Letter Sequence Response to RAI |
---|
|
|
MONTHYEARGO2-20-118, Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating2020-08-24024 August 2020 Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating Project stage: Response to RAI ML20239A9702020-08-26026 August 2020 NRR E-mail Capture - Columbia Additional Request for Additional Information: Exigent License Amendment Request to Extend Technical Specification 3.8.7, Distribution Systems - Operating, Completion Time Project stage: RAI ML20240A3452020-08-27027 August 2020 Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating Project stage: Response to RAI ML20245E2822020-08-31031 August 2020 NRR E-mail Capture - Columbia Additional Request for Additional Information: Exigent License Amendment Request to Extend Technical Specification 3.8.7, Distribution Systems - Operating, Completion Time Project stage: RAI GO2-20-120, Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating2020-09-0101 September 2020 Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating Project stage: Response to RAI ML20242A0022020-09-0404 September 2020 Issuance of Amendment No. 261 Revise Technical Specification 3.8.7, Distribution Systems - Operating (Exigent Circumstances) Project stage: Approval ML20245H6212020-09-11011 September 2020 Notice of Issuance, License Amendment; Issuance, Opportunity to Request a Hearing, and Petition for Leave to Intervene Project stage: Other ML20245G7742020-09-11011 September 2020 Transmittal Letter with Notice of Issuance, License Amendment; Issuance, Opportunity to Request a Hearing, and Petition for Leave to Intervene Project stage: Other 2020-08-31
[Table View] |
|
---|
Category:Letter
MONTHYEARIR 05000397/20240022024-08-0909 August 2024 Integrated Inspection Report 05000397/2024002 GO2-24-060, Reply to a Notice of Violation, EA-21-170 and EA-23-0542024-07-30030 July 2024 Reply to a Notice of Violation, EA-21-170 and EA-23-054 GO2-24-070, Response to Request for Additional Information Regarding Fifth Interval Inservice Testing Program2024-07-29029 July 2024 Response to Request for Additional Information Regarding Fifth Interval Inservice Testing Program GO2-24-063, Notification of Extension to Columbias Fourth 10-Year Interval Inservice Testing Program Plan2024-07-15015 July 2024 Notification of Extension to Columbias Fourth 10-Year Interval Inservice Testing Program Plan IR 05000397/20240122024-07-10010 July 2024 – Safety Conscious Work Environment Issue of Concern Follow-up Inspection 05000397/2024012 ML24180A1482024-06-28028 June 2024 Notification of an NRC Fire Protection Baseline Inspection (NRC Inspection Report 05000397/2024011) and Request for Information IR 05000397/20244202024-06-27027 June 2024 – Security Baseline Inspection Report 05000397 2024420 Cover Letter GO2-24-057, Notice of Readiness for Supplemental Inspection2024-06-19019 June 2024 Notice of Readiness for Supplemental Inspection ML24099A2232024-06-12012 June 2024 Issuance of Amendment No. 275 to Adopt TSTF-230, Revision 1, Add New Condition B to LCO 3.6.2.3, RHR Suppression Pool Cooling GO2-24-056, Relief Request for the Columbia Generating Station Fourth Ten-Year Interval Inservice Testing2024-06-11011 June 2024 Relief Request for the Columbia Generating Station Fourth Ten-Year Interval Inservice Testing ML24128A2242024-05-31031 May 2024 Issuance of Amendment No. 274 to Revise Technical Specifications to Adopt TSTF-584, Eliminate Automatic RWCU System Isolation on SLC Initiation GO2-24-049, 2023 Annual Radiological Environmental Operating Report2024-05-13013 May 2024 2023 Annual Radiological Environmental Operating Report GO2-24-050, Annual Environmental Operating Report2024-04-30030 April 2024 Annual Environmental Operating Report IR 05000397/20240012024-04-24024 April 2024 Integrated Inspection Report 05000397/2024001 GO2-24-042, 2023 Annual Radioactive Effluent Release Report2024-04-22022 April 2024 2023 Annual Radioactive Effluent Release Report GO2-24-044, Voluntary Response to Regulatory Issue Summary 2024-012024-04-11011 April 2024 Voluntary Response to Regulatory Issue Summary 2024-01 GO2-24-004, License Amendment Request to Revise Emergency Plan2024-01-30030 January 2024 License Amendment Request to Revise Emergency Plan 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 IR 05000397/20230042024-01-29029 January 2024 Integrated Inspection and Independent Spent Fuel Storage Installation Report 05000397/2023004 and 07200035/2023001 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 2024-08-09
