...

  4. 10 CFR 1.44 - Office of New Reactors.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 1 2013-01-01 2013-01-01 false Office of New Reactors. 1.44 Section 1.44 Energy NUCLEAR... safeguarding of nuclear reactor facilities licensed under part 52 of this chapter prior to initial commencement... Office of New Reactors. The Office of New Reactors— (a) Develops, promulgates and implements regulations...

  5. 10 CFR 1.44 - Office of New Reactors.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Office of New Reactors. 1.44 Section 1.44 Energy NUCLEAR... safeguarding of nuclear reactor facilities licensed under part 52 of this chapter prior to initial commencement... Office of New Reactors. The Office of New Reactors— (a) Develops, promulgates and implements regulations...

  6. 10 CFR 1.44 - Office of New Reactors.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Office of New Reactors. 1.44 Section 1.44 Energy NUCLEAR... safeguarding of nuclear reactor facilities licensed under part 52 of this chapter prior to initial commencement... Office of New Reactors. The Office of New Reactors— (a) Develops, promulgates and implements regulations...

  7. 10 CFR 55.5 - Communications.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    .... Nuclear Regulatory Commission, Washington, DC 20555-0001. The guidance discusses, among other topics, the.... (b)(1) Except for test and research reactor facilities, the Director, Office of Nuclear Reactor... involving a test and research reactor facility licensed under 10 CFR part 50 and any related inquiry...

  8. 10 CFR 55.5 - Communications.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    .... Nuclear Regulatory Commission, Washington, DC 20555-0001. The guidance discusses, among other topics, the.... (b)(1) Except for test and research reactor facilities, the Director, Office of Nuclear Reactor... involving a test and research reactor facility licensed under 10 CFR part 50 and any related inquiry...

  9. 10 CFR 72.16 - Filing of application for specific license.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Filing of application for specific license. 72.16 Section 72.16 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C...

  10. 10 CFR 72.60 - Modification, revocation, and suspension of license.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Modification, revocation, and suspension of license. 72.60 Section 72.60 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C...

  11. 10 CFR 72.56 - Application for amendment of license.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Application for amendment of license. 72.56 Section 72.56 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE...

  12. 10 CFR 72.42 - Duration of license; renewal.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Duration of license; renewal. 72.42 Section 72.42 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE Issuance and...

  13. 10 CFR 72.40 - Issuance of license.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Issuance of license. 72.40 Section 72.40 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE Issuance and Conditions of...

  14. 10 CFR 72.16 - Filing of application for specific license.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Filing of application for specific license. 72.16 Section 72.16 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C...

  15. 78 FR 46255 - Revisions to Environmental Review for Renewal of Nuclear Power Plant Operating Licenses; Correction

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-31

    ... environmental effect of renewing the operating license of a nuclear power plant. This document is necessary to..., Environmental impact statement, Nuclear materials, Nuclear power plants and reactors, Reporting and... Environmental Review for Renewal of Nuclear Power Plant Operating Licenses; Correction AGENCY: Nuclear...

  16. 31 CFR 552.501 - General and specific licensing procedures.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... provisions relating to licensing procedures, see part 501, subpart E of this chapter. Licensing actions taken... actions taken pursuant to this part. General licenses and statements of licensing policy relating to this part also may be available through the Yemen sanctions page on OFAC's Web site: www.treasury.gov/ofac. ...

  17. 31 CFR 552.501 - General and specific licensing procedures.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... provisions relating to licensing procedures, see part 501, subpart E of this chapter. Licensing actions taken... actions taken pursuant to this part. General licenses and statements of licensing policy relating to this part also may be available through the Yemen sanctions page on OFAC's Web site: www.treasury.gov/ofac. ...

  18. 75 FR 76923 - Domestic Licensing of Production and Utilization Facilities; Updates to Incorporation by...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-10

    ..., Classified information, Criminal penalties, Fire protection, Intergovernmental relations, Nuclear power plants and reactors, Radiation protection, Reactor siting criteria, Reporting and recordkeeping...

  19. 10 CFR 55.5 - Communications.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    .... Nuclear Regulatory Commission, Washington, DC 20555-0001. The guidance discusses, among other topics, the.... (b)(1) Except for test and research reactor facilities, the Director, Office of Nuclear Reactor... this part involving a test and research reactor facility licensed under 10 CFR part 50 and any related...

  20. 10 CFR 2.1105 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... Nuclear Fuel Storage Capacity at Civilian Nuclear Power Reactors § 2.1105 Definitions. As used in this part: (a) Civilian nuclear power reactor means a civilian nuclear power plant required to be licensed... nuclear fuel means fuel that has been withdrawn from a nuclear reactor following irradiation, the...

  1. 10 CFR 2.1105 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... Nuclear Fuel Storage Capacity at Civilian Nuclear Power Reactors § 2.1105 Definitions. As used in this part: (a) Civilian nuclear power reactor means a civilian nuclear power plant required to be licensed... nuclear fuel means fuel that has been withdrawn from a nuclear reactor following irradiation, the...

  2. 10 CFR Appendix A to Part 52 - Design Certification Rule for the U.S. Advanced Boiling Water Reactor

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... Water Reactor A Appendix A to Part 52 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES... Rule for the U.S. Advanced Boiling Water Reactor I. Introduction Appendix A constitutes the standard design certification for the U.S. Advanced Boiling Water Reactor (ABWR) design, in accordance with 10 CFR...

  3. 10 CFR Appendix A to Part 52 - Design Certification Rule for the U.S. Advanced Boiling Water Reactor

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... Water Reactor A Appendix A to Part 52 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES... Rule for the U.S. Advanced Boiling Water Reactor I. Introduction Appendix A constitutes the standard design certification for the U.S. Advanced Boiling Water Reactor (ABWR) design, in accordance with 10 CFR...

  4. 10 CFR 50.64 - Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... domestic non-power reactors. 50.64 Section 50.64 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... Director of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC... Director of the Office of Nuclear Reactor Regulation a written proposal for meeting the requirements of...

  5. 10 CFR 50.64 - Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... domestic non-power reactors. 50.64 Section 50.64 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... Director of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC... Director of the Office of Nuclear Reactor Regulation a written proposal for meeting the requirements of...

  6. 10 CFR 50.64 - Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... domestic non-power reactors. 50.64 Section 50.64 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... Director of the Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC... Director of the Office of Nuclear Reactor Regulation a written proposal for meeting the requirements of...

  7. Operators in the Plum Brook Reactor Facility Control Room

    NASA Image and Video Library

    1970-03-21

    Donald Rhodes, left, and Clyde Greer, right, monitor the operation of the National Aeronautics and Space Administration’s (NASA) Plum Brook Reactor Facility from the control room. The 60-megawatt test reactor, NASA’s only reactor, was the eighth largest test reactor in the world. The facility was built by the Lewis Research Center in the late 1950s to study the effects of radiation on different materials that could be used to construct nuclear propulsion systems for aircraft or rockets. The reactor went critical for the first time in 1961. For the next two years, two operators were on duty 24 hours per day working on the fission process until the reactor reached its full-power level in 1963. Reactor Operators were responsible for monitoring and controlling the reactor systems. Once the reactor was running under normal operating conditions, the work was relatively uneventful. Normally the reactor was kept at a designated power level within certain limits. Occasionally the operators had to increase the power for a certain test. The shift supervisor and several different people would get together and discuss the change before boosting the power. All operators were required to maintain a Reactor Operator License from the Atomic Energy Commission. The license included six months of training, an eight-hour written exam, a four-hour walkaround, and testing on the reactor controls.

  8. 77 FR 69663 - Agency Information Collection Activities: Proposed Collection; Comment Request

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-11-20

    ... required or asked to report: Holders of and applicants for facility (i.e., nuclear power, non-power research and test reactor) operating licenses and individual operators; licenses. 5. The number of annual...

  9. 75 FR 27368 - Aerotest Operations, Inc., Aerotest Radiography and Research Reactor; Notice of Consideration of...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-05-14

    ...., Aerotest Radiography and Research Reactor; Notice of Consideration of Approval of Transfer and Conforming Amendment, Opportunity for a Hearing, and Order Imposing Procedures for Access to Sensitive Unclassified Non... Manager, Research and Test Reactors Licensing Branch, Division of Policy and Rulemaking, Office of Nuclear...

  10. 77 FR 41206 - Guidelines for Preparing and Reviewing Licensing Applications for Instrumentation and Control...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-07-12

    ... Applications for Instrumentation and Control Upgrades for Non-Power Reactors AGENCY: Nuclear Regulatory... (NRC or the Commission) is requesting public comment on Chapter 7, Section 7.3, Reactor Control System...-Power Reactors: Format and Content,'' for instrumentation and control (I&C) upgrades and NUREG-1537...

  11. 10 CFR 140.96 - Appendix F-Indemnity locations.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... construction area of the nuclear power reactor, as determined by the Commission. Such area will not necessarily... or combined license under 10 CFR part 52 is issued for such additional nuclear power reactors. (2) In... an existing nuclear power reactor, the geographical boundaries of the indemnity location shall...

  12. 77 FR 26050 - Burnup Credit in the Criticality Safety Analyses of Pressurized Water Reactor Spent Fuel in...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-02

    ... Pressurized Water Reactor Spent Fuel in Transportation and Storage Casks AGENCY: Nuclear Regulatory Commission... of pressurized water reactor spent nuclear fuel (SNF) in transportation packages and storage casks... for the licensing basis, (b) provide recommendations regarding advanced isotopic depletion and...

  13. 10 CFR 50.72 - Immediate notification requirements for operating nuclear power reactors.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Immediate notification requirements for operating nuclear power reactors. 50.72 Section 50.72 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... notification requirements for operating nuclear power reactors. (a) General requirements. 1 (1) Each nuclear...

  14. 10 CFR 50.44 - Combustible gas control for nuclear power reactors.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 1 2013-01-01 2013-01-01 false Combustible gas control for nuclear power reactors. 50.44 Section 50.44 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... for nuclear power reactors. (a) Definitions—(1) Inerted atmosphere means a containment atmosphere with...

  15. 10 CFR 50.44 - Combustible gas control for nuclear power reactors.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Combustible gas control for nuclear power reactors. 50.44 Section 50.44 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION... for nuclear power reactors. (a) Definitions—(1) Inerted atmosphere means a containment atmosphere with...

  16. 10 CFR 50.72 - Immediate notification requirements for operating nuclear power reactors.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 1 2013-01-01 2013-01-01 false Immediate notification requirements for operating nuclear power reactors. 50.72 Section 50.72 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... notification requirements for operating nuclear power reactors. (a) General requirements. 1 (1) Each nuclear...

  17. 75 FR 11375 - Revision of Fee Schedules; Fee Recovery for FY 2010

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-10

    ... Spent Fuel Storage/Reactor Decommissioning..... 2.7 0.2 0.2 Test and Research Reactors 0.2 0.0 0.0 Fuel... categories of licenses. The FY 2009 fee is also shown for comparative purposes. Table V--Rebaselined Annual...) Spent Fuel Storage/Reactor 122,000 143,000 Decommissioning Test and Research Reactors (Non-power 87,600...

  18. 10 CFR 50.64 - Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... domestic non-power reactors. 50.64 Section 50.64 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... Permits § 50.64 Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors. (a) Applicability. The requirements of this section apply to all non-power reactors. (b) Requirements. (1) The...

  19. 10 CFR 50.64 - Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... domestic non-power reactors. 50.64 Section 50.64 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF... Permits § 50.64 Limitations on the use of highly enriched uranium (HEU) in domestic non-power reactors. (a) Applicability. The requirements of this section apply to all non-power reactors. (b) Requirements. (1) The...

  20. Review Team Focused Modeling Analysis of Radial Collector Well Operation on the Hypersaline Groundwater Plume beneath the Turkey Point Site near Homestead, Florida

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Oostrom, Martinus; Vail, Lance W.

    Researchers at Pacific Northwest National Laboratory served as members of a U.S. Nuclear Regulatory Commission review team for the Florida Power & Light Company’s application for two combined construction permits and operating licenses (combined licenses or COLs) for two proposed new reactor units—Turkey Point Units 6 and 7. The review team evaluated the environmental impacts of the proposed action based on the October 29, 2014 revision of the COL application, including the Environmental Report, responses to requests for additional information, and supplemental information. As part of this effort, team members tasked with assessing the environmental effects of proposed construction andmore » operation of Units 6 and 7 at the Turkey Point site reviewed two separate modeling studies that analyzed the interaction between surface water and groundwater that would be altered by the operation of radial collector wells (RCWs) at the site. To further confirm their understanding of the groundwater hydrodynamics and to consider whether certain actions, proposed after the two earlier modeling studies were completed, would alter the earlier conclusions documented by the review team in their draft environmental impact statement (EIS; NRC 2015), a third modeling analysis was performed. The third modeling analysis is discussed in this report.« less

  1. 10 CFR 50.21 - Class 104 licenses; for medical therapy and research and development facilities.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Class 104 licenses; for medical therapy and research and...; for medical therapy and research and development facilities. A class 104 license will be issued, to an... Administration entered into under the Cooperative Power Reactor Demonstration Program, except as otherwise...

  2. 10 CFR 2.629 - Finality of partial decision on site suitability issues in a combined license proceeding.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... a combined license proceeding. 2.629 Section 2.629 Energy NUCLEAR REGULATORY COMMISSION RULES OF... Work Authorizations Early Partial Decisions on Site Suitability-Combined License Under 10 Cfr Part 52... complete and acceptable for docketing under § 2.101(a)(3), the Director of the Office of New Reactors or...

  3. 78 FR 4465 - PPL Bell Bend, LLC; Combined License Application for Bell Bend Nuclear Power Plant; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-22

    ... License Application for Bell Bend Nuclear Power Plant; Exemption 1.0 Background PPL Bell Bend, LLC... Regulations (10 CFR), Subpart C of Part 52, ``Licenses, Certifications, and Approvals for Nuclear Power Plants.'' This reactor is to be identified as Bell Bend Nuclear Power Plant (BBNPP), in Salem County...

  4. 31 CFR 560.501 - General and specific licensing procedures.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... chapter. Licensing actions taken pursuant to part 501 of this chapter with respect to the prohibitions contained in this part are considered actions taken pursuant to this part. General licenses and statements of licensing policy relating to this part also may be available through the Iran sanctions page on...

  5. 31 CFR 560.501 - General and specific licensing procedures.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... chapter. Licensing actions taken pursuant to part 501 of this chapter with respect to the prohibitions contained in this part are considered actions taken pursuant to this part. General licenses and statements of licensing policy relating to this part also may be available through the Iran sanctions page on...

  6. 31 CFR 558.501 - General and specific licensing procedures.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    .... Licensing actions taken pursuant to part 501 of this chapter with respect to the prohibitions contained in this part are considered actions taken pursuant to this part. General licenses and statements of licensing policy relating to this part also may be available through the South Sudan sanctions page on OFAC...

  7. 31 CFR 537.501 - General and specific licensing procedures.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    .... Licensing actions taken pursuant to part 501 of this chapter with respect to the prohibitions contained in this part are considered actions taken pursuant to this part. General licenses and statements of licensing policy relating to this part also may be available through the Burma sanctions page on OFAC's Web...

  8. 31 CFR 542.501 - General and specific licensing procedures.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    .... Licensing actions taken pursuant to part 501 of this chapter with respect to the prohibitions contained in this part are considered actions taken pursuant to this part. General licenses and statements of licensing policy relating to this part also may be available through the Syria sanctions page on OFAC's Web...

  9. 31 CFR 590.501 - General and specific licensing procedures.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... this chapter. Licensing actions taken pursuant to part 501 of this chapter with respect to the prohibitions contained in this part are considered actions taken pursuant to this part. General licenses and statements of licensing policy relating to this part also may be available through the following page on OFAC...

  10. 31 CFR 590.501 - General and specific licensing procedures.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    ... this chapter. Licensing actions taken pursuant to part 501 of this chapter with respect to the prohibitions contained in this part are considered actions taken pursuant to this part. General licenses and statements of licensing policy relating to this part also may be available through the following page on OFAC...

  11. 31 CFR 570.501 - General and specific licensing procedures.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    .... Licensing actions taken pursuant to part 501 of this chapter with respect to the prohibitions contained in this part are considered actions taken pursuant to this part. Additional general licenses and statements of licensing policy relating to this part may be available through the following page on OFAC's...

  12. 31 CFR 590.501 - General and specific licensing procedures.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    ... this chapter. Licensing actions taken pursuant to part 501 of this chapter with respect to the prohibitions contained in this part are considered actions taken pursuant to this part. General licenses and statements of licensing policy relating to this part also may be available through the following page on OFAC...

  13. 31 CFR 570.501 - General and specific licensing procedures.

    Code of Federal Regulations, 2012 CFR

    2012-07-01

    .... Licensing actions taken pursuant to part 501 of this chapter with respect to the prohibitions contained in this part are considered actions taken pursuant to this part. Additional general licenses and statements of licensing policy relating to this part may be available through the following page on OFAC's...

  14. 31 CFR 570.501 - General and specific licensing procedures.

