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MONTHYEARNL-12-1893, License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition)2012-09-25025 September 2012 License Amendment Request to Adopt NFPA-805 Performance Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (2001 Edition) Project stage: Request ML12345A3982012-12-12012 December 2012 Supplemental Information Needed for Acceptance of Requested Licensing Action Concerning Voluntary Fire Protection Risk Initiative Request (TAC Nos. ME9741 and ME9742)(NL-12-1893) Project stage: Acceptance Review NL-12-2566, Supplemental Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition)2012-12-20020 December 2012 Supplemental Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants (2001 Edition) Project stage: Supplement ML13022A1582013-01-24024 January 2013 Acceptance Review Concerning Voluntary Fire Protection Risk Initiative Request (TAC Nos. ME9741 and ME9742) (N-1-2-1893) Project stage: Acceptance Review ML13050A2862013-02-22022 February 2013 3/7/2013 - Forthcoming Meeting Notice with Southern Nuclear Company to Discuss Responses to Requests for Additional Information Related to Amendment Requests to Transition to the National Fire Protection Association NFPA-805 Methodology Project stage: RAI ML13067A2692013-03-11011 March 2013 03/21/2013 Forthcoming Meeting with Southern Nuclear Company Regarding Voluntary Fire Protection Risk Initiative Amendment Request for Joseph M. Farley Nuclear Plant, Units 1 and 2 Project stage: Meeting ML13176A0932013-07-0808 July 2013 Request for Additional Information Concerning Voluntary Fire Protection Risk Initiative Request (TAC Nos. ME9741 and ME9742) (NL-12-1893) Project stage: RAI ML14038A0192013-09-16016 September 2013 Joseph M. Farley, Units 1 and 2, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generati Project stage: Request NL-13-2039, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants2013-10-30030 October 2013 Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Response to RAI NL-13-2269, Response to Request for Additional Information Re License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants2013-11-12012 November 2013 Response to Request for Additional Information Re License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Response to RAI ML14066A0472014-03-0707 March 2014 Electronic Transmission, Draft Request for Additional Information Regarding License Amendment Request to Adopt Nation Fire Protection Association Standard 805 (TAC ME9741 and ME9742 Project stage: Draft RAI ML14073A0532014-03-28028 March 2014 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: RAI ML14114A5502014-04-23023 April 2014 Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Response to RAI NL-14-0733, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants2014-05-23023 May 2014 Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Response to RAI NL-14-0927, Response to RAI Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants. Part 1 of 32014-07-0303 July 2014 Response to RAI Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants. Part 1 of 3 Project stage: Response to RAI ML14176A0702014-07-11011 July 2014 Request for Additional Information Project stage: RAI NL-14-1106, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Lioht Water Reactor Generating Plants2014-08-11011 August 2014 Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Lioht Water Reactor Generating Plants Project stage: Response to RAI NL-14-1273, Response to Request for Additional Information Re License Amendment Request for Transition to 10CFR50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for LWR Generating Plants2014-08-29029 August 2014 Response to Request for Additional Information Re License Amendment Request for Transition to 10CFR50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for LWR Generating Plants Project stage: Response to RAI NL-14-1937, Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants2015-01-16016 January 2015 Response to Request for Additional Information Regarding License Amendment Request for Transition to 10 CFR 50.48(c) - NFPA 805 Performance Based Standard for Fire Protection for Light Water Reactor Generating Plants Project stage: Response to RAI ML15023A0522015-01-23023 January 2015 U.S. Nuclear Regulatory Commission, Record of Review Dispositions to Fire PRA Facts and Observations for Southern Nuclear Operating Company Joseph M. Farley Nuclear Plant, Units 1 and 2 Project stage: Request ML15043A4592015-02-24024 February 2015 Summary of Site Audit to Support the Review of a License Amendment Request for Joseph M. Farley Nuclear Plant, Units 1 and 2, to Transition to the National Fire Protection Association Standard 805 Fire Protection Licensing Basis Project stage: Approval ML14308A0482015-03-10010 March 2015 Issuance of Amendment Regarding Transition to a Risk-Informed, Performance-Based Fire Protection Program in Accordance with 10 CFR 50.48(c) Project stage: Approval 2014-03-28
