ML091980362

Submittal of Revision 17 to the Updated Final Safety Analysis Report

ML091980362
Person / Time
Site:	Beaver Valley
Issue date:	11/20/2008
From:	Sena P P FirstEnergy Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
Shared Package
ML091980364	List: L-08-231, Updated Final Safety Analysis Report, Rev. 17, List of Effective Pages ML091980362
References
L-08-231
Download: ML091980362 (5)

Text

__ 1 FENOC Peter P. Sena III 724-682-5234 Site Vice President FAX: 724-643-8069 November 20, 2008 L-08-231 10 CFR 50.71(e)ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Beaver Valley Power Station, Unit No. 2 Docket No. 50-412, License No. NPF-73 Submittal of Revision 17 to the Updated Final Safety Analysis Report The FirstEnergy Nuclear Operating Company (FENOC) hereby submits, pursuant to the requirements of 10 CFR 50.71(e), Revision 17 to the Beaver Valley Power Station (BVPS), Unit No. 2 Updated Final Safety Analysis Report (UFSAR) in CD-ROM format.This submittal reflects facility and procedure changes implemented between November 12, 2006 (the end of Refueling Outage 12) and May 22, 2008 (the end of Refueling Outage 13), along with several changes implemented after Refueling Outage 13.As requested by Nuclear Regulatory Commission (NRC) guidance for electronic submissions to the Commission, Attachment 1 provides a listing of document components that make up the enclosed CD-ROM. In addition to the UFSAR, the enclosure includes the BVPS Unit No. 2 Licensing Requirements Manual, Revision 62, incorporated by reference in the UFSAR, and the Technical Specification Bases, Revision 9. The Technical Specification Bases are submitted to satisfy Technical Specification 5.5.10.d, which requires submittal of Bases changes implemented without prior NRC approval.The enclosure also contains a copy of Revision 9 to the FENOC Quality Assurance Program Manual (QAPM), submitted pursuant to 10 CFR 50.54(a)(3).

Revision 9 is the current version of the FENOC QAPM, and includes changes since the previous revision of the FENOC QAPM. Revision 8 was most recently submitted along with the Beaver Valley Power Station Unit No. 2 (Docket No. 50-412) UFSAR submittal, letter number L-07-064, dated May 14, 2007.Attachment 2 includes a summary of information removed from the UFSAR in accordance with Appendix A to Nuclear Energy Institute (NEI) 98-03, "Guidelines for Updating Final Safety Analysis Reports," Revision 1, as endorsed by Regulatory Guide 1.181, "Content of the Updated Final Safety Analysis Report in Accordance with 10 CFR 50.71(e)."

Beaver Valley Power Station, Unit No. 1.L-08-231 Page 2 Attachment 3 contains a summary of regulatory commitment changes, in accordance with NEI 99-04, "Guidelines for Managing NRC Commitment Changes," Revision 0, as endorsed by NRC Regulatory Issue Summary 2000-17, "Managing Regulatory Commitments Made by Power Reactor Licensees to the NRC Staff," dated September 21, 2000.This certifies, to the best of our judgment and belief, that Revision 17 of the UFSAR accurately presents changes made since the previous submittal which are necessary to reflect information and analysis submitted to the Commission or prepared pursuant to Commission requirements.

There are no regulatory commitments contained in this letter. If there are any questions or if additional information is required, please contact Mr. Thomas A. Lentz, Manager -FENOC Fleet Licensing, at (330) 761-6071.Sincerely, Peter P. Sena III Attachments:

1. Document Components on CD-ROM 2. Information Removed From the Updated Final Safety Analysis Report 3. Commitment Change Summary Report

Enclosure:

Beaver Valley Power Station Unit No. 2 UFSAR, Technical Specification Bases, Licensing Requirements Manual and QAPM (on CD-ROM disc)c: Mr. S. J. Collins, NRC Region I Administrator Mr. D. L. Werkheiser, NRC Senior Resident Inspector Ms. N. S. Morgan, NRR Project Manager Mr. D. J. Allard, Director BRP/DEP Mr. L. E. Ryan (BRP/DEP)