    Code of Federal Regulations, 2013 CFR

    2013-07-01

    .... Licensing actions taken pursuant to part 501 of this chapter with respect to the prohibitions contained in this part are considered actions taken pursuant to this part. Additional general licenses and statements of licensing policy relating to this part may be available through the following page on OFAC's...

  15. 10 CFR 72.8 - Denial of licensing by Agreement States.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General... the storage of spent fuel and reactor-related GTCC waste in an ISFSI or the storage of spent fuel, high-level radioactive waste, and reactor-related GTCC waste in an MRS. [66 FR 51839, Oct. 11, 2001] ...

  16. 10 CFR 72.22 - Contents of application: General and financial information.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN... of spent fuel, high-level radioactive waste, and/or reactor-related GTCC waste from storage. (f) Each applicant for a license under this part to receive, transfer, and possess power reactor spent fuel, power...

  17. 10 CFR 52.141 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.141 Section 52.141 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... Committee on Reactor Safeguards (ACRS). The Commission shall refer a copy of the application to the ACRS...

  18. 10 CFR 52.87 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.87 Section 52.87 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... Reactor Safeguards (ACRS). The Commission shall refer a copy of the application to the ACRS. The ACRS...

  19. 10 CFR 52.53 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.53 Section 52.53 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... Committee on Reactor Safeguards (ACRS). The Commission shall refer a copy of the application to the ACRS...

  20. 10 CFR 52.165 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.165 Section 52.165 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... Committee on Reactor Safeguards (ACRS). The Commission shall refer a copy of the application to the ACRS...

  1. 10 CFR 52.23 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.23 Section 52.23 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... on Reactor Safeguards (ACRS). The Commission shall refer a copy of the application for an early site...

  2. 10 CFR 52.165 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.165 Section 52.165 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... Committee on Reactor Safeguards (ACRS). The Commission shall refer a copy of the application to the ACRS...

  3. 10 CFR 52.23 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.23 Section 52.23 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... on Reactor Safeguards (ACRS). The Commission shall refer a copy of the application for an early site...

  4. 10 CFR 52.87 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.87 Section 52.87 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... Reactor Safeguards (ACRS). The Commission shall refer a copy of the application to the ACRS. The ACRS...

  5. 10 CFR 52.141 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.141 Section 52.141 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... Committee on Reactor Safeguards (ACRS). The Commission shall refer a copy of the application to the ACRS...

  6. 10 CFR 2.809 - Participation by the Advisory Committee on Reactor Safeguards.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Participation by the Advisory Committee on Reactor Safeguards. 2.809 Section 2.809 Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF ORDERS Rulemaking § 2.809 Participation by the Advisory Committee on Reactor...

  7. 10 CFR 72.8 - Denial of licensing by Agreement States.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General... the storage of spent fuel and reactor-related GTCC waste in an ISFSI or the storage of spent fuel, high-level radioactive waste, and reactor-related GTCC waste in an MRS. [66 FR 51839, Oct. 11, 2001] ...

  8. 10 CFR 52.53 - Referral to the Advisory Committee on Reactor Safeguards (ACRS).

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Referral to the Advisory Committee on Reactor Safeguards (ACRS). 52.53 Section 52.53 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS... Committee on Reactor Safeguards (ACRS). The Commission shall refer a copy of the application to the ACRS...

  9. 76 FR 77021 - Notice of Availability of Combined License Applications

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-09

    ... searching on Docket ID NRC-2008-0170 (William States Lee III Nuclear Station Units 1 and 2), NRC-2008-0231...://www.nrc.gov/reactors/new-reactors/col.html . FOR FURTHER INFORMATION CONTACT: Donald Habib, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, telephone: (301) 415-1035...

  10. 76 FR 71608 - Notice of Availability of Combined License Applications

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-18

    ... searching on Docket ID NRC-2008-0170 (William States Lee III Nuclear Station Units 1 and 2), NRC-2008-0231...://www.nrc.gov/reactors/new-reactors/col.html . FOR FURTHER INFORMATION CONTACT: Donald Habib, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, telephone: (301) 415-1035...

  11. 76 FR 75566 - Notice of Availability of Combined License Applications

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-02

    ....regulations.gov by searching on Docket ID NRC-2008-0170 (William States Lee III Nuclear Station Units 1 and 2... available at http://www.nrc.gov/reactors/new-reactors/col.html . FOR FURTHER INFORMATION CONTACT: Donald Habib, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, telephone...

  12. 76 FR 72725 - Notice of Availability of Combined License Applications

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-25

    ... searching on Docket ID NRC-2008-0170 (William States Lee III Nuclear Station Units 1 and 2), NRC-2008-0231...://www.nrc.gov/reactors/new-reactors/col.html . FOR FURTHER INFORMATION CONTACT: Donald Habib, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, telephone: (301) 415-1035...

  13. 77 FR 42771 - License Renewal for the Dow Chemical TRIGA Research Reactor

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-07-20

    ... Chemical Company in Midland, MI and is a part of the Analytical Sciences Laboratory. The reactor is housed...-Radiological Impacts The Dow TRIGA Research Reactor core is cooled by a light water primary system consisting... provided by the volume of primary coolant allows several hours of full-power operation without any...

  14. 10 CFR 50.36a - Technical specifications on effluents from nuclear power reactors.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Technical specifications on effluents from nuclear power reactors. 50.36a Section 50.36a Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND...; Ineligibility of Certain Applicants § 50.36a Technical specifications on effluents from nuclear power reactors...

  15. 10 CFR 50.36a - Technical specifications on effluents from nuclear power reactors.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 1 2013-01-01 2013-01-01 false Technical specifications on effluents from nuclear power reactors. 50.36a Section 50.36a Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND...; Ineligibility of Certain Applicants § 50.36a Technical specifications on effluents from nuclear power reactors...

  16. 78 FR 63516 - Initial Test Program of Emergency Core Cooling Systems for New Boiling-Water Reactors

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-24

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0134] Initial Test Program of Emergency Core Cooling....79.1, ``Initial Test Program of Emergency Core Cooling Systems for New Boiling-Water Reactors.'' This... emergency core cooling systems (ECCSs) for boiling- water reactors (BWRs) whose licenses are issued after...

  17. 10 CFR 50.44 - Combustible gas control for nuclear power reactors.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Combustible gas control for nuclear power reactors. 50.44... FACILITIES Standards for Licenses, Certifications, and Regulatory Approvals § 50.44 Combustible gas control... capability for ensuring a mixed atmosphere. (2) Combustible gas control. (i) All boiling water reactors with...

  18. 10 CFR 50.44 - Combustible gas control for nuclear power reactors.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Combustible gas control for nuclear power reactors. 50.44... FACILITIES Standards for Licenses, Certifications, and Regulatory Approvals § 50.44 Combustible gas control... capability for ensuring a mixed atmosphere. (2) Combustible gas control. (i) All boiling water reactors with...

  19. 10 CFR 50.44 - Combustible gas control for nuclear power reactors.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 1 2012-01-01 2012-01-01 false Combustible gas control for nuclear power reactors. 50.44... FACILITIES Standards for Licenses, Certifications, and Regulatory Approvals § 50.44 Combustible gas control... capability for ensuring a mixed atmosphere. (2) Combustible gas control. (i) All boiling water reactors with...

  20. 10 CFR 2.340 - Initial decision in certain contested proceedings; immediate effectiveness of initial decisions...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... those matters, the Commission, the Director, Office of Nuclear Reactor Regulation or Director, Office of... Nuclear Reactor Regulation, as appropriate, after making the requisite findings, will issue, deny or... acceptance criteria in nuclear power reactor combined licenses. In any initial decision under § 52.103(g) of...

  1. 10 CFR 50.63 - Loss of all alternating current power.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... information defined below to the Director of the Office of Nuclear Reactor Regulation by April 17, 1989. For... Office of Nuclear Reactor Regulation, by 270 days after the date of license issuance. For each light... accordance with paragraph (c)(3) of this section, submit to the Director of the Office of Nuclear Reactor...

  2. 10 CFR 2.340 - Initial decision in certain contested proceedings; immediate effectiveness of initial decisions...

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... those matters, the Commission, the Director, Office of Nuclear Reactor Regulation or Director, Office of... Nuclear Reactor Regulation, as appropriate, after making the requisite findings, will issue, deny or... acceptance criteria in nuclear power reactor combined licenses. In any initial decision under § 52.103(g) of...

  3. 10 CFR 140.52 - Indemnity agreements.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ...) authorizing the licensee to operate the nuclear reactor involved; or (2) The effective date of the license... material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after... 10 Energy 2 2014-01-01 2014-01-01 false Indemnity agreements. 140.52 Section 140.52 Energy NUCLEAR...

  4. 10 CFR 50.63 - Loss of all alternating current power.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... information defined below to the Director of the Office of Nuclear Reactor Regulation by April 17, 1989. For... Office of Nuclear Reactor Regulation, by 270 days after the date of license issuance. For each light... accordance with paragraph (c)(3) of this section, submit to the Director of the Office of Nuclear Reactor...

  5. 10 CFR 50.63 - Loss of all alternating current power.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... information defined below to the Director of the Office of Nuclear Reactor Regulation by April 17, 1989. For... Office of Nuclear Reactor Regulation, by 270 days after the date of license issuance. For each light... accordance with paragraph (c)(3) of this section, submit to the Director of the Office of Nuclear Reactor...

  6. 10 CFR 140.52 - Indemnity agreements.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ...) authorizing the licensee to operate the nuclear reactor involved; or (2) The effective date of the license... material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after... 10 Energy 2 2010-01-01 2010-01-01 false Indemnity agreements. 140.52 Section 140.52 Energy NUCLEAR...

  7. 10 CFR 2.340 - Initial decision in certain contested proceedings; immediate effectiveness of initial decisions...

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... those matters, the Commission, the Director, Office of Nuclear Reactor Regulation or Director, Office of... Nuclear Reactor Regulation, as appropriate, after making the requisite findings, will issue, deny or... acceptance criteria in nuclear power reactor combined licenses. In any initial decision under § 52.103(g) of...

  8. 76 FR 11521 - Prairie Island Nuclear Generating Plant, Unit 1, Northern States Power Company-Minnesota; Notice...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-03-02

    ..., Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001..., Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2011-4557 Filed 3-1... NUCLEAR REGULATORY COMMISSION [Docket No. 50-282; NRC-2011-0040] Prairie Island Nuclear Generating...

  9. 10 CFR 50.63 - Loss of all alternating current power.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... information defined below to the Director of the Office of Nuclear Reactor Regulation by April 17, 1989. For... Office of Nuclear Reactor Regulation, by 270 days after the date of license issuance. For each light... accordance with paragraph (c)(3) of this section, submit to the Director of the Office of Nuclear Reactor...

  10. 77 FR 21592 - Guidelines for Preparing and Reviewing Licensing Applications for the Production of Radioisotopes

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-04-10

    ... Regulatory Commission. Jessie F. Quichocho, Chief, Research and Test Reactors Licensing Branch, Division of... information in comment submissions that you do not want to be publicly disclosed. The NRC posts all comment...

  11. 77 FR 14445 - Application for a License To Export Steel Forging

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-03-09

    ...) 415-1677, to request a digital ID certificate and allow for the creation of an electronic docket. In...Energy Nuclear Operating Co Reactor vessel One The reactor vessel Spain. December 15, 2011 head steel...

  12. 10 CFR 73.60 - Additional requirements for physical protection at nonpower reactors.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... nonpower reactors licensed to operate at or above a power level of 2 megawatts thermal. [38 FR 35430, Dec... OF PLANTS AND MATERIALS Physical Protection Requirements at Fixed Sites § 73.60 Additional...

  13. 10 CFR 73.60 - Additional requirements for physical protection at nonpower reactors.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... nonpower reactors licensed to operate at or above a power level of 2 megawatts thermal. [38 FR 35430, Dec... OF PLANTS AND MATERIALS Physical Protection Requirements at Fixed Sites § 73.60 Additional...

  14. 10 CFR 73.60 - Additional requirements for physical protection at nonpower reactors.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... nonpower reactors licensed to operate at or above a power level of 2 megawatts thermal. [38 FR 35430, Dec... OF PLANTS AND MATERIALS Physical Protection Requirements at Fixed Sites § 73.60 Additional...

  15. 10 CFR Appendix N to Part 50 - Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... FACILITIES Pt. 50, App.N Appendix N to Part 50—Standardization of Nuclear Power Plant Designs: Permits To..., apply to construction permits and operating licenses subject to this appendix N. 2. Applications for...

  16. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Grabaskas, David; Bucknor, Matthew; Jerden, James

    A mechanistic source term (MST) calculation attempts to realistically assess the transport and release of radionuclides from a reactor system to the environment during a specific accident sequence. The U.S. Nuclear Regulatory Commission (NRC) has repeatedly stated its expectation that advanced reactor vendors will utilize an MST during the U.S. reactor licensing process. As part of a project to examine possible impediments to sodium fast reactor (SFR) licensing in the U.S., an analysis was conducted regarding the current capabilities to perform an MST for a metal fuel SFR. The purpose of the project was to identify and prioritize any gapsmore » in current computational tools, and the associated database, for the accurate assessment of an MST. The results of the study demonstrate that an SFR MST is possible with current tools and data, but several gaps exist that may lead to possibly unacceptable levels of uncertainty, depending on the goals of the MST analysis.« less

  17. Health physics aspects of advanced reactor licensing reviews

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hinson, C.S.

    1995-03-01

    The last Construction Permit to be issued by the U.S. Nuclear Regulatory Commission (NRC) for a U.S. light water reactor (LWR) was granted in the late 1970s. In 1989 the NRC issued 10 CFR Part 52 which is intended to serve as a framework for the licensing of future reactor designs. The NRC is currently reviewing four different future on {open_quotes}next-generation{close_quotes} reactor designs. Two of these designs are classified as evolutionary designs (modified versions of current generation LWRs) and two are advanced designs (reactors incorporating simplified designs and passive means for accident mitigation). These {open_quotes}next-generation{close_quotes} reactor designs incorporate many innovativemore » design features which are intended to maintain personnel doses ALARA and ensure that the annual average collective dose at these reactors does not exceed 100 person-rems (1 person-sievert) per year. This paper discusses some of the ALARA design features which are incorporated in the four {open_quotes}next-generation{close_quotes} reactor designs incorporate many innovative design features which are intended to maintain personnel doses ALARA and ensure that the annual average collective dose at these reactors does not exceed 100 person-rems (1 person-sievert) per year. This paper discusses some of the ALARA design features which are incorporated in the four {open_quotes}next-generation{close_quotes} reactor designs currently being reviewed by the NRC.« less

  18. A Research Reactor Concept to Support NTP Development

    NASA Technical Reports Server (NTRS)

    Eades, Michael J.; Blue, T. E.; Gerrish, Harold P.; Hardin, Leroy A.

    2014-01-01

    In support of efforts for research into the design and development of man rated Nuclear Thermal Propulsion (NTP), the National Aeronautics and Space Administration (NASA), Marshall Space Flight Center (MSFC), is evaluating the potential for building a Nuclear Regulatory Commission (NRC) licensed NTP based research reactor (NTPRR). The proposed NTPRR would be licensed by NASA and operated jointly by NASA and university partners. The purpose of the NTPRR would be used to perform further research into the technologies and systems needed for a successful NTP project and promote nuclear training and education.

  19. 77 FR 73684 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-11

    ... interval extension is bounded by the 15 year ILRT Interval currently authorized within NEI [Nuclear Energy... following benefits: (1) Allows the plant to reach the all-rods-in condition prior to significant reactor...

  20. 76 FR 69296 - University of Utah, University of Utah TRIGA Nuclear Reactor, Notice of Issuance of Renewed...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-08

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-407, NRC-2011-0153] University of Utah, University of Utah TRIGA Nuclear Reactor, Notice of Issuance of Renewed Facility Operating License No. R-126 AGENCY... University of Utah (UU, the licensee), which authorizes continued operation of the UU TRIGA Nuclear Reactor...

  1. 10 CFR 50.69 - Risk-informed categorization and treatment of structures, systems and components for nuclear...

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ..., systems and components for nuclear power reactors. 50.69 Section 50.69 Energy NUCLEAR REGULATORY..., systems and components for nuclear power reactors. (a) Definitions. Risk-Informed Safety Class (RISC)-1... holder of a license to operate a light water reactor (LWR) nuclear power plant under this part; a holder...

  2. 10 CFR 50.69 - Risk-informed categorization and treatment of structures, systems and components for nuclear...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ..., systems and components for nuclear power reactors. 50.69 Section 50.69 Energy NUCLEAR REGULATORY..., systems and components for nuclear power reactors. (a) Definitions. Risk-Informed Safety Class (RISC)-1... holder of a license to operate a light water reactor (LWR) nuclear power plant under this part; a holder...

  3. 10 CFR 50.69 - Risk-informed categorization and treatment of structures, systems and components for nuclear...

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ..., systems and components for nuclear power reactors. 50.69 Section 50.69 Energy NUCLEAR REGULATORY..., systems and components for nuclear power reactors. (a) Definitions. Risk-Informed Safety Class (RISC)-1... holder of a license to operate a light water reactor (LWR) nuclear power plant under this part; a holder...