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Category:Letter type:NL
MONTHYEARNL-24-0261, 10 CFR 50.46 ECCS Evaluation Model Annual Report for 20232024-07-19019 July 2024 10 CFR 50.46 ECCS Evaluation Model Annual Report for 2023 NL-24-0281, License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions2024-07-18018 July 2024 License Amendment Request to Change Technical Specification 3.6.5, Containment Air Temperature Actions NL-24-0227, Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1)2024-07-0303 July 2024 Proposed Inservice Inspection Alternative GEN-ISI-AL T-2024-03 for Pressurizer Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0234, Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown2024-06-28028 June 2024 Application to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown NL-24-0230, Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-3602024-06-28028 June 2024 Plants Units 1&2, License Amendment Request for Adoption of Technical Specifications Task Force (TSTF) Traveler TSTF-500, Revision 2, DC Electrical Rewrite – Update to TSTF-360 NL-24-0143, Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in2024-06-27027 June 2024 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and Treatment for Repair/ Replacement Activities in NL-24-0201, Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1)2024-06-18018 June 2024 Proposed Inservice Inspection Alternative GEN-ISI-ALT-2024-002 for Steam Generator Welds in Accordance with 10 CFR 50.55a(z)(1) NL-24-0238, RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information2024-06-14014 June 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions, Supplemental Information NL-24-0229, Notice of Intent to Pursue Subsequent License Renewal2024-06-0707 June 2024 Notice of Intent to Pursue Subsequent License Renewal NL-24-0202, SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations2024-05-24024 May 2024 SNC Response to Regulatory Issue Summary 2024-01: Preparation and Scheduling of Operator Licensing Examinations NL-24-0191, Annual Radiological Environmental Operating Reports for 20232024-05-10010 May 2024 Annual Radiological Environmental Operating Reports for 2023 NL-24-0064, Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.52024-05-0303 May 2024 Units 1 & 2 and Hatch Nuclear Plant - Units 1 & 2 License Amendment Request to Revise Technical Specification 1.1 and Add Online Monitoring Program to Technical Specification 5.5 NL-24-0188, Cycle 33 Core Operating Limits Report2024-05-0101 May 2024 Cycle 33 Core Operating Limits Report NL-24-0165, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20232024-04-25025 April 2024 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2023 NL-24-0137, RIPE License Amendment Request to Change Containment Air Temperature Actions2024-04-19019 April 2024 RIPE License Amendment Request to Change Containment Air Temperature Actions NL-24-0011, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2024-01-11011 January 2024 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0901, 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers2023-12-15015 December 2023 30-Day 10 CFR 21 Notification - Framatome Supplied Siemens Medium Voltage (Mv) Circuit Breakers NL-23-0908, Cycle 30 Core Operating Limits Report2023-12-13013 December 2023 Cycle 30 Core Operating Limits Report NL-23-0877, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0825, Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection2023-11-14014 November 2023 Reply to Notice of Violation EA-23-080 and Readiness for 95001 Inspection NL-23-0739, Response to NRC Inspection Report and Preliminary White Finding2023-09-0808 September 2023 Response to NRC Inspection Report and Preliminary White Finding NL-23-0713, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0716, Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-23023 August 2023 Response to Request for Additional Information Regarding Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0704, Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit2023-08-22022 August 2023 Emergency License Amendment Request: Technical Specification 3.6.5, Containment Air Temperature, One-Time Temporary Change to Limit NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0628, Readiness for Supplemental Inspection EA-22-1012023-07-26026 July 2023 Readiness for Supplemental Inspection EA-22-101 NL-23-0566, ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use2023-07-13013 July 2023 ISFSI and Edwin I. Hatch Nuclear Plant ISFSI - Registration of Spent Fuel Cask Use NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0457, ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use2023-06-12012 June 2023 ISFSI, and Edwin I. Hatch Nuclear Plant, ISFSI - Registration of Spent Fuel Cask Use NL-23-0449, National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application2023-06-0202 