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Category:Letter
MONTHYEARML24025A0922024-01-25025 January 2024 Requalification Program Inspection L-23-267, Submittal of Discharge Monitoring Report (Npdes), Permit No. PA00256152023-12-18018 December 2023 Submittal of Discharge Monitoring Report (Npdes), Permit No. PA0025615 IR 05000334/20230112023-12-0404 December 2023 Age-Related Degradation Inspection Report 05000334/2023011 and 05000412/2023011 L-23-229, Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports2023-11-29029 November 2023 Request for Additional Information Regarding the Spring 2023 Generic Letter 95-05 Voltage-Based Alternate Repair Criteria and Steam Generator F-Star Reports IR 05000334/20233012023-11-27027 November 2023 Initial Operator Licensing Examination Report 05000334/2023301 L-23-247, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-11-17017 November 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 IR 05000334/20230032023-11-0606 November 2023 Integrated Inspection Report 05000334/2023003 and 05000412/2023003 L-23-227, Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 20232023-10-20020 October 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 for Third Quarter 2023 ML23279A0612023-10-0505 October 2023 Paragon Energy Solutions LLC, Part 21 Final Report Re Potential Defect with Eaton Jd and Hjd Series Molded Case Circuit Breakers (Mccbs) ML23198A3592023-10-0202 October 2023 Issuance of Amendment Nos. 322 and 212 Analytical Methodology to the Core Operating Limits Report for a Full Spectrum Loss of Coolant Accident (EPID L-2022-LLA-0129) - Nonproprietary IR 05000334/20234022023-09-29029 September 2023 Security Baseline Inspection Report 05000334/2023402 and 05000412/2023402 (Cover Letter Only) ML23237B4222023-09-28028 September 2023 Energy Harbor Nuclear Corp. - Vistra Operations Company LLC - Letter Regarding Order Approving Transfer of Licenses and Draft Conforming License Amendments ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure IR 05000334/20234012023-09-21021 September 2023 Cybersecurity Inspection Report 05000334/2023401 and 05000412/2023401 (Cover Letter Only) ML23263A0192023-09-20020 September 2023 Operator Licensing Examination Approval ML23243A9272023-09-19019 September 2023 Review of the Fall 2022 Steam Generator Tube Inspection Report ML23249A1842023-09-18018 September 2023 Authorization and Safety Evaluation for Alternative Request No. 2-TYP-4-RV-06 L-23-208, Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA00256152023-09-14014 September 2023 Submittal of Discharge Monitoring Report Cnpdes), Permit No. PA0025615 L-23-167, Twenty-Third Refueling Outage Inservice Inspection Summary Report2023-09-13013 September 2023 Twenty-Third Refueling Outage Inservice Inspection Summary Report L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments IR 05000334/20230052023-08-31031 August 2023 Updated Inspection Plan for Beaver Valley Power Station Units 1 and 2 (Report 05000334/2023005 and 05000412/2023005) L-23-172, Quality Assurance Program Manual2023-08-31031 August 2023 Quality Assurance Program Manual ML23129A1722023-08-25025 August 2023 Request for Withholding Information from Public Disclosure for Beaver Valley Power Station, Units 1 and 2; Davis Besse Nuclear Power Station, Unit 1; and Perry Nuclear Power Plant, Unit 1 IR 05000334/20230022023-08-0909 August 2023 Integrated Inspection Report 05000334/2023002 and 05000412/2023002 ML23219A0592023-08-0707 August 2023 Steam Generator Inspection Reports - Spring 2023 Spring Refueling Outrage L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments L-23-179, Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA00256152023-07-18018 July 2023 Submittal of Discharge Monitoring Report, (NPDES) Permit No. PA0025615 ML23188A0982023-07-17017 July 2023 Correction to the Safety Evaluation Issued Related to Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time ML23188A0672023-07-10010 July 2023 Project Manager Assignment L-23-165, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-06-26026 June 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 