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MONTHYEARL-15-150, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052015-05-27027 May 2015 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: Response to RAI ML15280A0742015-10-0909 October 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: RAI L-15-325, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052015-11-0606 November 2015 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: Response to RAI ML15320A4132015-11-24024 November 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: RAI L-15-371, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052015-12-21021 December 2015 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: Response to RAI L-16-058, Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052016-02-24024 February 2016 Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: Supplement ML16099A0112016-03-0303 March 2016 NRR E-mail Capture - Draft 3rd Round PRA RAIs - Beaver Valley Units 1 & 2 - NFPA-805 LAR (CAC Nos. MF3301 & MF3302) Project stage: Draft RAI ML16084A8442016-03-30030 March 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: RAI ML16089A0622016-03-30030 March 2016 Meeting to Discuss BVPS Draft PRA RAI - Slides Project stage: Request ML16071A1222016-04-0707 April 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: RAI ML16105A0082016-04-25025 April 2016 March 30, 2016, Summary of Meeting with Firstenergy Nuclear Operating Company on Its Draft Probabilistic Risk Assessment RAI Related to Its License Amendment Request to Adopt NFPA Standard 805 Project stage: Draft RAI L-16-162, Response to Requests for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, and Request to Change Implementation Schedule2016-05-12012 May 2016 Response to Requests for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805, and Request to Change Implementation Schedule Project stage: Response to RAI ML16158A0022016-06-0101 June 2016 NRR E-mail Capture - Beaver Valley, Units 1 & 2 - Update on NFPA 805 (CAC Nos. MF3301 & MF3302) Project stage: Other ML16333A0162016-12-0202 December 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: RAI L-17-024, Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052017-01-30030 January 2017 Response to Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: Response to RAI L-17-197, Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 8052017-06-23023 June 2017 Response to Request for Additional Information and Supplemental Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 Project stage: Supplement ML17220A2342017-08-0808 August 2017 E-mail Regarding Request for Additional Information for NFPA 805 License Amendment Request Project stage: RAI ML17313A6422017-11-0909 November 2017 Transmittal of Draft Safety Evaluation for Proposed Amendments Transition to NFPA 805 (CAC Nos. MF3301 and MF3302; EPID L-2013-LLF-0001) Project stage: Draft Approval ML17335A0962017-11-27027 November 2017 NRR E-mail Capture - Beaver Valley: NFPA 805 LAR: License Condition: Fire Protection Program Changes That Have More than Minimal Risk Impact (CAC Nos. MF3301 and MF3302; EPID L-2013-LLF-0001) Project stage: Other ML18058A9422017-12-11011 December 2017 NFPA 805 Amendment Application Transition License Condition Project stage: Other ML17291A0812018-01-22022 January 2018 Issuance of Amendments Transition to NFPA 805, Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants (CAC Nos. MF3301 and MF3302; EPID L-2013-LLF-0001) Project stage: Approval ML18058B0722018-02-23023 February 2018 BVPS NFPA 805 License Amendment Change Requested, and Other SE Comments Project stage: Other ML18059A7982018-02-26026 February 2018 BVPS NFPA 805 License Amendment Change Requested, and Other SE Comments Project stage: Other ML18058A9852018-02-27027 February 2018 BVPS-1 License Condition Page Project stage: Other ML18058A9532018-02-27027 February 2018 Comments on BVPS SE Project stage: Other ML18065A4032018-04-0505 April 2018 Correction of Errors in Safety Evaluation Associated with License Amendment Nos. 301 and 190 Project stage: Approval ML18099A2322018-04-18018 April 2018 Correction of an Error in the Renewed Facility Operating License No. DPR-66 Associated with License Amendment No. 301 CAC No. MF3301; EPID L-2013-LLF-0001) Project stage: Other 2016-06-01
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Category:Letter