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARGO2-24-070, Response to Request for Additional Information Regarding Fifth Interval Inservice Testing Program2024-07-29029 July 2024 Response to Request for Additional Information Regarding Fifth Interval Inservice Testing Program GO2-22-122, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-11-28028 November 2022 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-096, Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2022-10-0404 October 2022 Supplement to License Amendment Request to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b GO2-22-075, Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves2022-07-11011 July 2022 Response to Request for Additional Information Related to Revised Pressure-Temperature Limit Curves GO2-21-101, Response to Request for Additional Information Related to Remove License Condition 2.C.(34) and Revise License Condition 2.C.(35)2021-08-24024 August 2021 Response to Request for Additional Information Related to Remove License Condition 2.C.(34) and Revise License Condition 2.C.(35) GO2-21-108, Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO2021-08-20020 August 2021 Response to Request for Additional Information Related to License Amendment Request to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO GO2-21-084, Response to Request for Additional Information Related to On-Site Cooling System Sediment Disposal2021-06-23023 June 2021 Response to Request for Additional Information Related to On-Site Cooling System Sediment Disposal GO2-20-150, Response to Request for Additional Information Related to Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-On-Force Exercises, Due to COVID-192020-12-0303 December 2020 Response to Request for Additional Information Related to Request for a One-Time Exemption from 10 CFR 73, Appendix B, Section VI, Subsection C.3.(I)(1) Regarding Annual Force-On-Force Exercises, Due to COVID-19 GO2-20-127, Response to Request for Additional Information Related to Fourth Interval Inservice Inspection (ISI) Program Request 4ISI-092020-10-22022 October 2020 Response to Request for Additional Information Related to Fourth Interval Inservice Inspection (ISI) Program Request 4ISI-09 GO2-20-120, Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating2020-09-0101 September 2020 Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating ML20240A3452020-08-27027 August 2020 Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating GO2-20-118, Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating2020-08-24024 August 2020 Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating GO2-20-086, Response to Request for Additional Information Related to Reduction in Commitment to the Columbia Operational Quality Program Description2020-06-0101 June 2020 Response to Request for Additional Information Related to Reduction in Commitment to the Columbia Operational Quality Program Description GO2-20-071, Response to Request for Additional Information Related to Exigent License Amendment Request for One-Time Change to Completion Times for Inoperable Electrical Distribution Systems2020-04-23023 April 2020 Response to Request for Additional Information Related to Exigent License Amendment Request for One-Time Change to Completion Times for Inoperable Electrical Distribution Systems GO2-20-029, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance...2020-02-19019 February 2020 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance... GO2-19-124, Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating2019-08-20020 August 2019 Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating GO2-19-111, Response to Request for Additional Information Related to License Amendment Request for Licensing Basis Change to Control Room Air Conditioning System2019-07-30030 July 2019 Response to Request for Additional Information Related to License Amendment Request for Licensing Basis Change to Control Room Air Conditioning System GO2-18-102, Response to Supplemental Information Needed for Acceptance of Requested Licensing Action Re-Renewed Facility Operating License and Technical Specification Clean-Up2018-08-0707 August 2018 Response to Supplemental Information Needed for Acceptance of Requested Licensing Action Re-Renewed Facility Operating License and Technical Specification Clean-Up GO2-18-075, Response to Request for Additional Information for TSTF-542 License Amendment Request2018-06-27027 June 2018 Response to Request for Additional Information for TSTF-542 License Amendment Request ML18191A2052018-06-19019 June 2018 Forwards Response to NRC Comments of July 7, 1977 and February 23, 1978 on Caorso Test Plan GO2-17-186, Response to Request for Additional Information Related to License Amendment Request - Revise Technical Specification 5.5.12 for Permanent Extension of Type a Test and Type C Leak Rate Test Frequencies2018-01-0202 January 2018 Response to Request for Additional Information Related to License Amendment Request - Revise Technical Specification 5.5.12 for Permanent Extension of Type a Test and Type C Leak Rate Test