L-23-139, Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report2023-06-13013 June 2023 Response to Request for Additional Information Regarding Fall 2022 180-Day Steam Generator Tube Inspection Report ML23157A1072023-06-0707 June 2023 Request for Information and Notification of Conduct of IP 71111.21.N.04, Age-Related Degradation, Reference Inspection Report 05000334/2023011 and 05000412/2023011 ML23143A0272023-05-23023 May 2023 Licensed Operator Positive Fitness-For-Duty Test L-23-055, Submittal of the Updated Final Safety Analysis Report, Revision 342023-05-23023 May 2023 Submittal of the Updated Final Safety Analysis Report, Revision 34 ML23102A1472023-05-22022 May 2023 Issuance of Amendment Nos. 321 and 211 Consolidate Fuel Decay Time Technical Specifications in a New Limiting Condition for Operation Titled Decay Time L-23-065, Annual Financial Report2023-05-22022 May 2023 Annual Financial Report ML23135A7872023-05-19019 May 2023 Summary of Conference Calls Regarding the Spring 2023 Steam Generator Tube Inspections L-23-137, Discharge Monitoring Report (NPDES) Permit No. PA00256152023-05-18018 May 2023 Discharge Monitoring Report (NPDES) Permit No. PA0025615 ML23124A1742023-05-17017 May 2023 Energy Harbor Fleet Vistra License Transfer - Request for Withholding Information from Public Disclosure for Commance Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 L-23-125, Cycle 24 Core Operating Limits Report2023-05-17017 May 2023 Cycle 24 Core Operating Limits Report ML23124A3882023-05-16016 May 2023 Summary of Regulatory Audit in Support of License Amendment Request to Revise Technical Specification 5.6.3, Core Operating Limits Reports (COLR) and TS 4.2.1 Fuel Assemblies ML23129A0112023-05-16016 May 2023 Notice of Consideration of Approval of Indirect and Direct License Transfer for Comanche Peak Plant, Units 1 & 2, Beaver Valley Station, Units 1 & 2, Davis Besse Station, Unit 1 and Perry Plant, Unit 1 (EPID L-2023-LLM-0000) (Letter) L-23-132, Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations2023-05-10010 May 2023 Response to NRC Regulatory Issue Summary 2023-01 Preparation and Scheduling of Operator Licensing Examinations IR 05000334/20230012023-05-0808 May 2023 Integrated Inspection Report 05000334/2023001 and 05000412/2023001 L-23-129, Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations2023-05-0505 May 2023 Response to Request for Additional Information for 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations ML23118A3812023-04-28028 April 2023 10 CFR 50.55a Request 2-TYP-4-RV-06 for Alternative Repair Methods for Reactor Pressure Vessel Head Penetrations L-23-115, Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological2023-04-27027 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report, 2022 Annual Radiological Environmental Operating Report, and 2022 Annual Environmental Operating Report (Non-Radiological L-23-126, Discharge Monitoring Report (Npdes), Permit No. PA00256152023-04-22022 April 2023 Discharge Monitoring Report (Npdes), Permit No. PA0025615 CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments ML23107A2502023-04-18018 April 2023 Requalification Program Inspection 2024-01-25
[Table view] Category:Updated Final Safety Analysis Report (UFSAR)
MONTHYEARML23144A3052023-05-23023 May 2023 Updated Final Safety Analysis Report, Revision 34 ML22144A1282022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program ML22144A1162022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML22144A1142022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations ML22144A1312022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Featres ML22144A1302022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML22144A1362022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML22144A1172022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 4, Reactor ML22144A1192022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 16, Technical Specifications ML22144A1202022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML22144A1292022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 18, Human Factors Engineering