ML20062N427

Application to Amend License DPR-28,revising Tech Spec Page 180-01 Re Max Critical Power Ratio to Reflect Changes Based on Methodology Per Util

ML20062N427
Person / Time
Site:	Vermont Yankee
Issue date:	08/19/1982
From:	Heider L VERMONT YANKEE NUCLEAR POWER CORP.
To:	Office of Nuclear Reactor Regulation
Shared Package
ML20062N429	List: ML20062N427 ML20062N432
References
FVY-82-93, NUDOCS 8208230165
Download: ML20062N427 (3)

Text

' VERMONT YANKEE Proposed Change No. 98

, NUCLEAR POWER CORPORATION

- Suppiement 2

. 2.C.15.2

. , RD 5. Box 169, Ferry Road. Brattleboro, VT 05301 y y FVY 82-93 g'

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ENGINEERING OFFICE 1671 WORCESTER ROAD FRAMINGHAM. MASSACHUSETTS 01701 TEL E PHONE 617-6 72-8100 August 19, 1982 United States Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Office of Nuclear Reactor Regulation

Reference:

(a) License No. DPR-28 (Docket 50-271)

(b) Letter, VYNPC to USNRC, FVY 82-36, March 31,1982, YAEC-1299P (c) Letter, VYNPC to USNRC, FVY 81-128, dated September 2,1981, (Proposed Change No. 98)

(d) Letter, USNRC to VYNPC, SER, dated November 27, 1981 (e) Letter, VYNPC to USNRC, FVY 81-167, dated November 23, 1981

Subject:

Supplement (2) to Reload 8 Licensing Submittal

Dear Sir:

Pursuant to Section 50.59 of the Commission's Rules and Regulations, Vermont Yankee Nuclear Power Corporation hereby proposes the following changes to Appendix A of the Operating License.

Proposed Change The change involves revision to page 180-01 of Vermont Yankee Technical Specifications. The revised page is provided as Attachment 1.

Reason for Change The detailed reasons for this change are described in Reference (b). In general, this change reflects the Technical Specification MCPR Operating Limit changes and revisions based on the methodology described in the attachment to that Reference. Further, this change fulfills the commitment made in Reference (b).

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. VEHMONT YANKEE NUCLEAR POWEH CORPOHATION U. S. Nuclear Regulatory Commission August 19, 1982 Page 2 Basis for Change The basis for the Vermont Yankee Reload 8 licensing analysis is provided in Reference (c). This reference presents licensing analysis results using methods developed by Vermont Yankee. Upon review of these methods, the staff concluded

[ Reference (d)] that the method for calculating the MCPR operating limits using the MAYUO4-YAEC computer code was not acceptable. However, plant operation was allowed until EOC-2000 because the MCPR operating limits for operation between BOC through EOC-2000 were determined independent of MAYUO4-YAEC methodology as documented in Reference (e). _ As a result, Vermont Yankee was requested to submit an improved or a new method for determining MCPR operating limits via Reference (d). In response, Vermont Yankee chose to submit a new method for determining MCPR operating limits as documented in Reference (b). This method is currently under review by the staff.

"De revised MCPR operating limits submitted with this change are based on this new methodology, as described in Reference (b).

This change will also require an update to the Core Performance Analysis Report, YAEC-1275, which was submitted in Reference (c). This update is provided as Attachment 2.

Safety Considerations:

The method for calculating MCPR operating limits has received extensive review at Yankee. External technical peer review was attained through a presentation describing this method at the Second RETRAN International meeting held this April at San Diego. The method has been qualified against experimental data, and the results have shown excellent agreement.with'the data. Ihe results of Vermont Yankee _ Reload 8 MCPR operating limits based on this method show no-unexpected trends or deviations from the previous reload analysis. Therefore, Vermont Yankee concludes that this method can be used with l confidence to evaluate core reloads and for compliance with licensing

. requirements. This change has been determined not to involve an unreviewed.

safety question.

This submittal has been~ reviewed by the Vermont Yankee Nuclear Safety' Audit-and' Review Committee.

Fee Determination:

This proposed change requires an approval that involves a single safety issue and is deemed not to involve a significant hazards consideration..?For these reasons, Vermont _ Yankee Nuclear Power Corporation proposes this change as

- a Class III Amendment. A payment of $4,000.00 was previously forwarded with' Reference (c).

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O VERMONT YANKEE NUCLEAR POWEH COH1'OHATION U. S. Nuclear Regulatory Commission August 19, 1982 Page 3 Schedule of Change:

This proposed change should te approved before August 31, 1982, which is the currently expected date for approaching E0C-2000 burnup limit.

Very truly yours, VER NT YANKEE NUCLEAR POWER CORPORATION Y

L. H. Heider Vice President COMMONWEALTH OF MASSACHUSETTS)

)ss MIDDLESEX COUNTY )

Then personally appeared before me, L. H. Heider, who, being duly sworn, did state that he is a Vice President of Vermont Yankee Nuclear Power Corporation, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Vermont Yankee Nuclear Power Corporation and that the statements therein are true to the best of his knowledge and belief.

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