Frequencies GO2-17-204, Energy Northwest Submittal of the Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 Crf 50.54(F) Regarding Recommendation 2.1 of the Near-Term Task Force Review ...2017-12-28028 December 2017 Energy Northwest Submittal of the Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 Crf 50.54(F) Regarding Recommendation 2.1 of the Near-Term Task Force Review ... GO2-17-175, Response to Request for Additional Information Related to License Amendment Request for Reclassifying Quality Group of Low Temperature Portions of Reactor Water Cleanup System2017-11-20020 November 2017 Response to Request for Additional Information Related to License Amendment Request for Reclassifying Quality Group of Low Temperature Portions of Reactor Water Cleanup System GO2-17-166, Response to Request for Additional Information for Relief Request 3ISI-192017-10-0303 October 2017 Response to Request for Additional Information for Relief Request 3ISI-19 GO2-17-107, Response to Request for Additional Information for Relief Request 3ISI-162017-06-26026 June 2017 Response to Request for Additional Information for Relief Request 3ISI-16 GO2-17-119, Supplement to Response to Request for Additional Information Related to License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01 Revision 62017-06-21021 June 2017 Supplement to Response to Request for Additional Information Related to License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI 99-01 Revision 6 GO2-17-093, Response to Request for Supplemental Information Related to Generic Letter 2016-01, Monitoring of Neutro-Absorbing Materials in Spent Fuel Pools - Licensee-Reported Category 3 Plants2017-05-0202 May 2017 Response to Request for Supplemental Information Related to Generic Letter 2016-01, Monitoring of Neutro-Absorbing Materials in Spent Fuel Pools - Licensee-Reported Category 3 Plants ML17066A4932017-03-0707 March 2017 Submittal of Additional Information in Response to Mur LAR: Primary Element Accuracy Calculation GO2-17-048, Response to Request for Additional Information Related to License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI-99-01 Revision 6 (MF8219)2017-02-23023 February 2017 Response to Request for Additional Information Related to License Amendment Request to Adopt Emergency Action Level Scheme Pursuant to NEI-99-01 Revision 6 (MF8219) GO2-17-049, Response to Request for Additional Information, Columbia Mur LAR Evib Rais, Enclosure 22017-02-16016 February 2017 Response to Request for Additional Information, Columbia Mur LAR Evib Rais, Enclosure 2 GO2-17-014, Response to Request for Additional Information Human Performance2017-01-0909 January 2017 Response to Request for Additional Information Human Performance GO2-16-173, Supplement to Response to Request for Additional Information Related to Columbia LAR: Fire Protection RAI-12016-12-12012 December 2016 Supplement to Response to Request for Additional Information Related to Columbia LAR: Fire Protection RAI-1 GO2-16-161, Response to Request for Additional Information, Columbia Mur LAR: Esgb, Coating and FAC2016-12-0808 December 2016 Response to Request for Additional Information, Columbia Mur LAR: Esgb, Coating and FAC GO2-16-155, Response to Request for Additional Information for License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in Technical Specification 2.1.1, Reactor Core Sls from the Reactor Systems Branch2016-11-17017 November 2016 Response to Request for Additional Information for License Amendment Request to Reduce the Reactor Steam Dome Pressure Specified in Technical Specification 2.1.1, Reactor Core Sls from the Reactor Systems Branch GO2-16-153, Response to Request for Additional Information Regarding Mur License Amendment Request Fire Protection2016-11-10010 November 2016 Response to Request for Additional Information Regarding Mur License Amendment Request Fire Protection GO2-16-128, Response to Request for Additional Information Related to Relief Request 4ISI-06 Regarding Code Case N-666-12016-09-20020 September 2016 Response to Request for Additional Information Related to Relief Request 4ISI-06 Regarding Code Case N-666-1 GO2-16-107, Response to Request for Additional Information Related to Relief Request 4ISI-05 Regarding Reactor Pressure Vessel Flange Leak-Off Lines and Code Case N-8052016-08-0303 August 2016 Response to Request for Additional Information Related to Relief Request 4ISI-05 Regarding Reactor Pressure Vessel Flange Leak-Off Lines and Code Case N-805 GO2-16-090, Response to Request for Additional Information for Relief Request 4ISI-022016-07-14014 July 2016 Response to Request for Additional Information for Relief Request 4ISI-02 GO2-16-070, Response to Request for Additional Information Associated with Expedited Seismic Evaluation Process Submittal2016-05-17017 May 2016 Response