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Category:Letter
MONTHYEARGO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan IR 05000397/20230042024-01-29029 January 2024 Integrated Inspection and Independent Spent Fuel Storage Installation Report 05000397/2023004 and 07200035/2023001 GO2-24-003, Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing2024-01-29029 January 2024 Relief Requests for the Columbia Generating Station Fifth Ten-Year Interval Inservice Testing ML24011A1522024-01-10010 January 2024 March 2024 Emergency Preparedness Exercise Inspection-Request for Information GO2-24-005, Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-1702024-01-0808 January 2024 Docket No. 50-397 Supplement to Reply to a Notice of Violation; EA-21-170 GO2-23-136, Guarantee of Payment of Deferred Premium2023-12-20020 December 2023 Guarantee of Payment of Deferred Premium GO2-23-135, Notice of Readiness for Supplemental Inspection2023-12-14014 December 2023 Notice of Readiness for Supplemental Inspection GO2-23-130, Reply to a Notice of Violation; EA-23-0542023-12-14014 December 2023 Reply to a Notice of Violation; EA-23-054 GO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023 Licensing Basis Document Update and Biennial Commitment Change Report ML23288A0002023-12-0707 December 2023 Issuance of Amendment No. 272 to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-107, Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation2023-12-0505 December 2023 Application to Revise Technical Specifications to Adopt TSTS-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-23-126, Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-012023-11-28028 November 2023 Docket No. 50-397 Voluntary Response to Regulatory Issue Summary 2023-01 GO2-23-121, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-27027 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation IR 05000397/20230122023-11-20020 November 2023 Commercial Grade Dedication Inspection Report 05000397/2023012 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV IR 05000397/20230102023-11-0909 November 2023 Biennial Problem Identification and Resolution Inspection Report 05000397/2023010 IR 05000397/20230932023-11-0101 November 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023093 ML23299A2072023-10-26026 October 2023 Biennial Requalification Inspection Request for Information IR 05000397/20230032023-10-25025 October 2023 Integrated Inspection Report 05000397/2023003 IR 05000397/20230112023-10-0404 October 2023 License Renewal Phase 2 Report 05000397/2023011 IR 05000397/20234012023-09-11011 September 2023 Security Baseline Inspection Report 05000397/2023401 GO2-23-097, In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26)2023-09-0606 September 2023 In-Service Inspection Summary Report for the Twenty-Sixth Refueling Outage (R26) ML24032A2182023-09-0101 September 2023 Information Request, Security IR 2024401 GO2-23-100, Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication2023-08-31031 August 2023 Technical Specification Section 5.6.4 Post Accident Monitoring Instrumentation 14-Day Report for Inoperable Suppression Pool Level Indication GO2-23-056, Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling2023-08-29029 August 2023 Application to Revise Technical Specifications to Adopt TSTF-230, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling IR 05000397/20230052023-08-22022 August 2023 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2023005) - Mid Year Letter IR 05000397/20230022023-08-0101 August 2023 Integrated Inspection Report 05000397/2023002 GO2-23-093, Supplement to Reply to a Notice of Violation: EA-21-1702023-07-27027 July 2023 Supplement to Reply to a Notice of Violation: EA-21-170 ML23206A2442023-07-25025 July 2023 Energy Northwest Columbia Generating Station, Response to Apparent Violation in NRC Inspection Report 05000397/2023092; EA-23-054 GO2-23-068, Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation2023-07-19019 July 2023 Notification of Completion of Commitments Required Prior to Entry Into the Period of Extended Operation GO2-23-090, Reply to a Notice of Violation2023-07-12012 July 2023 Reply to a Notice of Violation ML23143A1202023-06-27027 June 2023 Request Number 4ISI-11 to the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Regarding Alternate Examination of Reactor Vessel Welds GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023 Notification of NPDES Permit Issuance ML23163A2502023-06-12012 June 2023 Summary of Changes and Analysis for Revision 41 of Plant Procedures Manual 13.8.1 Emergency Dose Projection System Operations GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023 Cycle 27 Core Operating Limits Report ML23157A2702023-06-0101 June 2023 4-2022-011 -022 Letter - OI Closure to Licensee IR 05000397/20230922023-06-0101 June 2023 NRC Inspection Report 05000397/2023092 and Preliminary White Finding IR 05000397/20230902023-06-0101 June 2023 Final Significance Determination of a White Finding, Notice of Violation and Follow-Up Assessment Letter; NRC Inspection Report 05000397/2023090 GO2-23-055, Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Independent Spent Fuel Storage Installation, 2022 Annual Radiological Environmental Operating Report IR 05000397/20230012023-05-0505 May 2023 Integrated Inspection Report 05000397/2023001 - April 26, 2023 