Attachment 1 L-08-231 Document Components on CD-ROM Page 1 of 1 File Name Size 001 List of Effective Pages, Rev. 17.pdf 97K 002 Section 1 .pdf 1,906K 003 Chapter 2.1 -2.4.pdf 16,264K 004 Chapter 2.5.pdf 38,989K 005 Chapter 3.pdf 34,116K 006 Chapter 4.pdf 3,285K 007 Chapter 5.pdf 2,623K 008 Chapter 6.pdf 6,828K 009 Chapter 7.pdf 13,284K 010 Chapter 8.pdf 1,859K 011 Chapter 9.pdf 4,422K 012 Chapter 10.pdf 3,231K 013 Chapter 11.pdf 1,927K 014 Chapter 12.pdf 23,129K 015 Chapter 13.pdf 1,133K 016 Chapter 14.pdf 1,337K 017 Chapter 15.pdf 3,762K 018 Chapter 16.pdf 970K 019 Chapter 17.pdf 968K 020 Chapter 18.pdf 937K BVPS Bases.pdf 2,991K BVPS-2 Licensing Requirements Manual, 2,395K Rev. 62.pdf FENOC QA Program Manual, Rev. 9.pdf 2,865K Attachment 2 L-08-231 Information Removed From the Updated Final Safety Analysis Report Page 1 of 1 In accordance with Nuclear Energy Institute (NEI) 98-03, Revision 1, "Guidelines for Updating Final Safety Analysis Reports," licensees should provide a brief description of unnecessary information removed from the Updated Final Safety Analysis Report (UFSAR) and the basis for its removal. The following provides-a listing of the information removed from the UFSAR in accordance with NEI 98-03 and the basis for removal.Section 9.1.4.2.3 was revised to remove a sentence describing the tensioning of Reactor Vessel Stud Tensioners on the basis that it was excessively detailed information.

Stud tensioning is controlled by approved refueling procedures.

Sections 9.3.1.1.5 and 9.3.2.1.5 were revised to remove descriptions of the local indications available for the station air compressors as this information would have no impact on the ability of plant systems, structures and components described in the UFSAR to perform their design basis function(s).

Table 9.5-10 was revised to remove the low pressure setpoint for the emergency diesel generator air starting system on the basis that it was excessively detailed information.

This setpoint is described in the Beaver Valley Power Station Unit 2 Improved Technical Specifications.

Section 9.5A.1.3.47 was revised to remove a statement concerning fire loading in the cooling tower pump house. The sentence was not important to the description of the facility or presentation of its safety analysis and design bases.Tables 10.2-1 and 10.2-4 were revised to remove the turbine overspeed trip setpoint and the specific locations of tests on partial integral rotors. Figure 10.2-13, which displays the locations removed from Table 10.2-4, was also removed. These were removed on the basis that it was excessively detailed information.

Section 12.3.2.1 was reworded to remove design details of the supplementary neutron shielding on the Reactor Vessel Hot and Cold Leg nozzles. The thickness and shape of the shielding was excessively detailed information.

Attachment 3 L-08-231 Commitment Change Summary Report Page 1 of 1 In accordance with NEI 99-04, "Guidelines for Managing NRC Commitment Changes," Revision 0, the following provides a summary of commitments changed, in lieu of filing individual notifications, since the last report.The following commitment was extended and then closed because Beaver Valley Power Station does not use the Delta suit and has no immediate plans for doing so.The Delta Protection Supplied-Air Containment Mururoa V4 MTH 2 Suits will be integrated into the FENOC respiratory program using the manufacturer's recommendations described in the Mururoa V4 Fully Enclosed Suit-General Description. (dated June 9, 2001) and the MTH 2 Instruction for Use (dated December 2000).