to Request for Additional Information Associated with Expedited Seismic Evaluation Process Submittal GO2-16-057, Response to Second Request for Additional Information RAI) Related to an Amendment to Adopt Technical Specification Task Force (TSTF)-425, Revision 3 to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program2016-04-0707 April 2016 Response to Second Request for Additional Information RAI) Related to an Amendment to Adopt Technical Specification Task Force (TSTF)-425, Revision 3 to Relocate Specific Surveillance Frequencies to a Licensee Controlled Program GO2-15-173, Supplement to Response to Second Request for Additional Information on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 32015-12-28028 December 2015 Supplement to Response to Second Request for Additional Information on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3 GO2-15-152, Response to Second Request for Additional Information on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 32015-11-17017 November 2015 Response to Second Request for Additional Information on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3 GO2-15-145, Response to Request to Additional Information (RAI) 3 on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 32015-10-29029 October 2015 Response to Request to Additional Information (RAI) 3 on License Amendment Request for Adoption of Technical Specification Task Force (TSTF)-425, Revision 3 GO2-16-021, R02 15-5462, Revision a, Expedited Seismic Evaluation Process (ESEP) Report2015-10-27027 October 2015 R02 15-5462, Revision a, Expedited Seismic Evaluation Process (ESEP) Report GO2-15-137, Response to the Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Reevaluations2015-09-24024 September 2015 Response to the Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Reevaluations GO2-15-128, Response to Request for Additional Information Regarding License Amendment Request for Adopt Technical Specification Task Force (TSTF)-425, Revision 32015-09-17017 September 2015 Response to Request for Additional Information Regarding License Amendment Request for Adopt Technical Specification Task Force (TSTF)-425, Revision 3 ML18191A2031978-06-30030 June 1978 Response to NRC Request for Additional Information (Round 3 Questions) ML18191A2381977-12-16016 December 1977 Advising of Intention to Complete Evaluation Regarding BWR Relief Valve Control System & Associated Containment Loads for Wppss Nuclear Project No. 2 Is Scheduled During 2nd Quarter of 1978 ML18191A8101976-04-28028 April 1976 Wppss Nuclear Project No. 2 Post-Construction Permit Item Drywell/Wetwell Leakage Study ML18191A2741976-01-12012 January 1976 Wppss Nuclear Project No. 2. Clarification of Criteria, Pipe Rupture Protection Inside Containment 2024-07-29
[Table view] |
Text
R.E. Schuetz ENERGY Columbia Generating Station P.O. Box 968, PE23 Richland, WA 99352-0968 NORTHWEST Ph. 509.377.2425 l F. 509.3774140 reschuetz@energy-northwest.com August 27, 2020 GO2 20-119 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
COLUMBIA GENERATING STATION, DOCKET NO. 50-397 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO EXIGENT LICENSE AMENDMENT REQUEST FOR CHANGE TO TECHNICAL SPECIFICATION 3.8.7 DISTRIBUTION SYSTEMS - OPERATING
References:
- 1. Letter from R.E. Schuetz, Energy Northwest, to NRC, Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating, dated August 20, 2020 (ADAMS Accession Number ML20233A976)
- 2. Email from S. Lee, NRC, to D. M. Wolfgramm, Energy Northwest, Columbia Request for Additional Information: Exigent License Amendment Request to Extend Technical Specification 3.8.7, Distribution Systems - Operating, completion time (EPID: L-2020-LLA-0180), dated August 22, 2020
- 3. Letter from R.E. Schuetz, Energy Northwest, to NRC, Response to Request for Additional Information Related to Exigent License Amendment Request for Change to Technical Specification 3.8.7 Distribution Systems - Operating, dated August 24, 2020 (ADAMS Accession Number ML20238A706)
- 4. Email from S. Lee, NRC to D. M. Wolfgramm, Energy Northwest, Columbia additional request for additional information: Exigent license amendment request to extend Technical Specification 3.8.7, Distribution Systems - Operating, completion time (EPID: L-2020-LLA-0181), dated August 26, 2020
Dear Sir or Madam:
By Reference 1, Energy Northwest submitted an exigent License Amendment Request for a change to Technical Specification (TS) 3.8.7 Distribution Systems - Operating. By Reference 2 the Nuclear Regulatory Commission (NRC) requested additional information related to the Energy Northwest submittal. By Reference 3 Energy Northwest submitted responses to Reference 2. By Reference 4, the NRC issued a second request for additional information. The enclosure to this letter contains the requested information.
