Pages that link to "10 CFR 50.120, Training and Qualification of Nuclear Power Plant Personnel"
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The following pages link to 10 CFR 50.120, Training and Qualification of Nuclear Power Plant Personnel:
Displayed 50 items.
- 10 CFR 50.54, Conditions of licenses (← links)
- 10 CFR 50.120 (redirect page) (← links)
- 10 CFR 50 (← links)
- IR 05000259/2007006 (← links)
- IR 05000382/2010005 (← links)
- IR 05000391/2015611 (← links)
- IR 05000390/2015611 (← links)
- 05000382/FIN-2010005-09 (← links)
- ML17046A537 (← links)
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- IR 05000361/2017002 (← links)
- IR 05000361/2017007 (← links)
- IR 05000416/2017014 (← links)
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- IR 05000335/1997011 (← links)
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- ML11131A133 (← links)
- ML111310633 (← links)
- ML110390263 (← links)
- ML110390224 (← links)
- NRC Generic Letter 2006-02 (← links)
- RIS 2000-13, Annual Report on the Effectiveness of Training in the Nuclear Industry for Calendar Year 1999 (← links)
- ML17157B247 (← links)
- ML18066A030 (← links)
- ML18024A321 (← links)
- ML17310A423 (← links)
- ML17298A868 (← links)
- ML060230011 (← links)
- ML18095A053 (← links)
- ML17290A005 (← links)
- ML18114A410 (← links)
- ML18093A907 (← links)
- DCL-17-038, Diablo Canyon Power Plant, Units 1 & 2, Revised Updated Final Safety Analysis Report, Rev. 23, Chapter 13, Conduct of Operations (← links)
- LR-N17-0088, Hope Creek Generating Station Updated Final Safety Analysis Report, Rev. 22, Chapter 13, Conduct of Operation (← links)
- LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 13.2, Training (← links)
- WM 16-0008, Wolf Creek Generating Station, Redacted Version of Revision 29 to Updated Safety Analysis Report, Chapter 13.0 - Conduct of Operations (← links)
- NRC-16-0034, Fermi 2 Revision 20 to Updated Final Safety Analysis Report, Chapter 13 (← links)
- NL-15-169, Browns Ferry, Units 1, 2, and 3, Template of NRC Review Standard for Extended Power Uprates, RS-001 Safety Evaluation Template GDC Markup (Retyped) (← links)
- BVY 13-096, Technical Specifications Proposed Change No. 307 Revision to Mitigation Strategy License Condition and Technical Specification Administrative Controls for Permanently Defueled Condition Vermont Yankee Nuclear Power Station (← links)
- NG-17-0111, Duane Arnold Energy Center, Revision 24 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations (← links)
- RS-11-100, Dresden, Units 2 and 3, Updated Final Safety Analysis Report (Ufsar), Revision 9, Chapter 13.0, Conduct of Operations Tables (← links)
- ML110110031 (← links)
- ML103420549 (← links)
- ML102500650 (← links)
- ML102460731 (← links)
- ML102120061 (← links)
- ML100210972 (← links)
- ML092960449 (← links)
- ML092810227 (← links)
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- ML082820029 (← links)
- ML082800200 (← links)
- ML082670360 (← links)
- ML082610423 (← links)
- WM 08-0003, Wolf Creek Updated Safety Analysis Report (Usar), Revision 21, Chapter 13 (← links)
- ML081790747 (← links)
- ML081640535 (← links)
- ML081570316 (← links)
- ML081510173 (← links)
- ML081260004 (← links)
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- ML18198A361 (← links)
- ML18143B713 (← links)
- ML17347A794 (← links)
- ML17338A072 (← links)
- ML17312B075 (← links)
- RS-16-201, Quad Cities Nuclear Power Station, Units 1 and 2 - License Amendment Request- Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition (← links)
- ML16259A347 (← links)
- ML16091A267 (← links)
- ML16013A217 (← links)
- ML16011A351 (← links)
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- ML073440041 (← links)
- IR 05000361/2007017 (← links)
- ML072680397 (← links)
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- ML060950434 (← links)
- ML060950363 (← links)
- ML060950306 (← links)
- ML060950094 (← links)
- ML060940432 (← links)
- LIC-06-0025, 60 Day Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power (← links)
- NL-06-0540, Southern Nuclear Operating Co., 60-Day Response to Generic Letter 2006-02, Grid Reliability and Impact on Plant Risk and the Operability of Offsite Power (← links)
- ML060610598 (← links)