MONTHYEARIR 05000334/20240112024-10-17017 October 2024 License Renewal Phase IV Inspection Report 05000334/2024011 L-24-038, License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References2024-09-17017 September 2024 License Amendment Request to Remove the Expired One-Time Action for Valve Leak Repair in Technical Specification (TS) 3.5.2 and to Correct Core Operating Limits Rep Ort (COLR) References L-24-015, Twenty-Ninth Refueling Outage Inservice Inspection Summary Report2024-09-17017 September 2024 Twenty-Ninth Refueling Outage Inservice Inspection Summary Report ML24134A1522024-09-17017 September 2024 Exemption from the Requirements of 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule (EPID L-2024-LLE-0005) - Letter ML24260A1912024-09-16016 September 2024 Operator Licensing Examination Approval IR 05000334/20240052024-08-29029 August 2024 Updated Inspection Plan for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2024005 and 05000412/2024005) L-24-188, Submittal of Quality Assurance Program Manual, Revision 302024-08-27027 August 2024 Submittal of Quality Assurance Program Manual, Revision 30 L-24-199, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-08-22022 August 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20244022024-08-22022 August 2024 Security Baseline Inspection Report 05000334/2024402 and 05000412/2024402 (Cover Letter Only) L-24-186, Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2024-08-15015 August 2024 Response to RAI for Exemption Request from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule IR 05000334/20240022024-08-0505 August 2024 Integrated Inspection Report 05000334/2024002 and 05000412/2024002 ML24208A0462024-07-26026 July 2024 NRC Office of Investigations Case No. 1-2023-005 L-24-182, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-23023 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-24-161, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-07-19019 July 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 05000334/LER-2024-004, Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control2024-07-17017 July 2024 Reactor Trip Due to Bypass Feedwater Regulating Valve Failure to Control L-24-014, Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models2024-07-16016 July 2024 Annual 10 CFR 50.46 Report of Changes to or Errors in Emergency Core Cooling Svstem Evaluation Models ML24193A2912024-07-16016 July 2024 Revision to Reactor Vessel Surveillance Capsule Withdrawal Schedule IR 05000334/20245012024-07-0808 July 2024 Emergency Preparedness Biennial Exercise Inspection Report 05000334/2024501 and 05000412/2024501 05000334/LER-2024-003, Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping2024-07-0202 July 2024 Unanalyzed Containment Bypass Condition Due to Degraded River Water Piping L-24-164, BV-2, Post Accident Monitor Report2024-06-27027 June 2024 BV-2, Post Accident Monitor Report IR 05000334/20244012024-06-26026 June 2024 Material Control and Accounting Program Inspection Report 05000334/2024401 and 05000412/2024401 (Cover Letter Only) L-24-094, Reactor Vessel Surveillance Capsule Withdrawal Schedule2024-06-24024 June 2024 Reactor Vessel Surveillance Capsule Withdrawal Schedule L-24-152, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-06-17017 June 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations 05000334/LER-2024-002, Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation2024-06-11011 June 2024 Automatic Reactor Trip Due to Low Reactor Coolant Flow Caused by Transformer Overexcitation Protection Relay Actuation 05000334/LER-2024-001, Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification2024-06-0606 June 2024 Offsite AC Power Source Inoperable Due to Breaker Failure Resulting in Condition Prohibited by Technical Specification ML24135A2282024-05-29029 May 2024 Review of the Spring 2023 Outage Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F Star Reports ML24135A1702024-05-29029 May 2024 – Steam Generator Tube Inspection - Review of the Spring 2023 Tube Inspection Reports L-24-021, Cycle 30 Core Operating Limits Report2024-05-23023 May 2024 Cycle 30 Core Operating Limits Report L-24-121, Discharge Monitoring Report (NPDES) Permit No. PA00256152024-05-23023 May 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML24141A1052024-05-20020 May 2024 Senior Reactor and Reactor Operator Initial License Examinations IR 05000334/20240102024-05-15015 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000334/2024010 and 05000412/2024010 L-24-107, CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair2024-05-13013 May 2024 CFR 50.55a Request 1-TYP-5-RRP-l, for Alternative Method of Nondestructive Examination for River Water Outlet Piping Weld Repair IR 05000334/20240012024-05-0808 May 2024 Integrated Inspection Report 05000334/2024001 and 05000412/2024001 L-23-269, Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions2024-05-0707 May 2024 Application to Revise Technical Specifications to Adopt TSTF-569, Revision of Response Time Testing Definitions L-24-054, Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological)2024-04-29029 April 2024 Submittal of 2023 Annual Radioactive Effluent Release Report 2023 Annual Radiological Environmental Operating Report and 2023 Annual Environmental Operating Report (Non-Radiological) L-24-089, Emergency Preparedness Plan2024-04-23023 April 2024 Emergency Preparedness Plan L-24-088, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 20242024-04-22022 April 2024 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for March 2024 ML24101A2752024-04-10010 April 2024 Response to Request for Additional Information Regarding Spring 2023 180-Day Steam Generator Tube Inspection Report L-24-082, Withdrawal of Exemption Request2024-04-0303 April 2024 Withdrawal