  4. 10 CFR 72.214 - List of approved spent fuel storage casks.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General License for Storage of Spent Fuel at Power Reactor Sites § 72.214 List of approved spent...

  5. 10 CFR 72.214 - List of approved spent fuel storage casks.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General License for Storage of Spent Fuel at Power Reactor Sites § 72.214 List of approved spent...

  6. 10 CFR 2.401 - Notice of hearing on construction permit or combined license applications pursuant to appendix N...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... pursuant to appendix N of part 50 of this chapter for construction permits for nuclear power reactors of... Procedures Applicable to Proceedings for the Issuance of Licenses To Construct and/or Operate Nuclear Power... license applications pursuant to appendix N of 10 CFR parts 50 or 52. 2.401 Section 2.401 Energy NUCLEAR...

  7. 10 CFR Appendix N to Part 52 - Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N to Part 52 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Pt. 52, App. N...

  8. 10 CFR Appendix N to Part 52 - Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate...

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N to Part 52 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Pt. 52, App. N...

  9. 31 CFR 589.501 - General and specific licensing procedures.

    Code of Federal Regulations, 2014 CFR

    2014-07-01

    ... chapter. Licensing actions taken pursuant to part 501 of this chapter with respect to the prohibitions contained in this part are considered actions taken pursuant to this part. General licenses and statements... page on OFAC's Web site: www.treasury.gov/ofac. ...

  10. High Temperature Gas-Cooled Test Reactor Point Design: Summary Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sterbentz, James William; Bayless, Paul David; Nelson, Lee Orville

    2016-01-01

    A point design has been developed for a 200-MW high-temperature gas-cooled test reactor. The point design concept uses standard prismatic blocks and 15.5% enriched uranium oxycarbide fuel. Reactor physics and thermal-hydraulics simulations have been performed to characterize the capabilities of the design. In addition to the technical data, overviews are provided on the technology readiness level, licensing approach, and costs of the test reactor point design.

  11. High Temperature Gas-Cooled Test Reactor Point Design: Summary Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sterbentz, James William; Bayless, Paul David; Nelson, Lee Orville

    2016-03-01

    A point design has been developed for a 200-MW high-temperature gas-cooled test reactor. The point design concept uses standard prismatic blocks and 15.5% enriched uranium oxycarbide fuel. Reactor physics and thermal-hydraulics simulations have been performed to characterize the capabilities of the design. In addition to the technical data, overviews are provided on the technology readiness level, licensing approach, and costs of the test reactor point design.

  12. 10 CFR 72.18 - Elimination of repetition.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Elimination of repetition. 72.18 Section 72.18 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE License...

  13. 10 CFR 72.18 - Elimination of repetition.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Elimination of repetition. 72.18 Section 72.18 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE License...

  14. 10 CFR 72.34 - Environmental report.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Environmental report. 72.34 Section 72.34 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE License Application, Form...

  15. 10 CFR 52.151 - Scope of subpart.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... applicable to Commission issuance of a license authorizing manufacture of nuclear power reactors to be... 10 Energy 2 2010-01-01 2010-01-01 false Scope of subpart. 52.151 Section 52.151 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS...

  16. Reactor safeguards system assessment and design. Volume I

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Varnado, G.B.; Ericson, D.M. Jr.; Daniel, S.L.

    1978-06-01

    This report describes the development and application of a methodology for evaluating the effectiveness of nuclear power reactor safeguards systems. Analytic techniques are used to identify the sabotage acts which could lead to release of radioactive material from a nuclear power plant, to determine the areas of a plant which must be protected to assure that significant release does not occur, to model the physical plant layout, and to evaluate the effectiveness of various safeguards systems. The methodology was used to identify those aspects of reactor safeguards systems which have the greatest effect on overall system performance and which, therefore,more » should be emphasized in the licensing process. With further refinements, the methodology can be used by the licensing reviewer to aid in assessing proposed or existing safeguards systems.« less

  17. AGC 2 Irradiated Material Properties Analysis

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Rohrbaugh, David Thomas

    2017-05-01

    The Advanced Reactor Technologies Graphite Research and Development Program is conducting an extensive graphite irradiation experiment to provide data for licensing of a high temperature reactor (HTR) design. In past applications, graphite has been used effectively as a structural and moderator material in both research and commercial high temperature gas cooled reactor designs. , Nuclear graphite H 451, used previously in the United States for nuclear reactor graphite components, is no longer available. New nuclear graphite grades have been developed and are considered suitable candidates for new HTR reactor designs. To support the design and licensing of HTR core componentsmore » within a commercial reactor, a complete properties database must be developed for these current grades of graphite. Quantitative data on in service material performance are required for the physical, mechanical, and thermal properties of each graphite grade, with a specific emphasis on data accounting for the life limiting effects of irradiation creep on key physical properties of the HTR candidate graphite grades. Further details on the research and development activities and associated rationale required to qualify nuclear grade graphite for use within the HTR are documented in the graphite technology research and development plan.« less

  18. AGC 2 Irradiation Creep Strain Data Analysis

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Windes, William E.; Rohrbaugh, David T.; Swank, W. David

    2016-08-01

    The Advanced Reactor Technologies Graphite Research and Development Program is conducting an extensive graphite irradiation experiment to provide data for licensing of a high temperature reactor (HTR) design. In past applications, graphite has been used effectively as a structural and moderator material in both research and commercial high temperature gas cooled reactor designs. Nuclear graphite H-451, used previously in the United States for nuclear reactor graphite components, is no longer available. New nuclear graphite grades have been developed and are considered suitable candidates for new HTR reactor designs. To support the design and licensing of HTR core components within amore » commercial reactor, a complete properties database must be developed for these current grades of graphite. Quantitative data on in service material performance are required for the physical, mechanical, and thermal properties of each graphite grade, with a specific emphasis on data accounting for the life limiting effects of irradiation creep on key physical properties of the HTR candidate graphite grades. Further details on the research and development activities and associated rationale required to qualify nuclear grade graphite for use within the HTR are documented in the graphite technology research and development plan.« less

  19. Licensed operating reactors: Status summary report, data as of December 31, 1995. Volume 20

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1996-06-01

    The US Nuclear Regulatory Commission`s monthly summary of licensed nuclear power reactor data is based primarily on the operating data report submitted by licensees for each unit. This report is divided into two sections: the first contains summary highlights and the second contains data on each individual unit in commercial operation. Section 1 availability factors, capacity factors, and forced outage rates are simple arithmetic averages. Section 2 items in the cumulative column are generally as reported by the licensees and notes to the use of weighted averages and starting dates other than commercial operation are provided.

  20. 10 CFR Appendix N to Part 50 - Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate...

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 1 2014-01-01 2014-01-01 false Standardization of Nuclear Power Plant Designs: Permits To Construct and Licenses To Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N to Part 50 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Pt. 50, App. N Appendix N to Par...

  1. 10 CFR 72.20 - Public inspection of application.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Public inspection of application. 72.20 Section 72.20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE License...

  2. 10 CFR 72.20 - Public inspection of application.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Public inspection of application. 72.20 Section 72.20 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE License...

  3. 10 CFR 2.310 - Selection of hearing procedures.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ..., licensee-initiated amendment, or termination of licenses or permits for nuclear power reactors, where the... of a civilian nuclear power plant must be conducted under the procedures of subpart L of this part... Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF...

  4. 10 CFR 52.153 - Relationship to other subparts.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Relationship to other subparts. 52.153 Section 52.153 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Manufacturing Licenses § 52.153 Relationship to other subparts. (a) A nuclear power reactor...

  5. 10 CFR 52.153 - Relationship to other subparts.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Relationship to other subparts. 52.153 Section 52.153 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Manufacturing Licenses § 52.153 Relationship to other subparts. (a) A nuclear power reactor...

  6. 77 FR 13376 - Notice of License Termination for the University of Arizona Research Reactor, License No. R-52

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-03-06

    ..., alpha plus beta measurements, smear sampling, and soil sampling activities. As a result of the...-Agency Radiation Survey and Site Investigation Manual.'' The U of AZ submitted a revised FSS Plan on... and that the [[Page 13377

  7. 10 CFR 50.10 - License required; limited work authorization.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... the land for public recreational purposes; (ii) Site exploration, including necessary borings to... building with space for installation of a training reactor). (b) Requirement for license. Except as... applicant and, except as to the matters determined under paragraph (e)(1) of this section, the issuance of...

  8. 10 CFR 50.10 - License required; limited work authorization.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... the land for public recreational purposes; (ii) Site exploration, including necessary borings to... building with space for installation of a training reactor). (b) Requirement for license. Except as... applicant and, except as to the matters determined under paragraph (e)(1) of this section, the issuance of...

  9. 10 CFR 50.10 - License required; limited work authorization.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... the land for public recreational purposes; (ii) Site exploration, including necessary borings to... building with space for installation of a training reactor). (b) Requirement for license. Except as... applicant and, except as to the matters determined under paragraph (e)(1) of this section, the issuance of...

  10. 10 CFR 50.10 - License required; limited work authorization.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... the land for public recreational purposes; (ii) Site exploration, including necessary borings to... building with space for installation of a training reactor). (b) Requirement for license. Except as... applicant and, except as to the matters determined under paragraph (e)(1) of this section, the issuance of...

  11. 10 CFR 50.57 - Issuance of operating license. 1

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... contested activity sought to be authorized. The Director of Nuclear Reactor Regulation will make findings on... Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Issuance... presiding officer will issue an order in accordance with § 2.319(p) authorizing the Director of Nuclear...

  12. 10 CFR 50.57 - Issuance of operating license. 1

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... contested activity sought to be authorized. The Director of Nuclear Reactor Regulation will make findings on... Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Issuance... presiding officer will issue an order in accordance with § 2.319(p) authorizing the Director of Nuclear...

  13. 10 CFR 50.57 - Issuance of operating license. 1

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... contested activity sought to be authorized. The Director of Nuclear Reactor Regulation will make findings on... Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Issuance... presiding officer will issue an order in accordance with § 2.319(p) authorizing the Director of Nuclear...

  14. 10 CFR 50.57 - Issuance of operating license. 1

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... contested activity sought to be authorized. The Director of Nuclear Reactor Regulation will make findings on... Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Issuance... presiding officer will issue an order in accordance with § 2.319(p) authorizing the Director of Nuclear...

  15. 10 CFR 50.57 - Issuance of operating license. 1

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... contested activity sought to be authorized. The Director of Nuclear Reactor Regulation will make findings on... Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND UTILIZATION FACILITIES Issuance... presiding officer will issue an order in accordance with § 2.319(p) authorizing the Director of Nuclear...

  16. 10 CFR 51.21 - Criteria for and identification of licensing and regulatory actions requiring environmental...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Criteria for and identification of licensing and regulatory actions requiring environmental assessments. 51.21 Section 51.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL PROTECTION REGULATIONS FOR DOMESTIC LICENSING AND RELATED REGULATORY...

  17. 10 CFR 51.21 - Criteria for and identification of licensing and regulatory actions requiring environmental...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Criteria for and identification of licensing and regulatory actions requiring environmental assessments. 51.21 Section 51.21 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL PROTECTION REGULATIONS FOR DOMESTIC LICENSING AND RELATED REGULATORY...

  18. 78 FR 24441 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on Evolutionary...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-04-25

    ... Reactor (U.S. EPR) will hold a meeting on May 8-9, 2013, Room T-2B1, 11545 Rockville Pike, Rockville... License Application (COLA) associated with the U.S. EPR Design Control Document (DCD). The Subcommittee...

  19. 10 CFR 52.131 - Scope of subpart.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Standard... review, and referral to the Advisory Committee on Reactor Safeguards of standard designs for a nuclear power reactor of the type described in § 50.22 of this chapter or major portions thereof. ...

  20. 10 CFR 52.75 - Filing of applications.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... New Reactors or Director, Office of Nuclear Reactor Regulation, as appropriate. (b) The application... 10 Energy 2 2014-01-01 2014-01-01 false Filing of applications. 52.75 Section 52.75 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Combined...

  1. 10 CFR 2.102 - Administrative review of application.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... completion of its review. (b) The Director, Office of Nuclear Reactor Regulation, Director, Office of New... as requested by the Commission. (c) The Director, Office of Nuclear Reactor Regulation, Director... Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF...

  2. 10 CFR 52.75 - Filing of applications.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... New Reactors or Director, Office of Nuclear Reactor Regulation, as appropriate. (b) The application... 10 Energy 2 2011-01-01 2011-01-01 false Filing of applications. 52.75 Section 52.75 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Combined...

  3. 10 CFR 52.75 - Filing of applications.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... New Reactors or Director, Office of Nuclear Reactor Regulation, as appropriate. (b) The application... 10 Energy 2 2012-01-01 2012-01-01 false Filing of applications. 52.75 Section 52.75 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Combined...

  4. 10 CFR 2.102 - Administrative review of application.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... completion of its review. (b) The Director, Office of Nuclear Reactor Regulation, Director, Office of New... as requested by the Commission. (c) The Director, Office of Nuclear Reactor Regulation, Director... Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF...

  5. 10 CFR 52.75 - Filing of applications.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... New Reactors or Director, Office of Nuclear Reactor Regulation, as appropriate. (b) The application... 10 Energy 2 2010-01-01 2010-01-01 false Filing of applications. 52.75 Section 52.75 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Combined...

  6. 10 CFR 52.75 - Filing of applications.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... New Reactors or Director, Office of Nuclear Reactor Regulation, as appropriate. (b) The application... 10 Energy 2 2013-01-01 2013-01-01 false Filing of applications. 52.75 Section 52.75 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Combined...

  7. 10 CFR 72.62 - Backfitting.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Backfitting. 72.62 Section 72.62 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE Issuance and Conditions of License § 72.62...

  8. 10 CFR 72.216 - [Reserved

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false [Reserved] 72.216 Section 72.216 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSING REQUIREMENTS FOR THE INDEPENDENT STORAGE OF SPENT NUCLEAR FUEL, HIGH-LEVEL RADIOACTIVE WASTE, AND REACTOR-RELATED GREATER THAN CLASS C WASTE General License for Storage of Spent Fuel at...

  9. 10 CFR 2.502-2.504 - [Reserved

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false [Reserved] 2.502-2.504 Section 2.502-2.504 Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF ORDERS Additional Procedures Applicable to Proceedings for the Issuance of Licenses To Manufacture Nuclear Power Reactors To Be...

  10. 10 CFR 50.76 - Licensee's change of status; financial qualifications.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... license) for a nuclear power reactor, no later than seventy-five (75) days prior to ceasing to be an... 10 Energy 1 2010-01-01 2010-01-01 false Licensee's change of status; financial qualifications. 50.76 Section 50.76 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF PRODUCTION AND...

  11. 77 FR 63343 - Biweekly Notice: Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-10-16

    ... PWR [Pressurized-Water Reactor] Steam Generator Tubes'' (Reference 32) and [Nuclear Energy Institute... maintains the required structural margins of the SG tubes for both normal and accident conditions. Nuclear Energy Institute 97-06, ``Steam Generator Program Guidelines'' (Reference 8), and NRC Regulatory Guide 1...

  12. 77 FR 75451 - Agency Information Collection Activities: Submission for the Office of Management and Budget (OMB...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-12-20

    ... upgraded licenses or license renewals to operate the controls at a nuclear reactor facility. This... NUCLEAR REGULATORY COMMISSION [Docket No. NRC-2012-0184] Agency Information Collection Activities: Submission for the Office of Management and Budget (OMB) Review; Comment Request AGENCY: Nuclear Regulatory...

  13. High-Temperature Gas-Cooled Test Reactor Point Design

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Sterbentz, James William; Bayless, Paul David; Nelson, Lee Orville

    2016-04-01

    A point design has been developed for a 200 MW high-temperature gas-cooled test reactor. The point design concept uses standard prismatic blocks and 15.5% enriched UCO fuel. Reactor physics and thermal-hydraulics simulations have been performed to characterize the capabilities of the design. In addition to the technical data, overviews are provided on the technological readiness level, licensing approach and costs.

  14. Atomic Safety and Licensing Board Panel Biennial Report, Fiscal Years 1993--1994. Volume 6

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1995-08-01

    In Fiscal Year 1993, the Atomic Safety and Licensing Board Panel (``the Panel``) handled 30 proceedings. In Fiscal Year 1994, the Panel handled 36 proceedings. The cases addressed issues in the construction, operation, and maintenance of commercial nuclear power reactors and other activities requiring a license form the Nuclear Regulatory Commission. This report sets out the Panel`s caseload during the year and summarizes, highlight, and analyzes how the wide- ranging issues raised in those proceedings were addressed by the Panel`s judges and licensing boards.

  15. 15 CFR 752.16 - Administrative actions.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 15 Commerce and Foreign Trade 2 2011-01-01 2011-01-01 false Administrative actions. 752.16 Section... COMPREHENSIVE LICENSE § 752.16 Administrative actions. (a)(1) If BIS is not satisfied that you or other parties... parties to such licenses are not adequate, BIS may, in addition to any enforcement action pursuant to part...

