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Category:Letter
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 ML24247A1572024-09-12012 September 2024 Withholding Determination Letter for Presentation Materials for Energy Northwest Pre-application Meeting 8-9-2024 ML24255A1012024-09-12012 September 2024 Request for Withholding Information from Public Disclosure Energy Northwest Regulatory Engagement Plan, Revision 0 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 IR 05000397/20240052024-08-22022 August 2024 Updated Inspection Plan for Columbia Generating Station (Report 05000397/2024005) IR 07200035/20244012024-08-19019 August 2024 Security Baseline Inspection Report 07200035/2024401 IR 05000397/20244022024-08-13013 August 2024 Security Baseline Inspection Report 05000397/2024402 IR 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 ML24089A2282024-04-15015 April 2024 – Acceptance of Requested Licensing Action License Amendment Request to Revise Columbia Generating Station Emergency Plan ML24074A4532024-04-11011 April 2024 Request for Withholding Information from Public Disclosure GO2-24-044, Voluntary Response to Regulatory Issue Summary 2024-012024-04-11011 April 2024 Voluntary Response to Regulatory Issue Summary 2024-01 IR 05000397/20244012024-04-0202 April 2024 – Security Baseline Inspection Report 05000397/2024401 (Cover Letter Only) IR 05000397/20244032024-03-28028 March 2024 Request for the Cybersecurity Baseline Inspection, Notification to Perform Inspection 05000397/2024403 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 ML24058A0692024-03-14014 March 2024 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Emergency Plan ML24044A0492024-03-12012 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0064 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting)) GO2-24-041, Level of Financial Protection - Annual Reporting Requirement2024-03-12012 March 2024 Level of Financial Protection - Annual Reporting Requirement 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 GO2-24-036, 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 ML24047A0422024-03-0707 March 2024 Issuance of Amendment No. 273 Renewed Facility Operating License and Technical Specification Clean Up IR 05000397/20230062024-02-28028 February 2024 Annual Assessment Letter for Columbia Generating Station (Report 05000397/2023006) IR 05000397/20253012024-02-14014 February 2024 Notification of NRC Initial Operator Licensing Examination 05000397/2025301 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 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 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 2024-09-24
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24215A3672024-08-0101 August 2024 NRR E-mail Capture - Final Request for Additional Information - Columbia Generating Station - License Amendment Request to Revise Emergency Plan - EPID L-2024-LLA-0011 ML24169A0402024-06-14014 June 2024 NRR E-mail Capture - Final Request for Additional Information - Columbia Generating Station (Columbia) - Relief Requests for the Fifth Ten-Year Interval Inservice Testing - EPIDs (L-2024-LLR-007 Through 0013) ML24058A0692024-03-14014 March 2024 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Emergency Plan ML24011A1522024-01-10010 January 2024 March 2024 Emergency Preparedness Exercise Inspection-Request for Information ML23110A2642023-04-20020 April 2023 Request for Information License Renewal Phase 2 Inspection ML22343A1802022-12-0808 December 2022 February 2023 Emergency Preparedness Program Inspection - Request for Information ML22301A1432022-10-28028 October 2022 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - License Amendment Request to Adopt TSTF-505 - EPID L-2022-LLA-0023 ML22242A1082022-08-30030 August 2022 Information Request, Information Request, Security IR 2022404 ML22235A1052022-08-22022 August 2022 August 2022 Emergency Preparedness Exercise Inspection Request for Information ML22145A4462022-06-0606 June 2022 Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000397/2022401 ML22144A0342022-05-18018 May 2022 NRR E-mail Capture - Draft - Request for Additional Information - Columbia Generating Station - LAR to Change TS 3.4.11 - Reactor Coolant System Pressure and Temperature Limits - EPID L-2021-LLA-0191 ML22041A4572022-02-10010 