ML22144A1222022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, List of Effective Pages ML22144A1212022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML22144A1262022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary Systems ML22144A1332022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 8, Electric Power ML22144A1322022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 19, Managing the Effects of Component Aging ML22144A1242022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 15, Accident Analysis ML22144A1232022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML22144A1182022-05-18018 May 2022 6 to Updated Final Safety Analysis Report, Chapter 5, Reactor Coolant System and Connected Systems L-22-058, Submittal of Revision 26 to Updated Final Safety Analysis Report2022-05-18018 May 2022 Submittal of Revision 26 to Updated Final Safety Analysis Report ML21334A0292021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, List of Effective Pages ML21334A0262021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary ML21334A0352021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Wastes and Radiation Protection ML21334A0312021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 3, Reactor ML21334A0252021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 16, Managing the Effects of Component Aging ML21334A0202021-11-22022 November 2021 Submittal of the Updated Final Safety Analysis Report, Revision 33 ML21334A0222021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 7, Instrumentation and Controls ML21334A0272021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Appendix B, Seismic Design ML21334A0232021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System ML21334A0332021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 14, Safety Analysis ML21334A0212021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 13, Initial Tests and Operation ML21334A0362021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Appendix a, Quality Assurance ML21334A0372021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features ML21334A0242021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 5, Containment Systems ML21334A0302021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 15, Technical Specifications and Bases L-21-164, 3 to Updated Final Safety Analysis Report, Chapter 12, Conduct of Operations2021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 12, Conduct of Operations ML21334A0322021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary and Emergency System ML21334A0392021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 8, Electrical Systems ML21334A0282021-11-22022 November 2021 3 to Updated Final Safety Analysis Report, Chapter 10, Steam and Power Conversion System ML20335A1382020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 11, Radioactive Waste Management ML20335A1412020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 8, Electric Power ML20335A1402020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 19, Managing the Effects of Component Aging ML20335A1252020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 13, Conduct of Operations L-20-186, 5 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection2020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 12, Radiation Protection ML20335A1392020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features ML20335A1202020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 1, Introduction and General Description of Plant ML20335A1302020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 17, Quality Assurance ML20335A1362020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 14, Initial Test Program ML20335A1372020-11-23023 November 2020 5 to Updated Final Safety Analysis Report, Chapter 18, Human Factors Engineering ML20335A1222020-11-23023 November 2020 Submittal of Revision 25 to Updated Final Safety Analysis Report 2023-05-23
[Table view] |
Text
FE NOCŽ RrstEnergy Nuclear Operating Company Marty L. Richey Site Vice President April 21, 2017 L-17-029 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-001
