ML20085J422

Application for Amend to Licenses NPF-4 & NPF-7 Adding Exemption Which Allows Engineering Evaluation to Be Performed If Failure Occurs on Steam Generator/Reactor Coolant Pump Support Snubber.Amend Fee Encl

ML20085J422
Person / Time
Site:	North Anna
Issue date:	10/04/1983
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Harold Denton, John Miller Office of Nuclear Reactor Regulation
Shared Package
ML20085J423	List: ML20085J422 ML20085J424
References
548, NUDOCS 8310130145
Download: ML20085J422 (4)

Text

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e VIRGINIA ELECTRIC AND Powan COMPANY RIcuxoNn, VIRGINIA 20261 W.L.SrawAmr Vics Passios=r weet . o . m on. October 4, 1983 .

Mr. Harold R. Denton, Director Serial No. 548 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 change to the Technical Specifications, to Operating License Nos. NPF-4 and NPF-7 for the North Anna Power Station Unit Nos. I and 2

The proposed changes will revise Technical Specification 3/4.7.10. Surveil-lance requirement 4.7.10c will be revised to add an exemption which will allow an engineering evaluation to be performed if a failure occurs on a steam generator / reactor coolant pump support snubber to determine if generic deficiencies exist. If integrity of other anubbers is suspected, additional samples will be functionally tested. The remaining changes to Technical Specification 3/4.7.10 are proposed in Tables 3.7-4a and 3.7-4b. These proposed changes reflect the current plant configurations due to various design changes. Table 3.7-4a reflects the addition, deletion, and typographical corrections to safety related hydraulic snubbers and Table 3.7-4b reflects the hydraulic snubber system abbreviations. The proposed Technical Specification changes for North Anna Unit No. I are provided in Attachment 1. The proposed Technical Specification 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 Staf f. It has been determined that this request does not involve an unreviewed safety question as defined in 10 CFR 50.59.

These proposed changes do not pose a significant hazards consideration as defined in 10CFR50. 92. Example (ii) in the Federal Register, dated April 6, 1983, Page 14870 states, "a change that constitutes an additional limitation, restriction, or control not presently included in the Technical Specifica- I tions: for example, a more stringent surveillance requirement." This example of a non significant hazards consideration fits the proposed exemption to surveillance requirement 4.7.10c. If a steam generator / reactor coolant pump ,

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support snubber fails, an engineering evaluation will The be performed evaluation toto determine if additional surveillance testing is required. the determine whether additional In snubbers needexample addition, functional (ii) testing alsoincreases fits a non surveillance requirements. The significant hazards consideration for the addition of hydraulic snubbers.

addition of hydraulic snebbers adds to thetypographical Several surveillance errors requirements existed inof g Technical Specification 3/4.7.10. non significant hazards example (i) of a Table 3.7-4a, therefore, r

wideration applies because correcting typographical errors is a purely Two hydraulic snubbers have been deleted from the aa. *rative change. Federal Register example (iii)

Unit 1 Technical Specifications.

North w constitut, 's change likely to involve a significant hazards consideration significant relaxation in limiting conditions for operation because there . mensatory changes, conditions, or actions that maintain not accompanied b, Vepco proposes that the deletion of the two

'afety.

a commensurate IcVel ignificant hazards consideration because a piping hydraulic snubbers is nos $ performed prior to initial criticality and flexibility analysis summary d Design the two snubbers were not requ...J and were removed by Engineering an Coordination Report P-2010-D-1.

Since this with the criteria in 10CFR170.22.

We have reviewed this requestinvolves a safety issue which the request Staff I and should be able to a dupli-does not involve a significant hazards consideration for Unit l I cate safety issue for Unit 2, a Class III license amendment fee and a C ass A license amendment fee are required for Unit I and Unit 2, respectively. d voucher check in the amount of $4,400 is enclosed in payment of the require fees.

Very truly yours,

/'

,d, b2 W. L. Stewart Attachments

1. Proposed Technical Specification Changes - Unit 1

2. Proposed Technical Specification Changes - Unit 2

3. Discussion of Proposed Technical Specification Changes

4. Voucher Check for $4,400 l

l cc: Mr. James P. O'Reilly Regional Administrator l

Region II f Mr. M. B. Shyclock NRC Resident Inspector l North Anna Power Station l

Mr. Charlie Price Department of Health 109 Governor Street

' Richmond, Virginia 23219 L

3 COMMONWEALTH OF VIRGINIA )

)

CITY OF RICHMOND )

The foregoing doctroent was acknowledged before me, in and for the City and Commonwealth 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 foregoing 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 Y day of [ScM /d ,19 72 .

My Commission expires: A-A6 , 19 2i .

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G.a C.7M"?n Notary Public l

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