  16. 15 CFR 752.16 - Administrative actions.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 15 Commerce and Foreign Trade 2 2010-01-01 2010-01-01 false Administrative actions. 752.16 Section... COMPREHENSIVE LICENSE § 752.16 Administrative actions. (a)(1) If BIS is not satisfied that you or other parties... parties to such licenses are not adequate, BIS may, in addition to any enforcement action pursuant to part...

  17. 10 CFR 51.20 - Criteria for and identification of licensing and regulatory actions requiring environmental...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Criteria for and identification of licensing and regulatory actions requiring environmental impact statements. 51.20 Section 51.20 Energy NUCLEAR REGULATORY... radioactive waste in a monitored retrievable storage installation (MRS). (10) Issuance of a license for a...

  18. 76 FR 73727 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses Involving No...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-11-29

    ... Detection Instrumentation,'' to define a new time limit for restoring inoperable RCS leakage detection... Specifications Section 3.4.15 regarding reactor coolant leakage detection instrumentation to be consistent with... amendments revised the Technical Specifications (TSs) ``RCS [reactor coolant system] Leakage Detection...

  19. 10 CFR 2.107 - Withdrawal of application.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ..., Office of Nuclear Reactor Regulation, Director, Office of New Reactors, or Director, Office of Nuclear... 10 Energy 1 2011-01-01 2011-01-01 false Withdrawal of application. 2.107 Section 2.107 Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF ORDERS...

  20. 10 CFR 2.107 - Withdrawal of application.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ..., Office of Nuclear Reactor Regulation, Director, Office of New Reactors, or Director, Office of Nuclear... 10 Energy 1 2012-01-01 2012-01-01 false Withdrawal of application. 2.107 Section 2.107 Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF ORDERS...

  1. High-temperature gas-cooled reactor technology development program. Annual progress report for period ending December 31, 1982

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Kasten, P.R.; Rittenhouse, P.L.; Bartine, D.E.

    1983-06-01

    During 1982 the High-Temperature Gas-Cooled Reactor (HTGR) Technology Program at Oak Ridge National Laboratory (ORNL) continued to develop experimental data required for the design and licensing of cogeneration HTGRs. The program involves fuels and materials development (including metals, graphite, ceramic, and concrete materials), HTGR chemistry studies, structural component development and testing, reactor physics and shielding studies, performance testing of the reactor core support structure, and HTGR application and evaluation studies.

  2. Some Implications of the Three Mile Island Accident for LMFBR Safety and Licensing: The Design Basis Issue

    DTIC Science & Technology

    1980-08-01

    metal fast breeder reactor (LMFBR) design. It also re-examines the impact of the accident at Three Mile Island on the design basis concept, and how...Water Reactors : ImpZications for Liquid MetaZ Fast Breeder Reactors , by W. E. Kastenberg and K. A. Solomon, July 1979. v SUNMARY The 1979 accident...the liquid metal fast breeder reactor (LMFBR). This Note assesses the impact of the TMI-2 accident on the LMFBR. Specifically, it: o Reviews the

  3. Revised analyses of decommissioning for the reference pressurized Water Reactor Power Station. Volume 2, Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure: Appendices, Final report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Konzek, G.J.; Smith, R.I.; Bierschbach, M.C.

    1995-11-01

    With the issuance of the final Decommissioning Rule (July 27, 1998), owners and operators of licensed nuclear power plants are required to prepare, and submit to the US Nuclear Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. The NRC staff is in need of bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to provide some of the needed bases documentation. This report contains the results of a review andmore » reevaluation of the 1978 PNL decommissioning study of the Trojan nuclear power plant (NUREG/CR-0130), including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the nuclear power plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5--7 year period during which time the spent fuel is stored in the spent fuel pool, prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clean structures on the site and to restore the site to a ``green field`` condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities.« less

  4. Revised analyses of decommissioning for the reference pressurized Water Reactor Power Station. Effects of current regulatory and other considerations on the financial assurance requirements of the decommissioning rule and on estimates of occupational radiation exposure, Volume 1, Final report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Konzek, G.J.; Smith, R.I.; Bierschbach, M.C.

    1995-11-01

    With the issuance of the final Decommissioning Rule (July 27, 1988), owners and operators of licensed nuclear power plants are required to prepare, and submit to the US Nuclear Regulatory Commission (NRC) for review, decommissioning plans and cost estimates. The NRC staff is in need of bases documentation that will assist them in assessing the adequacy of the licensee submittals, from the viewpoint of both the planned actions, including occupational radiation exposure, and the probable costs. The purpose of this reevaluation study is to provide some of the needed bases documentation. This report contains the results of a review andmore » reevaluation of the {prime}978 PNL decommissioning study of the Trojan nuclear power plant (NUREG/CR-0130), including all identifiable factors and cost assumptions which contribute significantly to the total cost of decommissioning the nuclear power plant for the DECON, SAFSTOR, and ENTOMB decommissioning alternatives. These alternatives now include an initial 5--7 year period during which time the spent fuel is stored in the spent fuel pool, prior to beginning major disassembly or extended safe storage of the plant. Included for information (but not presently part of the license termination cost) is an estimate of the cost to demolish the decontaminated and clean structures on the site and to restore the site to a ``green field`` condition. This report also includes consideration of the NRC requirement that decontamination and decommissioning activities leading to termination of the nuclear license be completed within 60 years of final reactor shutdown, consideration of packaging and disposal requirements for materials whose radionuclide concentrations exceed the limits for Class C low-level waste (i.e., Greater-Than-Class C), and reflects 1993 costs for labor, materials, transport, and disposal activities.« less

  5. Completed egoism and intended altruism boost healthy food choices.

    PubMed

    Weibel, Christian; Messner, Claude; Brügger, Adrian

    2014-06-01

    Based on the self-licensing literature and goal theory, we expected and found that completed (im)moral actions lead to markedly different food choices (Studies 1 & 2) than intended (im)moral actions (Study 2). In Study 1, people more often chose healthy over unhealthy food options when they recalled a completed egoistic action than when they recalled a completed altruistic action. Study 2 confirmed this finding and furthermore showed that the self-licensing effect in food choices is moderated by the action stage (completed versus intended) of the moral or immoral action. This article extends the existing self-licensing literature and opens up new perspectives for changing consumers' food consumption behavior. Copyright © 2014 Elsevier Ltd. All rights reserved.

  6. 77 FR 3009 - Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Advanced Boiling Water Reactors

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-01-20

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0010] Knowledge and Abilities Catalog for Nuclear Power... comment a draft NUREG, NUREG-2104, Revision 0, ``Knowledge and Abilities Catalog for Nuclear Power Plant... developed using this Catalog along with the Operator Licensing Examination Standards for Power Reactors...

  7. 75 FR 68629 - Massachusetts Institute of Technology Reactor Notice of Issuance of Renewed Facility Operating...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-11-08

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 50-020; NRC-2010-0313] Massachusetts Institute of Technology Reactor Notice of Issuance of Renewed Facility Operating; License No. R-37 The U.S. Nuclear... Institute of Technology (the licensee), which authorizes continued operation of the Massachusetts Institute...

  8. 10 CFR 50.82 - Termination of license.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... to the NRC, consistent with the requirements of § 50.4(b)(8); (ii) Once fuel has been permanently... fuel from the reactor vessel, or when a final legally effective order to permanently cease operations... emplacement or retention of fuel into the reactor vessel. (3) Decommissioning will be completed within 60...

  9. 78 FR 24438 - Evaluations of Explosions Postulated To Occur at Nearby Facilities and on Transportation Routes...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-04-25

    ... Nearby Facilities and on Transportation Routes Near Nuclear Power Plants AGENCY: Nuclear Regulatory... Nearby Facilities and on Transportation Routes Near Nuclear Power Plants.'' This regulatory guide describes for applicants seeking nuclear power reactor licenses and licensees of nuclear power reactors...

  10. 76 FR 14747 - Revision of Fee Schedules; Fee Recovery for Fiscal Year 2011

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-03-17

    ... Standards VI. Environmental Impact: Categorical Exclusion VII. Paperwork Reduction Act Statement VIII... nuclear reactors. The NRC has prepared a paper for the Commission's information in support of the Nuclear Energy Institute's position to calculate annual fees for each new licensed power reactor as a function of...

  11. 10 CFR 52.35 - Use of site for other purposes.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ..., Office of New Reactors or Director, Office of Nuclear Reactor Regulation, as appropriate, (Director) of... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS... informs the Director that the holder no longer intends to use the site for a nuclear power plant, the...

  12. 10 CFR 2.318 - Commencement and termination of jurisdiction of presiding officer.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ..., whichever is earliest. (b) The Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, or the Director, Office of Nuclear Material Safety and Safeguards, as appropriate, may issue an... officer. 2.318 Section 2.318 Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING...

  13. 10 CFR 2.318 - Commencement and termination of jurisdiction of presiding officer.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ..., whichever is earliest. (b) The Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, or the Director, Office of Nuclear Material Safety and Safeguards, as appropriate, may issue an... officer. 2.318 Section 2.318 Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING...

  14. 10 CFR 52.15 - Filing of applications.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... permit with the Director, Office of New Reactors, or the Director, Office of Nuclear Reactor Regulation... 10 Energy 2 2012-01-01 2012-01-01 false Filing of applications. 52.15 Section 52.15 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Early Site...

  15. 10 CFR 52.35 - Use of site for other purposes.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ..., Office of New Reactors or Director, Office of Nuclear Reactor Regulation, as appropriate, (Director) of... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS... informs the Director that the holder no longer intends to use the site for a nuclear power plant, the...

  16. 10 CFR 52.35 - Use of site for other purposes.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ..., Office of New Reactors or Director, Office of Nuclear Reactor Regulation, as appropriate, (Director) of... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS... informs the Director that the holder no longer intends to use the site for a nuclear power plant, the...

  17. 10 CFR 52.35 - Use of site for other purposes.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ..., Office of New Reactors or Director, Office of Nuclear Reactor Regulation, as appropriate, (Director) of... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS... informs the Director that the holder no longer intends to use the site for a nuclear power plant, the...

  18. 10 CFR 52.35 - Use of site for other purposes.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ..., Office of New Reactors or Director, Office of Nuclear Reactor Regulation, as appropriate, (Director) of... NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS... informs the Director that the holder no longer intends to use the site for a nuclear power plant, the...

  19. 10 CFR 52.15 - Filing of applications.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... permit with the Director, Office of New Reactors, or the Director, Office of Nuclear Reactor Regulation... 10 Energy 2 2011-01-01 2011-01-01 false Filing of applications. 52.15 Section 52.15 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Early Site...

  20. 10 CFR 52.15 - Filing of applications.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... permit with the Director, Office of New Reactors, or the Director, Office of Nuclear Reactor Regulation... 10 Energy 2 2013-01-01 2013-01-01 false Filing of applications. 52.15 Section 52.15 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Early Site...

  1. 10 CFR 52.15 - Filing of applications.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... permit with the Director, Office of New Reactors, or the Director, Office of Nuclear Reactor Regulation... 10 Energy 2 2014-01-01 2014-01-01 false Filing of applications. 52.15 Section 52.15 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Early Site...

  2. 10 CFR 52.15 - Filing of applications.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... permit with the Director, Office of New Reactors, or the Director, Office of Nuclear Reactor Regulation... 10 Energy 2 2010-01-01 2010-01-01 false Filing of applications. 52.15 Section 52.15 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) LICENSES, CERTIFICATIONS, AND APPROVALS FOR NUCLEAR POWER PLANTS Early Site...

  3. 10 CFR 2.318 - Commencement and termination of jurisdiction of presiding officer.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ..., whichever is earliest. (b) The Director, Office of Nuclear Reactor Regulation, Director, Office of New Reactors, or the Director, Office of Nuclear Material Safety and Safeguards, as appropriate, may issue an... officer. 2.318 Section 2.318 Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING...

  4. 10 CFR 2.1331 - Commission action.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Commission action. 2.1331 Section 2.1331 Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF ORDERS Procedures for Hearings on License Transfer Applications § 2.1331 Commission action. (a) Upon completion of a...

  5. 10 CFR 2.1331 - Commission action.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 1 2011-01-01 2011-01-01 false Commission action. 2.1331 Section 2.1331 Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF ORDERS Procedures for Hearings on License Transfer Applications § 2.1331 Commission action. (a) Upon completion of a...

  6. 78 FR 33120 - Final Interim Staff Guidance LR-ISG-2011-04; Updated Aging Management Criteria for Reactor Vessel...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-03

    ..., ``Generic Aging Lessons Learned Report'' (GALL Report), for the aging management of Pressurized Water... communicate insights and lessons learned and to address emergent issues not covered in license renewal... ensure that PWR license renewal applicants will adequately address age-related degradation and aging...

  7. 76 FR 30204 - Exelon Nuclear, Dresden Nuclear Power Station, Unit 1; Exemption From Certain Security Requirements

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-24

    ... Power Station, Unit 1; Exemption From Certain Security Requirements 1.0 Background Exelon Nuclear is the licensee and holder of Facility Operating License No. DPR-2 issued for Dresden Nuclear Power Station (DNPS... protection of licensed activities in nuclear power reactors against radiological sabotage,'' paragraph (b)(1...

  8. 31 CFR 500.584 - Energy sector projects in North Korea.

    Code of Federal Regulations, 2010 CFR

    2010-07-01

    ... 31 Money and Finance: Treasury 3 2010-07-01 2010-07-01 false Energy sector projects in North Korea... Licenses, Authorizations and Statements of Licensing Policy § 500.584 Energy sector projects in North Korea... energy sector projects in North Korea in connection with that country's transition to light-water reactor...

  9. 77 FR 47123 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-08-07

    ...-Water Reactors] Steam Generator Tubes'' [Reference 7] and NEI [Nuclear Energy Institute] 97-06, ``Steam... CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared for these... the required structural margins of the SG tubes for both normal and accident conditions. Nuclear...

  10. 78 FR 2295 - Charlissa C. Smith; Establishment of Atomic Safety and Licensing Board

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-01-10

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 55-23694-SP; ASLBP No. 13-925-01-SP-BD01] Charlissa C... (Board) is being established to preside over the following proceeding: Charlissa C. Smith, (Denial of Senior Reactor Operator License). This proceeding concerns a hearing request from Charlissa C. Smith...

  11. 1996 NRC annual report. Volume 13

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1997-10-01

    This 22nd annual report of the US Nuclear Regulatory Commission (NRC) describes accomplishments, activities, and plans made during Fiscal Year 1996 (FH 1996)--October 1, 1995, through September 30, 1996. Significant activities that occurred early in FY 1997 are also described, particularly changes in the Commission and organization of the NRC. The mission of the NRC is to ensure that civilian uses of nuclear materials in the US are carried out with adequate protection of public health and safety, the environment, and national security. These uses include the operation of nuclear power plants and fuel cycle plants and medical, industrial, andmore » research applications. Additionally, the NRC contributes to combating the proliferation of nuclear weapons material worldwide. The NRC licenses and regulates commercial nuclear reactor operations and research reactors and other activities involving the possession and use of nuclear materials and wastes. It also protects nuclear materials used in operation and facilities from theft or sabotage. To accomplish its statutorily mandated regulatory mission, the NRC issues rules and standards, inspects facilities and operations, and issues any required enforcement actions.« less

  12. Guideline for Performing Systematic Approach to Evaluate and Qualify Legacy Documents that Support Advanced Reactor Technology Activity

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Honma, George

    The establishment of a systematic process for the evaluation of historic technology information for use in advanced reactor licensing is described. Efforts are underway to recover and preserve Experimental Breeder Reactor II and Fast Flux Test Facility historical data. These efforts have generally emphasized preserving information from data-acquisition systems and hard-copy reports and entering it into modern electronic formats suitable for data retrieval and examination. The guidance contained in this document has been developed to facilitate consistent and systematic evaluation processes relating to quality attributes of historic technical information (with focus on sodium-cooled fast reactor (SFR) technology) that will bemore » used to eventually support licensing of advanced reactor designs. The historical information may include, but is not limited to, design documents for SFRs, research-and-development (R&D) data and associated documents, test plans and associated protocols, operations and test data, international research data, technical reports, and information associated with past U.S. Nuclear Regulatory Commission (NRC) reviews of SFR designs. The evaluation process is prescribed in terms of SFR technology, but the process can be used to evaluate historical information for any type of advanced reactor technology. An appendix provides a discussion of typical issues that should be considered when evaluating and qualifying historical information for advanced reactor technology fuel and source terms, based on current light water reactor (LWR) requirements and recent experience gained from Next Generation Nuclear Plant (NGNP).« less

  13. Optimizing Characterization of Site Hydrology in Support of New Reactor Licensing at the U.S. Nuclear Regulatory Commission (Invited)

    NASA Astrophysics Data System (ADS)

    Nicholson, T. J.; Raione, R.; Ahn, H.; Barnhurst, D.; Giacinto, J.; McBride, M.; Tiruneh, N. D.

