Letter Sequence Response to RAI |
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MONTHYEARGO2-19-090, License Amendment Request to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-08-15015 August 2019 License Amendment Request to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program Project stage: Request GO2-19-137, Supplemental Information Related to License Amendment Request to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-09-12012 September 2019 Supplemental Information Related to License Amendment Request to Revise Technical Specifications to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program Project stage: Supplement ML19262F6782019-09-19019 September 2019 NRR E-mail Capture - Subject: Columbia Generating Station - Acceptance of Requested Licensing Action TSTF-563 Amendment Project stage: Acceptance Review 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... Project stage: Response to RAI ML20135H0842020-06-29029 June 2020 Issuance of Amendment No. 260 Revise Technical Specifications to Adopt TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program Project stage: Approval 2019-09-19
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Category:Letter type:GO
MONTHYEARGO2-24-088, Supplement to Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan2024-09-24024 September 2024 Supplement to Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan GO2-24-051, Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements2024-09-23023 September 2024 Application to Revise Technical Specifications to Adopt TSTF-592, Revise Automatic Depressurization System (ADS) Instrumentation Requirements GO2-24-082, Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan2024-09-10010 September 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan 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 GO2-24-057, Notice of Readiness for Supplemental Inspection2024-06-19019 June 2024 Notice of Readiness for Supplemental Inspection 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 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 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 GO2-24-034, Supplement to License Amendment Request to Revise Columbia Generating Station Emergency Plan2024-03-20020 March 2024 Supplement to License Amendment Request to Revise Columbia Generating Station Emergency Plan GO2-24-041, Level of Financial Protection - Annual Reporting Requirement2024-03-12012 March 2024 Level of Financial Protection - Annual Reporting Requirement GO2-24-036, Presentation Information for Pre-Application Meeting Regarding Columbia’S Replacement Steam Dryer Evaluation Approach for Extended Power Uprate2024-03-11011 March 2024 Presentation Information for Pre-Application Meeting Regarding Columbia’S Replacement Steam Dryer Evaluation Approach for Extended Power Uprate GO2-24-039, Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.462024-03-11011 March 2024 Report of Changes or Errors in Emergency Core Cooling System Loss of Coolant Accident Analysis Models Pursuant to 10 CFR 50.46 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 GO2-24-014, Independent Spent Fuel Storage Installation, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2024-01-15015 January 2024 Independent Spent Fuel Storage Installation, Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation 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 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 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) 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 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 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 GO2-23-073, Notification of NPDES Permit Issuance2023-06-26026 June 2023 Notification of NPDES Permit Issuance GO2-23-072, Cycle 27 Core Operating Limits Report2023-06-0505 June 2023 Cycle 27 Core Operating Limits Report 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 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 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 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 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 GO2-23-035, Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-03-0909 March 2023 Supplement to License Amendment Request to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling GO2-23-019, Emergency Plan - Summary of Changes and Analysis for Revision 68 of the EP-012023-02-0808 February 2023 Emergency Plan - Summary of Changes and Analysis for Revision 68 of the EP-01 GO2-22-131, Guarantee of Payment of Deferred Premium2022-12-19019 December 2022 Guarantee of Payment of Deferred Premium 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 GO2-22-076, Status of License Renewal Commitments2022-10-31031 October 2022 Status of License Renewal Commitments GO2-22-110, Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor2022-10-17017 October 2022 Supplement to License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactor 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 2024-09-24
[Table view] Category:Response to Request for Additional Information (RAI)
MONTHYEARGO2-24-088, Supplement to Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan2024-09-24024 September 2024 Supplement to Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan GO2-24-082, Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan2024-09-10010 September 2024 Response to Request for Additional Information Regarding License Amendment Request to Revise Columbia Emergency Plan 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 GO2-22-122, 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 2024-09-24
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R.E. Schuetz Columbia Generating Station P.O. Box 968, PE23 Richland, WA 99352-0968 Ph. 509.377.2425 l F. 509.377.4150 rescheutz@energy-northwest.com February 19, 2020 GO2-20-029 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 LICENSE AMENDMENT REQUEST TO REVISE TECHNICAL SPECIFICATIONS TO ADOPT TSTF-563, "REVISE INSTRUMENT TESTING DEFINITIONS TO INCORPORATE THE SURVEILLANCE FREQUENCY CONTROL PROGRAM"
References:
- 1. Letter from R. E. Schuetz, Energy Northwest to NRC, dated August 15, 2019 (ADAMS Accession Number ML19227A397)
- 2. Letter from R. E. Schuetz, Energy Northwest to NRC, dated September 12, 2019 (ADAMS Accession Number ML19255H995)
- 3. Email from J. Klos, NRC to D. M. Wolfgramm, Energy Northwest, dated February 3, 2020 (ADAMS Accession Number ML20034E608)
Dear Sir or Madam:
By Reference 1 and as supplemented by Reference 2, Energy Northwest submitted a license amendment request to adopt Technical Specification Task Force (TSTF)-563 into Columbia Generating Station (Columbia) Technical Specification (TS). By Reference 3 the U.S. Nuclear Regulatory Commission (NRC) requested additional information related to the Energy Northwest submittal. Enclosure 1 to this letter contains the requested information. Enclosure 2 provides a markup of Columbia TS. provides a clean copy of Columbia TS.