- ML060050028 (← links)
- ML060040310 (← links)
- ML042470016 (← links)
- ML18269A174 (← links)
- ML18261A161 (← links)
- ML18236A870 (← links)
- ML17212A083 (← links)
- ML18277A289 (← links)
- ML18270A130 (← links)
- ML18267A259 (← links)
- L-18-145, Firstenergy Nuclear Operating Company Request for Approval of Certified Fuel Handler Training Program (← links)
- CNRO-2012-00009, Entergy Responses to Request for Additional Information Regarding Changes to the Quality Assurance Program Manual & Associated Plant Technical Specifications Re Staff Qualifications (← links)
- CNRO-2012-00004, Request for Additional Information Regarding Changes to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Plant Technical Specifications Regarding Staff Qualifications (← links)
- CNRO-2011-00006, Request for Approval of Change to the Entergy Quality Assurance Program Manual (QAPM) and Associated Plant Technical Specifications Regarding Staff Qualifications (← links)
- CNL-18-069, Tennessee Valley Authority - Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revisions 35 and 36 (← links)
- CNL-17-154, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 34 (← links)
- CNL-16-204, Bellefonte, Units 1 and 2, Browns Ferry, Units 1, 2, and 3, Sequoyah, Units 1 and 2, Watts Bar, Units 1 and 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, Revision 33 (← links)
- CNL-16-085, Bellefonte, Browns Ferry, Sequoyah, and Watts Bar - Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A (← links)
- CNL-14-162, Bellefonte, Units 1 and 2, Browns Ferry, Units 1, 2, and 3, Sequoyah, Units 1 and 2, Watts Bar, Units 1 & 2, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A (← links)
- CNL-13-134, Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A (← links)
- ML18305B419 (← links)
- ML18285A609 (← links)
- ML18233A533 (← links)
- LIC-17-0020, Response to Request for Additional Information, Final Request for Additional Information Concerning Post-Shutdown Eplan Amendment (← links)
- LIC-16-0092, License Amendment Request 16-03, Technical Specifications to Align Staffing Requirements to Those Required for Decommissioning (← links)
- LIC-16-0076, License Amendment Request (LAR) 16-02: Revise the Fort Calhoun Station Emergency Plan to Address the Permanently Defueled Condition (← links)
- LIC-16-0049, Request for Approval of Certified Fuel Handler Training Program (← links)
- RC-15-0182, Transmittal of the Quality Assurance Program Description (QAPD) (← links)
- RC-15-0109, License Amendment Request - LAR 14-02981, Proposed Revision to Technical Specification 6.0, Administrative Controls. (← links)
- NL-18-0074, License Amendment Request for Technical Specification 3.3.8.1 Regarding Degraded Voltage Protection (← links)
- LIC-17-0048, Response to Request for Additional Information Regarding the Fort Calhoun Station Request to Revise Technical Specifications to Align Staffing Requirements for Permanently Defueled Condition (← links)
- NL-09-141, Submittal of Response to Request for Supplemental Information Regarding the Spent Fuel Transfer License Amendment (← links)
- LR-N09-0103, Submittal of 2008 Summary of Revised Regulatory Commitments (← links)
- NL-07-1925, Revised Technical Specifications Revision Request, Section 5.3.1 - Unit Staff Qualifications (← links)
- ULNRC-05313, Follow-Up Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and Operability of Offsite Power. (← links)
- LR-N06-0131, Response to NRC Generic Letter 2006-02 Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. (← links)
- NL-06-043, Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power (← links)
- DCL-06-042, 60-Day Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. (← links)
- DCL-05-121, Correction of Information Contained in License Amendment Request 05-04. Revision to Technical Specification 5.3.1. 'Unit Staff Qualifications.' (← links)
- ML19029A009 (← links)
- ML19017A253 (← links)
- TMI-17-060, Request for Approval of Certified Fuel Handler Training Program (← links)
- TMI-13-105, Update 10 of the Post-Defueling Monitored Storage Safety Analysis Report (← links)
- TMI-13-050, Re-issue of Update 9 of the Post-Defueling Monitored Storage Safety Analysis Report (← links)
- ML18334A143 (← links)
- ML17298B251 (← links)