GO2-23-006, License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications2023-05-0101 May 2023 License Amendment Request to Clean-Up Operating License and Appendix a Technical Specifications IR 05000397/20233012023-05-0101 May 2023 NRC Examination Report 05000397/2023301 GO2-23-053, 2022 Annual Environmental Operating Report2023-04-26026 April 2023 2022 Annual Environmental Operating Report GO2-23-057, 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 2022 Annual Radioactive Effluent Release Report ML23110A2642023-04-20020 April 2023 Request for Information License Renewal Phase 2 Inspection GO2-23-012, Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2023-03-27027 March 2023 Application to Revise Technical Specifications to Adopt Tstf-541, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position GO2-23-041, Generation Station - Level of Financial Protection - Annual Reporting Requirement2023-03-15015 March 2023 Generation Station - Level of Financial Protection - Annual Reporting Requirement GO2-23-038, Plant Decommissioning Fund Status Report2023-03-15015 March 2023 Plant Decommissioning Fund Status Report ML23013A0812023-03-15015 March 2023 Issuance of Amendment No. 270 Revision to Technical Specifications to Adopt TSTF 505, Revision 2, Provide Risk-Informed Extended Completion Times-RITSTF Initiative 4B GO2-23-034, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462023-03-13013 March 2023 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 2024-01-08
[Table view] Category:Report
MONTHYEARGO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023 Licensing Basis Document Update and Biennial Commitment Change Report ML21349B3532021-12-15015 December 2021 Attachment 4: Technical Specification Bases, Revision 124 ML21349B3382021-12-15015 December 2021 10 CFR 50.71 Maintenance of Records Licensing Basis Document Update and Biennial Commitment Change Report ML21349B3522021-12-15015 December 2021 Attachment 4: Licensee Controlled Specifications, Revision 122 GO2-21-041, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462021-03-15015 March 2021 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 GO2-20-039, Energy Northwest to EFSEC, Fish Entraiment Characterization Final Report2020-02-26026 February 2020 Energy Northwest to EFSEC, Fish Entraiment Characterization Final Report GO2-19-136, Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to 10 CFR 50.54(F)Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-Ichi2019-09-26026 September 2019 Seismic Probabilistic Risk Assessment Response to NRC Request for Information Pursuant to 10 CFR 50.54(F)Regarding Recommendation 2.1 of the Near-Term Task Force (NTTF) Review of Insights from the Fukushima Dai-Ichi GO2-19-100, Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order No. EA-13-109)2019-08-20020 August 2019 Report of Full Compliance with Phase 1 and Phase 2 of June 6, 2013 Commission Order Modifying Licenses with Regard to Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions (Order No. EA-13-109) GO2-19-035, Energy Northwest to Energy Facility Site Evaluation Council, Columbia Generating Station Fish Entrainment Study Interim Report2019-02-0707 February 2019 Energy Northwest to Energy Facility Site Evaluation Council, Columbia Generating Station Fish Entrainment Study Interim Report ML18285A4502018-04-18018 April 2018 1175ENWCGS, Revision 00, Computational Fluid Dynamics Analysis of Perforated Intake Screens at Columbia Generating Station. GO2-17-139, Technical Specifications Section 5.6.4 Post Accident Monitoring Instrumentation Report2017-08-0303 August 2017 Technical Specifications Section 5.6.4 Post Accident Monitoring Instrumentation Report ML17072A0362017-03-10010 March 2017 Endangered Species Act Section 7(a)(2) Biological Opinion, and Magnuson-Stevens Fishery Conservation Act Essential Fish Habitat Response for Renewing the Operating License for Columbia Generating Station, Richland, Washington ML16337A1092016-12-0707 December 2016 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request; Flood-Causing Mechanism Reevaluation ML16333A0942016-12-0707 December 2016 Current Design Basis Flood Hazards for Use in the MSA GO2-16-104, LAR to Change EAL Scheme2016-07-28028 July 2016 LAR to Change EAL Scheme ML16214A3722016-07-28028 July 2016 Summary of Radiological Calibration Turbine Building Ventilation System Exhaust Monitor TEA-RIS-13 GO2-16-024, Technical Specifications Section 5.6.4 Post Accident Monitoring Instrumentation Report2016-01-25025 January 2016 Technical Specifications Section 5.6.4 Post Accident Monitoring Instrumentation Report GO2-16-001, Independent Spent Fuel Storage Installation, (ISFSI) - Transmittal of the Biennial 50.59/72.48 Report2016-01-20020 January 2016 Independent Spent Fuel Storage Installation, (ISFSI) - Transmittal of the Biennial 50.59/72.48 Report ML15355A4862015-12-21021 December 2015 Revision 87 to Licensee Controlled Specifications (LCS) GO2-15-110, Enclosure 2, Revision 2 to 001N6043.5-NP, Energy Northwest Columbia Generating Station Jet Pump 17/18 Riser Evaluation at 106% Rated Core Flow (115 Mlbs/Hr), Non-Proprietary2015-08-31031 August 2015 Enclosure 2, Revision 2 to 001N6043.5-NP, Energy Northwest Columbia Generating Station Jet Pump 17/18 Riser Evaluation at 106% Rated Core Flow (115 Mlbs/Hr), Non-Proprietary ML14335A1582015-03-25025 March 