ML14339A408

Beaver Valley, Unit 2, Submittal of the Updated Final Safety Analysis Report, Revision 21

ML14339A408
Person / Time
Site:	Beaver Valley
Issue date:	11/24/2014
From:	Larson E A FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML14339A419	List: L-14-360, Firstenergy Nuclear Operation Company, Quality Assurance Program Manual, Revision 19 ML14339A408 ML14339A410 ML14339A411 ML14339A412 ML14339A413 ML14339A414 ML14339A415 ML14339A416 ML14339A417 ML14339A418 ML14339A420 ML14339A429 ML14339A430 ML14339A431 ML14339A433 ML14339A434 ML14339A435 ML14339A437 ML14339A438 ML14339A439 ML14339A440 ML14339A451 ML14339A452 ML14339A453 ML14339A454
References
L-14-360
Download: ML14339A408 (4)

Text

Beaver Valley Power StationP.O. Box 4FE O Shippingport, PA 15077FirstEnergy Nuclear Operating CompanyEric A. Larson. 724-682-5234Site Vice President Fax: 724-643-8069November 24, 2014L-14-360 10 CFR 50.71(e)10 CFR 50.54(a)10 CFR 54.37(b)ATTN: Document Control DeskU.S. Nuclear Regulatory CommissionWashington, DC 20555-001

SUBJECT:

Beaver Valley Power Station, Unit No. 2Docket No. 50-412, License No. NPF-73Submittal of the Updated Final Safety Analysis Report, Revision 21In accordance with the requirements of 10 CFR 50.71(e), the FirstEnergy NuclearOperating Company (FENOC) is hereby submitting to the Nuclear RegulatoryCommission (NRC) the Beaver Valley Power Station (BVPS), Unit No. 2, Updated FinalSafety Analysis Report (UFSAR) Revision 21 in CD-ROM format. This submittalreflects facility and procedure changes implemented between November 2, 2012 (theend of Refueling Outage 16), and May 23, 2014 (the end of Refueling Outage 17), alongwith several changes implemented after Refueling Outage 17.In accordance with NRC guidance for electronic submissions, Attachment 1 provides alisting of the document components that comprise the enclosed CD-ROM. In addition tothe UFSAR, the CD-ROM includes the BVPS, Unit No. 2 Licensing RequirementsManual, Revision 81, and the Technical Specification Bases, Revision 27. TheTechnical Specification Bases are submitted in accordance with TechnicalSpecification 5.5.10.d, "Technical Specifications (TS) Bases Control Program."In accordance with 10 CFR 50.54(a), FENOC is hereby submitting a copy of the currentrevision of the FENOC Quality Assurance Program Manual (QAPM). The QAPM,Revision 19, is included in the enclosed CD-ROM.Attachment 2 includes a summary of information removed from the BVPS, Unit No. 2UFSAR in accordance with Appendix A to Nuclear Energy Institute (NEI) 98-03,"Guidelines for Updating Final Safety Analysis Reports," Revision 1.

Beaver Valley Power Station, Unit No. 2L-14-360Page 2FENOC conducted a review of BVPS, Unit No. 2 plant changes for 10 CFR 54.37(b)applicability. No components were determined to meet the criteria for newly identifiedcomponents as clarified by Regulatory Issue Summary (RIS) 2007-16, Revision 1,"Implementation of the Requirements of 10 CFR 54.34(b) for Holders of RenewedLicenses."There are no regulatory commitment changes to be submitted in accordance with NEI99-04, "Guidelines for Managing NRC Commitment Changes."This certifies, to the best of my judgment and belief, that Revision 21 of the BVPS, UnitNo. 2 UFSAR accurately presents changes made since the previous submittal that arenecessary to reflect information and analysis submitted to the Commission or pursuantto Commission requirements.This letter contains no new regulatory commitments. If you have any questionsregarding this report, please contact Mr. Thomas A. Lentz, Manager -Fleet Licensing,at 330-315-6810.Sincerely,Eric A. LarsonAttachments:1. Document Components on CD-ROM2. Information Removed from the BVPS, Unit No. 2 UFSAR

Enclosures:

Beaver Valley Power Station, Unit No. 2 UFSAR, Licensing Requirements Manual,Technical Specification Bases, and QAPM (on CD-ROM)cc: NRC Region I AdministratorNRC Resident InspectorNRC Project ManagerDirector BRP/DEP (without Enclosures)Site BRP/DEP Representative (without Enclosures)

.. I I IAttachment 1L-14-360Document Components on CD-ROMPage 1 of 1File NameSize001 UFSAR List of Effective Pages Rev 21.pdf002 UFSAR Section l.pdf003 UFSAR Section 2 Part I of 2.pdf004 UFSAR Section 2 Part 2 of 2.pdf005 UFSAR Section 3 Part 1 of 2.pdf006 UFSAR Section 3 Part 2 of 2.pdf007 UFSAR Section 4.pdf008 UFSAR Section 5.pdf009 UFSAR Section 6.pdf010 UFSAR Section 7.pdf011 UFSAR Section 8.pdf012 UFSAR Section 9.pdf013 UFSAR Section 10.pdf014 UFSAR Section 11 .pdf015 UFSAR Section 12.pdf016 UFSAR Section 13.pdf017 UFSAR Section 14.pdf018 UFSAR Section 15.pdf019 UFSAR Section 16.pdf020 UFSAR Section 17.pdf021 UFSAR Section 18.pdf022 UFSAR Section 19.pdf023 BVPS-2 LRM Rev 81.pdf024 BVPS TS Bases Rev 27.pdf025 FENOC QAPM Rev 19.pdf158KB917KB5,584KB26,726KB32,207KB13,249KB2,376KB1,448KB4,056KB8,899KB782KB2,874KB1,596KB929KB10,717KB137KB382KB2,197KB35KB56KB26KB369KB10,675KB45,711KB2,632KB L-14-360Information Removed from BVPS, Unit No. 2 UFSARPage 1 of 1In accordance with Nuclear Energy Institute (NEI) 98-03, Revision 1, "Guidelines forUpdating Final Safety Analysis Reports," licensees periodically report a brief descriptionof information removed from the Updated Final Safety Analysis Report (UFSAR) andthe basis for its removal. The following provides a summary of the information removedfrom the UFSAR and the basis for removal.1. Removed the capacity value and associated descriptive text from Section 10.4.9.2regarding the auxiliary feedwater system (AFW) associated with a loss of mainfeedwater design basis accident scenario. The statement that the AFW is capable ofsupplying 400 gallons per minute (gpm) distributed equally to three steamgenerators within 1 minute following a loss of main feedwater was removed. Theability of the plant and AFW system to mitigate the design basis accident scenario ofa loss of main feedwater, as described In UFSAR Section 15.2.7, is unaffected. Theinformation being removed is not a minimum required design basis value, nor is it adesign value for the system components. This is information that, if changed duringthe life of the plant, would have no impact on the ability of the plant structures,systems, and components described in the UFSAR to perform their design basisfunctions.