of Exemption Request L-24-013, Annual Notification of Property Insurance Coverage2024-03-26026 March 2024 Annual Notification of Property Insurance Coverage L-24-064, Submittal of Discharge Monitoring Report (NPDES) Permit No. PA00256152024-03-13013 March 2024 Submittal of Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML24044A0662024-03-0404 March 2024 Exemption from Select Requirements of 10 CFR Part 73 (EPID L-2023-LLE-0083 (Security Notifications, Reports, and Recordkeeping and Suspicious Activity Reporting ML24057A0752024-03-0101 March 2024 The Associated Independent Spent Fuel Storage Installations IR 05000334/20230062024-02-28028 February 2024 Annual Assessment Letter for Beaver Valley Power Station, Units 1 and 2 (Reports 05000334/2023006 and 05000412/2023006) L-23-264, Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule2024-02-23023 February 2024 Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Report Update Schedule CP-202300502, Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions2024-02-23023 February 2024 Notice of Planned Closing of Transaction and Provision of Documents to Satisfy Order Conditions L-24-050, Retrospective Premium Guarantee2024-02-22022 February 2024 Retrospective Premium Guarantee 05000412/LER-2023-003-01, Missile Barrier Door Left Open Resulting in a Loss of Safety Function2024-02-20020 February 2024 Missile Barrier Door Left Open Resulting in a Loss of Safety Function IR 05000334/20230042024-02-12012 February 2024 Integrated Inspection Report 05000334/2023004 and 05000412/2023004 ML24025A0922024-01-25025 January 2024 Requalification Program Inspection 2024-09-17
[Table view] Category:Request for Additional Information (RAI)
MONTHYEARML24204A0012024-07-17017 July 2024 NRR E-mail Capture - Request for Additional Information Vistraops Fleet Exemption for the Requirements in 10 CFR 50.71 Pertaining to the Submittal of Updated Final Safety Analysis Reports IR 05000334/20240102024-05-15015 May 2024 Information Request for Quadrennial Baseline Comprehensive Engineering Team Inspection; Notification to Perform Inspection 05000334/2024010 and 05000412/2024010 ML24044A1772024-02-14014 February 2024 RAI for 180 Days Steam Generator Report ML23143A0272023-05-23023 May 2023 Licensed Operator Positive Fitness-For-Duty Test ML23125A1462023-05-0505 May 2023 NRR E-mail Capture - Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23125A1602023-05-0505 May 2023 NRR E-mail Capture - Correction to Beaver Valley - RAI Regarding Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23122A0342023-05-0202 May 2023 NRR E-mail Capture - Beaver Valley - Request for Additional Information Regarding Unit 1 - 180 Day Steam Generator Tube Inspection Report ML22312A5912022-11-0808 November 2022 NRR E-mail Capture - Beaver Valley Power Station, Units 1&2 - Request for Additional Information LAR to Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML22278A0972022-10-0606 October 2022 Supplemental Information Needed for Acceptance of Requested Licensing Action Amendment Request for Fire Protection Program Changes ML22178A1322022-06-24024 June 2022 Request for Additional Information for Beaver Valley Unit 2 Steam Generator Inspection Report - Fall 2021 Refueling Outage ML22068A1822022-03-0909 March 2022 NRR E-mail Capture - Beaver Valley Power Station, Units 1 & 2 - Request for Additional Information for License Amendment Request to Revise Technical Specification 3.3.5 IR 05000334/20220102022-01-13013 January 2022 Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000334/2022010 and 05000412/2022010 ML21292A0482021-10-19019 October 2021 Ti 2515/194 Inspection Documentation Request ML21259A1642021-09-16016 September 2021 NRR E-mail Capture - Request for Additional Information Regarding the LAR for Core Operating Limits ML21124A1322021-05-0404 May 2021 Notification of Conduct of a Fire Protection Team Inspection ML21102A1542021-04-0909 April 2021 Request for Additional Information (2nd Round) - Steam Generator Tube Sleeve LAR ML21082A4942021-03-23023 March 2021 Final RAIs for GL 04-02 Closure (Email) ML21068A3502021-03-0909 March 2021 Final Request for Additional Information for Reactor Coolant System (RCS) and Pressure and Tempature Limits Report(Ptlr) TS LAR ML21053A0252021-02-20020 February 2021 NRR E-mail Capture - Request for Additional Information (Rais) - LaSalle Request for Exemption from Pre-Access Drug and Alcohol Testing ML21015A5762021-01-14014 January 2021 Final RAIs for Steam Generator 180 Day Tube Inspection Report ML21007A3732021-01-0707 January 2021 NRR E-mail Capture - (External_Sender) (External) Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff, ML21004A1442020-12-30030 December 2020 NRR E-mail Capture - Request for Additional Information Regarding License Amendment Request to Incorporate the Applicable Standard Technical Specification 5.2.2, Unit Staff ML20290B0082020-10-0808 October 2020 Draft Request for Additional Information - Steam Generator Letter ML20127H8672020-05-0606 May 2020 NRR E-mail Capture - Beaver Valley, Davis-Besse, and Perry - Request for