    2009-12-01

    The NRC regulates the civilian use of radioactive materials and facilities in an open and transparent manner. The NRC regulatory criteria are designed to protect human health and safety, and the environment by regulating nuclear facilities. During review of new reactor licensing applications, NRC staff reviews and independently verifies hydrogeologic information submitted by the applicant in several topical areas such as development and testing of Conceptual Site Models (CSM) which may involve perched aquifers; engineered water level fluctuations of surface-water reservoirs; ground-water collector wells and local ground-water uses; design-basis ground-water levels for structural analysis; analysis of scenarios for potential release of radionuclides to the subsurface; deep well injection of effluents; and monitoring to detect radionuclide releases. This information is reviewed in a systematic manner in accordance with NRC requirements and guidance to evaluate safety and environmental impacts and reduce the uncertainties for these impacts. NRC licensing staff is reviewing 14 applications for siting new reactors. Experience gained through these licensing activities has shown the value of using site-specific data to evaluate the CSM and its use to assess design and operational issues. Optimizing the information flow process through a systemically and thorough review process creates efficiencies. Through an iterative process of evaluating various geographical settings and associated ground-water conditions, NRC staff has developed methods to minimize prediction uncertainty through the use of confirmatory analyses performed under conservative, hierarchal approaches.

  14. Factors associated with high-severity disciplinary action by a state medical board: a Texas study of medical license revocation.

    PubMed

    Cardarelli, Roberto; Licciardone, John C

    2006-03-01

    There has been an increase in research evaluating factors associated with disciplinary action of physicians by state medical boards. However, factors related to the severity of disciplinary action are lacking. By investigating these factors while controlling for the type of violation, the authors sought to determine whether physician characteristics influenced the process of disciplinary action by state medical boards. Physicians disciplined by the Texas Medical Board between January 1, 1989, and December 31, 1998, were included in this case-controlled study (N=1129). Multivariate logistic regression analysis was used to compute odds ratios (ORs) and 95% confidence intervals (CIs) for factors associated with license revocation, the most severe disciplinary action, compared with all other forms of disciplinary action combined. Anesthesiologists (OR, 2.45; 95% CI, 1.05-5.74), general practitioners (OR, 1.80; 95% CI, 1.01-3.19), and psychiatrists (OR, 2.68; 95% CI, 1.41-5.13), as well as those with multiple disciplinary actions (OR, 1.91; 95% CI, 1.29-2.83) were most susceptible to license revocation. The more years a disciplined physician was in practice, the greater risk he or she had of license revocation (OR, 1.05; 95% CI, 1.04-1.07). Factors associated with a greater likelihood of license revocation for physicians are: primary medical specialty, number of years in practice, and a history of multiple disciplinary actions.

  15. ACHP | About ACHP | General Information

    Science.gov Websites

    thresholds are met: 1) there is a federal or federally licensed action, including grants, licenses, and permits, and 2) that action has the potential to affect properties listed in or eligible for listing in

  16. Knowledge and abilities catalog for nuclear power plant operators: Boiling water reactors, Revision 1

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1995-08-01

    The Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling-Water Reactors (BWRs) (NUREG-1123, Revision 1) provides the basis for the development of content-valid licensing examinations for reactor operators (ROs) and senior reactor operators (SROs). The examinations developed using the BWR Catalog along with the Operator Licensing Examiner Standards (NUREG-1021) and the Examiner`s Handbook for Developing Operator Licensing Written Examinations (NUREG/BR-0122), will cover the topics listed under Title 10, Code of Federal Regulations, Part 55 (10 CFR 55). The BWR Catalog contains approximately 7,000 knowledge and ability (K/A) statements for ROs and SROs at BWRs. The catalog is organized intomore » six major sections: Organization of the Catalog, Generic Knowledge and Ability Statements, Plant Systems grouped by Safety Functions, Emergency and Abnormal Plant Evolutions, Components, and Theory. Revision 1 to the BWR Catalog represents a modification in form and content of the original catalog. The K/As were linked to their applicable 10 CFR 55 item numbers. SRO level K/As were identified by 10 CFR 55.43 item numbers. The plant-wide generic and system generic K/As were combined in one section with approximately one hundred new K/As. Component Cooling Water and Instrument Air Systems were added to the Systems Section. Finally, High Containment Hydrogen Concentration and Plant Fire On Site evolutions added to the Emergency and Abnormal Plant Evolutions section.« less

  17. 75 FR 4493 - Natural Resources Defense Council; Denial of Petition for Rulemaking

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-28

    ... NRC continues to license the civilian use of HEU to fuel seven existing research and test reactors... predicts that the three HEU-fueled TRIGA-type research reactors at Oregon State University, the University...) is scheduled for conversion to LEU but notes that the newer and larger LEU-fueled TRIGA facility at...

  18. 10 CFR 51.23 - Temporary storage of spent fuel after cessation of reactor operation-generic determination of no...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Temporary storage of spent fuel after cessation of reactor operation-generic determination of no significant environmental impact. 51.23 Section 51.23 Energy NUCLEAR REGULATORY COMMISSION (CONTINUED) ENVIRONMENTAL PROTECTION REGULATIONS FOR DOMESTIC LICENSING AND RELATED...

  19. 78 FR 37591 - Entergy Nuclear Operations, Inc., Entergy Nuclear Indian Point Unit 2, LLC, Issuance of Director...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-06-21

    ... NUCLEAR REGULATORY COMMISSION [NRC-2012-0284; Docket No. 50-247; License No. DPR-26] Entergy Nuclear Operations, Inc., Entergy Nuclear Indian Point Unit 2, LLC, Issuance of Director's Decision Notice is hereby given that the Deputy Director, Reactor Safety Programs, Office of Nuclear Reactor...

  20. 77 FR 30435 - In-core Thermocouples at Different Elevations and Radial Positions in Reactor Core

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-23

    ... NUCLEAR REGULATORY COMMISSION 10 CFR Part 50 [Docket No. PRM-50-105; NRC-2012-0056] In-core Thermocouples at Different Elevations and Radial Positions in Reactor Core AGENCY: Nuclear Regulatory Commission... of operating licenses for nuclear power plants (``NPP'') to operate NPPs with in-core thermocouples...

  1. Development of New Transportation/Storage Cask System for Use by DOE Russian Research Reactor Fuel Return Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Michael Tyacke; Frantisek Svitak; Jiri Rychecky

    2010-04-01

    The United States, the Russian Federation, and the International Atomic Energy Agency (IAEA) have been working together on a program called the Russian Research Reactor Fuel Return (RRRFR) Program. The purpose of this program is to return Soviet or Russian supplied high-enriched uranium (HEU) fuel currently stored at Russian-designed research reactors throughout the world to Russia. To accommodate transport of the HEU spent nuclear fuel (SNF), a new large-capacity transport/storage cask system was specially designed for handling and operations under the unique conditions for these research reactor facilities. This new cask system is named the ŠKODA VPVR/M cask. The design,more » licensing, testing, and delivery of this new cask system are the results of a significant international cooperative effort by several countries and involved numerous private and governmental organizations. This paper contains the following sections: (1) Introduction/Background; (2) VPVR/M Cask Description; (3) Ancillary Equipment, (4) Cask Licensing; (5) Cask Demonstration and Operations; (6) IAEA Procurement, Quality Assurance Inspections, Fabrication, and Delivery; and, (7) Summary and Conclusions.« less

  2. Development of a New Transportation/Storage Cask System for Use by the DOE Russian Research Reactor Fuel Return Program

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Michael J. Tyacke; Frantisek Svitak; Jiri Rychecky

    2007-10-01

    The United States, the Russian Federation, and the International Atomic Energy Agency (IAEA) have been working together on a program called the Russian Research Reactor Fuel Return (RRRFR) Program. The purpose of this program is to return Soviet or Russian-supplied high-enriched uranium (HEU) fuel, currently stored at Russian-designed research reactors throughout the world, to Russia. To accommodate transport of the HEU spent nuclear fuel (SNF), a new large-capacity transport/storage cask system was specially designed for handling and operations under the unique conditions at these research reactor facilities. This new cask system is named the ŠKODA VPVR/M cask. The design, licensing,more » testing, and delivery of this new cask system result from a significant international cooperative effort by several countries and involved numerous private and governmental organizations. This paper contains the following sections: 1) Introduction; 2) VPVR/M Cask Description; 3) Ancillary Equipment, 4) Cask Licensing; 5) Cask Demonstration and Operations; 6) IAEA Procurement, Quality Assurance Inspections, Fabrication, and Delivery; and, 7) Conclusions.« less

  3. 76 FR 30404 - Advisory Committee On Reactor Safeguards; Meeting

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-25

    ... Room T2-B1, 11545 Rockville Pike, Rockville, Maryland 8:30 a.m.-8:35 a.m.: Opening Remarks by the ACRS... Alloy Cladding.'' 10:45 a.m.-11:45 a.m.: Revised Safety Evaluation Report Associated with the License... to the safety evaluation report associated with the license renewal application for the Hope Creek...

  4. 78 FR 29393 - University of Missouri-Columbia Facility Operating License No. R-103

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-20

    ... Curators of the University of Missouri--Columbia (the licensee) to operate the Missouri University Research Reactor (MURR) at a maximum steady-state thermal power of 10 megawatts (MW). The renewed license would authorize the licensee to operate the MURR up to a steady-state thermal power of 10 MW for an additional 20...

  5. 10 CFR 2.402 - Separate hearings on separate issues; consolidation of proceedings.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... appendix N of part 50 of this chapter for construction permits for nuclear power reactors of a type... Licenses To Construct and/or Operate Nuclear Power Plants of Identical Design at Multiple Sites § 2.402... proceedings. 2.402 Section 2.402 Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING...

  6. 76 FR 23848 - Carolina Power And Light Company; Notice of Withdrawal of Application for Amendment to Renewed...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-04-28

    ...; Notice of Withdrawal of Application for Amendment to Renewed Facility Operating License The U.S. Nuclear... December 9, 2010, for a proposed amendment to Renewed Facility Operating License No. NPF-63 for the Shearon... Pressurized Water Reactors,'' to the Core Operating Limits Report methodologies list. This change would have...

  7. 76 FR 81992 - PPL Bell Bend, LLC; Combined License Application for Bell Bend Nuclear Power Plant; Exemption

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-12-29

    ... License Application for Bell Bend Nuclear Power Plant; Exemption 1.0 Background PPL Bell Bend, LLC... for Nuclear Power Plants.'' This reactor is to be identified as Bell Bend Nuclear Power Plant (BBNPP... based upon the U.S. EPR reference COL (RCOL) application for UniStar's Calvert Cliffs Nuclear Power...

  8. JPRS Report, Science & Technology, Europe & Latin America, Argentina: Specifications of ARGOS 380 MW Reactor.

    DTIC Science & Technology

    1988-02-18

    programme. It has a licensing agreement with Siemens AG’s Kraftwerk Union AG, which is its minor shareholder. Under this agreement, ENACE has the...Argentine nuclear programme. It has a licensing agreement with Siemens AG’s Kraftwerk Union AG, which is its minor shareholder. Under this agreement, ENACE

  9. 78 FR 15747 - Charlissa C. Smith (Denial of Senior Reactor Operator License)

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-03-12

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 55-23694-SP; ASLBP No. 13-925-01-SP-BD01] Charlissa C... Reconstitution Pursuant to 10 CFR 2.313(c) and 2.321(b), the Atomic Safety and Licensing Board (Board) in the above-captioned Charlissa C. Smith case is hereby reconstituted because Administrative Judge Alan S...

  10. Chapter 5, "License Renewal and Aging Management for Continued Service

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Naus, Dan J

    As of August 2011, there were 104 commercial nuclear power reactors licensed to operate in 31 states in the United States. Initial operating licenses in the United States are granted for a period of 40 years. In order to help assure an adequate energy supply, the USNRC has established a timely license renewal process and clear requirements that are needed to ensure safe plant operation for an extended plant life. The principals of license renewal and the basic requirements that address license renewal are identified as well as additional sources of guidance that can be utilized as part of themore » license renewal process. Aging management program inspections and operating experience related to the concrete and steel containment structures are provided. Finally, several lessons learned are provided based on containment operating experience.« less

  11. Professional licensure: investigation and disciplinary action.

    PubMed

    Brous, Edie

    2012-11-01

    This is the second article in a three-part series on nursing boards' disciplinary actions and what nurses need to know to maintain their license in good standing. This article discusses common reasons boards of nursing conduct investigations and take disciplinary action. The third and final article will discuss strategies for protecting your license.

  12. 10 CFR 40.45 - Commission action on applications to renew or amend.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 1 2010-01-01 2010-01-01 false Commission action on applications to renew or amend. 40.45 Section 40.45 Energy NUCLEAR REGULATORY COMMISSION DOMESTIC LICENSING OF SOURCE MATERIAL Licenses § 40.45 Commission action on applications to renew or amend. In considering an application by a licensee to renew or...

  13. 10 CFR 110.84 - Commission action on a hearing request or intervention petition.

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... 10 Energy 2 2010-01-01 2010-01-01 false Commission action on a hearing request or intervention... Commission action on a hearing request or intervention petition. (a) In an export licensing proceeding, or in an import licensing proceeding in which a hearing request or intervention petition does not assert or...

  14. 10 CFR 110.84 - Commission action on a hearing request or intervention petition.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... 10 Energy 2 2014-01-01 2014-01-01 false Commission action on a hearing request or intervention... Commission action on a hearing request or intervention petition. (a) In an export licensing proceeding, or in an import licensing proceeding in which a hearing request or intervention petition does not assert or...

  15. 10 CFR 110.84 - Commission action on a hearing request or intervention petition.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... 10 Energy 2 2013-01-01 2013-01-01 false Commission action on a hearing request or intervention... Commission action on a hearing request or intervention petition. (a) In an export licensing proceeding, or in an import licensing proceeding in which a hearing request or intervention petition does not assert or...

  16. 10 CFR 110.84 - Commission action on a hearing request or intervention petition.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... 10 Energy 2 2012-01-01 2012-01-01 false Commission action on a hearing request or intervention... Commission action on a hearing request or intervention petition. (a) In an export licensing proceeding, or in an import licensing proceeding in which a hearing request or intervention petition does not assert or...

  17. 10 CFR 110.84 - Commission action on a hearing request or intervention petition.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Commission action on a hearing request or intervention... Commission action on a hearing request or intervention petition. (a) In an export licensing proceeding, or in an import licensing proceeding in which a hearing request or intervention petition does not assert or...

  18. 78 FR 48456 - Notice of Cancellation of Customs Broker Licenses Due to Death of the License Holder

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-08

    ... Customs Broker Licenses Due to Death of the License Holder AGENCY: U.S. Customs and Border Protection, Department of Homeland Security. ACTION: Customs broker license cancellation due to death of the broker... without prejudice due to the death of the license holders. SUPPLEMENTARY INFORMATION: Notice is hereby...

  19. 21 CFR 515.23 - Voluntary revocation of medicated feed mill license.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 21 Food and Drugs 6 2010-04-01 2010-04-01 false Voluntary revocation of medicated feed mill... SERVICES (CONTINUED) ANIMAL DRUGS, FEEDS, AND RELATED PRODUCTS MEDICATED FEED MILL LICENSE Administrative Actions on Licenses § 515.23 Voluntary revocation of medicated feed mill license. A license issued under...

  20. 10 CFR 110.42 - Export licensing criteria.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... research on or development of any nuclear explosive device. (3) Adequate physical security measures will be... to exports of high-enriched uranium to be used as a fuel or target in a nuclear research or test... can be used in the reactor. (iii) A fuel or target “can be used” in a nuclear research or test reactor...

  1. 10 CFR 2.603 - Acceptance and docketing of application for early review of site suitability issues in a...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING PROCEEDINGS AND ISSUANCE OF ORDERS Additional... Issuance of Limited Work Authorizations Early Partial Decisions on Site Suitability-Construction Permit § 2... processing, the Director of the Office of New Reactors or the Director of the Office of Nuclear Reactor...

  2. 78 FR 79506 - Tennessee Valley Authority: Exemption From Requirements To Revise Combined License Application To...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-30

    ..., Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington DC, 20555- 0001; telephone: 301...) application for two units of Westinghouse Electric Company's AP1000 advanced pressurized water reactors to be... Bellefonte Nuclear Plant, Units 3 and 4 (BLN 3&4) COL application on January 28, 2008. On September 29, 2010...

  3. 78 FR 47802 - Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on US-APWR...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-06

    ... NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards (ACRS); Meeting of the ACRS Subcommittee on US-APWR; Notice of Meeting The ACRS Subcommittee on US-APWR will hold a meeting on September 17...) associated with the US-APWR design certification and the Comanche Peak Combined License Application (COLA...

  4. 10 CFR 140.13 - Amount of financial protection required of certain holders of construction permits and combined...

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ..., possession and storage only of special nuclear material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after issuance of either an operating license under 10 CFR part 50 or... NUCLEAR REGULATORY COMMISSION (CONTINUED) FINANCIAL PROTECTION REQUIREMENTS AND INDEMNITY AGREEMENTS...

