BVY 08-090, License Renewal Application Annual Update

License Renewal Application Annual Update

ML090050028
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
Issue date:	12/31/2008
From:	Michael Colomb Entergy Nuclear Operations, Entergy Nuclear Vermont Yankee
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 08-090
Download: ML090050028 (5)

Text

Entergy Nuclear Operations, Inc.

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December 31, 2008 BVY 08-090 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

Reference:

1. Letter, Entergy to USNRC, "Vermont Yankee Nuclear Power Station, License No. DPR-28, License Renewal Application," BVY 06-009, dated January 25, 2006.

Subject:

Vermont Yankee Nuclear Power Station License No. DPR-28 (Docket No. 50-271)

License Renewal Application Annual Update

Dear Sir or Madam,

On January 25, 2006, Entergy Nuclear Operations, Inc. and Entergy Nuclear Vermont Yankee, LLC (Entergy) submitted the License Renewal Application (LRA) for the Vermont Yankee Nuclear Power Station (VYNPS) as indicated by Reference 1.

During the NRC review of the VYNPS LRA, Entergy is required by 10CFR54.21(b) to report changes to the current licensing basis (CLB) that materially affect the content of the VYNPS LRA, including the Safety Analysis Report (SAR) supplement. This information is required to be submitted annually and at least three months prior to the scheduled completion of the NRC review. In accordance with the requirements of 10 CFR 54.21(b), Entergy has completed a review and LRA impacts are discussed in of this letter.

There are no new regulatory commitments being made in this letter.

Should you have any questions or require additional information concerning this submittal, please contact Mr. David J. Mannai at (802) 451-3304.

I declare under penalty of perjury, that the foregoing is true and accurate.

Executed on December 31, 2008 Sincerely, MichaQl . Co* b Site Vice President Vermont Yankee Nuclear Power Station Attachments (1) cc listing (next page)

A/lil

BVY 08-090 / Page 2 of 2 cc: Mr. James Dyer, Director U.S. Nuclear Regulatory Commission Office 05E7 Washington, DC 20555-00001 Mr. Samuel J. Collins, Regional Administrator U.S. Nuclear Regulatory Commission, Region 1 475 Allendale Road King of Prussia, PA 19406-1415 Mr. Jack Strosnider, Director U.S. Nuclear Regulatory Commission Office T8A23 Washington, DC 20555-00001 Mr. Jonathan Rowley, Senior Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike MS-O-1 1F1 Rockville, MD 20853 Mr. Mike Modes USNRC RI 475 Allendale Rd, King of Prussia, PA 19406 Mr. James S. Kim, Project Manager U.S. Nuclear Regulatory Commission Mail Stop 0 8 C2A Washington, DC 20555 USNRC Resident Inspector Entergy Nuclear Vermont Yankee, LLC P.O. Box 157 (for mail delivery)

Vernon, Vermont 05354 Mr. David O'Brien, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05620-2601 Diane Curran, Esq.

Harmon, Curran, Spielberg & Eisenberg, LLP 1726 M Street, N.W., Suite 600 Washington, D.C. 20036

BVY 08-090 / Attachment 1, Page 1 of 2 Attachment 1 Vermont Yankee Nuclear Power Station Licensing Renewal Application Annual Update Information The review performed as part of the annual update identified the following impacts to the LRA:

1. The Condensate Demineralizer System description was revised in the UFSAR due to extended power uprate. The aging management review results provided in LRA Table 3.3.2-13-4, Condensate Demineralizer System - Nonsafety-Related Components affecting Safety-Related Systems were not affected. To clarify the condensate demineralizer system description, LRA Section 2.3.3.13.2 is revised as follows. (strikeout text deleted, underlined text added)

Condensate Demineralizer The purpose of the CD system is to maintain the required purity of feedwater supplied to the reactor. The system functions to minimize corrosion product input to the nuclear system so as not to affect fuel performance, accessibility of nuclear system components, or the capacity required of the reactor water cleanup system. The CD system protects the nuclear system against the entry of foreign materials such as could occur due to condenser leaks.

The system uses finely ground, mixed ion-exchange resins deposited upon the tubular elements of pressure precoat type filters (the filter-demineralizer units).

The condensate demineralizers consist of five filter-demineralizer units

• (n*c~ln*g~an i.nctalld sparc) operating in parallel. All are normally operated but ar. sized .uch that four uni. can suppo. t oporati. . The system and auxiliaries include a precoat system, a body feed system, a backwash system, holding pumps and effluent strainers for each unit, and associated piping and valves.

2. Carbon steel piping and valves supplying service water to nonsafety-related refueling floor chillers were replaced with copper alloy components. The nonsafety-related system components were evaluated in LRA Table 3.3.2-13-42, Service Water System - Nonsafety-Related Components Affecting Safety-Related Systems. New component type-material-environment combinations were added to the Nonsafety-Related portion of the System. The identical component type-material-environment-program combinations are in LRA Table 3.3.2-2, Service Water. To accurately account for the configuration change, the following line items are added to LRA Table 3.3.2-13-42, Service Water System - Nonsafety-Related Components Affecting Safety-Related Systems.

BVY 08-090 / Attachment 1, Page 2 of 2 Piping Pressure Copper Condensation Loss of System VII.F1- 3.3.1- E boundary alloy (ext) material Walkdown 16 25

<15% Zn (A-46)

Piping Pressure Copper Raw water Loss of Service VI1.C1-9 3.3.1- B boundary alloy (int) material Water (A-44) 81

<15% Zn Integrity Valve Pressure Copper Condensation Loss of System VII.F1- 3.3.1- E body boundary alloy (ext) material Walkdown 16 25

>15% Zn (A-46)

Valve Pressure Copper Raw water Loss of Service VI1.C1-9 3.3.1- B body boundary alloy (int) material Water (A-44). 81

>15% Zn Integrity Valve Pressure Copper Raw water Loss of Selective VII.C1- 3.3.1- A body boundary alloy (int) material Leaching 10 84

>15% Zn (A-47)

. gy Nuclear Northeast E1nJtJ~erg Vermont Yankee P.O. Box 157 Governor Hunt Road Vernon, VT 05354--

U.S. Nuclear Regulatory Commission Attn: Document Control Desk One White Flint North 11555 Rockville Pike Rockville, MD 20852-2738