ML20063A985

Application for Amend to License DPR-59 Changing Safety/Relief Valve Inoperability Requirements & Limiting Conditions for Operation for HPCI Sys.Amend Effective Until Oct 1982 Outage

ML20063A985
Person / Time
Site:	FitzPatrick
Issue date:	08/12/1982
From:	Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	Vassallo D Office of Nuclear Reactor Regulation
Shared Package
ML20063A987	List: ML20063A985 ML20063A989 ML20063A992
References
JPN-82-69, NUDOCS 8208250143
Download: ML20063A985 (2)

Text

-

t o .

e POWER AUTHORITY OF THE STATE OF NEW YORK to CoLUMous CIRCLE NEW YORK. N. Y too19 (212) 397 6200 LEROY S LAIR TRUSTEES =' A TING OP P BC a R JOHN S.DYSON W ALTER T. KICINSKI c-.~=~ ',l~ :.".':::".

GEORGE L. ING ALLS P e as

_ JOSEPH R. SC HMIEDER RICH ARD M. FLYNN ,,',[o,'[,' a c[g ,

August 12, 1382 sowa w.soSTon rREDERicx R. cLaRx JPN-82-69 [';".*"=}3j'*)f ou .

THOM AS R. FREY

& esNs at couse L Director of Nuclear Reactor Regulation U.W. Nuclear Regulatc,ry 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 Proposed Changes to the Technical Specifications Concerning Safety / Relief Valve Operability

Dear Sir:

Enclosed for filing are three (3) signed originals and nineteen (19) copies of a document entitled, " Application for Amendment to Operating License," together with forty (40) copies of Attachment I and II thereto, comprising a statement of the proposed changes to the Technical Specifications and the associated Safety Evaluation.

The proposed amendment to Appendix A of the Facility Operating License changes the-safety / relief valve operability requirements, which are contained in Specifications 3.5.C, 3.5.D and 3.6.E. The limits are conservative and are not necessary to assure the safe operation of the plant or to protect the health and safety of the public. The proposed amendment, which would be effective only until the October 1982 outage, changes the specifications that limit reactor operation to thirty days in the event that a safety / relief valve be-comes inoperable. This proposed amendment also changes the limiting conditions for operation for the HPCI System, to reflect permissible reaction operation for 7 days with HPCI and one ADS safety / relief valve inoperable. This conclusion and the proposed amendment are supported by the Final Safety Analysis Report and additional analyses contained in Attachment II.

{ool w clGc h '-

[ yooO.co 8208250143 820812 PDR ADOCK 05000333 P PDR l

8 >

1 .

The proposed amendment also deletes the safety / relief valve ,

bellows monitoring requirement, which is contained in Specification l 4.6.E.3. This requirement is no longer necessary since all safety / )

relief valves are now equipped with two-stage topworks, which do not have a bellows arrangement. Existing typographical errors, specification numbers and references, as required, have also been changed.

The Authority also proposes Specification 3.6.E.5 which specifies actions which will be taken if significant increases occur in SRV discharge pipe temperatures or acoustical monitor readings. In additi'on to this new specification, the Authority is committed to do the following: conduct a test of the F safety / relief valve in the as-found condition during the October 1982 outage; repair the in-operable SRV discharge pipe thermocouples during the October 1982 outage; and, conduct as-found tests of at least 6 SRV's during the next refueling outage.

The proposed changes are Attachment I to the Application of Amendment to the Operating License which is included with this letter. The Safety Evaluation for the proposed changes to the Technical Specifications is Attachment II to the Application for Amendment.

The Authority has classified this operating license Amendment Application as Class III. Enclosed is a check in the amount of

$4,000 as the filing fee per 10 CFR 170.22, which the Authority pays under protest pending a final determination of the legality of the fee schedule.

Very truly yours, 9

"j. .

Executive Vice 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