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{{Adams
#REDIRECT [[L-17-262, Revision 23 to Updated Safety Analysis Report]]
| number = ML17334A069
| issue date = 11/20/2017
| title = Beaver Valley Power Station, Unit 2, Revision 23 to Updated Safety Analysis Report
| author name = Bologna R D
| author affiliation = FirstEnergy Nuclear Operating Co
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000412
| license number = NPF-073
| contact person =
| case reference number = L-17-262
| package number = ML17334A067
| document type = Letter
| page count = 9
}}
 
=Text=
{{#Wiki_filter:FENOCŽ F/rsfEn~rgy M.g:1~8' Operatiog ¢.anJpany Bec1v~r Valley PQWe,r station P.O. Box4 Shippingport, PA 150n Richal'.'d D. Bologna Site Vice President 724-662-0234 Fax: 724-643-8069 November 20, 2017 .L-17-262 ATTN: Document Control Desk: U. S. Nuclear Regulatory Commission *wash_ington, DC 20555-0001.
 
==SUBJECT:==
Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF73 Submittal of' the Updated Final Safety Analysis Report, Revision 23 10 CFR 50. 71 (e) 10 CFR 50.54(a) 10 GfR 54,37(b) In accordance with the requirements of 10 C~R 5Ct71(e), the FirstEne:rgy Nuclear Operating Company (FENOC) is hereby submitting to the Nuclear Regulatory Commission (NRC) the Beaver Valley Power Station, Unit No .. 2 (BVPS-2), Updated Final Safety Analysis Report {UFSAR) Revision 23 in CD-ROM format. This *submittal reflects. facility and procedure_ ch~nges im,pleroented betWe.en October 30, 2015 (the end of Refueling Outage -1 aJ, and May 21, 2017 (the end of Refueling Outage: 18)! :along with several changes implemented after Refueling Outage 1R In accord;ance with 10 CFR 50.4(b)(6), the BVPS-2, UFSAR, Revision 23, is being submitted electronically on a total replacement basis. As .reqqired by NRC guidance for electroni.c submissions to the Commission, Attachments 1 and 2 provide a listing of the document components that make up the two enclosed CD-ROM$. The first enclosed CD .. ROM include~ th.e BVPS-2 UFSAR and the following documents.
* BVPS-2, Licensing Requirements Manual (LRM), Revision 90
* Technical Specific_ation (TS) Bases, Revision 34, submitted to satisfy TS 5.5. 10.d, which requires submittal of TS Bases* changes implemented without prior NRC approval
* FENOC Quality Assurance Program Manual (QAPM), Revfsion 21, submitted in accordance with 10 CFR 50.54(a) The second enclosed CD-ROM includes the BVPS-2 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. AD53 jttt.f S jf D b (,, . [VI~. J Beaver Valley Power Station, Unit No. 2 L-17-262 Page 2 Attachment 3 includes a summary of information removed from the BVPS-2 UFSAR in accordance with Appendix A to Nuclear Energy Institute (NEI) 98-03, Revision 1, "Guidelines for Updating Final Safety Analysis Reports," as endorsed by Regulatory Guide 1.181, "Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50J1(e)." FENOC conducted a review of BVPS-2 plant changes implemented between October 30, 2015 and May 21, 2017 for 10 CFR 54.37(b) applicability. No components 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 54.37(b) for Holders of Renewed Licenses." However, corrections to the previous review provided with BVPS'-2 UFSAR, Revision 22 (ADAMS Accession No. ML 16134A150), were identified. A corrected copy of the review is provided in Attachment 4 of this letter with changes indicated by a revision bar. There are no regulatory commitment changes to be submitted in accordance with Nuclear Energy Institute, NEI 99-04, "Guidelines for Managing NRC Commitment Changes," Revision 0, as endorsed by RIS 2000-17, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff." This certifies, to the best of my judgment and belief, that Revision 23 of the BVPS-2 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 330-315-681 O. Sincerely, /0 Richard D. Bologna 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 BVPS, Unit No. 2 UFSAR 4. Review of Plant Changes for 10 CFR 54.37(b) Applicability Beaver Valley Power Station, Unit No. 2 L-17-262 Page 3
 
==Enclosures:==
A. Beaver Valley Power Station, Unit No. 2 UFSAR, Licensing Requirements Manual, Technical Specification Bases, and QAPM (on CD-ROM 1) B. Beaver Valley Power Station, Unit No. 4 UFSAR With Information Identified Per RIS 2015-17 Removed (on CD-ROM 2) cc: NRC Region I Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP Site BRP/DEP Representative    L-17-262 Information Removed from BVPS, Unit No. 2 UFSAR Page 1 of 1 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 9.1.4.2.3.8. The reactor vessel stud tensioners are tools used to disassemble and reassemble the reactor vessel and head, and its design has no design bases or safety analyses. Parameters used to ensure the structures, systems, and components (SSCs) are left in the proper condition remain valid and unchanged, regardless of tensioner style. The removed information has no impact on the ability of plant SSCs described in the UFSAR to perform their design basis functions and has no impact on plant operations. In addition, per Regulatory Guide 1.70 Revision 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.
