ML17117A435

Beaver Valley Power Station, Unit 1, Submittal of Revision 30 to Updated Final Safety Analysis Report

ML17117A435
Person / Time
Site:	Beaver Valley
Issue date:	04/21/2017
From:	Richey M L FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML17117A433	List: L-17-029, Redacted - Beaver Valley Power Station, Unit 1, Revision 30 to Updated Final Safety Analysis Report, Section 8, Electrical Systems ML17117A435 ML17117A438 ML17117A439 ML17117A441 ML17117A442 ML17117A443 ML17117A444 ML17117A445 ML17117A447 ML17117A449 ML17117A450 ML17117A451 ML17117A452 ML17117A453 ML17117A454 ML17117A455 ML17117A456 ML17117A457 ML17117A458 ML17117A459 ML17244A912
References
L-17-029
Download: ML17117A435 (9)

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) 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

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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 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. 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 .. 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. 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.