Additional Information Regarding Request for Exemptions from Part 73 Security Requalification Requirements ML20072N0402020-03-12012 March 2020 Request for Additional Information - Control Envelope Habitability LAR ML19192A2222019-07-18018 July 2019 Request for Additional Information Regarding Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML19143A0732019-05-29029 May 2019 FENOC Fleet - Beaver Valley, Units 1 and 2; Davis-Besse, Unit 1, Perry, Unit 1 - Supplemental Information Needed for Acceptance of Requested Licensing Action; Application for Order Consenting to License Transfer and Conforming Amendments ML18242A3642018-08-29029 August 2018 Request for Additional Information (Final) -Steam Generator Technical Specification LAR ML18102B0852018-04-12012 April 2018 NRR E-mail Capture - Follow-up Request for Additional Information (RAI) FENOC FLEET-- Exemption Request for a Physical Barrier Requirement for Beaver ML18043A0102018-02-0909 February 2018 NRR E-mail Capture - FENOC--MG0010-MG0011, MG-0012, MG0013-- Request for Additional Information (RAI) - Exemption Request Security Barrier in Physical Plans ML18024B3642018-01-24024 January 2018 NRR E-mail Capture - Beaver Valley 10 CFR 50.54(f) - NTTF 2.1 SPRA Review ML18019A0722018-01-18018 January 2018 NRR E-mail Capture - Beaver Valley Unit No. 1: Request for Additional Information - Modified Rtpts Values and Reactor Vessel Surveillance Capsule Withdrawal Schedule ML17353A1582017-12-19019 December 2017 NRR E-mail Capture - Request for Additional Information: Beaver Valley Unit No. 1 - Proposed Alternative Request, 1-TYP-4-BA-01 ML17352B2612017-12-18018 December 2017 NRR E-mail Capture - Request for Additional Information: Beaver Valley Unit No. 1 - Proposed Alternative Request, 1-TYP-4-BA-01 ML17303B1582017-11-0707 November 2017 FENOC-Beaver Valley Power Station, Units 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, Perry Nuclear Power Plant Unit 1 - Generic Letter 2016-01, Request for Supplemental Information ML17256A2502017-09-13013 September 2017 NRR E-mail Capture - Beaver Valley Power Station Units 1&2: Request for Additional Information for Emergency Plan EAL Change to Adopt NEI 99-01, Rev. 6, ML17220A2342017-08-0808 August 2017 E-mail Regarding Request for Additional Information for NFPA 805 License Amendment Request ML17093A7622017-04-10010 April 2017 Request for Additional Information Regarding Emergency Action Level Scheme Change License Amendment Request ML17031A0362017-02-0303 February 2017 Request for Additional Information Regarding Relief Request Numbers PR6 and PR7 ML16333A0162016-12-0202 December 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML16147A2842016-06-14014 June 2016 Request for Additional Infomation Regarding Fall 2015 Refueling Steam Generator Tube Inspections ML16071A1222016-04-0707 April 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML16084A8442016-03-30030 March 2016 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML16060A0122016-02-29029 February 2016 FENOC - Email RAI to Licensee Regarding LAR for Changes to TS 5.3.1 CAC Nos. MF7118, MF7119, and MF7120 ML15320A4132015-11-24024 November 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML15280A0742015-10-0909 October 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 ML15279A1252015-10-0505 October 2015 Licensed Operator Positive for Fitness-for-Duty-Test ML15181A2142015-07-14014 July 2015 Request for Additional Information Regarding License Amendment Request to Revise Steam Generator Technical Specifications to Reflect TSTF-510 and to Revise Alloy 800 Sleeve Technical Specifications (TAC Nos. MF6054 & MF6055) ML15125A4162015-05-11011 May 2015 Request for Additional Information Regarding License Amendment Request to Adopt National Fire Protection Association Standard 805 (TAC Nos. MF3301 & MF3302) ML15016A4392015-01-20020 January 2015 Draft Request for Additional Information 2024-07-17
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 24, 2015 Mr. Eric A. Larson, Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NOS. 1 AND 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805 (CAC NOS. MF3301 AND MF3302)
Dear Mr. Larson:
By letter dated December 23, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14002A086), as supplemented by letters dated February 14, 2014 (ADAMS Accession No. ML14051A499); April 27, 2015 (ADAMS Accession No. ML15118A484);
May 27, 2015 (ADAMS Accession No. ML15147A372); June 26, 2015 (ADAMS Accession No. ML15177A110); and November 6, 2015 (ADAMS Accession No. ML15313A306), FirstEnergy Nuclear Operating Company submitted a license amendment request to change the Beaver Valley Power Station, Unit Nos. 1 and 2, fire protection program to one based on the National Fire Protection Association Standard 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants, 2001 Edition, as incorporated into Title 10 of the Code of Federal Regulations, Part 50, Section 50.48(c). To complete its review, the U.S. Nuclear Regulatory Commission staff requests a response to the enclosed request for additional information questions.