  5. 10 CFR 140.13 - Amount of financial protection required of certain holders of construction permits and combined...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ..., possession and storage only of special nuclear material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after issuance of either an operating license under 10 CFR part 50 or... NUCLEAR REGULATORY COMMISSION (CONTINUED) FINANCIAL PROTECTION REQUIREMENTS AND INDEMNITY AGREEMENTS...

  6. 10 CFR 140.13 - Amount of financial protection required of certain holders of construction permits and combined...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ..., possession and storage only of special nuclear material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after issuance of either an operating license under 10 CFR part 50 or... NUCLEAR REGULATORY COMMISSION (CONTINUED) FINANCIAL PROTECTION REQUIREMENTS AND INDEMNITY AGREEMENTS...

  7. 75 FR 57535 - Northern States Power Company-Minnesota Notice of Issuance of Amendments to Facility Operating...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-21

    ... issuance. FOR FURTHER INFORMATION CONTACT: Thomas J. Wengert, Office of Nuclear Reactor Regulation, U.S... Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2010-23516 Filed 9-20-10; 8:45 am] BILLING CODE... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-282 and 50-306; NRC-2010-0290] Northern States Power...

  8. 10 CFR 140.13 - Amount of financial protection required of certain holders of construction permits and combined...

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ..., possession and storage only of special nuclear material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after issuance of either an operating license under 10 CFR part 50 or... NUCLEAR REGULATORY COMMISSION (CONTINUED) FINANCIAL PROTECTION REQUIREMENTS AND INDEMNITY AGREEMENTS...

  9. 10 CFR 2.643 - Acceptance and docketing of application for limited work authorization.

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... § 2.101(a)(9) is incomplete and not acceptable for processing, the Director of New Reactors or the Director of Nuclear Reactor Regulation will inform the applicant of this determination and the respects in... authorization. 2.643 Section 2.643 Energy NUCLEAR REGULATORY COMMISSION RULES OF PRACTICE FOR DOMESTIC LICENSING...

  10. 10 CFR 140.13 - Amount of financial protection required of certain holders of construction permits and combined...

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ..., possession and storage only of special nuclear material at the site of the nuclear reactor for use as fuel in operation of the nuclear reactor after issuance of either an operating license under 10 CFR part 50 or... NUCLEAR REGULATORY COMMISSION (CONTINUED) FINANCIAL PROTECTION REQUIREMENTS AND INDEMNITY AGREEMENTS...

  11. 75 FR 23820 - Notice of Docketing of Amendment Request for Materials License No. SNM-2506; Northern States...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-05-04

    ... INFORMATION CONTACT: Pamela Longmire, Ph.D., Project Manager, Licensing Branch, Division of Spent Fuel Storage... Generating Plant (PINGP), Unit Nos. 1 and 2, site in Goodhue County, Minnesota. The TN-40 cask is currently..., higher burnup spent fuel used in the PINGP reactor as well as associated changes to the ISFSI's technical...

  12. 76 FR 6638 - Virginia Electric and Power Company D/B/A/ Dominion Virginia Power and Old Dominion Electric...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-02-07

    ... Company D/B/A/ Dominion Virginia Power and Old Dominion Electric Cooperative, North Anna Power Station... combined license (COL) application to build and operate a new reactor at its North Anna Power Station (NAPS... Combined License (COL) for North Anna Power Station, Unit 3.'' A notice of availability of the final...

  13. Regulatory Risk Reduction for Advanced Reactor Technologies – FY2016 Status and Work Plan Summary

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Moe, Wayne Leland

    2016-08-01

    Millions of public and private sector dollars have been invested over recent decades to realize greater efficiency, reliability, and the inherent and passive safety offered by advanced nuclear reactor technologies. However, a major challenge in experiencing those benefits resides in the existing U.S. regulatory framework. This framework governs all commercial nuclear plant construction, operations, and safety issues and is highly large light water reactor (LWR) technology centric. The framework must be modernized to effectively deal with non-LWR advanced designs if those designs are to become part of the U.S energy supply. The U.S. Department of Energy’s (DOE) Advanced Reactor Technologiesmore » (ART) Regulatory Risk Reduction (RRR) initiative, managed by the Regulatory Affairs Department at the Idaho National Laboratory (INL), is establishing a capability that can systematically retire extraneous licensing risks associated with regulatory framework incompatibilities. This capability proposes to rely heavily on the perspectives of the affected regulated community (i.e., commercial advanced reactor designers/vendors and prospective owner/operators) yet remain tuned to assuring public safety and acceptability by regulators responsible for license issuance. The extent to which broad industry perspectives are being incorporated into the proposed framework makes this initiative unique and of potential benefit to all future domestic non-LWR applicants« less

  14. USING CFD TO ANALYZE NUCLEAR SYSTEMS BEHAVIOR: DEFINING THE VALIDATION REQUIREMENTS

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Richard Schultz

    2012-09-01

    A recommended protocol to formulate numeric tool specifications and validation needs in concert with practices accepted by regulatory agencies for advanced reactors is described. The protocol is based on the plant type and perceived transient and accident envelopes that translates to boundary conditions for a process that gives the: (a) key phenomena and figures-of-merit which must be analyzed to ensure that the advanced plant can be licensed, (b) specification of the numeric tool capabilities necessary to perform the required analyses—including bounding calculational uncertainties, and (c) specification of the validation matrices and experiments--including the desired validation data. The result of applyingmore » the process enables a complete program to be defined, including costs, for creating and benchmarking transient and accident analysis methods for advanced reactors. By following a process that is in concert with regulatory agency licensing requirements from the start to finish, based on historical acceptance of past licensing submittals, the methods derived and validated have a high probability of regulatory agency acceptance.« less

  15. 21 CFR 515.25 - Revocation of order refusing to approve a medicated feed mill license application or suspending...

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... medicated feed mill license application or suspending or revoking a license. 515.25 Section 515.25 Food and..., FEEDS, AND RELATED PRODUCTS MEDICATED FEED MILL LICENSE Administrative Actions on Licenses § 515.25 Revocation of order refusing to approve a medicated feed mill license application or suspending or revoking a...

  16. 21 CFR 515.21 - Refusal to approve a medicated feed mill license application.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 21 Food and Drugs 6 2010-04-01 2010-04-01 false Refusal to approve a medicated feed mill license... SERVICES (CONTINUED) ANIMAL DRUGS, FEEDS, AND RELATED PRODUCTS MEDICATED FEED MILL LICENSE Administrative Actions on Licenses § 515.21 Refusal to approve a medicated feed mill license application. (a) The...

  17. 21 CFR 515.20 - Approval of medicated feed mill license applications.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 21 Food and Drugs 6 2010-04-01 2010-04-01 false Approval of medicated feed mill license... SERVICES (CONTINUED) ANIMAL DRUGS, FEEDS, AND RELATED PRODUCTS MEDICATED FEED MILL LICENSE Administrative Actions on Licenses § 515.20 Approval of medicated feed mill license applications. Within 90 days after an...

  18. 78 FR 73566 - Standard Format and Content for a License Application for an Independent Spent Fuel Storage...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-06

    ...The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment draft regulatory guide (DG), DG-3042, ``Standard Format and Content for a License Application for an Independent Spent Fuel Storage Installation or a Monitored Retrievable Storage Facility.'' This draft regulatory guide is proposed revision 2 of Regulatory Guide 3.50, which provides a format that the NRC considers acceptable for submitting the information for license applications to store spent nuclear fuel, high-level radioactive waste, and/or reactor-related Greater than Class C waste.

  19. Safety approach to the selection of design criteria for the CRBRP reactor refueling system

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Meisl, C J; Berg, G E; Sharkey, N F

    1979-01-01

    The selection of safety design criteria for Liquid Metal Fast Breeder Reactor (LMFBR) refueling systems required the extrapolation of regulations and guidelines intended for Light Water Reactor refueling systems and was encumbered by the lack of benefit from a commercially licensed predecessor other than Fermi. The overall approach and underlying logic are described for developing safety design criteria for the reactor refueling system (RRS) of the Clinch River Breeder Reactor Plant (CRBRP). The complete selection process used to establish the criteria is presented, from the definition of safety functions to the finalization of safety design criteria in the appropriate documents.more » The process steps are illustrated by examples.« less

  20. 10 CFR Appendix N to Part 52 - Standardization of Nuclear Power Plant Designs: Combined Licenses To Construct and Operate...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... Licenses To Construct and Operate Nuclear Power Reactors of Identical Design at Multiple Sites N Appendix N... FOR NUCLEAR POWER PLANTS Pt. 52, App. N Appendix N to Part 52—Standardization of Nuclear Power Plant... that the applicant wishes to have the application considered under 10 CFR part 52, appendix N, and must...

  1. 75 FR 3946 - License Nos. DPR-42 and DPR-60; Northern States Power Company; Prairie Island Nuclear Generating...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-01-25

    ..., Office of Nuclear Reactor Regulation. [FR Doc. 2010-1309 Filed 1-22-10; 8:45 am] BILLING CODE 7590-01-P ... NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-282 and 50-306; NRC-2010-0022] License Nos. DPR-42 and DPR-60; Northern States Power Company; Prairie Island Nuclear Generating Plant, Units 1 and 2...

  2. 77 FR 19362 - Environmental Assessment and Finding of No Significant Impact for License Renewal for the Reed...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-03-30

    ... serves about 1,300 students. The Reed Research Reactor is housed in a section of the Psychology Building constructed specifically for that purpose. The section of the Psychology building housing the Reed Research... encompasses the entire Psychology Building and all areas 76 meters (250 feet) from the center of the reactor...

  3. Reduced enrichment for research and test reactors: Proceedings

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Not Available

    1993-07-01

    The 15th annual Reduced Enrichment for Research and Test Reactors (RERTR) international meeting was organized by Ris{o} National Laboratory in cooperation with the International Atomic Energy Agency and Argonne National Laboratory. The topics of the meeting were the following: National Programs, Fuel Fabrication, Licensing Aspects, States of Conversion, Fuel Testing, and Fuel Cycle. Individual papers have been cataloged separately.

  4. Developing Ultra-small Scale Mechanical Testing Methods and Microstructural Investigation Procedures for Irradiated Materials

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hosemann, Peter; Kaoumi, Djamel

    Nuclear materials are an essential aspect of nuclear engineering. While great effort is spent on designing more advanced reactors or enhancing a reactor’s safety, materials have been the bottleneck of most new developments. The designs of new reactor concepts are driven by neutronic and thermodynamic aspects, leading to unusual coolants (liquid metal, liquid salt, gases), higher temperatures, and higher radiation doses than conventional light water reactors have. However, any (nuclear) engineering design must consider the materials used in the anticipated application in order to ever be realized. Designs which may look easy, simple and efficient considering thermodynamics or neutronic aspectsmore » can show their true difficulty in the materials area, which then prevents them from being deployed. In turn, the materials available are influencing the neutronic and thermodynamic designs and therefore must be considered from the beginning, requiring close collaborations between different aspects of nuclear engineering. If a particular design requires new materials, the licensing of the reactor must be considered, but licensing can be a costly and time consuming process that results in long lead times to realize true materials innovation.« less

  5. 21 CFR 515.24 - Notice of revocation of a medicated feed mill license.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... 21 Food and Drugs 6 2010-04-01 2010-04-01 false Notice of revocation of a medicated feed mill... SERVICES (CONTINUED) ANIMAL DRUGS, FEEDS, AND RELATED PRODUCTS MEDICATED FEED MILL LICENSE Administrative Actions on Licenses § 515.24 Notice of revocation of a medicated feed mill license. When a license...

  6. 21 CFR 515.22 - Suspension and/or revocation of approval of a medicated feed mill license.

    Code of Federal Regulations, 2010 CFR

    2010-04-01

    ... medicated feed mill license. 515.22 Section 515.22 Food and Drugs FOOD AND DRUG ADMINISTRATION, DEPARTMENT... MILL LICENSE Administrative Actions on Licenses § 515.22 Suspension and/or revocation of approval of a medicated feed mill license. (a) The Secretary of Health and Human Services may suspend a medicated feed...

  7. 75 FR 11472 - Perishable Agricultural Commodities Act: Increase in License Fees

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-03-11

    ... increase. Paperwork Reduction Act In accordance with Office of Management and Budget (OMB) regulations (5...: Increase in License Fees AGENCY: Agricultural Marketing Service, USDA. ACTION: Proposed rule. SUMMARY: The... Commodities Act (PACA or Act) to increase license fees. Current annual license fees of $550 would increase to...

  8. 75 FR 17052 - Issuance of Electronic Documents and Related Recordkeeping Requirements

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-04-05

    ... BIS to eliminate the paper versions of most export and reexport licenses, notices of denial of license applications, notices of return of a license application without action, notices of results of classification requests, License Exception AGR notification results, and encryption review request results. This rule also...

  9. Air Shipment of Spent Nuclear Fuel from Romania to Russia

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Igor Bolshinsky; Ken Allen; Lucian Biro

    Romania successfully completed the world’s first air shipment of spent nuclear fuel transported in Type B(U) casks under existing international laws and without shipment license special exceptions when the last Romanian highly enriched uranium (HEU) spent nuclear fuel was transported to the Russian Federation in June 2009. This air shipment required the design, fabrication, and licensing of special 20 foot freight containers and cask tiedown supports to transport the eighteen TUK 19 shipping casks on a Russian commercial cargo aircraft. The new equipment was certified for transport by road, rail, water, and air to provide multi modal transport capabilities formore » shipping research reactor spent fuel. The equipment design, safety analyses, and fabrication were performed in the Russian Federation and transport licenses were issued by both the Russian and Romanian regulatory authorities. The spent fuel was transported by truck from the VVR S research reactor to the Bucharest airport, flown by commercial cargo aircraft to the airport at Yekaterinburg, Russia, and then transported by truck to the final destination in a secure nuclear facility at Chelyabinsk, Russia. This shipment of 23.7 kg of HEU was coordinated by the Russian Research Reactor Fuel Return Program (RRRFR), as part of the U.S. Department of Energy Global Threat Reduction Initiative (GTRI), in close cooperation with the Rosatom State Atomic Energy Corporation and the International Atomic Energy Agency, and was managed in Romania by the National Commission for Nuclear Activities Control (CNCAN). This paper describes the planning, shipment preparations, equipment design, and license approvals that resulted in the safe and secure air shipment of this spent nuclear fuel.« less

  10. Baseline Concept Description of a Small Modular High Temperature Reactor

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hans Gougar

    2014-05-01

    The objective of this report is to provide a description of generic small modular high temperature reactors (herein denoted as an smHTR), summarize their distinguishing attributes, and lay out the research and development (R&D) required for commercialization. The generic concepts rely heavily on the modular high temperature gas-cooled reactor designs developed in the 1980s which were never built but for which pre-licensing or certification activities were conducted. The concept matured more recently under the Next Generation Nuclear Plant (NGNP) project, specifically in the areas of fuel and material qualification, methods development, and licensing. As all vendor-specific designs proposed under NGNPmore » were all both ‘small’ or medium-sized and ‘modular’ by International Atomic Energy Agency (IAEA) and Department of Energy (DOE) standards, the technical attributes, challenges, and R&D needs identified, addressed, and documented under NGNP are valid and appropriate in the context of Small Modular Reactor (SMR) applications. Although the term High Temperature Reactor (HTR) is commonly used to denote graphite-moderated, thermal spectrum reactors with coolant temperatures in excess of 650oC at the core outlet, in this report the historical term High Temperature Gas-Cooled Reactor (HTGR) will be used to distinguish the gas-cooled technology described herein from its liquid salt-cooled cousin. Moreover, in this report it is to be understood that the outlet temperature of the helium in an HTGR has an upper limit of 950 degrees C which corresponds to the temperature to which certain alloys are currently being qualified under DOE’s ARC program. Although similar to the HTGR in just about every respect, the Very High Temperature Reactor (VHTR) may have an outlet temperature in excess of 950 degrees C and is therefore farther from commercialization because of the challenges posed to materials exposed to these temperatures. The VHTR is the focus of R&D under the Generation IV program and its specific R&D needs will be included in this report when appropriate for comparison. The distinguishing features of the HTGR are the refractory (TRISO) coated particle fuel, the low-power density, graphite-moderated core, and the high outlet temperature of the inert helium coolant. The low power density and fuel form effectively eliminate the possibility of core melt, even upon a complete loss of coolant pressure and flow. The graphite, which constitutes the bulk of the core volume and mass, provides a large thermal buffer that absorbs fission heat such that thermal transients occur over a timespan of hours or even days. As chemically-inert helium is already a gas, there is no coolant temperature or void feedback on the neutronics and no phase change or corrosion product that could degrade heat transfer. Furthermore, the particle coatings and interstitial graphite retain fission products such that the source terms at the plant boundary remain well below actionable levels under all anticipated nominal and off-normal operating conditions. These attributes enable the reactor to supply process heat to a collocated industrial plant with negligible risk of contamination and minimal dynamic coupling of the facilities (Figure 1). The exceptional retentive properties of coated particle fuel in a graphite matrix were first demonstrated in the DRAGON reactor, a European research facility that began operation in 1964.« less

  11. Baseline Concept Description of a Small Modular High Temperature Reactor

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Gougar, Hans D.