- ML071270283 (← links)
- ML062200317 (← links)
- ML062140589 (← links)
- ML062090523 (← links)
- ML053010152 (← links)
- ML19015A137 (← links)
- L-18-254, License Amendment Request - Proposed Changes to Technical Specifications Sections 1.1, Definitions, and 5.0, Administrative Controls, for Permanently Defueled Condition (← links)
- RC-17-0069, (Vcsns), Unit 1 - Quality Assurance Approval Certificate No. 0479, Transmittal of the Quality Assurance Program Description (← links)
- PNP 2017-035, License Amendment Request - Administrative Controls for a Permanently Defueled Condition (← links)
- L-2017-122, NextEra Energy Quality Assurance Topical Report (FPL-1) Revision 21 Annual Submittal (← links)
- PNP 2017-010, Program Approval - Certified Fuel Handler Training and Retraining Program (← links)
- RA-17-012, License Amendment Request - Proposed Changes to the Oyster Creek Emergency Plan for Permanently Defueled Condition (← links)
- NL-16-2486, Submittal of Quality Assurance Topical Report, Version 15.0 (← links)
- RS-16-201, License Amendment Request- Proposed Changes to Technical Specifications Section 5.0 Administrative Controls for Permanently Defueled Condition (← links)
- LR-N16-0175, License Amendment Request - Administrative Controls (← links)
- JAFP-16-0131, Response to Request for Additional Information Regarding Request for Approval of a Certified Fuel Handler Training and Retraining Program (← links)
- RS-16-153, License Amendment Request for Proposed Change to Technical Specifications Section 5.0, Administrative Controls for Permanently Defueled Condition (← links)
- RA-16-058, Response to Request for Additional Regarding Approval of Certified Fuel Handler Training Program (← links)
- JAFP-16-0078, Response to Request for Additional Information (RAI) Regarding Request for Approval of Certified Fuel Handler Training and Retaining Program (← links)
- L-2016-117, Revised-Annual Summary of Commitment Changes Implemented Without Prior NRC Notification for Calendar Year 2015 (← links)
- RA-16-021, License Amendment Request for Proposed Changes to Technical Specifications Section 6.0 Administrative Controls for Permanently Defueled Condition (← links)
- NLS2016020, Emergency Plan Implementing Procedures, Including Revision 67 to EPIP 5.7.6, Revision 35 to EPIP 5.7.7, Revision 26 to Tpp 101 (← links)
- JAFP-16-0012, Attachments 1 - 6: License Amendment Request to Revise the Emergency Plan to Address the Permanently Defueled Condition (← links)
- RA-16-005, Request for Approval of Certified Fuel Handler Training Program (← links)
- JAFP-15-0143, License Amendment Request Revision to Technical Specification Administrative Controls for Permanently Defueled Condition (← links)
- JAFP-15-0142, Request for Approval of a Certified Fuel Handler Training and Retraining Program (← links)
- L-15-341, License Amendment Request to Modify Technical Specifications 5.3.1 (← links)
- NG-19-0003, Request for Approval of Certified Fuel Handler Training Program (← links)
- RS-16-140, Request for Approval of Certified Fuel Handler Training Program Relevant to Clinton, Quad Cities, and Oyster Creek Stations (← links)
- NL-16-0998, Edwin I. Hatch Nuclear Plant; Vogtle Electric Generating Plant - Quality Assurance Topical Report (← links)
- BVY 14-054, Proposed Changes to the Vermont Yankee Emergency Plan - Supplement 2 (← links)
- NL-13-2418, Edwin I. Hatch Nuclear Plant; Vogtle Electric Generating Plant - Quality Assurance Topical Report (← links)
- BVY 13-095, Request for Approval of Certified Fuel Handler Training Program (← links)
- PNP 2013-017, Response to NRC Draft Safety Evaluation for License Amendment Request Replacement of Spent Fuel Pool Region I Storage Racks (← links)
- PNP 2013-015, Entergy Nuclear Operations, Inc. Response to NRC Draft Safety Evaluation for License Amendment Request Replacement of Spent Fuel Pool Region I Storage Racks (← links)
- RA-12-007, License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators (← links)
- NL-11-1435, Edwin I. Hatch Nuclear Plant, Vogtle Electric Generating Plant, Quality Assurance Topical Report (← links)
- L-2010-122, Proposed License Amendment, Application to Delete Structural Integrity Technical Specifications, Update Accident Monitoring Instrumentation Requirements, and Minor Corrections (← links)