February 2022 Notification of NRC Design Bases Assurance Inspection (Team) (05000397/2022010) and Request for Information ML21277A3572021-10-12012 October 2021 CGS Brq RFI Letter, Columbia Generating Station - Notification of Inspection (NRC Inspection Report 05000397/2021004) and Request for Information ML21216A0502021-08-0303 August 2021 NRR E-mail Capture - Final - Request for Additional Information - Columbia - License Amendment Request to Adopt TSTF-439, Eliminate Second Completion Times Limiting Time from Discovery of Failure to Meet an LCO EPID L-2021-LLA-0259 ML21209A9792021-07-28028 July 2021 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - License Amendment Request to Remove License Condition 2.C.(34) and Revise License Condition 2.C.(35) - EPID L-2021-LLA-0074 ML21120A1182021-04-30030 April 2021 NRR E-mail Capture - Final - Request for Additional Information - Columbia Generating Station - On-Site Cooling System Sediment Disposal Approval Request - EPID L-2020-LLL-0031 ML21068A2842021-03-0404 March 2021 2021002 Inservice Inspection (ISI) Request for Information (RFI) ML20336A1852020-11-30030 November 2020 NRR E-mail Capture - Final - RAI - Columbia - One -Time Exemption from 10 CFR 73, App B, Sect VI, Subsection C.3.(l)(1) Regarding Annual Force-On-Force Exercises Due to COVID-19 Pandemic - EPID L-2020-LLE-0172 ML20325A0402020-11-19019 November 2020 NRR E-mail Capture - Draft - RAI - Columbia - 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 Pandemic - EPID L-2020-LLE-0172 ML20267A5162020-09-23023 September 2020 NRR E-mail Capture - Columbia Generating Station - Final - Request for Additional Information - Fourth Ten-Year Interval Inservice Inspection (ISI) Program Relief Request 4ISI-09 - EPID L-2020-LLR-0068 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 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 ML20149K4362020-05-26026 May 2020 NRR E-mail Capture - Formal RAIs for Columbia (COVID-19) QA Plan Change Surveillance, Request Response by Tuesday June 2, 2020 ML20112F4572020-04-21021 April 2020 NRR E-mail Capture - Official Release of NRC RAIs for Columbia Covid Exigent Due Friday April 24, 2020 ML20034E6082020-02-0303 February 2020 NRR E-mail Capture - RAI Formal Release Columbia TSTF 563 LAR, 30 Day Response Period Due March 3, 2020 ML20028E1512020-01-27027 January 2020 Notification of Evaluations of Changes, Tests, and Experiments Inspection (Inspection Report 05000397/2020002) and Request for Information ML19267A1842019-09-24024 September 2019 Request for Information for Upcoming Open Phase Condition Inspection at Columbia Generating Station ML19232A2282019-08-20020 August 2019 NRR E-mail Capture - Formal Release of RAIs Ref: Columbia Exigent Amendment - One Electrical RAI, ML19183A4752019-07-0202 July 2019 NRR E-mail Capture - Formal Release of RAIs Ref: Columbia HVAC LAR L-2019-LLA-0034 ML18088A0152018-03-29029 March 2018 Notification of NRC Inspection of the Implementation of Mitigation Strategies and Spent Fuel Pool Instrumentation Orders and Emergency Preparedness Communication/ Staffing/Multi-Unit Dose Assessment Plans (05000397/2018010) and Request for ML17341B0272017-12-0707 December 2017 NRR E-mail Capture - RAI Associated with Columbia Amendment Request Revise Tech Spec 5.5.12 for Permanent Extension of Type a and Type C Containment Testing Frequencies for MF9469, EPID: L-2017-LLA-0197, ILRT, LLRT LAR - New RAI Response Da ML17292A0572017-10-18018 October 2017 NRR E-mail Capture - New RWCU RAI Due Date Now November 24, 2017 ML17249A6882017-09-0606 September 2017 NRR E-mail Capture - RAIs for Columbia Relief Request RAI (MF8925), 3ISI-19 ML17205A3152017-07-20020 July 2017 Notification of Evaluations of Changes, Tests, and Experiments Inspection (05000397/2017004) and Request for Information ML17193A2192017-07-12012 July 2017 NRR E-mail Capture - Columbia RWCU LAR MF8318, Formal Release of RAIs ML17144A1702017-05-24024 May 2017 NRR E-mail Capture - NRC RAIs for Columbia Relief Request MF8922, 3ISI-16 ML17047A7492017-02-16016 February 2017 Response to Request for Additional Information, Columbia Mur LAR Evib Rais ML17006A0902017-01-0404 January 2017 NRR E-mail Capture - Non Proprietary Request for Additional Information Regarding Columbia Mur Power Uprate ML17006A0922017-01-0404 January 2017 NRR E-mail Capture - Eicb RAIs for Columbia Mur ML16356A1382016-12-21021 December 2016 NRR E-mail Capture - Columbia Mur LAR Evib RAIs Non - Proprietary Version - Revise Operating License and Technical Specifications for Measurement Uncertainty Recapture Power Uprate ML16342C4322016-12-0707 December 2016 NRR E-mail Capture - Columbia Measurement Uncertainty Recapture Power Uprate LAR Rais: Human Performance: MF8060, Formal Release for Response on Monday January 9, 2017 ML16327A1842016-11-22022 November 2016 NRR E-mail Capture - Non Proprietary Request for Additional Information Regarding Columbia Mur Power Uprate ML16323A1192016-11-16016 November 2016 NRR E-mail Capture - Eicb RAIs for Columbia Mur ML16218A3902016-08-0808 August 2016 Supplemental Information Needed for Acceptance of Requested Licensing Action, Request for Measurement Uncertainty Recapture (Mur) Power Uprate (from 3486 Mwt to 3544 Mwt) ML16194A3702016-07-11011 July 2016 Notification of NRC Triennial Heat Sink Performance Inspection 05000397/2016003 and Request for Information ML16069A3592016-03-0909 March 2016 NRR E-mail Capture - Second Round Rais: Columbia MF6042 LAR TSTF-425 ML16061A5542016-03-0101 March 2016 Notification of NRC Design Bases Inspection (05000397/2016007) and Initial Request for Information ML16061A5662016-03-0101 March 2016 Notification of Design Bases Inspection (Programs)(Inspection Report 05000397/2016008) and Initial Request for Information ML15254A2572015-09-16016 September 2015 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1 Seismic Reevaluations ML15215A0432015-08-18018 August 2015 Request for Additional Information Associated with Near-Term Task Force Recommendation 2.1, Seismic Reevaluations 2024-08-01
[Table view] |
Text
September 13, 2007Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023)
Richland, WA 99352-0968
SUBJECT:
COLUMBIA GENERATING STATION - REQUEST FOR ADDITIONALINFORMATION RELATED TO LICENSE AMENDMENT REQUEST ASSOCIATED WITH CONDENSATE STORAGE TANK LEVEL (TAC NO. MD6176)
Dear Mr. Parrish:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated August 8, 2007, EnergyNorthwest submitted a license amendment request for Columbia Generating Station to revise the requirements of Technical Specification (TS) 3.3.5.2, "Reactor Core Isolation Cooling (RCIC) System Instrumentation," and TS 3.5.2, "ECCS [Emergency Core Cooling System]-Shutdown," to increase the Condensate Storage Tank (CST) level. The NRC staff is reviewing your submittal and has determined that additional information isrequired to complete its review. The specific information requested is addressed in the enclosure to this letter. During a discussion with Mr. G. Cullen of your staff on August 31, 2007, it was agreed that you would provide a response by November 30, 2007, to this request for additional information. The NRC staff considers that timely responses to requests for additional information helpensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2296.Sincerely,/RA/Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-397
Enclosure:
Request for Additional Information cc w/encl: See next page June 2007Columbia Generating Station cc:Chairman Energy Facility Site Evaluation Council P.O. Box 43172 Olympia, WA 98504-3172Mr. Douglas W. Coleman (Mail Drop PE20)Manager, Regulatory Programs Energy Northwest P.O. Box 968 Richland, WA 99352-0968ChairmanBenton County Board of Commissioners P.O. Box 190 Prosser, WA 99350-0190Mr. William A. Horin, Esq.Winston & Strawn 1700 K Street, N.W.
Washington, DC 20006-3817Mr. Matt SteuerwaltExecutive Policy Division Office of the Governor P.O. Box 43113 Olympia, WA 98504-3113Ms. Lynn AlbinWashington State Department of Health P.O. Box 7827 Olympia, WA 98504-7827Technical Services Branch ChiefFEMA Region X 130 - 228th Street, SW Bothell, WA 98021-9796Mr. Mike HammondDepartment of Homeland Security FEMA/REP 130 - 228 th Street SWBothell, WA 98021-9796Regional Administrator, Region IVU.S. Nuclear Regulatory Commission 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-4005Senior Resident InspectorU.S. Nuclear Regulatory Commission P.O. Box 69 Richland, WA 99352-0069 Assistant DirectorNuclear Safety and Energy Siting Division Oregon Department of Energy 625 Marion Street NE Salem, OR 97301-3742Special Hazards Program ManagerWashington Emergency Management Div.