    2014-10-01

    The objective of this report is to provide a description of generic small modular high temperature reactors (herein denoted as an smHTR), summarize their distinguishing attributes, and lay out the research and development (R&D) required for commercialization. The generic concepts rely heavily on the modular high temperature gas-cooled reactor designs developed in the 1980s which were never built but for which pre-licensing or certification activities were conducted. The concept matured more recently under the Next Generation Nuclear Plant (NGNP) project, specifically in the areas of fuel and material qualification, methods development, and licensing. As all vendor-specific designs proposed under NGNPmore » were all both ‘small’ or medium-sized and ‘modular’ by International Atomic Energy Agency (IAEA) and Department of Energy (DOE) standards, the technical attributes, challenges, and R&D needs identified, addressed, and documented under NGNP are valid and appropriate in the context of Small Modular Reactor (SMR) applications. Although the term High Temperature Reactor (HTR) is commonly used to denote graphite-moderated, thermal spectrum reactors with coolant temperatures in excess of 650oC at the core outlet, in this report the historical term High Temperature Gas-Cooled Reactor (HTGR) will be used to distinguish the gas-cooled technology described herein from its liquid salt-cooled cousin. Moreover, in this report it is to be understood that the outlet temperature of the helium in an HTGR has an upper limit of 950 degrees C which corresponds to the temperature to which certain alloys are currently being qualified under DOE’s ARC program. Although similar to the HTGR in just about every respect, the Very High Temperature Reactor (VHTR) may have an outlet temperature in excess of 950 degrees C and is therefore farther from commercialization because of the challenges posed to materials exposed to these temperatures. The VHTR is the focus of R&D under the Generation IV program and its specific R&D needs will be included in this report when appropriate for comparison. The distinguishing features of the HTGR are the refractory (TRISO) coated particle fuel, the low-power density, graphite-moderated core, and the high outlet temperature of the inert helium coolant. The low power density and fuel form effectively eliminate the possibility of core melt, even upon a complete loss of coolant pressure and flow. The graphite, which constitutes the bulk of the core volume and mass, provides a large thermal buffer that absorbs fission heat such that thermal transients occur over a timespan of hours or even days. As chemically-inert helium is already a gas, there is no coolant temperature or void feedback on the neutronics and no phase change or corrosion product that could degrade heat transfer. Furthermore, the particle coatings and interstitial graphite retain fission products such that the source terms at the plant boundary remain well below actionable levels under all anticipated nominal and off-normal operating conditions. These attributes enable the reactor to supply process heat to a collocated industrial plant with negligible risk of contamination and minimal dynamic coupling of the facilities (Figure 1). The exceptional retentive properties of coated particle fuel in a graphite matrix were first demonstrated in the DRAGON reactor, a European research facility that began operation in 1964.« less

  12. 10 CFR Appendix I to Part 50 - Numerical Guides for Design Objectives and Limiting Conditions for Operation To Meet the...

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... in Light-Water-Cooled Nuclear Power Reactor Effluents I Appendix I to Part 50 Energy NUCLEAR... Criterion “As Low as is Reasonably Achievable” for Radioactive Material in Light-Water-Cooled Nuclear Power... light-water-cooled nuclear power reactors licensed under 10 CFR part 50 or part 52 of this chapter. The...

  13. 10 CFR Appendix I to Part 50 - Numerical Guides for Design Objectives and Limiting Conditions for Operation To Meet the...

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... in Light-Water-Cooled Nuclear Power Reactor Effluents I Appendix I to Part 50 Energy NUCLEAR... Criterion “As Low as is Reasonably Achievable” for Radioactive Material in Light-Water-Cooled Nuclear Power... light-water-cooled nuclear power reactors licensed under 10 CFR part 50 or part 52 of this chapter. The...

  14. 10 CFR Appendix I to Part 50 - Numerical Guides for Design Objectives and Limiting Conditions for Operation To Meet the...

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... in Light-Water-Cooled Nuclear Power Reactor Effluents I Appendix I to Part 50 Energy NUCLEAR... Criterion “As Low as is Reasonably Achievable” for Radioactive Material in Light-Water-Cooled Nuclear Power... light-water-cooled nuclear power reactors licensed under 10 CFR part 50 or part 52 of this chapter. The...

  15. Aging Management Guideline for commercial nuclear power plants: Motor control centers; Final report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Toman, G.; Gazdzinski, R.; O`Hearn, E.

    1994-02-01

    This Aging Management Guideline (AMG) provides recommended methods for effective detection and mitigation of age-related degradation mechanisms in Boiling Water Reactor (BWR) and Pressurized Water Reactor (PWR) commercial nuclear power plant motor control centers important to license renewal. The intent of this AMG is to assist plant maintenance and operations personnel in maximizing the safe, useful life of these components. It also supports the documentation of effective aging management programs required under the License Renewal Rule 10 CFR Part 54. This AMG is presented in a manner that allows personnel responsible for performance analysis and maintenance to compare their plant-specificmore » aging mechanisms (expected or already experienced) and aging management program activities to the more generic results and recommendations presented herein.« less

  16. Hydropower resources at risk: The status of hydropower regulation and development - 1997

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Hunt, R.T.; Hunt, J.A.

    This report documents today`s hydropower licensing and development status based on published data as follows: (a) Federal Energy Regulatory Commission (FERC) databases, maintained by FERC`s Office of Hydropower Licensing, of: (1) operating FERC-regulated projects, federal projects, and known unlicensed projects; (2) surrendered licenses; and, (3) recent licensing and relicensing actions; (b) Energy Information Administration (EIA) data on installed capacity and generation from 1949 through 1995 for the various resources used to produce electricity in the U.S.; and, (c) FERC licensing orders, and environmental assessments or environmental impact statements for each individual project relicensed since 1980. The analysis conducted to preparemore » this paper includes the effects of all FERC hydropower licensing actions since 1980, and applies those findings to estimate the costs of hydropower licensing and development activity for the next 15 years. It also quantifies the national cost of hydropower regulation. The future estimates are quite conservative. The are presented in 1996 dollars without speculating on the effects of future inflation, license surrenders, conditions imposed through open-ended license articles, license terms greater than 30 years, or low water years. Instead, they show the most directly predictable influences on licensing outcomes using actual experiences since ECPA (after 1986).« less

  17. 76 FR 62868 - Washington State University; Notice of Issuance of Renewed Facility Operating License No. R-76

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-11

    ...; Notice of Issuance of Renewed Facility Operating License No. R-76 AGENCY: Nuclear Regulatory Commission. ACTION: Notice of issuance of renewed facility operating license No. R- 76. ADDRESSES: You can access.... Nuclear Regulatory Commission (NRC, the Commission) has issued renewed Facility Operating License No. R-76...

  18. 77 FR 27096 - Notice of Intent To Grant Exclusive Copyright License

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-05-08

    ..., copyright-only license in the United States to software and its documentation described in NASA Case No. KSC... Exclusive Copyright License AGENCY: National Aeronautics and Space Administration. ACTION: Notice of Intent To Grant Exclusive Copyright License. SUMMARY: This notice is issued in accordance with 35 U.S.C. 209...

  19. Disciplinary careers of drug-impaired physicians.

    PubMed

    Holtman, Matthew C

    2007-02-01

    Alcohol and drug abuse are among the leading reasons for disciplinary action against physicians by state licensing authorities in the United States. I use event history models to describe the longitudinal patterns in disciplinary actions taken against physicians' licenses by state medical boards in the United States, 1990-2000. Adverse licensure action episodes that included discipline for drug or alcohol abuse were more likely to be followed by license restoration than episodes that did not. However, those restorations were also more likely to be followed by subsequent disciplinary action than episodes that did not include discipline for drug abuse. Furthermore, disciplinary licensure actions for drug abuse were the category most likely to be followed by a subsequent action for the same reason over the longer term (4-11 years). The increased risk of repeat disciplinary action associated with drug abuse may result in part from intensive surveillance of physicians who complete impaired physician programs, through mechanisms that include urine screening. However, it is also likely that the chronic nature of addiction leads to continued risk of relapse even among physicians receiving appropriate treatment.

  20. 10 CFR 51.4 - Definitions.

    Code of Federal Regulations, 2013 CFR

    2013-01-01

    ... include: (A) Changes for temporary use of the land for public recreational purposes; (B) Site exploration... building with space for installation of a training reactor). (2) For materials licenses, taking any site...

  1. 10 CFR 51.4 - Definitions.

    Code of Federal Regulations, 2014 CFR

    2014-01-01

    ... include: (A) Changes for temporary use of the land for public recreational purposes; (B) Site exploration... building with space for installation of a training reactor). (2) For materials licenses, taking any site...

  2. 10 CFR 51.4 - Definitions.

    Code of Federal Regulations, 2012 CFR

    2012-01-01

    ... include: (A) Changes for temporary use of the land for public recreational purposes; (B) Site exploration... building with space for installation of a training reactor). (2) For materials licenses, taking any site...

  3. Superfund record of decision (EPA region 10): Idaho National Engineering Lab, (USDOE) Operable Unit 26 (Stationary Low-Power Reactor-1 and Boiling Water Reactor Experiment-I Burial Grounds), Idaho Falls, ID, December 1, 1995

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    NONE

    1997-03-01

    This document presents the selected remedial action for the Stationary Low-Power Reactor-1 (SL-1) burial ground, the Boiling Water Reactor Experiment-I (BORAX-I) burial ground, and 10 no action sites in Waste Area Group 5. Actual or threatened releases of hazardous substances from the SL-1 and BORAX-I burial grounds, if not addressed by implementing the response action selected in this Record of Decision, may present a current or potential threat to public health, welfare, or the environment. The 10 no action sites do not present a threat to human health or the environment.

  4. COL Application Content Guide for HTGRs: Revision to RG 1.206, Part 1 - Status Report

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Wayne Moe

    2012-08-01

    A combined license (COL) application is required by the Nuclear Regulatory Commission (NRC) for all proposed nuclear plants. The information requirements for a COL application are set forth in 10 CFR 52.79, “Contents of Applications; Technical Information in Final Safety Analysis Report.” An applicant for a modular high temperature gas-cooled reactor (HTGR) must develop and submit for NRC review and approval a COL application which conforms to these requirements. The technical information necessary to allow NRC staff to evaluate a COL application and resolve all safety issues related to a proposed nuclear plant is detailed and comprehensive. To this, Regulatorymore » Guide (RG) 1.206, “Combined License Applications for Nuclear Power Plants” (LWR Edition), was developed to assist light water reactor (LWR) applicants in incorporating and effectively formatting required information for COL application review (Ref. 1). However, the guidance prescribed in RG 1.206 presumes a LWR design proposal consistent with the systems and functions associated with large LWR power plants currently operating under NRC license.« less

  5. 10 CFR 51.20 - Criteria for and identification of licensing and regulatory actions requiring environmental...

    Code of Federal Regulations, 2010 CFR

    2010-01-01

    ... design capacity license to operate an isotopic enrichment plant pursuant to part 50 of this chapter. (4... uranium enrichment facility. (11) Issuance of renewal of a license authorizing receipt and disposal of...

  6. 78 FR 29388 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-20

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (13-047)] Government-Owned Inventions, Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of Availability of Inventions for Licensing. SUMMARY: The inventions listed below assigned to the National...

  7. 78 FR 29388 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-20

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (13-052)] Government-Owned Inventions, Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of Availability of Inventions for Licensing. SUMMARY: Patent applications on the inventions listed below assigned...

  8. 78 FR 29388 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-20

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (13-054)] Government-Owned Inventions, Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of Availability of Inventions for Licensing. SUMMARY: Patent applications on the inventions listed below assigned...

  9. 78 FR 29387 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-20

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (13-058)] Government-Owned Inventions, Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of Availability of Inventions for Licensing. SUMMARY: Patent applications on the inventions listed below assigned...

  10. 78 FR 29386 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-05-20

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (13-053)] Government-Owned Inventions, Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of Availability of Inventions for Licensing. SUMMARY: Patent applications on the inventions listed below assigned...

  11. 78 FR 57664 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-19

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 13-106] Government-Owned Inventions, Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of Availability of Inventions for Licensing. SUMMARY: Patent applications on the inventions listed below assigned...

  12. 78 FR 13906 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-03-01

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 13-015] Government-Owned Inventions, Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of Availability of Inventions for Licensing. SUMMARY: Patent applications on the inventions listed below assigned...

  13. 78 FR 13905 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-03-01

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 13-018] Government-Owned Inventions, Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of Availability of Inventions for Licensing. SUMMARY: Patent applications on the inventions listed below assigned...

  14. 78 FR 19744 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-04-02

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 13-026] Government-Owned Inventions, Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of Availability of Inventions for Licensing. SUMMARY: Patent applications on the inventions listed below assigned...

  15. 75 FR 54656 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-08

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (10-109)] Government-Owned Inventions, Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of Availability of Inventions for Licensing. SUMMARY: Patent applications on the inventions listed below assigned...

  16. 78 FR 13905 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-03-01

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 13-017] Government-Owned Inventions, Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of Availability of Inventions for Licensing. SUMMARY: Patent applications on the inventions listed below assigned...

  17. 78 FR 57663 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-19

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 13-104] Government-Owned Inventions, Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of availability of inventions for licensing. SUMMARY: Patent applications on the inventions listed below assigned...

  18. 78 FR 57664 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-19

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 13-103] Government-Owned Inventions, Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of Availability of Inventions for Licensing. SUMMARY: Patent applications on the inventions listed below assigned...

  19. 75 FR 54656 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-09-08

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (10-107)] Government-Owned Inventions, Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of availability of inventions for licensing. SUMMARY: Patent applications on the inventions listed below assigned...

  20. 75 FR 28663 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-05-21

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice (10-057)] Government-Owned Inventions, Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of availability of inventions for licensing. SUMMARY: Patent applications on the inventions listed below assigned...

  1. 75 FR 43486 - Proposed Information Collection; Comment Request; Special Comprehensive License

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-07-26

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Proposed Information Collection; Comment Request; Special Comprehensive License AGENCY: Bureau of Industry and Security, Commerce ACTION: Notice....gov . SUPPLEMENTARY INFORMATION: I. Abstract The Special Comprehensive License (SCL) procedure...

  2. 78 FR 57665 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-09-19

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 13-105] Government-Owned Inventions, Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of Availability of Inventions for Licensing. SUMMARY: The inventions listed below assigned to the National...

  3. 10 CFR 51.20 - Criteria for and identification of licensing and regulatory actions requiring environmental...

    Code of Federal Regulations, 2011 CFR

    2011-01-01

    ... 10 Energy 2 2011-01-01 2011-01-01 false Criteria for and identification of licensing and regulatory actions requiring environmental impact statements. 51.20 Section 51.20 Energy NUCLEAR REGULATORY... the Commission, in the exercise of its discretion, has determined should be covered by an...

  4. 45 CFR 61.7 - Reporting licensure actions taken by Federal or State licensing and certification agencies.

    Code of Federal Regulations, 2011 CFR

    2011-10-01

    ... 45 Public Welfare 1 2011-10-01 2011-10-01 false Reporting licensure actions taken by Federal or State licensing and certification agencies. 61.7 Section 61.7 Public Welfare DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL ADMINISTRATION HEALTHCARE INTEGRITY AND PROTECTION DATA BANK FOR FINAL ADVERSE...

  5. 45 CFR 61.7 - Reporting licensure actions taken by Federal or State licensing and certification agencies.

    Code of Federal Regulations, 2010 CFR

    2010-10-01

    ... 45 Public Welfare 1 2010-10-01 2010-10-01 false Reporting licensure actions taken by Federal or State licensing and certification agencies. 61.7 Section 61.7 Public Welfare DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL ADMINISTRATION HEALTHCARE INTEGRITY AND PROTECTION DATA BANK FOR FINAL ADVERSE...

  6. 45 CFR 61.7 - Reporting licensure actions taken by Federal or State licensing and certification agencies.

    Code of Federal Regulations, 2012 CFR

    2012-10-01

    ... 45 Public Welfare 1 2012-10-01 2012-10-01 false Reporting licensure actions taken by Federal or State licensing and certification agencies. 61.7 Section 61.7 Public Welfare DEPARTMENT OF HEALTH AND HUMAN SERVICES GENERAL ADMINISTRATION HEALTHCARE INTEGRITY AND PROTECTION DATA BANK FOR FINAL ADVERSE...

  7. 45 CFR 60.8 - Reporting licensure actions taken by Boards of Medical Examiners.

    Code of Federal Regulations, 2014 CFR

    2014-10-01

    ... must report to the NPDB any action based on reasons relating to a physician's or dentist's professional... dentist's license, (2) Which censures, reprimands, or places on probation a physician or dentist, or (3) Under which a physician's or dentist's license is surrendered. (b) Information that must be reported...

  8. 45 CFR 60.8 - Reporting licensure actions taken by Boards of Medical Examiners.