- L-2009-262, Proposed License Amendment Application to Delete Structural Integrity Technical Specifications, Update Accident Monitoring Instrumentation Requirements, and Minor Corrections (← links)
- L-2008-150, Duane Arnold, and Point, Beach, Units 1 and 2, Quality Assurance Topical Report (QATR-FPL-1) Revisions 1 & 2 (← links)
- L-07-093, Response to Confirmatory Order EA-06-152 (← links)
- RS-07-078, Amergen - License Amendment Request to Change Technical Specification Unit Staff Qualifications Education and Experience Eligibility Requirements for Licensed Operators (← links)
- ML19028A030 (← links)
- NOC-AE-13002962, License Amendment Request for Approval of a Revision to the South Texas Project Fire Protection Program Related to the Alternative Shutdown Capability (← links)
- NOC-AE-13002981, Supplemental Reply to Notice of Violation EA-12-227 (← links)
- NOC-AE-12002929, Reply to Notice of Violation EA-12-227 (← links)
- NMP1L2956, License Amendment Request Pursuant to 10 CFR 50.90: Change to Technical Specification Requirement Regarding Education and Experience Eligibility Requirements for Licensed Operators (← links)
- NOC-AE-11002643, License Amendment Request for Approval of a Revision to the South Texas Project Fire Protection Program Related to the Alternative Shutdown Capability (← links)
- L-2019-050, License Amendment Request (TSCR-181): Application to Align Technical Specification Staffing and Administrative Requirements for Permanently Defueled Condition (← links)
- NL-19-013, Proposed Technical Specifications Change - Administrative Controls for Permanently Defueled Condition (← links)
- NL-19-012, Request for Approval of a Certified Fuel Handler Training and Retraining Program (← links)
- ML19101A262 (← links)
- L-2016-129, NextEra Energy Quality Assurance Topical Report (QATR FPL-1) Revision 19 Annual Submittal (← links)
- L-2015-184, Units 1 and 2, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 17 (← links)
- L-2013-208, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 13 (← links)
- CNL-19-043, Bellefont Nuclear Plant, Units 1 & 2; Browns Ferry Nuclear Plan, Units 1, 2 & 3; Clinch River Nuclear Site; Sequoyah Nuclear Plant, Units 1 & 2; and Watts Bar Nuclear Plant, Units 1 & 2 - Nuclear Quality Assurance Plan, TVA-NQA-PLN89-A, R (← links)
- ML19123A101 (← links)
- ML19092A087 (← links)
- ML19155A164 (← links)
- ML19007A070 (← links)
- L-2011-243, Submittal of Quality Assurance Topical Report (QATR FPL-1), Revision 9 (← links)
- L-2010-138, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 7 (← links)
- ML19175A071 (← links)
- ML19101A396 (← links)
- ML19101A395 (← links)
- NOC-AE-08002366, License Amendment Request for Deviation from Fire Protection Program Requirements (← links)
- L-2006-246, Response to RAI Follow-Up Questions Regarding Fpl'S Common Quality Assurance Topical Report Request (← links)
- L-2006-208, Plants - Response to Request for Additional Information Regarding Common Quality Assurance Topical Report (← links)
- WM 06-0027, Day Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. (← links)
- L-HU-06-030, Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. (← links)
- NL-06-2352, Southern Nuclear Operating Company Quality Assurance Topical Report (← links)
- GO2-06-092, Supplemental Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. (← links)
- HNP-06-032, Day Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. (← links)
- BSEP 06-0026, Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power (← links)
- LR-N06-0132, Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. (← links)
- BVY 06-032, Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. (← links)
- 0CAN030601, Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power (← links)
- NOC-AE-06001979, 60-Day Response to NRC Generic Letter 2006-02: Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. (← links)
- NRC-06-0013, 60-Day Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power (← links)
- L-2006-073, NRC Generic Letter 2006/02 60-Day Response (← links)
- PLA-6031, Response to NRC Generic Letter 2006-02 Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power PLA-6031 (← links)
