ML20215G534

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Application for Amends to Licenses NPF-4 & NPF-7,reflecting Implementation of Statistical DNBR Evaluation Methodology Documented in VEP-NE-2 & Accompanying FSAR Chapter 15 Accident Analyses.Fee Paid
ML20215G534
Person / Time
Site: North Anna  Dominion icon.png
Issue date: 06/17/1987
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML20215G537 List:
References
87-231, NUDOCS 8706230289
Download: ML20215G534 (3)


Text

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. VIMOINIA-ELECTHIC AND POWEH COMPANY IIICMMOND,VINGINIA 2 02(il W. L. STawAmr :

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_Jggg }7,..}gg7 United. States Nuclear Regulatory Commission Serial No.87-231 Attention - Document Control Desk E&C/RCA/cdk Washington, DC 20555 Docket Nos.

50-338-50-339 License Nos.

NPF-4 NPF-7

.Centlemen:

VIRGINIA ~ ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNITS 1 AND 2 PROPOSED TECHNICAL SPECIFICATIONS CHANGE Pursuant to 10.CFR 50.90, the Virginia Electric and Power Company requests amendmente, in the form of changes to the Technical Specifications, to Operating License Nos. NPF-4 and 7 for North Anna Power Station Units 1 and 2, respectively.

These amendments support the implementation of our Statistical DNBR (Departure from Nucleate Boiling Ratio)-Evaluation Methodology, as documented in Topical Report VEP-NE-2 of the same name, and the accompanying FSAR Chapter 15 accident analyses.

The proposed Technical Specifications changes are presented in (Unit 1) and Attachment 2 (Unit 2).

The' new methodology employs Monte Carlo methods to evaluate,the DNBR sensitit.ity of key parameter uncertainties.

The methodology is similar to

'those which have been licensed' by the vendors, and uses the WRB-1 CHF correlation.

In support of these changes, a safety evaluation is provided in.

In order to benefit from the revised moderator temperature coefficient (MTC) specification during North Anna Unit 1. Cycle 7, we request approval of this package by December 31, 1987.

This request has been reviewed by the Station Nuclear Safety and Operating Committee and the Safety Evaluation and Control staff.

It has been determined that this request does not involve any unreviewed safety questions as defined in 10.CFR. 50.59 or a significant hazards consideration as defined in 10 CFR 50.92.

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We have evaluated this request in accordance with-the criteria in 10 Cin 170.12. A voucher check in the amount of $150.00 is enclosed as an application fee.

Very truly yours,

((ys A.

s W. L. Stewart Attachments 1.

Proposed Technical Specification Changes Unit 1 2.

Proposed Technical Specification Changes Unit 2 3.

Safety Evaluation for Change in Methodology & Supporting Analyses 4.

10 CFR 50.92 Evaluation

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Application Fee cc: U. S. Nuclear Regulatory Commission 101 Marietta Street, N.W.

Suite 2900 Atlanta, GA 30323 J

l Mr. J. L. Caldwell NRC Senior Resident Inspector North Anna Power Station i

Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219

COMMONWEALTH OF VIRGINIA )

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CITY OF RICHMOND

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The foregoing' document was acknowledged' before me, in and'for the City and Commonwealth aforesaid, today by W. L. Stewart who is Vice President - Nuclear

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Operations, of Virginia Electric and Power Company. He is duly authorized to execute and file the aforegoing document in behalf of-that Company, and the statements in the document are.true to the best of his knowledge and belief.

Acknowledged before me this /7 day of

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My Commission expires #- /////#so f5 19 '/d.

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Notary'Public i

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