ML20028B107

Confirms Verbal Agreements Constituting Interim Resolution of Issue Re safety-relief Valve Leakage.Draft Tech Spec Changes Encl

ML20028B107
Person / Time
Site:	FitzPatrick
Issue date:	11/22/1982
From:	Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Vassallo D Office of Nuclear Reactor Regulation
References
JPN-82-86, NUDOCS 8211290465
Download: ML20028B107 (3)

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POWER AUTHORITY OF THE STATE OF NEW YORK 10 COLUMaus CincLE NEW Yonx, N. Y.1o019 (212) 397 6200 sn LE RO Ygs _,

TRUSTEES ***"*""**""*""

A' JOMN s.DYSON ,,",T C,1,N.s M t c e a mens se vm rev s CEORGE L. ING ALL3 orrecen vic s c"*>"=aa ovember 22, 1982 20sE,w n.sCwuiECE.

ocwARo u.rLYNN JPN-82-86 """",!,"

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RosERT 1. MILLONZ8 JOH N W. sOsTON rREDERICK R. CLARK ,' ass"o'a' v a sounse

& penromasames THOM A. n. FR EY

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Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attention: Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Safety / Relief Valve Leakage

Reference:

PASNY letter, J.P. Bayne to D.B. Vassallo dated August 12, 1982 (JPN-82-69)

Dear Sir:

As a result of recent FitzPatrick operating experience with safety / relief valve (SRV) leakage, there have been several discussions between members of your staff and Mr. J.A. Gray, Jr.

of my staff. During these discussions, verbal agreements were reached which constitute an interim resolution of the issue. These agreements are restated in this letter to eliminate any potential for misunderstanding.

The Power Authority has committed to abide by the requirements of the attached draft changes to the FitzPatrick Technical Specifica-tions, beginning October 22, 1982. These draft changes require prompt notification of elevated SRV tailpipe temperatures. It was understood that this reporting requirement was satisfied for the "D" SRV by virtue of the fact that the NRC was already aware of the condition.

The attached draft changes also require the submission of an engineering evaluation for the corresponding temperature increase.

This evaluation was to have been submitted in conjunction with a proposed license amendment which would have: incorporated the attached reporting requirements into the Technical Specifications; and, permitted continued operation with any one SRV inoperable. Submittal of this proposed amendment is no longer being requested by the NRC staff. However, the engineering evaluation to fulfill the requirements of the attached changes is essentially the same as the cafety evaluation submitted with the referenced letter.

8211290465 821122 Aool PDR ADOCK 05000333 P PDR R

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The Power Authority's commitments with regard to as-found testing of SRVs were stated in the referenced letter. .The commitments remain unchanged.

If you have any questions, please contact Mr. J.A. Gray, Jr.

of my staff.

Very truly yours, w-(,J.P. B)ayne, Executive ice President Nuclear Generation cc: Mr. J. Linville Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, N.Y. 13093 Mr. Ron Barton United Engineers & Constructors, Inc.

30 S. 17th Street Philadelphia, PA 19101 1

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JAFNPP 3.6 (cont'd) 5.. If, for a period of longer than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the temperature of any safety / relief discharge pipe is more than 400F above its steady state valu e, or the acoustical monitor reading of any safety / relief valve discharge pipe is more than 3 times greater than its steady state value, the following actions shall be taken:

a. a report shall be issued in accordance with 6.9.A.4.1 which addresses the actions that have been taken or a schedule of actions to be taken.

b. an engineering evaluation shall be per-formed justifying continued operation for the corresponding increase in tem-perature or acoustical monitor reading.

c. the affected safety / relief valve shall be removed at the next cold shutdown of 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more, tested in the as-found condition, and recalibrated as necessary prior to reinstallation.

l The steady state values of temperature and acoustical monitor readings shall be as measured after 5 days of steady state power operation. If the steady state temperature is greater than 275oF a., b. and c. above This page is effective until the apply without regard to temperature increase. Reload 5/ Cycle 6 refueling outage.

. Amendment No. 70 143b O-1 l