The draft questions were sent to Mr. Phil Lashley of your staff to ensure that the questions were understandable, the regulatory basis for the questions was clear, and to determine if the information was previously docketed. Please respond to the enclosed questions within 30 days from the date of this letter.
E. Larson If you have any questions regarding this matter, please contact me at (301) 415-7128 or Taylor.Lamb@nrc.gov.
Sincerely,
~u~~
Taylor A. Lamb, Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-334 and 50-412
Enclosure:
Request for Additional Information cc w/enclosure: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION LICENSE AMENDMENT REQUEST TO ADOPT NATIONAL FIRE PROTECTION ASSOCIATION STANDARD 805, "PERFORMANCE-BASED STANDARD FOR FIRE PROTECTION FOR LIGHT WATER REACTOR ELECTRIC GENERATING PLANTS."
FIRSTENERGY NUCLEAR OPERATING COMPANY BEAVER VALLEY POWER STATION. UNIT NOS. 1 AND 2 DOCKET NOS. 50-334 AND 50-412 By letter dated December 23, 2013 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML14002A086), as supplemented by letters dated February 14, 2014 (ADAMS Accession No. ML14051A499); April 27, 2015 (ADAMS Accession No. ML15118A484);
May 27, 2015 (ADAMS Accession No. ML15147A372); June 26, 2015 (ADAMS Accession No. ML15177A110); and November 6, 2015 (ADAMS Accession No. ML15313A306), FirstEnergy Nuclear Operating Company (the licensee) submitted a license amendment request (LAR) to change the Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and BVPS-2) fire protection program to one based on the National Fire Protection Association Standard (NFPA) 805, "Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants," 2001 Edition, as incorporated into Title 10 of the Code of Federal Regulations (10 CFR),
Part 50, Section 50.48(c). To complete its review, the U.S. Nuclear Regulatory Commission (NRC) staff requests a response to the request for additional information (RAI) questions below.
Fire Protection Engineering (FPE) RAI 04.01 In its response to FPE RAI 04(a) in letter dated June 26, 2015, the licensee stated that an engineering evaluation analyzed compliance with NFPA 805, Section 3.3.5.3, for the low population of cables with potentially non-qualified electrical cable insulation material installed in electrical raceways at BVPS-1 and BVPS-2 and determined the configuration to be acceptable.
The licensee also stated that it will include the engineering evaluation as a reference and remove the "Submit for NRC Approval" compliance statement for this NFPA 805, Chapter 3, requirement. NFPA 805, Section 3.3.5.3, requires that electric cable construction comply with a flame propagation test as acceptable to the authority having jurisdiction (AHJ), and the guidance in NFPA 805 Frequently Asked Question (FAQ) 06-0022, "Electrical Cable Flame Propagation Tests," identifies the flame propagation tests that are acceptable to the AHJ (i.e., the NRC). In accordance with FAQ 06-0008, "Alternative Method for Fire Protection Engineering Analyses,"
Revision 9, and the limitations imposed in the NRC closure memorandum, dated March 12, 2009 (ADAMS Accession No. ML073380976), existing engineering equivalency evaluations (EEEEs) can only be self-approved by the licensee if the following conditions apply:
(1) The fire protection system or feature meets "Functional Equivalency" with the NFPA 805, Chapter 3, requirement; or Enclosure
(2) The fire protection system or feature required by NFPA 805, Chapter 4, is determined to be "Adequate for the Hazard" (e.g., Fire Alarm and Detection Systems (Section 3.8), Automatic and Manual Water-Based Fire Suppression Systems (Section 3.9), Gaseous Fire Suppression Systems (Section 3.10), and Passive Fire Protection Features (Section 3.11 )).
In the engineering evaluation, the licensee concluded that the low population of cables that do not meet Institute of Electrical and Electronics Engineers (IEEE) Standard 383, 1974 Edition, or equivalent, were considered in the fire modeling evaluation and determined to be adequate for the hazard. In accordance with FAQ 06-0008, this type of EEEE cannot be self-approved by the licensee. If performance-based engineering analysis of the non-qualified electrical cable insulation materials is credited in the compliance with NFPA 805, Section 3.3.5.3, then submit a request for NRC staff approval in accordance with 10 CFR 50.48(c)(2)(vii), and discuss how the configuration satisfies the nuclear safety and radiological release performance goals, performance objectives and performance criteria, maintains safety margins, and maintains fire protection defense-in-depth. If functional equivalency is credited in the compliance with NFPA 805, Section 3.3.5.3, then provide justification of the equivalency to this requirement.