File Name Attachment 1 L-17-262 List of Document Components on CD-ROM 1 Page 1 of 1 001 UFSAR List of Effective Pages Rev 23.pdf.. ......................... 118 KB 002 UFSAR Section 1.pdf ........................................................... 1,055 KB 003 UFSAR Section 2 Part 1 of 2.pdf .......................................... 12,639 KB 004 UFSAR Section 2 Part 2 of 2.pdf .......................................... 27,119 KB 005 UFSAR Section 3 Part 1 of 2.pdf.. ........................................ 25,517 KB 006 UFSAR Section 3 Part 2 of 2.pdf .......................................... 13,519 KB 007 UFSAR Section 4.pdf ........................................................... 3,503 KB 008 U FSAR Section 5. pdf .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. . 1 , 638 KB 009 UFSAR Section 6.pdf ........................................................... 4,315 KB 010 UFSAR Section 7.pdf ........................................................... 8,723 KB 011 UFSAR Section 8.pdf ........................................................... 1,029 KB 012 UFSAR Section 9.pdf ........................................................... 3, 159 KB 013 UFSAR Section 1 O.pdf...... .............................. .... .. .. .. .. .. .. .... . 1,822 KB 014 UFSAR Section 11.pdf ......................................................... 1,113 KB 015 UFSAR Section 12.pdf .. .. .. .. .. .... .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .... . 13,718 KB 016 UFSAR Section 13.pdf .. .. .. .. .. ...................................... ...... .. . 523 KB 017 U FSAR Section 14. pdf .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. . 424 KB 018 UFSAR Section 15.pdf ......................................................... 2,407 KB 019 UFSAR Section 16.pdf .. .. .. .. .. .. .. .. .. .. .. .. ...... .... .. .... .. .. .. .. .... .. .. . 35 KB 020 UFSAR Section 17.pdf .. .. .. .. .. .. .. .. .. .. .. .. ...... .. ................ ...... .. . 56 KB 021 UFSAR Section 18.pdf ......................................................... 26 KB 022 UFSAR Section 19. pdf .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. .. . 412 KB 023 BVPS-2 LRM Rev 90. pdf...................................................... 1 , 251 KB 024 BVPS TS Bases Rev 34. pdf................................................. 2,452 KB 025 FENOC QAPM Rev 21.pdf.. ................................................. 3,018 KB File Name Attachment 2 L-17-262 List of Document Components on CD-ROM 2 (Information Identified Per RIS 2015-17 Removed) Page 1 of 1 001 UFSAR List of Effective Pages Rev 23.pdf.. ......................... 118 KB 002 UFSAR Section 1.pdf ........................................................... 967 KB 003 UFSAR Section 2 Part 1 of 2.pdf .......................................... 11,551 KB 004 UFSAR Section 2 Part 2 of 2.pdf .......................................... 27,084 KB 005 UFSAR Section 3 Part 1 of 2.pdf .......................................... 25,516 KB 006 UFSAR Section 3 Part 2 of 2.pdf .......................................... 3,931 KB 007 UFSAR Section 4.pdf ........................................................... 3,504 KB 008 UFSAR Section 5.pdf ........................................................... 1,638 KB 009 UFSAR Section 6.pdf ........................................................... 4,269 KB 010 UFSAR Section 7.pdf ........................................................... 8,689 KB 011 UFSAR Section 8.pdf ........................................................... 1,030 KB 012 UFSAR Section 9.pdf ........................................................... 2,824 KB 013 UFSAR Section 10.pdf ......................................................... 1,823 KB 014 UFSAR Section 11.pdf . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . 1, 112 KB 015 UFSAR Section 12.pdf ......................................................... 9,571 KB 016 UFSAR Section 13.pdf ......................................................... 