June 2023 National Pollutant Discharge Elimination System (NPDES) Permit Renewal Application NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0337, Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52023-05-0505 May 2023 Response to Request for Additional Information Related to License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-23-0295, Reply to a Notice of Violation; EA-22-1012023-05-0101 May 2023 Reply to a Notice of Violation; EA-22-101 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0213, Inservice Inspection Program Owner'S Activity Report for Outage 1R312023-03-21021 March 2023 Inservice Inspection Program Owner'S Activity Report for Outage 1R31 NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-23-0080, Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.02023-02-0202 February 2023 Response to Request for Additional Information (RAI) Related to Proposed Inservice Inspection Alternative FNP-ISI-ALT-05-05, Version 1.0 NL-23-0008, Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting.2023-01-17017 January 2023 Response to Request for Additional Information Related to License Amendment Request to Revise Technical Specification 3.4.10, Pressurizer Safety Valves to Decrease Low Side Setpoint Tolerance Limiting. NL-23-0011, Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only2023-01-0505 January 2023 Update to Supporting Documentation Regulatory Conference EA-22-101. Cover Letter Only NL-22-0799, License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.52022-12-20020 December 2022 License Amendment Request to Revise the Frequency of Surveillance Requirement 3.6.3.5 NL-22-0897, Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A,2022-12-0909 December 2022 Supplement to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, 2024-07-03
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UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 December 12, 2012 Mr. M. J. Nuclear Licensing Southern Nuclear Operating Company, P. O. Box Bin -Birmingham, AL JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 -
INFORMATION NEEDED FOR ACCEPTANCE OF REQUESTED ACTION CONCERNING VOLUNTARY FIRE PROTECTION RISK REQUEST (TAC NOS. ME9741 AND ME9742)
Dear Mr. Ajluni:
By letter dated September 25, 2012, the Southern Nuclear Operating Company (SNC or the licensee) submitted a license amendment request for Joseph M. Farley Nuclear Plant, Units 1 and 2. The proposed amendment requests the review and approval for adoption of a new fire protection licensing basis which complies with the requirements in Sections 50.48(a) and 50.48(c) to Title 10 of the Code of Federal Regulations (10 CFR), and the guidance in Regulatory Guide 1.205, Revision 1, "Risk-Informed, Performance-Based Fire Protection for Existing Light-Water Nuclear Power Plants." The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's acceptance review of this [amendment/relief]
request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant. Consistent with 10 CFR 50.90 an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications.
Section 50.34 of 10 CFR addresses the content of technical information required.
This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and prinCipal safety considerations.
The NRC staff has reviewed your application and concluded that the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment/relief request in terms of regulatory requirements and the protection of public health and safety and the environment.
M. Ajluni -2 In order to make the application complete, the NRC staff requests that SNC supplement the application to address the information requested in the enclosure by December 26,2012. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application.
If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and associated timeframe in this letter were discussed with Mr. Ken McElroy of your staff on December 7,2012. If you have any questions, please contact me by phone (301) 415-2315 or email at Eva.Brown@nrc.gov. Sincerely, IRA! Eva A. Brown, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosure:
As stated cc w/encl: Distribution via Listserv SUPPLEMENTAL INFORMATION NEEDED VOLUNTARY FIRE PROTECTION RISK INITIATIVE SOUTHERN NUCLEAR OPERATING COMPANY JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364 As discussed in Attachment A to the submittal dated September 25, 2012 (Agencywide Documents Access and Management System) Accession No. ML 12279A235), the Electrical Raceway Fire Barrier System (ERFBS) Table B-1, Element 3.11.5 states "[c]omplies" as meeting the requirements of Chapter 3. Table B-1 also states that required ERFBS is identified in Table 4-3 (Attachment C, Table C-2), but ERFBS is never identified as a required feature in this table. Clarify if ERFBS is a required fire protection feature at Joseph M. Farley Nuclear Plant, Units 1 and 2. If so, identify the fire area locations where ERFBS is being credited.
