BVY 11-042, Technical Specifications Proposed Change No. 293, Supplement 1 Revised Reactor Vessel Pressure-Temperature Limitation Curves

Technical Specifications Proposed Change No. 293, Supplement 1 Revised Reactor Vessel Pressure-Temperature Limitation Curves

ML11140A083
Person / Time
Site:	Vermont Yankee
Issue date:	05/16/2011
From:	Michael Colomb Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
BVY 11-042
Download: ML11140A083 (2)

Text

Entergy Nuclear Operations, Inc.

Vermont Yankee 320 Governor Hunt Rd Vernon, VT 05354 Tel 802 257 7711 Michael J. Colomb Site Vice President BVY 11-042 May 16, 2011 ATTN: Document Control Desk U.S. Nuclear Regulatory Commission Washington, DC 20555-0001

SUBJECT:

Technical Specifications Proposed Change No. 293, Supplement 1 Revised Reactor Vessel Pressure-Temperature Limitation Curves Vermont Yankee'Nuclear Power Station Docket No. 50-271 License No. DPR-28

REFERENCE:

1. Letter, VYNPC to USNRC, "Revised Reactor Pressure Vessel Pressure-Temperature Limitation Curves," BVY 10-071, dated 12/21/10

Dear Sir or Madam:

Per discussion with your staff, we are providing additional clarifying information that was requested as part of the review of a request for a License Amendment (Reference 1) for the Vermont Yankee Nuclear Power Station (VYNPS).

In the proposed change submittal (Reference 1) two fluence figures are discussed - 5.16x1 017 n/cm 2 and 5.39x1 017 n/cm 2. The 5.16x1 017 n/cm 2 value was computed based on actual plant operating history data through 2002 and a projected 93 percent capacity factor for the period 2003 through March 2032. The computed effective full power years (EFPY) for that fluence value are 51.6 EFPY. The 7.943 x 108 MWH(t) power generation value is based on that fluence value.

VYNPS utilizes MWH(t), not EFPY, when tracking plant history for this Technical Specification.

As part of the License Renewal Application (LRA) process the expectation was to present a value for 54 EFPY in the LRA; this derives from 60 years time at an average 90 percent capacity factor.

As stated in LRA Section 4.2.1, the 5.16x1017 n/cm 2 value was extrapolated to 5.39x1 017 n/cm 2 at 54 EFPY. The LRA evaluations and the associated USNRC Safety Evaluation Report utilized this figure.

Our Proposed Change (Reference 1) requests a revised validity for the VYNPS Reactor Vessel Pressure-Temperature Limit Curves of up to 7.943 x 108 MWH(t) power generation value and is based upon a calculated 5.16x1 017 n/cm 2 fluence value.

This supplemental information does not affect or alter the content and scope of our original submittal, nor does it alter the scope and conclusion of no significant hazards determined in our original submittal.

TLin

,BVY 11-042 / page 2 of 2 There are no new regulatory commitments being made in this submittal.

If you have any questions on this transmittal, please contact Mr. Robert Wanczyk at 802-451-3166.

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

Executed on May 13, 2011.

Sincerely,

[MJC/JTM]

cc: Mr. William W. Dean Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Mr. James S. Kim, Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop 08C2A Washington, DC 20555 USNRC Resident Inspector Entergy Nuclear Vermont Yankee, LLC 320 Governor Hunt Rd Vernon, Vermont 05354 Ms. Elizabeth Miller, Commissioner VT Department of Public Service 112 State Street - Drawer 20 Montpelier, Vermont 05620-2601