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) GO2-15-045, Seismic Hazard and Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(F) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident2015-03-12012 March 2015 Seismic Hazard and Screening Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(F) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident GO2-15-039, TIA XXXX-XX, Tower Makeup System Unresolved Issue2015-03-0606 March 2015 TIA XXXX-XX, Tower Makeup System Unresolved Issue ML14176A9612014-06-24024 June 2014 Submittal of Non-Proprietary BWROG Technical Product, BWROGTP-11-006 - ECCS Containment Walkdown Procedure, Rev 1 (January 2011), as Formally Requested During the Public Meeting Held on April 30, 2014 ML14064A3112014-03-11011 March 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident ML13337A2662014-01-29029 January 2014 Interim Staff Evaluation and Audit Report Related to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14037A1752014-01-21021 January 2014 Independent Spent Fuel Storage Installation, Biennial Commitment Changes and 50.59/72.48 Report ML13357A3222013-12-21021 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Columbia Generating Station, TAC No.: MF0796 GO2-13-151, NEDO-33813, Rev. 2, Technical Specification Change Support for Rhr/Lpci and LPCS Flow Rate. Long-Term LOCA Containment Response and ECCS/Non-LOCA Evaluations.2013-09-30030 September 2013 NEDO-33813, Rev. 2, Technical Specification Change Support for Rhr/Lpci and LPCS Flow Rate. Long-Term LOCA Containment Response and ECCS/Non-LOCA Evaluations. ML13241A2642013-08-12012 August 2013 Enclosure 2 - Columbia Generating Station, Final Seismic Walkdown Summary Report (Public Version) ML13108A2192013-04-0404 April 2013 RWCU Regenerative Heat Exchanger Piping Repair Patch Analysis ML13015A2732012-12-31031 December 2012 NEDO-33698, Rev 2, Columbia Generating Station Power Range Neutron Monitoring System Design Report on Computer Integrity, Test and Calibration, and Fault Detection ML13015A2722012-12-31031 December 2012 NEDO-33685, Rev 2, Digital I&C-ISG-06 Compliance for Columbia Generating Station Numac Power Range Neutron Monitoring Retrofit Plus Option III Stability Trip Function. ML12328A0792012-11-30030 November 2012 NEDO-33789, Revision 0, Numac Power Range Neutron Monitoring Components 268X1331TCG001, 268X1332TCG001, G002 268X1333TCG001, Qualification Summary for Energy Northwest (Enw) Columbia Generating Station (Cgs), Attachment 5 ML12328A0782012-10-31031 October 2012 NEDO-33751, Revision 3, Columbia Generating Station Power Range Neutron Monitoring System Reliability Analysis, Attachment 3 GO2-12-165, Initial Seismic Walkdown Summary Report, Enclosure 22012-10-30030 October 2012 Initial Seismic Walkdown Summary Report, Enclosure 2 GO2-12-105, Submittal of Phase 2 Information in Support of License Amendment Request to Change Technical Specifications in Support of Prnm /Arts/Mellla Implementation; NEDO-33750, NEDO-33753; NEDO-33754: NEDO-33755; & NEDO-337582012-07-31031 July 2012 Submittal of Phase 2 Information in Support of License Amendment Request to Change Technical Specifications in Support of Prnm /Arts/Mellla Implementation; NEDO-33750, NEDO-33753; NEDO-33754: NEDO-33755; & NEDO-33758 ML12102A2382012-06-13013 June 2012 Memo Conclusion of Informal Section 7 Consultation with U.S. Fish and Wildlife Service for Columbia Generating Station and Section 7 Consultation Report ML1216000172012-06-11011 June 2012 Review of 60-Day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident ML12101A3952012-05-0404 May 2012 Conclusion of Efh Consultation for Columbia Generating Station and Efh Consultation Report ML12040A0772012-01-31031 January 2012 NEDO-33697, Revision 1, Columbia Generating Station Power Range Neutron Monitoring System Design Analysis Report ML12040A0742012-01-31031 January 2012 NEDO-33685, Revision 1, Digital I&C-ISG-06 Compliance for Columbia Generating Station Numac Power Range Neutron Monitoring Retrofit Plus Option III Stability Trip Function ML12040A0762012-01-31031 January 2012 NEDO-33694, Revision 1, Columbia Generating Station Power Range Neutron Monitoring System Diversity and Defense-in-Depth (D3) Analysis ML12040A0802012-01-31031 January 2012 NEDO-33507, Revision 1, Columbia Generating Station Aprm/Rbm/Technical Specifications / Maximum Extended Load Line Limit Analysis (Arts/Mellla) ML12040A0792012-01-31031 January 2012 NEDO-33698, Revision 1, Columbia Generating Station Power Range Neutron Monitoring System Design Report on Computer Integrity, Test and Calibration, and Fault Detection. Enclosure 2, Attachment 14 to List of Commitments and Enclosure 3 Are ML12040A0752011-11-30030 November 2011 NEDO-33690, Revision 0, Columbia Generating Station Power Range Neutron Monitoring System Response Time Analysis Report GO2-11-180, Response to Request for Additional Information Regarding the License Renewal Application2011-11-10010 November 2011 Response to Request for Additional Information Regarding the License Renewal Application ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants GO2-11-072, 10 CFR 50.46 Report of Changes or Errors in ECCS LOCA Analysis Models2011-04-0505 April 2011 10 CFR 50.46 Report of Changes or Errors in ECCS LOCA Analysis Models ML1024403422010-08-19019 August 2010 Columbia Generating Station - Response to Request for Additional Information License Renewal Application 2023-12-12