    Code of Federal Regulations, 2013 CFR

    2013-10-01

    ... must report to the NPDB any action based on reasons relating to a physician's or dentist's professional... dentist's license, (2) Which censures, reprimands, or places on probation a physician or dentist, or (3) Under which a physician's or dentist's license is surrendered. (b) Information that must be reported...

  9. Next generation fuel irradiation capability in the High Flux Reactor Petten

    NASA Astrophysics Data System (ADS)

    Fütterer, Michael A.; D'Agata, Elio; Laurie, Mathias; Marmier, Alain; Scaffidi-Argentina, Francesco; Raison, Philippe; Bakker, Klaas; de Groot, Sander; Klaassen, Frodo

    2009-07-01

    This paper describes selected equipment and expertise on fuel irradiation testing at the High Flux Reactor (HFR) in Petten, The Netherlands. The reactor went critical in 1961 and holds an operating license up to at least 2015. While HFR has initially focused on Light Water Reactor fuel and materials, it also played a decisive role since the 1970s in the German High Temperature Reactor (HTR) development program. A variety of tests related to fast reactor development in Europe were carried out for next generation fuel and materials, in particular for Very High Temperature Reactor (V/HTR) fuel, fuel for closed fuel cycles (U-Pu and Th-U fuel cycle) and transmutation, as well as for other innovative fuel types. The HFR constitutes a significant European infrastructure tool for the development of next generation reactors. Experimental facilities addressed include V/HTR fuel tests, a coated particle irradiation rig, and tests on fast reactor, transmutation and thorium fuel. The rationales for these tests are given, results are provided and further work is outlined.

  10. 78 FR 41032 - Proposed Information Collection; Comment Request; Special Comprehensive License

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-07-09

    ... DEPARTMENT OF COMMERCE Bureau of Industry and Security Proposed Information Collection; Comment Request; Special Comprehensive License AGENCY: Bureau of Industry and Security. ACTION: Notice. [email protected] . SUPPLEMENTARY INFORMATION: I. Abstract The Special Comprehensive License (SCL) procedure...

  11. DOE Office of Scientific and Technical Information (OSTI.GOV)

    Little, G.A.

    For better than ten years there was little public notice of the TRIGA reactor at UC-Berkeley. Then: a) A non-student persuaded the Student and Senate to pass a resolution to request Campus Administration to stop operation of the reactor and remove it from campus. b) Presence of the reactor became a campaign-issue in a City Mayoral election. c) Two local residents reported adverse physical reactions before, during, and after a routine tour of the reactor facility. d) The Berkeley City Council began a study of problems associated with radioactive material within the city. e) Friends Of The Earth formally petitionedmore » the NRC to terminate the reactor's license. Campus personnel have expended many man-hours and many pounds of paper in responding to these happenings. Some of the details are of interest, and may be of use to other reactor facilities. (author)« less

  12. 78 FR 76328 - Application for Renewal of Special Nuclear Material License SNM-2014 From Tennessee Valley...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-12-17

    ... SNM in the form of fully-assembled fuel assemblies that would later form the initial reactor core of WBN2. The SNM in the fuel assemblies is enriched up to 5% in the isotope U-235. The fresh fuel... received the initial core for WBN2. The NRC has not yet issued the OL for the Unit 2 reactor. The...

  13. 77 FR 43866 - Notice of Intent To Grant Exclusive License

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-07-26

    ... License AGENCY: National Aeronautics and Space Administration. ACTION: Notice of intent to grant exclusive license. SUMMARY: This notice is issued in accordance with 35 U.S.C. 209(e) and 37 CFR 404.7(a)(1)(i). NASA hereby gives notice of its intent to grant an exclusive, license in the United States to practice...

  14. 77 FR 71404 - Notice of Intent to License Government-Owned Inventions; Intent to License on a Partially...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-11-30

    ... DEPARTMENT OF DEFENSE Department of the Army Notice of Intent to License Government-Owned Inventions; Intent to License on a Partially-Exclusive Basis AGENCY: Department of the Army, DoD. ACTION..., issued 07/ 28/2009 and entitled ``Radiation source with self-aligning optics,'' U.S. Patent 7,852,469...

  15. 76 FR 35480 - Notice of Intent To Grant Exclusive License

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-17

    ... Exclusive License AGENCY: National Aeronautics and Space Administration. ACTION: Notice of intent to grant exclusive license. SUMMARY: This notice is issued in accordance with 35 U.S.C. 209(c)(1) and 37 CFR 404.7(a)(1)(i). NASA hereby gives notice of its intent to grant an exclusive patent and copyright license in...

  16. Technology, safety, and costs of decommissioning reference nuclear research and test reactors: sensitivity of decommissioning radiation exposure and costs to selected parameters

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Konzek, G.J.

    1983-07-01

    Additional analyses of decommissioning at the reference research and test (R and T) reactors and analyses of five recent reactor decommissionings are made that examine some parameters not covered in the initial study report (NUREG/CR-1756). The parameters examined for decommissioning are: (1) the effect on costs and radiation exposure of plant size and/or type; (2) the effects on costs of increasing disposal charges and of unavailability of waste disposal capacity at licensed waste disposal facilities; and (3) the costs of and the available alternatives for the disposal of nuclear R and T reactor fuel assemblies.

  17. Generation III reactors safety requirements and the design solutions

    NASA Astrophysics Data System (ADS)

    Felten, P.

    2009-03-01

    Nuclear energy's public acceptance, and hence its development, depends on its safety. As a reactor designer, we will first briefly remind the basic safety principles of nuclear reactors' design. We will then show how the industry, and in particular Areva with its EPR, made design evolution in the wake of the Three Miles Island accident in 1979. In particular, for this new generation of reactors, severe accidents are taken into account beyond the standard design basis accidents. Today, Areva's EPR meets all so-called "generation III" safety requirements and was licensed by several nuclear safety authorities in the world. Many innovative solutions are integrated in the EPR, some of which will be introduced here.

  18. 78 FR 19743 - Government-Owned Inventions, Available for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-04-02

    ..., Available for Licensing AGENCY: National Aeronautics and Space Administration. ACTION: Notice of Availability of Inventions for Licensing. SUMMARY: Patent applications on the inventions listed below assigned... Continuous Aerodynamic Control Surfaces and Methods for Active Wing Shaping Control; NASA Case No.: ARC-16846...

  19. 77 FR 21573 - Government-Owned Inventions; Availability for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-04-10

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institutes of Health Government-Owned Inventions; Availability for Licensing AGENCY: National Institutes of Health, Public Health Service, HHS. ACTION: Notice... the indicated licensing contact at the Office of Technology Transfer, National Institutes of Health...

  20. 76 FR 13193 - Government-Owned Inventions; Availability for Licensing

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-03-10

    ... DEPARTMENT OF HEALTH AND HUMAN SERVICES National Institutes of Health Government-Owned Inventions; Availability for Licensing AGENCY: National Institutes of Health, Public Health Service, HHS. ACTION: Notice... the indicated licensing contact at the Office of Technology Transfer, National Institutes of Health...

  1. 76 FR 39846 - Proposed Information Collection; Comment Request; Steel Import License

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-07-07

    ... Request; Steel Import License AGENCY: International Trade Administration, Commerce. ACTION: Notice... Proclamation on Steel Safeguards mandated that the Departments of Commerce and Treasury institute an import licensing system to facilitate the monitoring of certain steel imports. Regulations were established that...

  2. 75 FR 24755 - License No. SUB-459; Acknowledgement of Request for Enforcement Action Against U.S. Army...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-05-05

    ... NUCLEAR REGULATORY COMMISSION [Docket No. 40-9083; NRC-2009-0352] License No. SUB-459; Acknowledgement of Request for Enforcement Action Against U.S. Army Installation Command (Schofield Barracks and Pohakuloa Training Area, Hawaii) Notice is hereby given that by petition dated March 4, 2010, Isaac D. Harp...

  3. Scientist vs. Citizen: The Shoreham Controversy

    ERIC Educational Resources Information Center

    Carl, Ann; Sailor, Vance L.

    1972-01-01

    Two views on the issue of nuclear reactor safety with reference to the license application of a nuclear power plant on Long Island. Each side presents scientific arguments concerning the safety standards proposed. (AL)

  4. Pre-Licensing Evaluation of Legacy SFR Metallic Fuel Data

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Yacout, A. M.; Billone, M. C.

    2016-09-16

    The US sodium cooled fast reactor (SFR) metallic fuel performance data that are of interest to advanced fast reactors applications, can be attributed mostly to the Integral Fast Reactor (IFR) program between 1984 and 1994. Metallic fuel data collected prior to the IFR program were associated with types of fuel that are not of interest to future advanced reactors deployment (e.g., previous U-Fissium alloy fuel). The IFR fuels data were collected from irradiation of U-Zr based fuel alloy, with and without Pu additions, and clad in different types of steels, including HT9, D9, and 316 stainless-steel. Different types of datamore » were generated during the program, and were based on the requirements associated with the DOE Advanced Liquid Metal Cooled Reactor (ALMR) program.« less

  5. Expanded scope of training and education programs at the UFTR

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Vernetson, W.G.; Whaley, P.M.

    1985-01-01

    Historically, the University of Florida Training Reactor (UFTR) has been used to train both hot and cold license reactor operator candidates in intensive two- and three-week training programs consisting of a correlated set of classroom lectures, hands-on reactor operations, and laboratory exercises. These training programs provide nuclear plant operating staff with fundamental operational experience in understanding, controlling, and evaluating subcritical multiplication, reactivity effects, reactivity manipulations, and reactor operations; a sufficient number of startups and shutdowns is also assured. The UDTR is also used in a nuclear engineering course entitled ''Principles of Nuclear Reactor Operations.'' The purpose of this paper ismore » to report the results of efforts to redirect and refine tractor operations educational and training programs at the UFTR.« less

  6. 78 FR 61398 - Notice of Intent To Grant Exclusive License

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-10-03

    ... NATIONAL AERONAUTICS AND SPACE ADMINISTRATION [Notice 13-117] Notice of Intent To Grant Exclusive License AGENCY: National Aeronautics and Space Administration. ACTION: Notice of intent to grant exclusive... Aeronautics and Space Administration. The prospective exclusive license will comply with the terms and...

  7. 78 FR 48457 - Correction of Document Revoking Customs Broker Licenses

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-08

    ... DEPARTMENT OF HOMELAND SECURITY U.S. Customs and Border Protection Correction of Document Revoking Customs Broker Licenses AGENCY: U.S. Customs and Border Protection, Department of Homeland Security. ACTION: Correction of document revoking certain customs broker licenses. SUMMARY: In a notice published...

  8. 78 FR 48456 - Notice of Cancellation of Customs Broker Licenses

    Federal Register 2010, 2011, 2012, 2013, 2014

    2013-08-08

    ... DEPARTMENT OF HOMELAND SECURITY U.S. Customs and Border Protection Notice of Cancellation of Customs Broker Licenses AGENCY: U.S. Customs and Border Protection, Department of Homeland Security. ACTION: Customs broker license cancellations. SUMMARY: Notice is hereby given that the customs broker...

  9. Changing concepts of geologic structure and the problem of siting nuclear reactors: Examples from Washington State

    NASA Astrophysics Data System (ADS)

    Tabor, R. W.

    1986-09-01

    The conflict between regulation and healthy evolution of geological science has contributed to the difficulties of siting nuclear reactors. On the Columbia Plateau in Washington, but for conservative design of the Hanford reactor facility, the recognition of the little-understood Olympic-Wallowa lineament as a major, possibly still active structural alinement might have jeopardized the acceptability of the site for nuclear reactors. On the Olympic Peninsula, evolving concepts of compressive structures and their possible recent activity and the current recognition of a subducting Juan de Fuca plate and its potential for generating great earthquakes—both concepts little-considered during initial site selection—may delay final acceptance of the Satsop site. Conflicts of this sort are inevitable but can be accommodated if they are anticipated in the reactor-licensing process. More important, society should be increasing its store of geologic knowledge now, during the current recess in nuclear reactor siting.

  10. NGNP Data Management and Analysis System Analysis and Web Delivery Capabilities

    DOE Office of Scientific and Technical Information (OSTI.GOV)

    Cynthia D. Gentillon

    2010-09-01

    Projects for the Very High Temperature Reactor Technology Development Office provide data in support of Nuclear Regulatory Commission licensing of the very high temperature reactor. Fuel and materials to be used in the reactor are tested and characterized to quantify performance in high-temperature and high-fluence environments. In addition, thermal-hydraulic experiments are conducted to validate codes used to assess reactor safety. The Very High Temperature Reactor Technology Development Office has established the NGNP Data Management and Analysis System (NDMAS) at the Idaho National Laboratory to ensure that very high temperature reactor data are (1) qualified for use, (2) stored in amore » readily accessible electronic form, and (3) analyzed to extract useful results. This document focuses on the third NDMAS objective. It describes capabilities for displaying the data in meaningful ways and for data analysis to identify useful relationships among the measured quantities.« less

  11. 76 FR 66090 - Facility Operating License Amendment From Virginia Electric and Power Company, Surry Power...

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-10-25

    ... operating pressures, leakage from primary water stress corrosion cracking below the proposed limited... discussed in Regulatory Guide (RG) 1.121, ``Bases for Plugging Degraded PWR [Pressurized-Water Reactor...

  12. 76 FR 28244 - Agency Information Collection Activities: Proposed Collection; Comment Request

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-05-16

    ... occur. 4. Who is required or asked to report: Nuclear power reactor licensees, licensed under 10 CFR..., special nuclear material; Category I fuel facilities; Category II and III facilities; research and test...

  13. 77 FR 38771 - Prospective Grant of Exclusive Patent License

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-06-29

    ... DEPARTMENT OF COMMERCE National Institute of Standards and Technology Prospective Grant of Exclusive Patent License AGENCY: National Institute of Standards and Technology, Commerce. ACTION: Notice of prospective grant of exclusive patent license. SUMMARY: This is a notice in accordance with 35 U.S.C. 209(e...

  14. 76 FR 38108 - Notice of Intent to Grant Exclusive License

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-06-29

    ... Service Notice of Intent to Grant Exclusive License AGENCY: Agricultural Research Service, USDA. ACTION... Research Service, intends to grant to P & M Signs, Inc. of Mountainair, New Mexico, an exclusive license to the Federal Government's rights in U.S. Patent No. 6,586,504, ``Wood And Plastic Composite Material...

  15. 76 FR 60531 - National Institute of Justice Interview Room Recording Systems and License Plate Readers Workshop

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-09-29

    ... Justice Interview Room Recording Systems and License Plate Readers Workshop AGENCY: National Institute of Justice. ACTION: Notice of the Interview Room Recording Systems and License Plate Readers Workshops.... The focus of the workshops is the development of NIJ performance standards for Interview Room...

  16. 76 FR 2382 - Radio Broadcasting Services; AM or FM Proposals To Change the Community of License

    Federal Register 2010, 2011, 2012, 2013, 2014

    2011-01-13

    ... FEDERAL COMMUNICATIONS COMMISSION Radio Broadcasting Services; AM or FM Proposals To Change the Community of License AGENCY: Federal Communications Commission. ACTION: Notice. SUMMARY: The following applicants filed AM or FM proposals to change the community of license: Educational Radio for the Public of...

  17. 77 FR 18815 - Radio Broadcasting Services; AM or FM Proposals To Change the Community of License

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-03-28

    ... FEDERAL COMMUNICATIONS COMMISSION Radio Broadcasting Services; AM or FM Proposals To Change the Community of License AGENCY: Federal Communications Commission. ACTION: Notice. SUMMARY: The following applicants filed AM or FM proposals to change the community of license: ALLIED COMMUNICATIONS NETWORK TWO...

  18. 77 FR 38631 - Radio Broadcasting Services; AM or FM Proposals To Change the Community of License

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-06-28

    ... FEDERAL COMMUNICATIONS COMMISSION Radio Broadcasting Services; AM or FM Proposals To Change the Community of License AGENCY: Federal Communications Commission. ACTION: Notice. SUMMARY: The following applicants filed AM or FM proposals to change the community of license: AGNUS DEI COMMUNICATIONS, INC...

  19. 75 FR 74732 - Radio Broadcasting Services; AM or FM Proposals To Change The Community of License

    Federal Register 2010, 2011, 2012, 2013, 2014

    2010-12-01

    ... FEDERAL COMMUNICATIONS COMMISSION Radio Broadcasting Services; AM or FM Proposals To Change The Community of License AGENCY: Federal Communications Commission. ACTION: Notice. SUMMARY: The following applicants filed AM or FM proposals to change the community of license: Armada Media--McCook, Inc., Station...

  20. 77 FR 33217 - Radio Broadcasting Services; AM or FM Proposals To Change the Community of License

    Federal Register 2010, 2011, 2012, 2013, 2014

    2012-06-05

    ... FEDERAL COMMUNICATIONS COMMISSION Radio Broadcasting Services; AM or FM Proposals To Change the Community of License AGENCY: Federal Communications Commission. ACTION: Notice. SUMMARY: The following applicants filed AM or FM proposals to change the community of license: LOST COAST COMMUNICATIONS, INC...

Some links on this page may take you to non-federal websites. Their policies may differ from this site.
Top