GO2-20-119 Page 2 of 2 The No Significant Hazards Consideration Determination provided in the original submittal is not altered by this submittal. No new commitments are being made by this letter or the enclosure.
If there are any questions or if additional information is needed, please contact Ms. D.M.
Wolfgramm, Regulatory Affairs Manager, at 509-377-4792.
I declare under penalty of perjury that the foregoing is true and correct.
Executed this 27th day of August, 2020.
Respectfully, R.E. Schuetz Site Vice President
Enclosure:
As stated cc: NRC RIV Regional Administrator NRC NRR Project Manager NRC Senior Resident Inspector NRC NRR Plant Licensing Branch Chief CD Sonoda - BPA/1399 EFSECutc.wa.gov - EFSEC E Fordham - WDOH R Brice - WDOH L Albin - WDOH
GO2-20-119 Enclosure Page 1 of 9 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION
Background
By letter dated August 20, 2020 (Agencywide Documents Access and Management System (ADAMS) Accession number ML20233A976), Energy Northwest (the licensee) requested a license amendment to revise the Columbia Generating Station Technical Specification (TS) 3.8.7, Distribution Systems - Operating. This license amendment request (LAR) would add a one-time extension of the Completion Time (CT) of TS Action 3.8.7.A, from 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to 16 hours1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br />, specifically associated with Division 2 Alternating Current (AC) electrical power distribution inoperability caused by inoperability of Division 2, 120/240V Power Panel E-PP-8AE during repairs on its supply transformer E-TR-8A/1. The NRC staff has reviewed the LAR and determined that additional information is required to complete the review. The NRC staff issued request for additional information (RAIs) on August 22, 2020. The NRC staffs additional RAIs are listed below. The staff may have additional RAIs. The staff held an RAI clarification call with Energy Northwest on August 26, 2020. The Energy Northwest staff requested, and NRC agreed, to a RAI response by August 27, 2020.
NRC RAI No. 6:
Based on review of responses to RAI No. 2 and 5, in order to provide confidence that the following three voltage regulating type distribution transformers (which are also nearing their end of life - approximate 10 years from the date of last installation) would not fail/degrade during the requested allowed outage time (AOT) extension, please provide voltage plots for the following power panels (similar to voltage plots for panels E-PP-8AE, E-PP-7AE provided in response to RAI No. 5 Question 1).
E-PP-8AF (E-TR-8A/2)
E-PP-7AA (E-TR-IN/3)
E-PP-8AA (E-TR-IN/2)
Energy Northwest Response to RAI No. 6:
TS Bases 3.8.7 AC Distribution Systems Operating notes that OPERABLE AC electrical power distribution subsystems require the associated buses to be energized to their proper voltages. The figure below plots data obtained from weekly voltage surveillance under TS Surveillance Requirement (SR) 3.8.7.1 for E-PP-8AF.
GO2-20-119 Enclosure Page 2 of 9 E-PP-8AF - E-TR-8A/2 Voltage 122.0 121.5 121.0 120.5 120.0 119.5 119.0
-E-PP-8AF -E-PP-8AF Phase A-G* Phase B-G*
E-PP-7AA receives input voltage from two sources - normally from in-service redundant inverters E-IN-3A/3B, or from bypass source regulating transformer E-TR-IN/3.