- RNP-RA/06-0014, Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power (← links)
- L-2006-067, Request for Approval of FPL Quality Assurance Topical Report (← links)
- GNRO-2006/00014, Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power (← links)
- NLS2006008, Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power, Dated February 1, 2006 (← links)
- JAFP-06-0057, Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power (← links)
- NRC Generic Letter 06-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power (← links)
- RA-19-0006, License Amendment Application to Relocate Technical Specification Unit/Facility Staff Qualification ANSI N18.1-1971, ANSI/ANS-3.1-1978 and ANSI/ANS-3.1-1981 Requirements to the Duke Energy Corporation Quality Assurance Program Description (← links)
- ML19213A160 (← links)
- L-2019-134, Units 1 and 2 - Quality Assurance Topical Report, Revision 22, Annual Submittal (← links)
- ML18351A453 (← links)
- L-2014-201, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 14 (← links)
- L-2009-134, Submittal of Quality Assurance Topical Report (QATR FPL-1) Revision 4 (← links)
- ML19204A287 (← links)
- NL-19-0710, Quality Assurance Topical Report Submittal (← links)
- W3F1-2006-0014, Response to Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power (← links)
- CY-05-152, Proposed Change to Revision 5 of the Connecticut Yankee Quality Assurance Program (← links)
- SECY-04-0233, Atch3 - Draft Regulatory Guide 1136, Demonstrating the Feasibility and Reliability of Operator Manual Actions in Response to Fire (← links)
- ML19240A383 (← links)
- ML19205A218 (← links)
- ML18247A251 (← links)
- ML18180A141 (← links)
- ML18065A194 (← links)
- NUREG-1650, Rev 7, the United States of America Eighth National Report for the Convention on Nuclear Safety. (← links)
- ML19275F299 (← links)
- ML19114A191 (← links)
- ML19114A162 (← links)
- ML19302E170 (← links)
- ML19165A286 (← links)
- CPSES-200601160, Revised Response to the 60-Day Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. (← links)
- CPSES-200600580, 60-Day Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. (← links)
- ML19270D454 (← links)
- ML15222A880 (← links)
- ML15334A250 (← links)
- BVY 06-080, Vermont Yankee, Extended Power Uprate - License Amendment No. 229 Clarifications to Nrc'S Final Safety Evaluation (← links)
- RS-06-036, Egc/Amergen, 60-Day Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. (← links)
- ML053470194 (← links)
- ML053470094 (← links)
- ML053010167 (← links)
- ML052490337 (← links)
- ML052450178 (← links)
- ML052200226 (← links)
- ML052150047 (← links)
- ML051960044 (← links)
- NLS2005037, License Amendment Request to Revise Technical Specifications - Unit Staff Qualifications (← links)
- ML051300559 (← links)
- ML051300556 (← links)
- ML051300552 (← links)
- ML051300550 (← links)
- ML051300544 (← links)
- ML051300539 (← links)
- DCL-19-094, License Amendment Request 19-02 to Relocate Technical Specification 5.3, Unit Staff Qualifications, to the Updated Final Safety Analysis Report (← links)
- ML19297D159 (← links)
- ML050700416 (← links)
- ML050600380 (← links)
- ML050560337 (← links)
- ML050560150 (← links)
- ML050340189 (← links)
- ML050140453 (← links)
- ML050140293 (← links)
- ML19340A065 (← links)
- ML19333B868 (← links)
- ML20015A413 (← links)
- ML19310C204 (← links)
- 3F0817-03, Rev. 0, Defueled Safety Analysis Report (← links)
- 3F0514-08, NRC Commitment Change Report - May 2014 (← links)
- 3F0214-04, Response to Request for Additional Information for Approval of the Certified Fuel Handler Training and Retraining Program (← links)
- ML20029D014 (← links)
- L-20-009, License Amendment Request - Proposed Change to Technical Specifications Sections 1.1. Definitions, and 5.0 Administrative Controls. for Permanently Defueled Condition (← links)
- ML15334A249 (← links)
- ML15222A877 (← links)
- ML20036D465 (← links)
- ML19241A427 (← links)
- ML19030A488 (← links)
- L-2018-123, Quality Assurance Program Description for 10 CFR Part 52 Licenses FPL-2 Revision 4 (← links)
- ML18310A341 (← links)
- ML18228A665 (← links)
- ML18227A141 (← links)
- ML18212A345 (← links)
- ML18178A222 (← links)
- ML18086A191 (← links)
- ML18081A099 (← links)
- ND-18-0295, Nuclear Development Quality Assurance Manual Version 18.0 (← links)