[Table view] Category:Miscellaneous
MONTHYEARGO2-23-105, Licensing Basis Document Update and Biennial Commitment Change Report2023-12-12012 December 2023 Licensing Basis Document Update and Biennial Commitment Change Report ML21349B3382021-12-15015 December 2021 10 CFR 50.71 Maintenance of Records Licensing Basis Document Update and Biennial Commitment Change Report GO2-21-041, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462021-03-15015 March 2021 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 GO2-17-139, Technical Specifications Section 5.6.4 Post Accident Monitoring Instrumentation Report2017-08-0303 August 2017 Technical Specifications Section 5.6.4 Post Accident Monitoring Instrumentation Report ML16337A1092016-12-0707 December 2016 Interim Staff Response to Reevaluated Flood Hazards Submitted in Response to 10 CFR 50.54(f) Information Request; Flood-Causing Mechanism Reevaluation ML16333A0942016-12-0707 December 2016 Current Design Basis Flood Hazards for Use in the MSA ML16214A3722016-07-28028 July 2016 Summary of Radiological Calibration Turbine Building Ventilation System Exhaust Monitor TEA-RIS-13 GO2-16-104, LAR to Change EAL Scheme2016-07-28028 July 2016 LAR to Change EAL Scheme GO2-16-024, Technical Specifications Section 5.6.4 Post Accident Monitoring Instrumentation Report2016-01-25025 January 2016 Technical Specifications Section 5.6.4 Post Accident Monitoring Instrumentation Report GO2-16-001, Independent Spent Fuel Storage Installation, (ISFSI) - Transmittal of the Biennial 50.59/72.48 Report2016-01-20020 January 2016 Independent Spent Fuel Storage Installation, (ISFSI) - Transmittal of the Biennial 50.59/72.48 Report ML14335A1582015-03-25025 March 2015 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-13-109 (Severe Accident Capable Hardened Vents) GO2-15-039, TIA XXXX-XX, Tower Makeup System Unresolved Issue2015-03-0606 March 2015 TIA XXXX-XX, Tower Makeup System Unresolved Issue ML14037A1752014-01-21021 January 2014 Independent Spent Fuel Storage Installation, Biennial Commitment Changes and 50.59/72.48 Report ML13241A2642013-08-12012 August 2013 Enclosure 2 - Columbia Generating Station, Final Seismic Walkdown Summary Report (Public Version) ML1216000172012-06-11011 June 2012 Review of 60-Day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Review of Fukushima Dai-ichi Accident ML12101A3952012-05-0404 May 2012 Conclusion of Efh Consultation for Columbia Generating Station and Efh Consultation Report GO2-11-180, Response to Request for Additional Information Regarding the License Renewal Application2011-11-10010 November 2011 Response to Request for Additional Information Regarding the License Renewal Application ML1127000692011-09-26026 September 2011 Enclosure 2, Mfn 10-245 R4, Description of the Evaluation and Surveillance Recommendations for BWR/2-5 Plants GO2-11-072, 10 CFR 50.46 Report of Changes or Errors in ECCS LOCA Analysis Models2011-04-0505 April 2011 10 CFR 50.46 Report of Changes or Errors in ECCS LOCA Analysis Models ML1024403422010-08-19019 August 2010 Columbia Generating Station - Response to Request for Additional Information License Renewal Application ML1012704392010-05-0505 May 2010 Y020100187 - List of Historical Leaks and Spills at U.S. Commercial Nuclear Power Plants ML1002506582010-01-19019 January 2010 Columbia Generating Station - License Renewal Application, Technical Information, Cover Page - 3.3-400 GO2-09-051, Initial License Written Examination Documentation2009-03-23023 March 2009 Initial License Written Examination Documentation ML0832306632008-11-18018 November 2008 Draft of BWROG ECCS Strainers Walkdown Guidance, Rev. C GO2-06-081, Request for Use of Higher Assigned Protection Factors with Use of French-Designed Air-Line Respirator Equipment2006-05-22022 May 2006 Request for Use of Higher Assigned Protection Factors with Use of French-Designed Air-Line Respirator Equipment GO2-05-108, CFR 50.46 Report of Significant Changes in Cycle 17 and 18 Emergency Core Cooling System Evaluation Analysis2005-06-16016 June 2005 CFR 50.46 Report of Significant Changes in Cycle 17 and 18 Emergency Core Cooling System Evaluation Analysis ML0532204612004-06-14014 June 2004 Power Reactor Status Report for 6/14/04 ML0626304082004-03-0101 March 2004 PSEG Nuclear, LLC Salem/Hope Creek Safety Culture Assessment 2023-12-12
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ENERGY David P. Brown Columbia Generating Station NORTHWEST P.O. Box 968, MD PE23 Richland, WA 99352-0968 Ph. 509-377-8385 dpbrown@energy-northwest.com December 15, 2021 10 CFR 50.71(e)
GO2-21-131 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397, 10 CFR 50.71 MAINTENANCE OF RECORDS LICENSING BASIS DOCUMENT UPDATE AND BIENNIAL COMMITMENT CHANGE REPORT
Reference:
Letter, GO2-21-132, R.E. Schuetz (Energy Northwest) to NRC, 10 CFR 50.71 Maintenance of Records - Non-Public Version of the Final Safety Analysis Report
Dear Sir or Madam:
In accordance with the requirements of 10 CFR 50.71(e), Energy Northwest hereby submits the following updated Columbia Generating Station (Columbia) Licensing Basis Documents:
x Final Safety Analysis Report (FSAR), Amendment 66 (Publicly Available) x Licensee Controlled Specifications (LCS), Revision 122 x Technical Specification Bases (TSB), Revision 124 x Operational Quality Assurance Program Description (OQAPD), Revision 57.