127 W. Clark Street Pasco, WA 99301 September 13, 2007Mr. J. V. Parrish Chief Executive Officer Energy Northwest P.O. Box 968 (Mail Drop 1023)
Richland, WA 99352-0968
SUBJECT:
COLUMBIA GENERATING STATION - REQUEST FOR ADDITIONALINFORMATION RELATED TO LICENSE AMENDMENT REQUEST ASSOCIATED WITH CONDENSATE STORAGE TANK LEVEL (TAC NO. MD6176)
Dear Mr. Parrish:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated August 8, 2007, EnergyNorthwest submitted a license amendment request for Columbia Generating Station to revise the requirements of Technical Specification (TS) 3.3.5.2, "Reactor Core Isolation Cooling (RCIC) System Instrumentation," and TS 3.5.2, "ECCS [Emergency Core Cooling System]-Shutdown," to increase the Condensate Storage Tank (CST) level. The NRC staff is reviewing your submittal and has determined that additional information isrequired to complete its review. The specific information requested is addressed in the enclosure to this letter. During a discussion with Mr. G. Cullen of your staff on August 31, 2007, it was agreed that you would provide a response by November 30, 2007, to this request for additional information. The NRC staff considers that timely responses to requests for additional information helpensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-2296.Sincerely,/RA/Carl F. Lyon, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-397
Enclosure:
Request for Additional Information cc w/encl: See next pageDISTRIBUTION
- PUBLIC LPL4 R/F RidsAcrsAcnwMailCenter RidsNrrDeEicbRidsNrrDorlLpl4RidsNrrLAJBurkhardt RidsNrrPMFLyon RidsNrrDorlDprRidsOgcRpRidsRgn4MailCenter SMazumdar, NRRADAMS Accession Number: ML072480037*Memo datedOFFICELPL4/PMLPL4/LAEICB/BCLPL4/BCNAMEFLyonJBurkhardtWKemper*THiltz, MTM for DATE9/12/079/10/078/30/079/13/07OFFICIAL RECORD COPY REQUEST FOR ADDITIONAL INFORMATIONRELATED TO LICENSE AMENDMENT REQUEST ASSOCIATED WITHCONDENSATE STORAGE TANK LEVELENERGY NORTHWESTCOLUMBIA GENERATING STATIONDOCKET NUMBER 50-397The license amendment request (LAR), dated August 8, 2007, proposes the following TechnicalSpecifications (TS) changes:
!Condensate Storage Tank Level-Low Allowable Value in TS Table 3.3.5.2-1, Core Cooling Isolation System Instrumentation from "> 446 ft 0 inches elevation"to "> 447 ft 7 inches elevation."
!Condensate Storage Tank (CST) water level in SR [Surveillance Requirement]3.3.5.2-2, from "> 14.8 ft in a single CST or > 9.1 ft in each CST" to "> 16.5 ft ina single CST or > 10.5 ft in each CST."To support U.S. Nuclear Regulatory Commission (NRC) assessment of the acceptability of theLAR with regard to setpoint changes, please provide the following for each setpoint to be added or modified:1.Setpoint Calculation Methodology: Provide documentation (including samplecalculations) of the methodology used for establishing the limiting setpoint (or NSP) and the limiting acceptable values for the As-Found and As-Left setpoints as measured in periodic surveillance testing as described below. Indicate the related Analytical Limits and other limiting design values (and the sources of these values) for each setpoint.2.Safety Limit (SL)-related Determination: Provide a statement as to whether ornot the setpoint is a limiting safety system setting (LSSS) for a variable on which a safety limit (SL) has been placed as discussed in paragraph 50.36(c)(1)(ii)(A) of Title 10 of the Code of Federal Regulations (10 CFR). Such setpoints aredescribed as "SL-Related" in the discussions that follow. In accordance with 10 CFR 50.36(c)(1)(ii)(A), the following guidance is provided for identifying a list of functions to be included in the subset of LSSSs specified for variables on which SLs have been placed as defined in Standard Technical Specifications (STS) Sections 2.1.1, Reactor Core SLs, and 2.1.2, Reactor Coolant System Pressure SLs. This subset includes automatic protective devices in TSs for specified variables on which SLs have been placed that: (1) initiate a reactor trip; or (2) actuate safety systems. As such, these variables provide protection against violating reactor core safety limits, or reactor coolant system pressure boundary safety limits. Examples of instrument functions that might have LSSSs included in this subsetin accordance with the plant-specific licensing basis, are pressurizer pressure reactor trip (pressurized-water reactors), rod block monitor withdrawal blocks (boiling-water reactors), feedwater and main turbine high-water level trip (boiling-water reactors), and end-of-cycle recirculation pump trip (boiling-water reactors).