523 KB 017 UFSAR Section 14.pdf ......................................................... 424 KB 018 UFSAR Section 15.pdf . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . .. . . . . . . 2,407 KB 019 UFSAR Section 16.pdf ......................................................... 35 KB 020 UFSAR Section 17.pdf ......................................................... 56 KB 021 UFSAR Section 18.pdf ......................................................... 26 KB 022 UFSAR Section 19.pdf ....................................... , ................. 413 KB 023 BVPS-2 LRM Rev 90.pdf ...................................................... 1,251 KB 024 BVPS TS Bases Rev 34.pdf ................................................. 2,452 KB 025 FENOC QAPM Rev 21.pdf ................................................... 3,018 KB    L-17-262 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 NRC Regulatory Information Summary (RIS) 2007-16, Revision 1, "Implementation of the Requirements of 10 CFR 54.37(b) for Holders of Renewed Licenses." A recently approved Updated Final Safety Analysis Report (UFSAR) change now credits the fire suppression system in the ERFS, including the ERFDGB, as being within the scope of 10 CFR 50.48, "Fire Protection." Therefore, this system meets the license renewal scoping criteria of 10 CFR 54.4(a)(3) as described in NUREG-1800, Revision 2, "Standard Review Plan for Review of License Renewal Applications for Nuclear Power Plants (December 2010)," 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 Section 19 of the Updated Final Safety Analysis Report 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 Type Function(s) Material Environment Requiring Management Management Program Bolting Pressure Steel Air-indoor Loss of Bolting Integrity Boundary uncontrolled Material Bolting Pressure Steel Air -outdoor Loss of Bolting Integrity Boundary Material Nozzle Direct Flow Stainless Air-indoor None* Fire Protection (CO2) steel uncontrolled Pressure Air-indoor Loss of External Piping (CO2) Boundary Steel uncontrolled Material Surfaces Monitorinq L Attachment 4 L-17-262 Page 2 of 3 Component Type Piping (CO2) Piping (CO2) Piping (CO2) Piping (CO2 fittings) Piping (CO2 fittings) Piping (CO2 fittings) Piping (CO2 fittings) Tank Insulated (CO2) Tank (CO2) Valve body (CO2/ Halon) Valve body (CO2/ Halon) Valve body (CO2/ Halon) Intended Function(s) Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Pressure Boundary Material Environment Steel Air -outdoor Steel Gas Steel Air-indoor uncontrolled Air-indoor Steel uncontrolled Steel Air -outdoor Steel Gas Steel Air-indoor uncontrolled Steel Air -Outdoor Steel Gas Steel Air -outdoor Steel Gas Air-indoor Steel uncontrolled Aging Effect Aging Requiring Management Management Program Loss of External Material Surfaces Monitoring None None Loss of Internal Surfaces Material Loss of External Surfaces Material Monitoring Loss of External Surfaces Material Monitoring None None Loss of Internal Surfaces Material Loss of Fire Protection Material None None Loss of External Material Surfaces Monitoring None None Loss of Material Internal Surfaces *Note: Inspection frequency will be changed to every 6 months, to satisfy UFSAR, Table 19-1, "Unit 2 License Renewal Commitments," Item No. 8, commitment to enhance the Fire Protection Program. L-17-262 Page 3 of 3 In summary, FENOC conducted a review of BVPS, Unit No. 2 plant changes implemented between May 23, 2014 and October 30, 2015 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. It has been determined that 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 UFSAR Sections 19.1.6, "Bolting Integrity Program," 19.1.15, "External Surfaces Monitoring Program," 19.1.16, "Fire Protection Program," 19.1.22, "Inspection of Internal Surfaces Program," and 19.1.39, "Structures Monitoring Program," as applicable. Therefore, no UFSAR changes were determined to be necessary. 
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