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, Licensing Supervisor, at 509-377-4792.
GO2-20-029 Page 2 of 2 I declare under penalty of perjury that the foregoing is true and correct.
Executed this ______ day of ___________, 201x.
Respectfully, R. E. Schuetz Site Vice President
Enclosures:
As stated cc: NRC RIV Regional Administrator NRC Senior Resident Inspector/988C NRC NRR Project Manager CD Sonoda - BPA/1399 EFSECutc.wa.gov - EFSEC E Fordham - WDOH R Brice - WDOH L Albin - WDOH
GO2-20-029 Page 1 of 2 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION NRC REQUEST No. STSB-RAI-1:
The license proposes to delete the language, so that the entire channel is tested, from the Channel Functional Test definition in Columbia [Columbia Generating Station] TS
[Technical Specification]. Columbias Channel Functional Test definition states:
A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps, so that the entire channel is tested.
Columbias Channel Functional Test definition differs from that in the Standard Technical Specifications on which TSTF-563 is based. The Channel Functional Test definition in the Boiling Water Reactor (BWR)/4 and BWR/6 Standard Technical Specifications NUREG- 1433 and 1434, Revision 4.0 states: (TSTF-563 Changes are shown in bold italics)
The CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.
The technical evaluation for the addition of the phrase in bold italics above is contained in the NRC staffs final safety evaluation of TSTF-563, Revision 0, and final model safety evaluation of TSTF-563, Revision 03. These safety evaluations do not describe nor provide a technical evaluation for any deletions of any kind contained in TSTF-563.
The deletion of the language from Columbias Channel Functional Test definition is a variation from TSTF-563.
Background:
In the letter dated September 12, 2019, Energy Northwest stated that deleting, so that the entire channel is tested from the definition of Channel Functional Test more closely aligns with the definition as described in TSTF-563 and as a point of clarification and consistent with the understanding expressed in TSTF-563 and the NRC Safety Evaluation, the requirement to perform a Channel Functional Test on the entire channel has not changed. The deletion of the language, so that the entire channel is tested, from Columbias Channel Functional Test appears to change the requirement to test the entire channel. Because Columbias Channel Functional Test definition differs from the
GO2-20-029 Page 2 of 2 Standard Technical Specifications in that it does not contain the language to verify operability of, all devices in the channel, it appears that the requirement to perform the Channel Functional Test on the entire channel may have changed and that the NRC staff model safety evaluation may not be applicable to this proposed change. Therefore, the NRC staff is requesting the following additional information be submitted.
Explain if the language in Columbias Channel Functional Test that states, including required alarm, interlock, display, and trip functions, and channel failure trips, describes the entire channel leaving nothing out and is equivalent to the language, all devices in the channel, or alternatively provide the technical basis for removing the requirement to test the entire channel during the Channel Functional Test.
ENERGY NORTHWEST RESPONSE TO RAI 1:
Energy Northwest has modified the Columbia TS markup for the Channel Functional Test to align with the language in NUREG-1434. The markup shows the generic language used in the Standard Technical Specifications. Columbia will continue to test all the devices in the channel (i.e. required alarm, interlock, display, and trip functions, and channel trips). This is an acceptable variation and does not change the conclusion of Final Safety Evaluation provided in the December 4, 2018 letter to the Technical Specification Task Force (ADAMS Accession Number ML18333A146).
GO2-20-029 Technical Specification Markup
Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions
NOTE-----------------------------------------------------------
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.
Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
AVERAGE PLANAR LINEAR The APLHGR shall be applicable to a specific planar height HEAT GENERATION RATE and is equal to the sum of the LHGRs for all the fuel rods in (APLHGR) the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.
CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel.
The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step so that the entire channel is calibrated.
CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
CHANNEL FUNCTIONAL A CHANNEL FUNCTIONAL TEST shall be the injection of a TEST simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY, including required alarm, interlock, display, and trip functions, and Columbia Generating Station 1.1-1 Amendment No. 149,169 225
Definitions 1.1 channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, Columbia Generating Station 1.1-2 Amendment No. 149,169 225
Definitions 1.1 1.1 Definitions CHANNEL FUNCTIONAL TEST (Continued) overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step so that the entire channel is tested.
CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel.
The following exceptions are not considered to be CORE ALTERATIONS:
- a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and
- b. Control rod movement, provided there are no fuel assemblies in the associated core cell.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle REPORT (COLR) specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.3. Plant operation within these limits is addressed in individual Specifications.
DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same Total Effective Dose Equivalent (TEDE) dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The dose conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1988.
DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:
a) The water inventory above the TAF is divided by the limiting drain rate; Columbia Generating Station 1.1-3 Amendment No. 190,199 225 251
GO2-20-029 Technical Specification Clean Pages
Definitions 1.1 1.0 USE AND APPLICATION 1.1 Definitions
NOTE-----------------------------------------------------------
The defined terms of this section appear in capitalized type and are applicable throughout these Technical Specifications and Bases.
Term Definition ACTIONS ACTIONS shall be that part of a Specification that prescribes Required Actions to be taken under designated Conditions within specified Completion Times.
AVERAGE PLANAR LINEAR The APLHGR shall be applicable to a specific planar height HEAT GENERATION RATE and is equal to the sum of the LHGRs for all the fuel rods in (APLHGR) the specified bundle at the specified height divided by the number of fuel rods in the fuel bundle at the height.
CHANNEL CALIBRATION A CHANNEL CALIBRATION shall be the adjustment, as necessary, of the channel output such that it responds within the necessary range and accuracy to known values of the parameter that the channel monitors. The CHANNEL CALIBRATION shall encompass the entire channel, including the required sensor, alarm, display, and trip functions, and shall include the CHANNEL FUNCTIONAL TEST. Calibration of instrument channels with resistance temperature detector (RTD) or thermocouple sensors may consist of an inplace qualitative assessment of sensor behavior and normal calibration of the remaining adjustable devices in the channel.
The CHANNEL CALIBRATION may be performed by means of any series of sequential, overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.
CHANNEL CHECK A CHANNEL CHECK shall be the qualitative assessment, by observation, of channel behavior during operation. This determination shall include, where possible, comparison of the channel indication and status to other indications or status derived from independent instrument channels measuring the same parameter.
CHANNEL FUNCTIONAL A CHANNEL FUNCTIONAL TEST shall be the injection of a TEST simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, Columbia Generating Station 1.1-1 Amendment No. 149,169 225
Definitions 1.1 1.1 Definitions CHANNEL FUNCTIONAL TEST (Continued) overlapping, or total channel steps, and each step must be performed within the Frequency in the Surveillance Frequency Control Program for the devices included in the step.
CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components within the reactor vessel with the vessel head removed and fuel in the vessel.
The following exceptions are not considered to be CORE ALTERATIONS:
- a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement); and
- b. Control rod movement, provided there are no fuel assemblies in the associated core cell.
Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.
CORE OPERATING LIMITS The COLR is the unit specific document that provides cycle REPORT (COLR) specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.3. Plant operation within these limits is addressed in individual Specifications.
DOSE EQUIVALENT I-131 DOSE EQUIVALENT I-131 shall be that concentration of I-131 (microcuries/gram) that alone would produce the same Total Effective Dose Equivalent (TEDE) dose as the quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The dose conversion factors used for this calculation shall be those listed in Federal Guidance Report (FGR) 11, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1988.
DRAIN TIME The DRAIN TIME is the time it would take for the water inventory in and above the Reactor Pressure Vessel (RPV) to drain to the top of the active fuel (TAF) seated in the RPV assuming:
a) The water inventory above the TAF is divided by the limiting drain rate; Columbia Generating Station 1.1-2 Amendment No. 190,199 225 251