ML20087G257

Application for Amend to Licenses NPF-4 & NPF-7,changing Tech Specs to Delete Requirements for Min & Max Temp Limits for A36 & A572 Beams in Steam Generator Supports & Determination of Beam Temps

ML20087G257
Person / Time
Site:	North Anna
Issue date:	03/15/1984
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, John Miller Office of Nuclear Reactor Regulation
Shared Package
ML20087G260	List: ML20087G257 ML20087G273
References
131, NUDOCS 8403190377
Download: ML20087G257 (3)

Text

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VIRGINIA ELECTRIC AND Powan COMPANY

! RIcnwoxn,VIROINIA 20061

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W.L.Sinw m Vics Punaineur wuci. i or==ano== March 15, 1984 Mr. Harold R. Denton, Director Serial No. 131 Office'of Nuclear Reactor Regulation N0/JHL:acm Attn: Mr. James R. Miller, Chief Docket Nos. 50-338

/ Operating Reactors Branch No. 3 50-339 Division of Licensing License Nos. NPF-4 U. S. Nuclear Regulatory Commission NPF-7 Washington, D. C. 20555 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION UNIT NOS. 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGES Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company requests an amendment, in the form of changes to the Technical Specifications, to Operating License Nos. NPF-4 and NPF-7, for North Anna Power Station Unit Nos.

I and 2.

The proposed Technical Specification changes reflect a revision to Technical Specifications 3.4.10.2.a. 3.4.10. 2.b and 3.4.10.2.c for Limiting Conditions for - Operation, Specifications 4.4.10.2.1 and 4.4.10.2.2 for Surveillance Requirements and BASES Section 3.4.10.2. These changes delete the requirements for minimum and maximum temperature limits for A36 and A572 beams

'in ' the ' steam generator supports and delete verification requirements for determination of beam temperatures. The inservice inspection requirements for beam inspection on a 40 month basis will continue to provide a reasonable degree of assurance of the integrity of the support structure. The proposed Technical . Specification ' changes for North Anna Unit No. I are provided in Attachment 1. The proposed Technical Speci.ication changes for North Anna Unit No. 2 are provided in Attachment 2. A discussion of the proposed Technical Specification changes is provided in Attachment 3.

This request has been reviewed and approved 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 an unreviewed safety question as defined in 10 CFR 50.59.

These proposed changes could be considered to pose a significant hazards consideration as stated in the Federal Register dated April 6, 1983, Page 14870, example (iii); a significant relaxation in a limiting condition for i 8403190377 840315 '

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VimorxtA Es.scTate awn Powna ConeAwr to Harold R. Denton

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operation not accompanied by compensatory changes, conditions or actions that maintain a commensurate level of safety. Deleting Technical Specifications 3.4.10.2.a. 3.4.10. 2.b, 3.4.10. 2.c, 4.4.10.2.1, 4.4.10. 2.2 and B3 /4.10.2 is a significant relaxation of a limiting condition for operation, but these changes should not be considered a significant hazards consideration because they are consistent with example (vii); A change to make a license conform to changes in the regulations where the license change results in very minor changes to facility operations and clearly keeping within regulations. The proposed changes have been _made with the guidance of NUREG-0577, Revision 1.

The proposed changes also fit example (iv); A relief granted upon demonstration of acceptable operation from an operating restriction that was imposed because acceptable operation was not yet demonstrated. Vepco had

-previously performed an analysis based on requirements almost identical to the requirements of Section 2.3.5 of NUREG-0577, Revision 1, and the results indicated that the supports were acceptable without elevated temperatures.

Based ' on this information, Vepco proposes that these changes do not pose a significant hazards consideration.

We have reviewed this request in accordance with the criteria in 10 CFR 170.22. Since this request involves a safety issue which the Staff should be able to determine does not involve a significant hazards consideration for Unit I and a duplicate safety issue for Unit 2, a Class III license amendment fee and a Class I license amendment fee are required for Unit 1 and Unit 2, respectively. A voucher check in the amount of $4,400 is enclosed in payment of the required fees.

Very truly yours.

W. L. Stewart Attachments

1. Proposed Technical Specification Changes-Unit 1

2. Proposed Technical Specification Changes-Unit 2

3. Discuseton of Proposed Technical Specification Changes

4. Voucher Check for $4,400 cc: Mr. Jsmes P. O'Reilly Regional Administrator Region II Mr. M. W. Branch NRC Resident Inspector North Anne Power Station Mr. Charles Price Department of Health 109 Governor Street Richmond, Virginia 23219

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COMMONWEALTH OF VIRGINIA )

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CITY OF RICHMOND )

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

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

-c4 Acknowledged before me this /5 day of MM , 19 PY .

My Commission expires: P .16 , 19 M .

b Notary d.MSAPublic (SEAL)

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