In addition to other changes, FSAR Amendment 66 removes some redundant information and excessive detail from the FSAR to improve its focus and clarity. In accordance with Nuclear Energy Institute (NEI) NEI 98-03, Revision 1, Guidelines for Updating Final Safety Analysis Reports, as endorsed by Regulatory Guide 1.181, Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e), a brief description of the information removed is provided in Attachment 1.
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GO2-21-131 Page 2 of 3 Attachment 2 contains the Columbia Generating Station 2020-2021 Commitment Change Report. This report is submitted pursuant to NEI 99-04, Guidelines for Managing NRC Commitment Changes.
Columbia License Basis Documents are provided in electronic format in Attachments 4 and 5. The files are in the Portable Document Format (PDF). Attachment 3 contains a listing of the individual document component file names comprising Attachments 4 and
- 5. The files have been sized to meet file size limitations for electronic submittals.
Additionally, the PDF files in Attachment 5 contain hyperlinks. These hyperlinks are not essential to the FSAR content and are disabled.
Energy Northwest has performed its biennial review of plant changes in accordance with 10 CFR 54.37(b) to determine whether there are any newly identified structures, systems or component (SSC) that require aging management or there are any time limited aging analyses (TLAA) that require re-evaluation. There were no SSCs that met the definition of newly identified. There were no new materials or environments identified. There were also no time limited aging analyses that required re-evaluation.
Consistent with Energy Northwests past FSAR submittals, Energy Northwest is providing a publicly available version of the FSAR (Attachment 5) in which information previously considered to be sensitive unclassified (non-safeguards) information has been removed. A list of information removed from the FSAR submittal is contained in Attachment 6. A complete copy of the FSAR is submitted under separate cover.
There are no commitments being made by this letter; however, one existing commitment has been changed as described in Attachment 2.
If you have any questions or desire additional information pertaining to this report, please contact Mr. R.M. Garcia, Licensing Supervisor, at (509) 377-8463.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on the ____ day of ___________
2021.
Respectfully, David P. Brown Site Vice President
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GO2-21-131 Page 3 of 3 Attachments: 1. Redundant Information and Excessive Detail Removed from the FSAR
- 2. Regulatory Commitment Changes (NEI 99-04 Process)
- 3. Document Components
- 4. Licensee Controlled Specifications, Revision 122 Technical Specification Bases, Revision 124 Operational Quality Assurance Program Description, Revision 57
- 5. Columbia Generating Station FSAR, Amendment 66, Publicly Available
- 6. Information Withheld from Columbia Generating Station FSAR, Amendment 66, Publicly Available (Attachment 5) cc: NRC Region IV Administrator NRC NRR Project Manager NRC Sr. Resident Inspector/988C CD Sonoda- BPA/1399
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GO2-21-131 Attachment 1 Page 1 of 2 Redundant Information and Excessive Detail Removed from the FSAR CHAPTER 3 Section Description of Change Type Table 3.5-2 Delete RRA-FN-16 from table Obsolete information Table 3.6-6 Remove subscript Redundant Information Table 3.9.2c Delete table Excessive Detail CHAPTER 4 Section Description of Change Type 4.3.2.1 Delete reference 4.3-9 Obsolete information Table 4.4-1 Replace GE14 reactor core thermal hydraulic design Obsolete description with GNF2 information Table 4.4-2 Delete table and replace with reference Obsolete information 4.5.1.5 Removed marked up humidity detector statement Obsolete information CHAPTER 6 Section Description of Change Type 6.3.3, 6.3.6, Delete GE14 ECCS performance evaluation Table 6.3-2b, Obsolete Table 6.3-4a, information Table 6.3-4b CHAPTER 8 Section Description of Change Type Delete last two sentences in paragraph prior to 8.3.1.1.7.2.1 8.3.1.1.7.2.2 which is a discussion on the Excessive detail configuration of cross connect breaker CHAPTER 9 Section Description of Change Type 9.5.3.1 c Remove only incandescent sources are used inside Obsolete primary containment. information CHAPTER 15 Section Description of Change Type 15.4.2.3.3 Delete reference to GE14 results Obsolete information
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GO2-21-131 Attachment 1 Page 2 of 2 Appendix A Section Description of Change Type A.2.1.25 and Removed statement at end of each section stating Obsolete A.3.1.26 NFPA recommendations and replaced with Section Information F.2.7.
