ML14339A408

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 Station P.O. Box 4 FE O Shippingport, PA 15077 FirstEnergy Nuclear Operating Company Eric A. Larson. 724-682-5234 Site Vice President Fax: 724-643-8069 November 24, 2014 L-14-360 10 CFR 50.71(e)10 CFR 50.54(a)10 CFR 54.37(b)ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-001

SUBJECT:

Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Submittal of the Updated Final Safety Analysis Report, Revision 21 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. 2, Updated Final Safety Analysis Report (UFSAR) Revision 21 in CD-ROM format. This submittal reflects facility and procedure changes implemented between November 2, 2012 (the end of Refueling Outage 16), and May 23, 2014 (the end of Refueling Outage 17), along with several changes implemented after Refueling Outage 17.In accordance with NRC guidance for electronic submissions, Attachment 1 provides a listing of the document components that comprise the enclosed CD-ROM. In addition to the UFSAR, the CD-ROM includes the BVPS, Unit No. 2 Licensing Requirements Manual, Revision 81, and the Technical Specification Bases, Revision 27. The Technical Specification Bases are submitted in accordance with Technical Specification 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 current revision 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. 2 UFSAR 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. 2 L-14-360 Page 2 FENOC 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 identified components as clarified by Regulatory Issue Summary (RIS) 2007-16, Revision 1,"Implementation of the Requirements of 10 CFR 54.34(b) for Holders of Renewed Licenses." There are no regulatory commitment changes to be submitted in accordance with NEI 99-04, "Guidelines for Managing NRC Commitment Changes." This certifies, to the best of my judgment and belief, that Revision 21 of the BVPS, Unit No. 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 330-315-6810.

Sincerely, Eric A. Larson Attachments:

1. Document Components on CD-ROM 2. 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 Administrator NRC Resident Inspector NRC Project Manager Director BRP/DEP (without Enclosures)

Site BRP/DEP Representative (without Enclosures)

.. I I I Attachment 1 L-14-360 Document Components on CD-ROM Page 1 of 1 File Name Size 001 UFSAR List of Effective Pages Rev 21.pdf 002 UFSAR Section l.pdf 003 UFSAR Section 2 Part I of 2.pdf 004 UFSAR Section 2 Part 2 of 2.pdf 005 UFSAR Section 3 Part 1 of 2.pdf 006 UFSAR Section 3 Part 2 of 2.pdf 007 UFSAR Section 4.pdf 008 UFSAR Section 5.pdf 009 UFSAR Section 6.pdf 010 UFSAR Section 7.pdf 011 UFSAR Section 8.pdf 012 UFSAR Section 9.pdf 013 UFSAR Section 10.pdf 014 UFSAR Section 11 .pdf 015 UFSAR Section 12.pdf 016 UFSAR Section 13.pdf 017 UFSAR Section 14.pdf 018 UFSAR Section 15.pdf 019 UFSAR Section 16.pdf 020 UFSAR Section 17.pdf 021 UFSAR Section 18.pdf 022 UFSAR Section 19.pdf 023 BVPS-2 LRM Rev 81.pdf 024 BVPS TS Bases Rev 27.pdf 025 FENOC QAPM Rev 19.pdf 158KB 917KB 5,584KB 26,726KB 32,207KB 13,249KB 2,376KB 1,448KB 4,056KB 8,899KB 782KB 2,874KB 1,596KB 929KB 10,717KB 137KB 382KB 2,197KB 35KB 56KB 26KB 369KB 10,675KB 45,711KB 2,632KB Attachment 2 L-14-360 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 the capacity value and associated descriptive text from Section 10.4.9.2 regarding the auxiliary feedwater system (AFW) associated with a loss of main feedwater design basis accident scenario.

The statement that the AFW is capable of supplying 400 gallons per minute (gpm) distributed equally to three steam generators within 1 minute following a loss of main feedwater was removed. The ability of the plant and AFW system to mitigate the design basis accident scenario of a loss of main feedwater, as described In UFSAR Section 15.2.7, is unaffected.

The information being removed is not a minimum required design basis value, nor is it a design value for the system components.

This is information that, if changed during the 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 basis functions.