For each setpoint, or related group of setpoints, that you determined not to be SL-Related, explain the basis for this determination.3.For Setpoints That Are Determined to Be SL-related: The NRC letter to the NEISMTF dated September 7, 2005 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML052500004), describes Setpoint-Related TS (SRTS) that are acceptable to the NRC for instrument settings associated with SL-related setpoints. Specifically, Part "A" of the Enclosure to the letter provides limiting conditions for operations notes to be added to the TS, and Part "B" includes a checklist of the information to be provided in the TS Bases related to the proposed TS changes.a.Describe whether and how you plan to implement the SRTS suggested inthe September 7 letter. If you do not plan to adopt the suggested SRTS, then explain how you will ensure compliance with 10 CFR 50.36 by addressing items 3b and 3c below:b.As-Found Setpoint Evaluation: Describe how surveillance test resultsand associated TS limits are used to establish operability of the safety system. Show that this evaluation is consistent with the assumptions and results of the setpoint calculation methodology. Discuss the plant corrective action processes (including plant procedures) for restoring channels to operable status when channels are determined to be "inoperable" or "operable but degraded." If the criteria for determining operability of the instrument being tested are located in a document other than the TS (e.g. plant test procedure) explain how the requirements of 10 CFR 50.36 are met.c.As-Left Setpoint Control: Describe the controls employed to ensure thatthe instrument setpoint is, upon completion of surveillance testing, consistent with the assumptions of the associated analyses. If the controls are located in a document other than the TS (e.g., plant test procedure) explain how the requirements of 10 CFR 50.36 are met.4.For Setpoints That Are Determined Not to Be SL-related: Describe themeasures to be taken to ensure that the associated instrument channel is capable of performing its specified safety functions in accordance with applicable design requirements and associated analyses. Include in your discussion information on the controls you employ to ensure that the as-left trip setting after completion of periodic surveillance is consistent with your setpoint methodology.
Also, discuss the plant corrective action processes (including plant procedures) for restoring channels to operable status when channels are determined to be "inoperable" or "operable but degraded." If the controls are located in a document other than the TS (e.g., plant test procedure), describe how it isensured that the controls will be implemented.
REFERENCES:
1.Letter from Timothy J. Kobetz, NRC, to Technical Specifications Task Force (TSTF),"TSTF Traveler 493, Revision 1, "Clarify Application of Setpoint Methodology for LSSS Functions," dated December 14, 2006, available on the NRC public website in ADAMS Accession No. ML063450324.2.NRC Regulatory Issue Summary 2006-17, "NRC Staff Position on the Requirements of10 CFR 50.36, 'Technical Positions,' Regarding Limiting Safety System Settings During Periodic Testing and Calibration of Instrument Channels," dated August 24, 2006, ADAMS Accession No. ML051810077. 3.Letter from Patrick L. Hiland, NRC, to NEI [Nuclear Energy Institute] Setpoint MethodsTask Force, "Technical Specification for Addressing Issues Related to Setpoint Allowable Values," dated September 7, 2005, ADAMS Accession No. ML052500004.4.Letter from Bruce A. Boger, NRC, to Alexander Marion, NEI, "Instrumentation, Systems,and Automatic Society (ISA) S67.04 Methods for Determining Trip Setpoints and Allowable Values for Safety-Related Instrumentation," dated August 23, 2005, ADAMS Accession No. ML051660447.5.Letter from James A. Lyons, NRC, to Alex Marion, NEI, "Instrumentation, Systems, andAutomation Society S67.04 Methods for Determining Trip Setpoints and Allowable Values for Safety-Related Instrumentation," dated March 31, 2005, ADAMS Accession No. ML050870008.