Similarly, E-PP-8AA receives input voltage from two sources - normally from in-service redundant inverters E-IN-2A/2B, or from bypass source regulating transformer E-TR-IN/2. The power panels E-PP-7AA and E-PP-8AA receive power via the static switch which monitors and transfers the load (i.e. the power panels) between the inverter and the bypass regulating transformer. Refer to drawing E504-1 in RAI 1 response in letter (ADAMS Accession Number ML20238A706).
Weekly voltage surveillance under TS SR 3.8.7.1 is done by the station for the power panels E-PP-7AA and E-PP-8AA. These readings represent inverter supplied voltage and not E-TR-IN/2 or E-TR-IN/3 supplied voltage. However, the static switch monitors the voltage from these transformers and provides an alarm. This alarm goes to the in-service inverter for Alternate Source Undervoltage light on the front of each inverter and provides a main control room trouble alarm input either IN-2A/2B Trouble, or IN-3A/3B Trouble. The alarm is set at 216 volts alternating current (VAC) which would indicate that E-TR-IN/2 or E-TR-IN/3 have a degraded output. The main control room trouble alarm prompts Operations to respond according to their alarm procedure for each inverter.
A condition report search was performed for the past two years which shows that these alarms have come in three times for IN-3A/3B Trouble. Although the alarm came in three times from the Alternate Source Undervoltage input alarm for E-IN-3A/3B, they were due to a switching transient and not due to a degraded transformer output.
Similarly, a condition report search was performed for the past two years which shows that the alarm has come in once for IN-2A/2B Trouble. This alarm was due to a grid
GO2-20-119 Enclosure Page 3 of 9 hit that momentarily took the inverter and alternate source out of sync. The condition was corrected after the grid hit and it was not from a degradation of E-TR-IN/2.
The alternate source is used if there is a failure of the inverter to supply power to the vital instrument bus E-PP-7AA or E-PP-8AA, or for planned maintenance such as transferring loads between the inverters E-IN-2A and E-IN-2B, or between the inverters E-IN-3A and E-IN-3B. When the vital instrument bus is lined up to the alternate source (E-TR-IN/2 or E-TR-IN/3) an entry into TS 3.8.7.A is required until the bus is powered from the inverter.
The voltages that are shown on the following graphs for E-PP-7AA and E-PP-8AA are voltages that are taken with the inverter supplying the vital instrument busses which is the normal and preferred lineup.
E-PP-7 AA Voltage 123.5 123.0 122.5 122.0 121.5 121.0 120.5
~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~
~ ~ ~ ~ ~ 'f"(:, ~ ~ ~ ~ ~ ~ ~ ~ ~
<-,~ G::,~ '\1' 'o~ 0,~ ..,,(;;)# ..,,'\)~ V'~ '):~ 'V~ ,,,~ I;,.~ <,~ (o~ '\1'
-E-PP-7M -E-PP-7M Phase A-G Phase B-G
GO2-20-119 Enclosure Page 4 of 9 E-PP-8AA Voltage 123.0 122.5 122.0 121.5 121.0 120.5 120.0
-E-PP-8M -E-PP-8M Phase A-G Phase B-G Based on available data and the fact that these transformers are "current" per station PM strategy, there is no evidence to suggest these transformers would fail during the planned replacement of E-TR-8A/1.
NRC RAI No. 7:
Based on the voltage plot of panel E-PP-7AE (response to RAI No. 5 Question 1), the E-TR-7A/1 transformer also appears to be showing sign of degradation. Please describe that the plant can safely shutdown under the following scenario: Loss of offsite power (LOOP) and loss of transformer E-TR-7A/1 (Division 1) while transformer E-TR-8A/1 (Division 2) is under maintenance.