SUBJECT:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Submittal of the Updated Final Safety Analysis.
Report. Revision 30 Beaver Valley Power Station P.O. Box4 Shippingport, PA 15077 724-682-5234 Fax: 724-643-8069 10 CFR 50.71(e) 10 CFR 50.54(a) 10 CFR 54.37(b) In accordance with the requirements of 10 CFR 50.71 (e), the FirstEnergy Nuclear Operating Company (FENOC) is hereby submitting to the Nuclear Regulatory Commission (NRC) the Beaver Valley Power Station (BVPS), Unit No. 1, Updated Final Safety Analysis Report (UFSAR) Revision 30 in CD-ROM format. This submittal reflects facility and procedure changes implemented between May 24, 2015 (the end of Refueling Outage 23), and October 25, 2016 (the end of Refueling Outage 24), along
- with several changes implemented after Refueling Outage 24. In accordance with 10 CFR 50.4(b)(6), the BVPS, Unit No. 1, UFSAR Revision 30 is being submitted electronically on a total replacement basis. As required by NRC guidance for electronic submissions to the Commission, Attachment 1 and 2 provide a listing of the document components that make up the two enclosed CD-ROMs. In addition to the UFSAR, the first enclosed CD-ROM includes the following:
- BVPS, Unit No. 1 Licensing Requirements Manual (LRM), Revision 96
- Technical Specification (TS) Bases, Revision 32, submitted to'satisfy TS 5.5.1 O.d, which requires submittal of TS Bases changes implemented without prior NRC approval * *FENOC Quality Assurance Program Manual (QAPM), Revision 21, submitted in accordance with 10 CFR 50.54(a)
Beaver Valley Power Station, Unit No. 1 L-17-029 Page 2 The second enclosed CD-ROM includes the BVPS-1 UFSAR, LRM, TS Bases and QAPM with information identified in accordance with NRC Regulatory Issue Summary (RIS) 2015-17, "Review and Submission of Updates to Final Safety Analysis Reports, Emergency Preparedness Documents, and Fire Protection Documents," removed. Attachment 3 includes a summary of information removed from the BVPS, Unit No. 1 UFSAR in accordance with Appendix A to Nuclear Energy Institute (NEI) 98-03, "Guidelines for Updating Final Safety Analysis Reports," Revision 1. FENOC conducted a review of BVPS-1 plant changes for 10 CFR 54.37(b) applicability and identified components that were determined to meet the criteria for newly identified components as clarified by RIS 2007-16, Revision 1, "Implementation of the Requirements of 10 CFR 54.34(b) for Holders of Renewed Licenses." Attachment 4 describes the review results. There are no regulatory commitment changes to be submitted in accordance with NEI 99-04, "Guidelines for Managing NRC Commitment Changes," Revision 0, as endorsed by NRC RIS 2000-17, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff." This certifies, to the best of our judgment and belief, that Revision 30 of the BVPS, Unit No. 1 UFSAR accurately presents changes made since the previous submittal that are necessary to reflect information and analysis submitted to the Commission or pursuant to Commission requirements.
This letter contains no new regulatory commitments.
If you have any questions regarding this report, please contact Mr. Thomas A. Lentz, Manager -Fleet Licensing, at 330-315-6810.
Sincerely, r Marty L.
Beaver Valley Power Station, Unit No. 1 L-17-029 Page 3 Attachments:
- 1. List of Document Components on CD-ROM 1 2. List of Document Components on CD-ROM 2 (Information Identified Per RIS 2015 -17 Removed) 3. Information Removed from the BVPS, Unit No. 1 UFSAR 4. Review of Plant Changes for 10 CFR 54.37(b) Applicability
Enclosures:
A. Beaver Valley Power Station, Unit No. 1 UFSAR, Licensing Requirements Manual, Technical Specification Bases, and QAPM (on CD-ROM 1) B. Beaver Valley Power Station, Unit No. 1 UFSAR With Information Identified Per RIS 2015-17 Removed, Licensing Requirements Manual, Technical Specification Bases, and QAPM (on CD-ROM 2) cc: NRG Region I Administrator NRG Resident Inspector NRG Project Manager Director BRP/DEP (without Enclosures)
Site BRP/DEP Representative (without Enclosures)