FPE RAI 05.01 In letter dated June 26, 2015, the licensee stated in its response to FPE RAI 05(a) that it is changing its compliance statement in LAR Attachment A from "Complies with Clarification" to "Complies with the use of EEEE" for certain NFPA 805, Chapter 3, requirements. In accordance with FAQ 06-0008, and the limitations imposed in the NRC closure memorandum for FAQ 06-0008, EEEEs can only be self-approved by the licensee if the following conditions apply:
(1) The fire protection system or feature meets "Functional Equivalency" with the NFPA 805, Chapter 3, requirement; or (2) The fire protection system or feature required by NFPA 805, Chapter 4, is determined to be "Adequate for the Hazard" (e.g., Fire Alarm and Detection Systems (Section 3.8), Automatic and Manual Water-Based Fire Suppression Systems (Section 3.9), Gaseous Fire Suppression Systems (Section 3.10), and Passive Fire Protection Features (Section 3.11 )).
The NRC reviewed the EEEEs in the licensee's NFPA 805 LAR supporting documents that evaluated the following configurations. Additional information is requested to support the bases for changing the compliance statement to "Complies with the Use of EEEE" for the NFPA 805, Chapter 3, requirement:
(a) In its response to FPE RAI 05(a)(i), the licensee stated that for the BVPS-2 outdoor hydrogen storage tank orientation, an EEEE was performed for compliance with NFPA 55, "Compressed Gases and Cryogenic Fluids Code,"
which concluded that the orientation of the tanks is acceptable to meet compliance with NFPA 805, Section 3.3.7.2. The separation distances in NFPA 55 are associated with protection from radiant heat based on the storage volume, and the requirement in NFPA 805, Section 3.3.7.2, is associated with
potential missile generation. Therefore, NFPA 55 is not applicable to this NFPA 805, Chapter 3, requirement, which goes beyond the requirements of NFPA 55. The EEEE for the NFPA 55 code evaluation determined that the configuration is adequate for the hazard. In accordance with FAQ 06-0008, this type of EEEE will need to be reviewed and approved by the NRC staff because "Adequate for the Hazard" EEEEs are associated with analyses performed under NFPA 805, Chapter 4, and this section provides requirements for fundamental fire protection program and design elements that require prior staff approval prior to making changes. Unless the design and installation of the hydrogen storage tanks is demonstrated by an EEEE to be functionally equivalent to the missile protection intended by the NFPA 805 requirement, provide the performance-based engineering analysis to obtain NRC staff approval in accordance with 10 CFR 50.48(c)(2)(vii). Discuss how the configuration satisfies the nuclear safety and radiological release performance goals, performance objectives and performance criteria, maintains safety margins, and maintains fire protection defense-in-depth.
(b) In its response to FPE RAI 05(a)(iii), the licensee stated that the existing fire pump installations and control circuits were evaluated for compliance with NFPA 20, 1970 Edition, "Centrifugal Fire Pumps," in an EEEE, which concluded that the configuration of the BVPS fire pumps installation and separation of control circuits is acceptable. The EEEE does not demonstrate "Functional Equivalency" with the requirements of NFPA 805, Section 3.5.5, but instead, it concludes that the configuration is "Adequate for the Hazard." In accordance with FAQ 06-0008, this type of EEEE will need to be reviewed and approved by the NRC staff because "Adequate for the Hazard" EEEEs are associated with analyses performed under NFPA 805, Chapter 4, and this section provides requirements for fundamental fire protection program and design elements that require prior staff approval prior to making changes. Since the design and installation of the fire pumps is not demonstrated by the EEEE to be functionally equivalent to the NFPA 805 requirement, provide the performance-based engineering analysis to obtain NRC staff approval in accordance with 10 CFR 50.48(c)(2)(vii). Discuss how the configuration satisfies the nuclear safety and radiological release performance goals, performance objectives and performance criteria, maintains safety margins, and maintains fire protection defense-in-depth.