If new ERFBS modifications will be installed, then identify those as well. Recovery actions are identified as the resolution of certain variances from the deterministic requirements (VFDRs) by fire area in Attachment C Table B-3 to the submittal.
However many of the recovery actions required for VFDR resolutions do not appear to be included in Attachment G Table G-1. Clarify whether Attachment G identifies all recovery actions credited in Attachment C Table B-3 VFDR resolutions.
If not, provide the additional recovery actions. Additionally, recovery actions in Attachment G do not identify the associated VFDRs. In some cases, the recovery actions can be traced back to the associated VFDRs by searching component numbers described in the action with those in the VFDR, but in many cases the correlation between recovery action and VFDR resolution cannot be Provide a revised Table G-1 that associates the recovery actions with the appropriate VFDR being resolved. Section 4.2.1.2 of the submittal states that "safe and stable ... assumes the plant to be taken subcritical and maintained in anyone of the modes of hot standby, hot shutdown, cold shutdown, or refueling conditions." However, the performance goals listed in Attachment C Table B-3 appear to show achievement of only hot shutdown goals, not cold shutdown or refueling.
Clarify the safe and stable condition for the plant. If cold shutdown, explain why the Nuclear Safety Capability Analyses and fire risk evaluations do not include this equipment. Attachment STable S-2 Item #11 to the submittal identifies a proposed modification to "install a new code compliant fire detection system and provide a code compliance evaluation to support the new system." Provide a more explicit description of this modification.
Address whether there will only be detectors, or will it also include new local and main panels. Discuss whether this is intended to be installed throughout the plant. Provide the version of the National Fire Protection Association (NFPA)-72, Enclosure
-"National Fire Alarm and Signaling Code," will be used for this new system. It appears that Attachment C, Table C-2 (Table 4-3) identifies detection used in each fire area/zone where it is credited for NFPA 805, "Performance-Based Standard for Fire Protection for Light-Water Reactor Electric Generating Plants." Address whether this table is based on existing detection or the new detection system, or both. Address whether Table V-2 includes all supporting requirements identified as either capability category (CC)-I or not met by the peer review. In doing so, clearly identify those SRs being carried forward as CC-I (or not met), and provide justification as to why dOing so is acceptable for transition. Provide the results (i.e., core damage frequency (CDF), large early release frequency (LERF), delta CDF, and delta LERF) of an aggregate sensitivity analYSis that removes both the credit given to Very Early Warning Fire Detection Systems (VEWFDS) in the main control room as well as that associated with electrical panel factors discussed in Attachment V,Section V.2.1.2 of the submittal.
In addition, identify any additional Unreviewed Analysis Methods (UAMs) employed within the fire probabilistic risk assessment, and incorporate all such UAMs within the aforementioned aggregate sensitivity study. Provide justification of how the Regulatory Guide 1.174, "An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis," risk acceptance guidelines are satisfied. Section 5.5 and Attachment S of the submittal proposes a completion schedule for plant modifications of November 6, 2017. Provide justification for this schedule.
M. Ajluni -In order to make the application complete, the NRC staff requests that SNC supplement the application to address the information requested in the enclosure by December 26,2012. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application.
If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
The information requested and associated timeframe in this letter were discussed with Mr. Ken McElroy of your staff on December 7,2012. If you have any questions, please contact me by phone (301) 415-2315 or email at Eva.Brown@nrc.gov. Sincerely, IRA! Eva A Brown, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-348 and 50-364
Enclosure:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC LPL2-1 Reading File RidsAcrsAcnw_MailCTR Resource RidsNrrDraAfpb Resource RidsNrrDraAPLA Resource RidsNrrDorl Resource RidsNrrDorlDpr Resource RidsNrrDorlLp2-1 Resource RidsNrrLASFigueroa Resource RidsNrrPMFarley Resource RidsOgcRp Resource RidsRg2MailCenter Resource LFields DPickett DBroaddus ADAMS Accession No ML 12345A398 OFFICE DORU2-1/PM DORULPL2-1/LA DORULPL2-1/BC NAME EBrown SFigueroa RPascarelli DATE 12/12/12 12/12/12 12112112 OFFICIAL RECORD COpy