Attachment 1 L-17-029 List of Document Components on CD-ROM 1 Page 1 of 1 File Name 001 UFSAR List of Effective Pages Rev 30.pdf 002 UFSAR Section 1.pdf 003 UFSAR Section 2.pdf 004 UFSAR Section 3.pdf 005 UFSAR Section 4.pdf 006 UFSAR Section 5.pdf 007 UFSAR Section 6.pdf 008 UFSAR Section 7.pdf 009 UFSAR Section 8.pdf 010 UFSAR Section 9.pdf 011 UFSAR Section 1 O.pdf 012 UFSAR Section 11.pdf 013 UFSAR Section 12.pdf 014 UFSAR Section 13.pdf 015 UFSAR Section 14.pdf 016 UFSAR Section 15.pdf 017 UFSAR Section 16.pdf 018 UFSAR Appendix A.pdf 019 UFSAR Appendix B.pdf 020 BVPS-1 LRM Rev 96.pdf 021 BVPS TS Bases Rev 32.pdf 022 FENOC QAPM Rev 21.pdf 71KB 1,261 KB 43,341KB 3,881KB 1,748KB 3,985KB 7,591KB 2,655KB 1,528KB 2,148KB 991KB 1, 107KB 91KB 414KB 6,904KB 131KB 317KB 582KB 1,733KB 1,393KB 2,301KB 2,545KB
Attachment 2 L-17-029 List of Document Components on CD-ROM 2 (Information Identified Per RIS 2015-17 Removed) Page 1 of 1 File Name 001 UFSAR List of Effective Pages Rev 30.pdf 002 UFSAR Section 1.pdf 003 UFSAR Section 2.pdf 004 UFSAR Section 3.pdf 005 UFSAR Section 4.pdf 006 UFSAR Section 5.pdf 007 UFSAR Section 6.pdf 008 UFSAR Section 7.pdf 009 UFSAR Section 8.pdf 010 UFSAR Section 9.pdf 011 UFSAR Section 1 O.pdf 012 UFSAR Section 11.pdf 013 UFSAR Section 12.pdf 014 UFSAR Section 13.pdf 015 UFSAR Section 14.pdf 016 UFSAR Section 15.pdf 017 UFSAR Section 16.pdf 018 UFSAR Appendix A.pdf 019 UFSAR Appendix B.pdf 020 BVPS-1 LRM Rev 96.pdf 021 BVPS TS Bases Rev 32.pdf 022 FENOC QAPM Rev 21.pdf 71KB 1, 132KB 42,832KB 3,881KB 1,748KB 2,923KB 7,591KB 2,655KB 1,528KB 2,148KB 991KB 1, 107KB 91KB 414KB 6,904KB 131KB 317KB 582KB 1,733KB 1,393KB 2,301KB 2,545KB Attachment 3 L-17-029 Information Removed from BVPS, Unit No. 1 UFSAR Page 1of1 In accordance with Nuclear Energy Institute (NEI) 98-03, Revision 1, "Guidelines for Updating Final Safety Analysis Reports," licensees periodically report a brief description of information removed from the Updated Final Safety Analysis Report (UFSAR) and the basis for its removal. The following provides a summary of the information removed from the UFSAR and the basis for removal. 1. Removed excessive detail in the description of the reactor vessel stud tensioner from Section 9.12.2.3.
A new style stud tensioner is to be used in the future and is not germane to the description of the pressure vessel, head, or studs. The removed information has no impact on the ability of plant structures, systems, and components described in the UFSAR to perform their design basis functions and has no impact on plant operations.
Additionally, per Regulatory Guide 1.70 Rev. 3, Volume 2, Section 9.1.4, "Fuel Handling System," reactor vessel stud tensioner detail is not required.
This section requires a description of the fuel handling system, including all components for transporting and handling fuel from the time it reaches the plant until it leaves the plant. The stud tensioner is not used to transport or handle fuel.
Attachment 4 L-17-029 Review of Plant Changes for 10 CFR 54.37(b) Applicability Page 1 of 3 During review of plant changes for 10 CFR 54.37(b) applicability, the carbon dioxide fire suppression system in the Emergency Response Facility Substation (ERFS), including the Emergency Response Facility Diesel Generator Building (ERFDGB), was determined to meet the criteria for newly identified components, as clarified in .* Regulatory Information Summary (RIS) 2007-16, Revision 1, "Implementation of the Requirements of 10 CFR 54.37{b) for Holders of Renewed Licenses." Recently approved UFSAR Change Notice now credits the fire detection (Note 1) and suppression system in the ERFS, including the ERFDGB, as being within the scope of 10 CFR 50.48, "Fire Protection." Therefore, the fire detection suppression system meets the license renewal scoping criteria of 10 CFR 54.4(a)(3) as described in NU REG 1800, Revision 2, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (December 201 O)," section 2.1.3.1.3.
License renewal application (LRA) section 2.1.1.3.1 described the scoping of systems and structures relied on in safety analyses or plant evaluations to perform a function that demonstrates compliance with the fire protection criterion.