Energy Northwest Response to RAI No. 7:
As discussed in the original License submittal, power panel E-PP-8AE provides power to a range of plant equipment. Systems which are most impacted by de-energization of E-PP-8AE are the Standby Gas Treatment (SGT) System, Containment Instrument Air (CIA) System, Automatic Depressurization System (ADS), Reactor Building Heating Ventilation and Air Conditioning (RB HVAC), and Primary and Secondary Containment Isolation Valves (PCIVs/SCIVs).
Operational impact summary for de-energizing power panel E-PP-8AE:
SGT System E-PP-8AE provides power to the SGT B standby electric strip heaters and some instrumentation. Loss of power to the SGT B instrumentation falsely results in some Main Control Room (MCR) annunciator actuation; e.g., differential pressure across
GO2-20-119 Enclosure Page 5 of 9 the carbon filter. The operating crew will still be able to determine that SGT B is operating correctly using MCR system flow and local differential pressure instrumentation. SGT B is capable of starting normally, both manually and automatically, and capable of fulfilling its safety function with the remaining heaters.
ADS The operating crew will be able to operate all main steam relief valves (MSRVs) normally. The Division B ADS MSRVs will be able to perform their safety function.
CIA System The normal nitrogen supply will isolate and all of the Division B backup nitrogen bottles will be placed in service simultaneously. The operating crew will be able to operate all MSRVs normally. The Division B ADS MSRVs will be able to perform their safety function. Following repairs to E-TR-8A/1 the operating crew will ensure that the Division B CIA nitrogen bottles have the required pressure.
Standby Liquid Control (SLC) System There is no short term impact expected from the loss of heat trace.
RB HVAC System SGT A will be placed in service to maintain Secondary Containment pressure negative. SGT A will be operable while it is in service.
Shutting down RB HVAC may cause the temperature in areas of the plant to rise.
This may require securing systems prior to high temperature isolations occurring; e.g. Reactor Water Clean Up (RWCU). Following repairs to E-TR-8A/1 the operating crew will restore those systems to service.
PCIVs The vast majority of these PCIVs are normally closed. The normally closed PCIVs will still fulfill their safety function when E-PP-8AE power is lost.
The exceptions are the suppression pool to reactor building vacuum relief isolation PCIVs. These valves fail open fulfilling their safety function to allow the suppression pool to reactor building vacuum relief valves to prevent excessive negative pressure in primary containment. Following repairs to E-TR-8A/1 the operating crew will ensure these valves close.
GO2-20-119 Enclosure Page 6 of 9 SCIVs The valves close on loss of power fulfilling their safety function. There is no operational impact beyond isolating RB HVAC.
Power panel E-PP-7AE provides power to a range of plant equipment. Systems which are most impacted by de-energization of E-PP-7AE are the Control Room Emergency Filtration (CREF) System, Control Room Air Conditioning (AC), SGT System, CIA System, ADS, RB HVAC, and PCIVs/SCIVs.
Brief descriptions of these systems if not already described above and Operational impact summary for de-energizing power panel E-PP-7AE:
CREF System The CREF system consists of two emergency filter units each with an emergency filter fan and a charcoal absorber carbon filter. The CREF system utilizes ground level remote fresh air intakes, the normal air intake is isolated. The CREF system operates in conjunction with the associated AC system.
E-PP-7AE provides power to CREF air dampers and instrumentation. The division 1 CREF subsystem will not perform its safety function when power is lost to E-PP-7AE.
Control Room Air Conditioning (AC) System The AC system consists of two subsystems each with one fan and two coolers; one supplied by service water, and one supplied by control room emergency chilled water system.
E-PP-7AE supplies power to the Division 1 temperature control valves of the AC system. The division 1 AC system will not provide control room cooling when power is lost to E-PP-7AE.
SGT System E-PP-7AE provides power to the SGT A standby electric strip heaters and some instrumentation. Loss of power to the SGT A instrumentation falsely results in some Main Control Room (MCR) annunciator actuation; e.g., differential pressure across the carbon filter. The operating crew will still be able to determine that SGT A is operating correctly using MCR system flow and local differential pressure instrumentation. SGT A is capable of starting normally, both manually and automatically, and capable of fulfilling its safety function with the remaining heaters.