Appendix F Section Description of Change Type F.4.3.a Delete valve listing through Obsolete F.4.3.f information F.7.5.p Deleted reference to Spec 300-306 Obsolete information F.7.8.e Removed word Transient from procedure title Obsolete information
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GO2-21-131 Attachment 2 Page 1 of 1 Regulatory Commitment Changes (NEI 99-04 Process)
This section reports changes to regulatory commitments consistent with the information pertaining to Regulatory Commitment Changes (RCC) and is included pursuant to the NEI 99-04 criteria for reporting.
The License Renewal commitment to prepare and submit the Inservice Inspection (ISI)
Program was revised to accurately reflect the approved interval dates, as well as the date the program plan was submitted to the NRC. The NRC verbally approved a temporary extension of the third 10-year interval of the ISI Program but the extension was not changed in the FSAR or the Commitment Tracking Log at the time.
The original commitment stated:
Columbia will prepare and submit the ISI Program Plan for the fourth 10-year interval no later than 2015. (The third 10-year ISI interval extends from December 2005 until December 2015.) The Small Bore Piping Program will be included in the fourth 10-year interval ISI Program Plan as an augmented inspection. The locations to be inspected, the sample size, the inspection methodology will be included in the program plan.
Commitment description has been revised to say:
The third 10-year ISI interval was approved by the NRC for extension to January 31, 2016. The fourth 10-year interval ISI Program Plan was issued on January 27, 2016 and was submitted to the NRC on May 8, 2017. The Small Bore Piping Program will be included in the fourth 10-year interval ISI Program Plan as an augmented inspection. The locations to be inspected, the sample size, the inspection methodology will be included in the program plan.
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GO2-21-131 Attachment 3 Page 1 of 1 Document Components TSB, LCS, OQAPD File Name Description Attachment 4_1.pdf LCS Attachment 4_2.pdf TSB Attachment 4_3.pdf OQAPD FSAR Amendment 66, Publicly Available Attachment 5_1 of 10.pdf General Table of Contents &
List of Effective Pages Attachment 5_2 of 10.pdf Chapters 1 & 2 Attachment 5_3 of 10.pdf Chapters 3 and 3a Attachment 5_4 of 10.pdf Chapters 4, 5 & 6 Attachment 5_5 of 10.pdf Chapter 7 Attachment 5_6 of 10.pdf Chapter 8 Attachment 5_7 of 10.pdf Chapter 9 Attachment 5_8 of 10.pdf Chapters 10 & 11 Attachment 5_9 of 10.pdf Chapter 12 Attachment 5_10 of 10.pdf Chapters 13, 14, 15, 16 & 17 Appendices A, B, F, I & J
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GO2-21-131 Attachment 6 Page 1 of 3 Information Withheld From Columbia Generating Station FSAR Amendment 66, Publicly Available (Attachment 5)
