ML17212A499

Application for Amend to License DPR-67 to Alleviate Undesirable Identified Primary Leakage Resulting from Closure of Power Operated Relief Valve Block Valve V-1403

ML17212A499
Person / Time
Site:	Saint Lucie
Issue date:	08/03/1981
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML17212A500	List: ML17212A499 ML17212A501
References
L-81-333, NUDOCS 8108110461
Download: ML17212A499 (5)

Text

REGULATOR~ NFORMATION I STR I BUT I ON 8 ~TE>>~1 (R IDS)

~ . ~>> D ACCESSION NBR:8108110461. DOC ~ DATE: 81/08/03 NOTARIlED:'O DOCKEiT FACILi:50-335 St. Lucie Plant~ Unit 1P. Florida Power L Light Co ~

AUTH',NAME AUTHOR AFFILIATION UHRIGg R ~ E ~ Florida>> Power 8 Light Co ~

RE C IP ~ iV A ME) RECIPE ENT AFFILIATION EISENHUT'iDRG ~ Division of Licensing h

SUBJECT Application for amend to License DPR 67 to alleviate) undesirable identified primary leakage resulting fromm closure of powe'r opet ated relief valve Block Valvei V>>1403;.

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P.O. BOX 529100 MIAMI,F L 33152 FLORIDA POWER & LIGHT COMPANY August 3, 1981 L-81-333 Office of Nuclear Reactor Regulation Attention: Mr. Darrell G. Eisenhut, Director o gf Division of Licensing ~SOUCI U. S. Nuclear Regulatory Commission ~>0 Washington, D. C. 20555 C fcfeIo 9j POhg ~%4 ig

Dear Mr. Eisenhut:

Re: St. Lucie Unit 1 Docket No. 50-335 Proposed License Amendment PORV Block Valves In accordance with 10 CFR 50.30, Florida Power 8 Light Company submits herewith three signed originals and forty copies of a request to amend Appendix A of Facility Operating License DPR-67.

This proposal is submitted to alleviate undersir able identified primary leakage resulting from the closure of PORV Block Valve V-1403.

On August 2, 1981, during periodic surveillance of V-1403, (PORV block valve) as required by Technical Specification 3.4.12, the valve was found to be inoperable. Action was taken in accordance with the Technical Specification and the valve was closed manually; however, with the valve closed, the valve packing developed a leak of approximately 1 - 1.5 GPM. With the valve open, (backseated) the 'packing is not subject to system pressure and will not leak; therefore, we propose to revise the Technical Specification to permit the PORV to be verified closed and then deenergized in lieu of closing the block valve.

Deenergi zing the valve will be accomplished by lifting the leads T> 8 T1 to V 1402 (the PORV) shown on CWD 117, thereby rendering it incapable of being opened. Position indication will remain operable.

The bases for the subject Technical Specification is to ensure the capability to isolate a manfunctioni ng PORV. With the PORV closed and deenergi zed, the block valve is no longer required for the purpose described in the bases.

The PORV piping is arranged with redundant parallel trains and the block valve in the redundant train has been verfied to be operable; therefore, a PORV flow path remains available. p~/

The revision to Technical Specification 3.4.12 as proposed should remain /f applicable until the refueling outage in October of 1981.

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Mr. Darrell G. Eisenhut, Director Page 2 The proposed amendment is described below and shown on the accofopanying Technical Specification pages bearing the date of this letter in the lower right hand corner.

Page 3/4 4-58 An exception to the Action statement to allow deenergizing the PORV instead PORV block valve.

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~P/4 4- 4 The Bases- pages are changed to reflect the above change to the limiting ti Condi on of Operati on.

This has been determined to be a Class III Amendment. A check for $ 4000 is enclosed.

The proposed amendment has been reviewed by the St. Lucie Facility Review Group and the Florida Power 8 Light Company Nuclear Review Board.

Very truly yours, Robert E. Uhrig Vice President Advanced Systems & Technology REU/PLP/ras cc: Mr . J. P. O'Reilly, Region II Harold F. Reis, Esquire