GO2-20-119 Enclosure Page 7 of 9 ADS The operating crew will be able to operate all MSRVs normally. The Division A ADS MSRVs will be able to perform their safety function.
CIA System E-PP-7AE provides power to several valves and the nitrogen bottle programmer in the CIA system. These components are related to both the normal and backup supply of nitrogen to the Division A ADS MSRVs. When E-PP-7AE is de-energized the normal nitrogen supply will isolate and all of the Division A nitrogen bottles will be placed in service simultaneously. The Division A ADS MSRVs will be able to perform their safety function.
RB HVAC System E-PP-7AE provides power to components in both the intake and exhaust pathways of the RB HVAC system. When E-PP-7AE is de-energized the RB HVAC system will isolate.
Shutting down RB HVAC may cause the temperature in areas of the plant to rise.
This may require securing systems prior to high temperature isolations occurring; e.g., Reactor Water Clean Up (RWCU).
PCIVs E-PP-7AE provides power to the PCIVs in several systems. The vast majority of these PCIVs are normally closed. The normally closed PCIVs will fulfill their safety function when E-PP-7AE power is lost.
SCIVs The valves close on loss of power fulfilling their safety function. There is no operational impact.
If we lose E-PP-7AE while performing maintenance on E-PP-8AE, we would require entry into TS limiting condition for operation (LCO) 3.0.3 and require the plant to be in mode 4 within 37 hours4.282407e-4 days <br />0.0103 hours <br />6.117725e-5 weeks <br />1.40785e-5 months <br />. The loss of both E-PP-7AE and 8AE will not prevent the plant from safely shutting down, removing decay heat, or achieving and maintaining cold shutdown using normal operating procedures.
GO2-20-119 Enclosure Page 8 of 9 Operational impact summary of de-energizing both E-PP-7AE and E-PP-8AE:
CREF System E-PP-7AE provides power to CREF air dampers and instrumentation. The division 1 CREF subsystem will not perform its safety function when power is lost to E-PP-7AE. The division 2 CREF will perform its safety function even with power lost to E-PP-8AE since division 2 is not powered from E-PP-8AE.
Control Room Air Conditioning (AC) System E-PP-7AE supplies power to the Division 1 temperature control valves of the AC system. The division 1 AC system will not provide control room cooling when power is lost to E-PP-7AE. The division 2 AC system will provide control room cooling even with power lost to E-PP-8AE since division 2 is not powered from E-PP-8AE.
SGT System Both SGT A and B are capable of starting normally, both manually and automatically, and capable of fulfilling its safety function with the remaining heaters.
However, the moisture alarms and instrumentation will be de-energized.
ADS The operating crew will be able to operate all MSRVs normally. All ADS MSRVs will be able to perform their safety function.
CIA System The normal nitrogen supply will isolate and all of the Division A and B backup nitrogen bottles will be placed in service simultaneously. The operating crew will be able to operate all MSRVs normally. The Division A and B ADS MSRVs will be able to perform their safety function.
SLC System There is no short term impact expected from the loss of heat trace.
RB HVAC System One train of SGT will be placed in service to maintain Secondary Containment pressure negative. SGT will be operable while it is in service.
GO2-20-119 Enclosure Page 9 of 9 Shutting down RB HVAC may cause the temperature in areas of the plant to rise.
This may require securing systems prior to high temperature isolations occurring; e.g. Reactor Water Clean Up (RWCU).
PCIVs The vast majority of these PCIVs are normally closed. The normally closed PCIVs will still fulfill their safety function when E-PP-7AE and E-PP-8AE power is lost.
The exceptions are the suppression pool to reactor building vacuum relief isolation PCIVs. These valves fail open fulfilling their safety function to allow the suppression pool to reactor building vacuum relief valves to prevent excessive negative pressure in primary containment.
SCIVs The valves close on loss of power fulfilling their safety function. There is no operational impact beyond isolating RB HVAC.
The loss of offsite power combined with the loss of E-PP-7AE while E-PP- 8AE maintenance is being performed will not prevent the plant from safely shutting down, removing decay heat, or achieving and maintaining cold shutdown since the onsite diesel generators will provide power to the necessary equipment with existing procedures.