Figure Figure/Table Figure Figure Figure 1.2-1 Figure 3.2-5 Figure 3.5-36 Figure 3.6-35.1 Figure 1.2-2.1 Figure 3.2-6 Figure 3.5-37 Figure 3.6-35.2 Figure 1.2-2.2 Figure 3.2-7 Figure 3.5-38 Figure 3.6-36.1 Figure 1.2-3.1 Table 3.5-5 Figure 3.5-39 Figure 3.6-36.2 Figure 1.2-3.2 Figure 3.5-1 Figure 3.5-41 Figure 3.6-37.1 Figure 1.2-4.1 Figure 3.5-2 Figure 3.5-42 Figure 3.6-37.2 Figure 1.2-4.2 Figure 3.5-3 Figure 3.5-43 Figure 3.6-38.1 Figure 1.2-5 Figure 3.5-4 Figure 3.5-44 Figure 3.6-38.2 Figure 1.2-6 Figure 3.5-5 Figure 3.5-45 Figure 3.6-38.3 Figure 1.2-7 Figure 3.5-6 Figure 3.5-46 Figure 3.6-39.1 Figure 1.2-8 Figure 3.5-7 Figure 3.5-47 Figure 3.6-39.2 Figure 1.2-9 Figure 3.5-8 Figure 3.5-49 Figure 3.6-39.3 Figure 1.2-10 Figure 3.5-9 Figure 3.5-50 Figure 3.6-40.1 Figure 1.2-11 Figure 3.5-10 Figure 3.6-1 Figure 3.6-40.2 Figure 1.2-12 Figure 3.5-11 Figure 3.6-2 Figure 3.6-41.1 Figure 1.2-13 Figure 3.5-12 Figure 3.6-3 Figure 3.6-41.2 Figure 1.2-14 Figure 3.5-13 Figure 3.6-4 Figure 3.6-42.1 Figure 1.2-15 Figure 3.5-14 Figure 3.6-5 Figure 3.6-42.2 Figure 1.2-16 Figure 3.5-15 Figure 3.6-6 Figure 3.6-43.1 Figure 1.2-17.1 Figure 3.5-16 Figure 3.6-7 Figure 3.6-43.2 Figure 1.2-17.2 Figure 3.5-17 Figure 3.6-8 Figure 3.6-44.1 Figure 1.2-18 Figure 3.5-18 Figure 3.6-9 Figure 3.6-44.2 Figure 1.2-19 Figure 3.5-19 Figure 3.6-10 Figure 3.6-45.1 Figure 1.2-20 Figure 3.5-20 Figure 3.6-11 Figure 3.6-45.2 Figure 1.2-21 Figure 3.5-21 Figure 3.6-12 Figure 3.6-46.1 Figure 1.2-22 Figure 3.5-22 Figure 3.6-13 Figure 3.6-46.2 Figure 1.2-23 Figure 3.5-23 Figure 3.6-14 Figure 3.6-47.1 Figure 1.2-24 Figure 3.5-24 Figure 3.6-15 Figure 3.6-47.2 Figure 2.1-3 Figure 3.5-25 Figure 3.6-16 Figure 3.6-48.1 Figure 2.4-6.1 Figure 3.5-26 Figure 3.6-17 Figure 3.6-48.2 Figure 2.4-6.2 Figure 3.5-27 Figure 3.6-18 Figure 3.6-49.1 Figure 2.4-6.3 Figure 3.5-28 Figure 3.6-19 Figure 3.6-49.2 Figure 2.4-6.4 Figure 3.5-29 Figure 3.6-20 Figure 3.6-50.1 Figure 2.4-6.5 Figure 3.5-30 Figure 3.6-32.1 Figure 3.6-50.2 Figure 2.4-16 Figure 3.5-31 Figure 3.6-32.2 Figure 3.6-50.3 Figure 2.4-28 Figure 3.5-32 Figure 3.6-33.1 Figure 3.6-51.1 Figure 3.2-2 Figure 3.5-33 Figure 3.6-33.2 Figure 3.6-51.2 Figure 3.2-3 Figure 3.5-34 Figure 3.6-34.1 Figure 3.6-51.3 Figure 3.2-4 Figure 3.5-35 Figure 3.6-34.2 Figure 3.6-52.1
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GO2-21-131 Attachment 6 Page 2 of 3 Information Withheld From Columbia Generating Station FSAR Amendment 66, Publicly Available (Attachment 5)
Figure/Section Figure Figure Figure Figure 3.6-52.2 Figure 3.8-11 Figure 3A.2.1-1 Figure 3A.5.1-14b Figure 3.6-53.1 Figure 3.8-12 Figure 3A.2.1-2 Figure 3A.5.1-15a Figure 3.6-53.2 Figure 3.8-13 Figure 3A.2.1-3 Figure 3A.5.1-15b Figure 3.6-54.1 Figure 3.8-17 Figure 3A.2.1-4 Figure 3A.5.1-16a Figure 3.6-54.2 Figure 3.8-18 Figure 3A.2.1-5 Figure 3A.5.1-16b Figure 3.6-55.1 Figure 3.8-20 Figure 3A.2.1-6 Figure 3A.5.1-17a Figure 3.6-55.2 Figure 3.8-21 Figure 3A.2.1-7 Figure 3A.5.1-17b Figure 3.6-56.1 Figure 3.8-22 Figure 3A.2.1-8 Figure 3A.5.1-18a Figure 3.6-56.2 Figure 3.8-23 Figure 3A.2.1-9 Figure 3A.5.1-18b Figure 3.6-57.1 Figure 3.8-24 Figure 3A.4.1-5 Figure 3A.5.1-19a Figure 3.6-57.2 Figure 3.8-25 Figure 3A.4.1-6 Figure 3A.5.1-19b Figure 3.6-57.3 Figure 3.8-26 Figure 3A.4.1-7 Figure 3A.5.1-20a Figure 3.6-58 Figure 3.8-27 Figure 3A.4.2-1 Figure 3A.5.1-20b Figure 3.6-59 Figure 3.8-28 Figure 3A.4.2-3 Figure 3A.5.1-21a Figure 3.6-60.1 Figure 3.8-29 Figure 3A.5.1-1b Figure 3A.5.1-21b Figure 3.6-60.2 Figure 3.8-30 Figure 3A.5.1-2 Figure 3A.5.1-22a Figure 3.6-65 Figure 3.8-31 Figure 3A.5.1-3a Figure 3A.5.1-22b Figure 3.6-66 Figure 3.8-32 Figure 3A.5.1-3b Figure 3A.5.1-23a Figure 3.6-85 Figure 3.8-33 Figure 3A.5.1-4a Figure 3A.5.1-23b Figure 3.6-86 Figure 3.8-34 Figure 3A.5.1-4b Figure 3A.5.1-24a Figure 3.6-87 Figure 3.8-35 Figure 3A.5.1-5a Figure 