- ML18079A480 (← links)
- ML18053A739 (← links)
- ML18003A495 (← links)
- ND-12-0606, Report of Changes to Quality Assurance Program Description (← links)
- NG-20-0006, Request for Approval of NextEra Energy Duane Arnold, Llc'S Quality Assurance Topical Report (FPL-3) Revision 0 (← links)
- ML20049A025 (← links)
- ML20046D527 (← links)
- ML20046C666 (← links)
- ML20046B971 (← links)
- ML110040885 (← links)
- ML083050449 (← links)
- ML20056D651 (← links)
- 3F0406-06, 60-Day Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. (← links)
- ML20034F637 (← links)
- ND-20-0005, Enclosure - Nuclear Development Quality Assurance Manual Version 20.0 (← links)
- ML042960007 (← links)
- 10 CFR 50.1, Basis, Purpose, and Procedures Applicable (← links)
- 10 CFR 50.2, Definitions (← links)
- 10 CFR 50.3, Interpretations (← links)
- 10 CFR 50.4, Written Communications (← links)
- 10 CFR 50.5, Deliberate Misconduct (← links)
- 10 CFR 50.7, Employee Protection (← links)
- 10 CFR 50.8, Information Collection Requirements: Omb Approval (← links)
- 10 CFR 50.9, Completeness and Accuracy of Information (← links)
- 10 CFR 50.10, License Required; Limited Work Authorization (← links)
- 10 CFR 50.11, Exceptions and Exemptions From Licensing Requirements (← links)
- 10 CFR 50.12, Specific Exemptions (← links)
- 10 CFR 50.13, Attacks and Destructive Acts by Enemies of the United States; and Defense Activities (← links)
- 10 CFR 50.20, Two Classes of Licenses (← links)
- 10 CFR 50.21, Class 104 Licenses; for Medical Therapy and Research and Development Facilities (← links)
- 10 CFR 50.22, Class 103 Licenses; for Commercial and Industrial Facilities (← links)
- 10 CFR 50.23, Construction Permits (← links)
- 10 CFR 50.30, Filing of Application for Licenses; Oath Or Affirmation (← links)
- 10 CFR 50.31, Combining Applications (← links)
- 10 CFR 50.32, Elimination of Repetition (← links)
- 10 CFR 50.33, Contents of Applications; General Information (← links)
- 10 CFR 50.34, Contents of Applications; Technical Information (← links)
- 10 CFR 50.36, Technical Specifications (← links)
- 10 CFR 50.37, Agreement Limiting Access to Classified Information (← links)
- 10 CFR 50.38, Ineligibility of Certain Applicants (← links)
- 10 CFR 50.39, Public Inspection of Applications (← links)
- 10 CFR 50.40, Common Standards (← links)
- 10 CFR 50.41, Additional Standards for Class 104 Licenses (← links)
- 10 CFR 50.42, Additional Standard for Class 103 Licenses (← links)
- 10 CFR 50.43, Additional Standards and Provisions Affecting Class 103 Licenses and Certifications for Commercial Power (← links)
- 10 CFR 50.44, Combustible Gas Control for Nuclear Power Reactors (← links)
- 10 CFR 50.45, Standards for Construction Permits, Operating Licenses, and Combined Licenses (← links)
- 10 CFR 50.46, Acceptance Criteria for Emergency Core Cooling Systems for Light-Water Nuclear Power Reactors (← links)
- 10 CFR 50.47, Emergency Plans (← links)
- 10 CFR 50.48, Fire Protection (← links)
- 10 CFR 50.49, Environmental Qualification of Electric Equipment Important to Safety for Nuclear Power Plants (← links)
- 10 CFR 50.50, Issuance of Licenses and Construction Permits (← links)
- 10 CFR 50.51, Continuation of License (← links)
- 10 CFR 50.52, Combining Licenses (← links)
- 10 CFR 50.53, Jurisdictional Limitations (← links)
- 10 CFR 50.55, Conditions of Construction Permits, Early Site Permits, Combined Licenses, and Manufacturing Licenses (← links)
- 10 CFR 50.56, Conversion of Construction Permit to License; Or Amendment of License (← links)
- 10 CFR 50.57, Issuance of Operating License. (← links)
- 10 CFR 50.58, Hearings and Report of the Advisory Committee On Reactor Safeguards (← links)
- 10 CFR 50.59, Changes, Tests and Experiments (← links)
- 10 CFR 50.60, Acceptance Criteria for Fracture Prevention Measures for Lightwater Nuclear Power Reactors for Normal Operation (← links)
- 10 CFR 50.61, Fracture Toughness Requirements for Protection Against Pressurized Thermal Shock Events (← links)
- 10 CFR 50.62, Requirements for Reduction of Risk From Anticipated Transients Without Scram (Atws) Events for Light-Water-Cooled Nuclear Power Plants (← links)
- 10 CFR 50.63, Loss of All Alternating Current Power (← links)