(c) In its response to FPE RAI 05(a)(iv), the licensee stated that it will include the results of the applicable fire hydrant evaluation in LAR Attachment A The EEEE for the NFPA 24 code evaluation involved the acceptability of the distance between Yard Fire Hydrant 9 and the Intake Structure as being functionally equivalent to the requirements of NFPA 805, Section 3.5.15, since adequate flow and pressure will be provided for the hydrant if no more than 100 feet of 1~ inches diameter hose is used, and all additional hose used is 2~ inches or larger in diameter. However, the licensee stated in LAR Attachment A that it "Complies with Clarification" because the distance from Yard Fire Hydrant 10 to the Intake Structure exceeds the allowable distance and is approximately 350 feet away. Discuss how the EEEE, which evaluates the distance between
Yard Fire Hydrant 9 and the Intake Structure, is credited as the basis for changing the compliance statement to "Complies with the Use of EEEE" in LAR Attachment A, which describes the distance between Yard Fire Hydrant 10 and the Intake Structure. In your discussion, address the discrepancy with the hydrant numbers (is it Hydrant 9 or Hydrant 1O?).
(d) In its response to FPE RAI 05(a)(v), the licensee stated that an EEEE of the BVPS-1 and BVPS-2 interior standpipe and hose station systems determined that they are equivalent to the requirements of NFPA 14, "Standard for the Installation of Standpipe and Hose Systems." In LAR Attachment A, the licensee stated in the compliance basis for NFPA 805, Section 3.6.2, that pressure reducers are not provided at the hose stations, even though available pressure can exceed 100 pounds per square inch (psi) at some hose stations, and that the fire brigade members are trained and drilled using the expected pressures available at BVPS, and thus, the existing installation is considered adequate.
Unless the EEEE that was performed for the NFPA 14 code evaluation demonstrates that the standpipe and hose station design is "Functionally Equivalent" to the requirements of NFPA 805, Section 3.6.2, provide the performance-based engineering analysis to obtain NRC staff approval in accordance with 10 CFR 50.48(c)(2)(vii), and discuss how the configuration satisfies the nuclear safety and radiological release performance goals, performance objectives, and performance criteria, maintains safety margins, and maintains fire protection defense-in-depth.
FPE RAI 05.02 In its response to FPE RAI 05(b) in letter dated June 26, 2015, the licensee stated that the compliance bases for each record identified in Table 5b, "BVPS-1 and BVPS-2 Revised Records From LAR Attachment A, Table B-1," will be revised to "Complies" and/or "Complies with Use of EEEE" for various NFPA 805, Chapter 3, elements. The guidance provided in FAQ 07-0036, "Incorporation of Pilot Plant Lessons Learned -Table B-1," states that the compliance statement to NFPA 805, Chapter 3, should be documented. In addition, FAQ 07-0033, Transition of Existing Engineering Equivalency Evaluations" Revision 1, and FAQ 06-0008 provide guidance on when the use of an EEEE can be credited to satisfy the NFPA 805, Chapter 3, requirement without prior NRC approval. As described in FAQ 06-0008, and the limitations imposed in the NRC closure memorandum for FAQ 06-0008, EEEEs can only be self-approved by the licensee if the following conditions apply:
(1) The fire protection system or feature meets "Functional Equivalency" with the NFPA 805, Chapter 3, requirement; or (2) The fire protection system or feature required by NFPA 805, Chapter 4, is determined to be "Adequate for the Hazard" (e.g., Fire Alarm and Detection Systems (Section 3.8), Automatic and Manual Water-Based Fire Suppression Systems (Section 3.9), Gaseous Fire Suppression Systems (Section 3.10), and Passive Fire Protection Features (Section 3.11 )).
Therefore, EEEEs that involve a bounding approach or are determined to be "adequate for the hazard" for fire protection systems and features that are not required by NFPA 805 Chapter 4 will require prior NRC staff approval, and the licensee may use the latitude provided in 10 CFR 50.48(c)(2)(vii) to obtain NRC staff approval of these types of EEEEs. The following information is requested to support the NRC staff's review of the licensee's response to FPE RAI OS(b):
(a) For each fire protection system and feature identified in Table Sb (except for the Carbon Dioxide (C02) system installed in Fire Compartment 2-SB-3 to meet the requirements of NFPA 805, Section 3.10.1 ), clearly identify if the NFPA 805, Chapter 3, compliance statement is either "Complies" or "Complies with Use of EEEE," and provide the compliance bases that will be credited to replace "Complies with Clarification" in LAR Attachment A If the compliance statement involves "Complies with the Use of EEEE," then provide a summary of the fire protection feature or system that is evaluated in the EEEE, the bases for concluding whether the EEEE meets functional equivalency of the NFPA 805, Chapter 3; requirement or is adequate for the hazard, and the reference source.