3A.5.1-24b Figure 3.6-88 Figure 3.8-36 Figure 3A.5.1-5b Figure 3A.5.1-25a Figure 3.6-92.1 Figure 3.8-37 Figure 3A.5.1-6a Figure 3A.5.1-25b Figure 3.6-92.2 Figure 3.8-38 Figure 3A.5.1-6b Figure 3A.5.1-26a Figure 3.6-92.3 Figure 3.8-39 Figure 3A.5.1-7a Figure 3A.5.1-26b Figure 3.6-93 Figure 3.8-40 Figure 3A.5.1-7b Figure 3A.5.2-1 Figure 3.6-94.1 Figure 3.8-41 Figure 3A.5.1-8a Figure 3A.5.2-2 Figure 3.6-94.2 Figure 3.8-42 Figure 3A.5.1-8b Figure 3A.5.2-3 Figure 3.6-95 Figure 3.8-43 Figure 3A.5.1-9a Figure 3A.5.2-4 Section 3.8.4 Figure 3.8-44 Figure 3A.5.1-9b Figure 3A.5.2-5 Figure 3.8-1 Figure 3.8-45 Figure 3A.5.1-10a Figure 3A.5.2-6 Figure 3.8-2 Figure 3.8-46 Figure 3A.5.1-10b Figure 3A.5.2-7 Figure 3.8-3 Figure 3.8-47 Figure 3A.5.1-11a Figure 3A.5.2-8 Figure 3.8-4.1 Figure 3.8-48 Figure 3A.5.1-11b Figure 3A.5.2-9 Figure 3.8-4.2 Figure 3.8-49 Figure 3A.5.1-12a Figure 3A.5.2-10 Figure 3.8-6 Figure 3.8-50 Figure 3A.5.1-12b Figure 3A.D-11 Figure 3.8-7 Figure 3.8-51 Figure 3A.5.1-13a Figure 3A.I-1 Figure 3.8-8 Figure 3.8-52 Figure 3A.5.1-13b Figure 4.6-4 Figure 3.8-10 Figure 3.8-53 Figure 3A.5.1-14a Figure 5.4-15.3
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GO2-21-131 Attachment 6 Page 3 of 3 Information Withheld From Columbia Generating Station FSAR Amendment 66, Publicly Available (Attachment 5)
Figure/Section Figure/Table Figure/Section Figure Figure 6.2-23 Figure 8.3-2 Figure 12.3-1 Figure F.6-21 Figure 6.2-32 Figure 8.3-4.1 Figure 12.3-2 Figure J.6-1.1 Figure 6.2-33 Figure 8.3-4.2 Figure 12.3-3 Figure J.6-1.2 Figure 8.1-1 Figure 8.3-4.3 Figure 12.3-4 Figure J.6-2.1 Figure 8.1-2.1 Figure 8.3-4.4 Figure 12.3-5 Figure J.6-2.2 Figure 8.1-2.2 Figure 8.3-4.5 Figure 12.3-6 Figure J.6-3.1 Figure 8.1-2.3 Figure 8.3-4.6 Figure 12.3-7 Figure J.6-3.2 Figure 8.1-2.4 Figure 8.3-5 Figure 12.3-8 Figure J.6-4 Figure 8.1-3 Figure 8.3-6 Figure 12.3-9 Figure J.6-5 Figure 8.1-4 Figure 8.3-7 Figure 12.3-10 Figure J.6-6 Figure 8.1-5 Figure 8.3-8 Figure 12.3-11 Figure J.6-7 Figure 8.1-6.1 Figure 8.3-9 Figure 12.3-12 Figure J.6-8 Figure 8.1-6.2 Figure 8.3-10 Figure 12.3-13 Figure J.6-9 Section 8.2.2 Figure 8.3-23 Figure 12.3-14 Figure J.6-10 Figure 8.2-1.1 Figure 8.3-24 Figure 12.3-15 Figure J.6-11 Figure 8.2-1.2 Figure 8.3-25 Figure 12.3-16 Figure J.6-12 Figure 8.2-2.1 Figure 8.3-26 Figure 12.3-17 Figure J.6-13 Figure 8.2-2.2 Figure 8.3-27 Figure 12.3-18 Figure J.6-14 Figure 8.2-3.1 Figure 8.3-28 Figure 12.3-22 Figure J.6-15 Figure 8.2-3.2 Figure 8.3-29 Section F.4.4.4 Figure J.6-16 Figure 8.2-3.3 Figure 8.3-30 Figure F.6-1 Figure J.6-17 Figure 8.2-3.4 Figure 8.3-32 Figure F.6-2 Figure J.6-18 Figure 8.2-4.1 Figure 8.3-33 Figure F.6-3 Figure 8.2-4.2 Figure 8.3-34 Figure F.6-4 Figure 8.2-4.3 Figure 8.3-35 Figure F.6-5 Figure 8.2-4.4 Figure 8.3-36 Figure F.6-6 Figure 8.2-5.1 Figure 8.3-37 Figure F.6-7 Figure 8.2-5.2 Figure 8.3-38 Figure F.6-8 Figure 8.2-5.3 Figure 8.3-52.1 Figure F.6-9 Figure 8.2-5.4 Figure 8.3-52.2 Figure F.6-10 Figure 8.2-6.1 Figure 8.3-53 Figure F.6-11 Figure 8.2-6.2 Figure 9.1-4 Figure F.6-12 Figure 8.2-6.3 Figure 9.1-5 Figure F.6-13 Figure 8.2-6.4 Figure 9.1-13 Figure F.6-14 Figure 8.2-7.1 Figure 9.2-7 Figure F.6-15 Figure 8.2-7.2 Figure 9.2-13 Figure F.6-16 Figure 8.2-7.3 Figure 9.2-14 Figure F.6-17 Figure 8.2-7.4 Table 9.5-1 Figure F.6-18 Figure 8.3-1 Figure 9.5-2 Figure F.6-19 Figure F.6-20