ML20005A956

Application for Amend to License NPF-7,changing Condition 2.C.21(f) Re Reactor Coolant Relief & Safety Valve Tests.Testing Is Being Performed on industry-wide Basis by Epri.Proposed Condition & Fee Encl

ML20005A956
Person / Time
Site:	North Anna
Issue date:	07/01/1981
From:	Ferguson J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	Clark R, Harold Denton Office of Nuclear Reactor Regulation
References
396, NUDOCS 8107060107
Download: ML20005A956 (2)

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VIRGINIA ELECTRIC AND Powan Coma xy RIcumoxn. VIMOINIA 23261 July 1, 1981 Jun H.Famor.ow 1: com. vic e . ..=

Mr. Harold R. Denton, Director Serial No. 396 Office of Nuclear Reactor Regulation N0/DWS,JR.:acm

' Attn: Mr. Robert A. Clark, Chief Docket No. 50-339 Operating Reactors Branch No. 3 License No. NPF-7 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C. 20555-Gentlemen:

AMENDMENT TO OPERATING LICENSE NPP-7 NORTH ANNA POWER STATION UNIT NO. 2 LICENSE CONDITION 2.C.21(f)

Pursuant to 10CFR50.90, the Virginia Electric and Power Company requests an amendment, in the form of a change to the Conditions of the License for Operating License JPF-7 for North Anna Power Station, Unit No. 2. The proposed change is attached.

The scheduled commitment of the North Anna Unit 2 Operating License Condition 2.C.21(f) to complete tests to qualify the reactor coolant relief and safety valves will not be completed by July 1, 1981. Testing of the valves is being performed on a generic, industry wide basis by the Electric Power Research Institute (EPRI) and this valve test program is incomplete.

The valve test program is responsive to the requirements of NUREG 0737, item II D.1.A. The objective of the program is to perform full scale operability tests on a set of primary system relief and safety valves representative of those utilized in or planned for use in NR's, under conditions expected as a result of FSAR, cold overpressurization and extended high pressure injection events.

Although testing is not complete, EPRI has been instructed to submit an Interim Data Report via EPRI Research Advisory Committee, Consumers Power Company, Mr. R. C. Youngdahl, Chairman. This preliminary report includes all tests performed on or before June 19, 1981 and will be submitted generically by Consumers Power Company on or before July 1, 1981. This submittal will explain the reason for the program delays.

The 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 pose an unreviewed safety question.

We have evaluated this request in accordance with the criteria in 10CFR170.22.

Since this request involves a safety issue which the 3taff should be able to detenine does not pose a significant hazards consideration, a Class III license amendment fee is required. Accordingly, a voucher check in the amount of $4000.00 is enclosed in payment of this required fee. d 8107060107 810 1 35 s PDR ADOCK 0500 P

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Va ucix 4 Etzakic Axo Ibwra COMPANY TO We regret the delay of the test program. We are encouraging EPRI to proceed toward completion as rapidly as possible.

Very truly yours, d-J. H. Ferguson Executive Vice President - Power Attachments:

1. Proposed License Condition 2.C.21.(f)

2. Voucher Caeck No. 31871 for $4000 cc: Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region II

COMMONWEALTH OF VIRGINIA )

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CITY OF RICHMOND ) ..

The foregoing document was acknowledged before me, in and for the City and Commonwealth aforesaid, today by J. H. Ferguson, who is Executive Vice President-Power, 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 / day of tw,_/~ , 19 9 / .

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My Cossaission expires: 43 6 , 19 S' s' .

L~ d . 7h cw Notary Public 1

(SEAL) l l

Proposed License Condition 2.C.21.(f):

(f) Relief and Safety Valve Test Requirements (Section 22.3 Item II.D.1)

VEPCO shall notify NRC following completion of tests to qualify the reactor coolant system relief and safety valves under ex-pected operating conditions for design basis transients and accidents.

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