(b) For the C02 system installed in Fire Compartment 2-SB-3, the licensee stated in LAR Attachment A that the testing frequency for the C02 system is every 18 months based on the performance of the system, and that the Electric Power Research Institute (EPRI) Technical Report (TR)-1006756, "Fire Protection Equipment Surveillance Optimization and Maintenance Guide for Fire Protection Systems and Features," suggests the use of this frequency as the basis for "Complies with Clarification." In its response to FPE RAI OS(b), the licensee stated that the compliance statement will change to "Complies" and/or "Complies with the Use of EEEE." The use of a performance-based method (i.e., EPRI TR-1006756) to determine acceptability of a testing frequency does not meet the criteria for "Complies" or "Complies with the Use of EEEE" and will require prior NRC staff approval in accordance with 10 CFR 50.48(c)(2)(vii). Provide the performance-based engineering analysis that evaluates the acceptability of the testing frequency for the C02 system in Fire Compartment 2-SB-3 for compliance with NFPA 805, Section 3.10.1, including the specific EPRI TR-1006756 reference, and obtain NRC staff approval in accordance with 10 CFR 50.48(c)(2)(vii). Discuss how the configuration satisfies the nuclear safety and radiological release performance goals, performance objectives and performance criteria, maintains safety margins, and maintains fire protection defense-in-depth.
FPE RAI 06.01 In its response to FPE RAI 06 in letter dated April 27, 2015, the licensee stated that the compliance statement for NFPA 805, Section 3.3.3, is changed from "Complies with Clarification" to "Complies by Previous NRC Approval" and provided the appropriate excerpts from its licensing bases documents that demonstrate that the interior finishes for both BVPS-1 and BVPS-2 have a flame spread rating of less than 25 per American Society for Testing and Materials Standard E-84 test method or equivalent. The licensee further stated that the requirements of NFPA 805, Section 3.3.3., with respect to compliance with NFPA 101, "Life
Safety Code," will be incorporated into the appropriate procurement and plant documents as an implementation item in LAR Attachment S. However, in its response to FPE RAI 05(b) in letter dated June 26, 2015, the licensee stated that the compliance statement for NFPA 805, Section 3.3.3, will be changed from "Complies with Clarification" to "Complies" and/or "Complies with Use of EEEE," and did not provide information as to whether its response to FPE RAI 05(b) will supersede its earlier response to FPE RAI 06 with respect to compliance with NFPA 805, Section 3.3.3.
Clarify how BVPS-1 and BVPS-2 will comply with NFPA 805, Section 3.3.3. If an implementation item will be required to meet its compliance bases, then provide the implementation item number and a clear description of the implementation item. If the licensee determines that it "Complies with Use of EEEE," then in accordance with the guidance in FAQ 07-0036 and FAQ 06-0008, provide a summary of the fire protection feature or system that is evaluated in the EEEE, the bases for concluding whether the EEEE meets functional equivalency of the NFPA 805, Chapter 3, requirement, and the reference source.
FPE RAI 12.01 In its response to FPE RAI 12 and FPE RAI 14(a) in letter dated June 26, 2015, the licensee stated that Approval Request 1 in LAR Attachment L will be withdrawn, and that the compliance statement for the requirements of NFPA 805, Section 3.3.5.1, will be changed to "Complies with Use of an EEEE" in LAR Attachment A. The licensee stated that an EEEE was performed and determined that cables that are not in conformance with NFPA 805, Section 3.3.5.1, above suspended ceilings do not adversely affect the nuclear safety capability; do not impact the radiological release performance goals and performance objectives and performance criteria of NFPA 805, Section 1.5; and maintain the safety margins and fire protection defense-in-depth.
This NFPA 805, Chapter 3, requirement is not associated with NFPA code compliance or a fire protection system or feature necessary to meet NFPA 805, Chapter 4, deterministic requirements. Therefore, the guidance in FAQ 06-0008, Revision 9, and limitations described in the NRC closure memo for FAQ 06-0008, states that this type of EEEE would require prior NRC approval.
Describe how BVPS-1 and BVPS-2 will comply with NFPA 805, Section 3.3.5.1. If the licensee decides to re-submit LAR Attachment L, Approval Request 1, or a new engineering evaluation to obtain NRC staff approval in accordance with 10 CFR 50.48(c)(2)(vii), then provide the information requested in FPE RAI 12 and FPE RAI 14(a), which was provided in the NRC letter dated March 4, 2015 (ADAMS Accession No. ML15049A507).
ML15320A413 *via e-mail OFFICE DORL/LPLl-2/PM DORL/LPLl-2/LA DRA/AFPB/BC DORL/LPLl-2/BC DORL/LPLl-2/PM NAME AK le in DBroaddus Tlamb Tlamb LRonewicz (HBarrett for)
DATE 11/20/15 11/18/15 11/20/15 11/24/15 11/24/15