If the LRA were being prepared today, it would now include the fire suppression system in the ERFS and ERFDGB. This fire suppression system is within the scope of the Beaver Valley Power Station Fire Protection Program. The results of an aging management review for the fire suppression system in the ERFS, including the ERFDGB, is provided in the table below. The table and the corresponding aging management program descriptions contained in the UFSAR, already describe how the effects of aging will be managed for the newly identified components, as required by 10 CFR 54.37(b).
Other newly added components in the fire suppression system in the ERFS, including the ERFDGB, requiring aging management review (that is, the associated piping and component supports) were already addressed in the LRA and associated Aging Management Program (that is, the Structures Monitoring Program).
AGING MANAGEMENT REVIEW Component Intended Aging Effect Aging Material Environment Requiring Management Type Function(s)
Management Program Bolting Pressure Steel Air-indoor Loss of Bolting Integrity Boundar uncontrolled Material Bolting Pressure Steel Air -outdoor Loss of Bolting Integrity Bounda Material Note 1: Fire Detection does not meet 10 CFR 54.21 (a)(1 )(i) per Item 73 of Appendix B -Typical Structure, Component and Commodity Groupings and Active/Passive Determinations for Integrated Plant Assessment of NEI 95-10, Revision 6, and therefore, is excluded from this evaluation
..
Attachment 4 L-17-029 Page 2 of 3 Component Type Nozzle (C02) Piping (C02) Piping (C02) Piping (C02) Piping (C02) Piping (C02 fittings)
Piping (C02 fittings)
Piping (C02 fittings)
Piping (C02 fittings)
Tank Insulated (C02) Tank (C02) Valve body (C02/ Halon) Valve body (C02/ Halon) Valve body (C02/ Halon) Intended Function(s)
Direct Flow Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary AGING MANAGEMENT REVIEW Aging Effect Aging Material Environment Requiring Management Manaaement ProQram Stainless Air-indoor None* Fire Protection steel uncontrolled Air-indoor Loss of External Steel Surfaces uncontrolled Material MonitorinQ Loss of External Steel Air -outdoor Surfaces Material MonitorinQ Steel Gas None None Steel Air-indoor Loss of Internal uncontrolled Material Surfaces Air -indoor Loss of External Steel Surfaces uncontrolled Material Monitoring Loss of External Steel Air -outdoor Surfaces Material Monitoring Steel Gas None None Steel Air -indoor Loss of Internal uncontrolled Material Surfaces Loss of Steel Air -outdoor Fire Protection Material Steel Gas None None Loss of External Steel Air -outdoor Material Surfaces MonitorinQ Steel Gas None None Air-indoor Loss of Internal Steel uncontrolled Material Surfaces *Note: Inspection frequency was changed to every 6 months to satisfy UFSAR, Table 16-1, "Unit 1 License Renewal Commitments," Item No. 7, commitment to enhance the Fire Protection Program.
Attachment 4 L-17-029 Page 3 of 3 In summary, FENOC conducted a review of BVPS, Unit No. 1 plant changes implemented between May 24, 2015 and October 25, 2016 for 10 CFR 54.37(b) applicability.
The fire suppression system in the ERFS, including the ERFDGB, was determined to meet the criteria for newly identified components as clarified by RIS 2007-16. The fire suppression system in the ERFS, including the ERFDGB was not previously credited for aging management at BVPS. This condition has been entered into the FENOC corrective action program to ensure the newly identified components are included in appropriate aging management programs.
The carbon dioxide (C02) fire suppression system in the ERFS, including the ERFDGB, supports both units, but the system components are assigned Unit 1 functional location designations.
The effects of aging will be managed for the newly identified components such that the intended functions will be effectively maintained during the period of extended operation by the Aging Management Programs described in Unit 1 UFSAR Sections 16.1.6, "Bolting Integrity Program," 16.1.15, "External Surfaces Monitoring Program," 16.1.16, "Fire Protection Program," 16.1.39, "Structures Monitoring Program," and 16.1.21, "Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program," as applicable.
Therefore, no UFSAR changes were determined to be necessary.