ML17297A567

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Requests Extension for Completion of EPRI Safety & Relief Valve Test Program to Allow for Testing of Dresser 31709NA Safety Valves.Evaluations & Other plant-specific Data Will Be Submitted Per Schedule Transmitted by
ML17297A567
Person / Time
Site: Palo Verde  
Issue date: 07/10/1981
From: Van Brunt E
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To: Harold Denton
Office of Nuclear Reactor Regulation
References
ANPP-18374-JMA, NUDOCS 8107170244
Download: ML17297A567 (4)


Text

REGULATORQINPORMATION DISTRIBUTION LITEM (RIBS)

ACCESSION NBR: 8107170244 DOC; DATE! 81/07/10 NOTARIZED!

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STN 50 528 Palo Verde Nuclear Station, Unit 1E Arizona Publ.i 0005 STN 50 529 Palo Verde Nuclear. Station~

Un)t 2E Arizona Publi 9

STN 50-530 Palo Verde Nuclear Station<, Undt 3<

Ar izona Publi 05000530 AUTH',NA(>>IIE'UTHOR AFFILIATION VAN BRUNTEE".E, Arizona Public Service>>

Go,,'EC IP ~ NAME RECIP IENT AFF IL,'IATION DENTONiH ~ RB Office( of Nuclear Reactor Regulationp Director<

SUBJECT!'equestsextension for>> completion of.EPRI safety

& relief valve test program to allow for testing of Dresser 31709NA safety val ves,E'val uations

& other" plant specific data>> wil l ~

beI submitted per schedule transmitted by 801215 1 tr ~

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'HOENIX'RIZONA85036 July 10, 1981 ANPP-18374 JMA/KWG Mr. H. R.

Denton

-U.S. Nuclear Regulatory Commission Washington',

D.C.

20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2 and 3

'ocket Nos. 50-528/529/530

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Reference:

Letter from R.

C. Youngdahl to H. R. Denton dated July 1, 1981

Dear Mr. Denton:

By the referenced letter, Mr. Youngdahl of Consumer's

Power, Chairman of the EPRI Research Advisory Committee,'ransmitted the'nterim Data'Re ort for the EPRI Safety andRelief'Valve Test Program.

This report summarizes the test data collected to date on relief and safety valves.

Palo Verde Nuclear Generating Station (PVNGS) utilizes Dresser Model 31709NA safety valves on all three units.

I As per Mr. Youngdahl's letter, PVNGS'alves have-not been tested fully as described in the original Combustion Engineering Test Facility test matrix.

As the matrix has not yet been fully revised, the exact date our valves will be t'ested is undetermined at this time.

We request an extension until the tests can be completed.

We will continue to appraise the NRC of our test status and completion when available.

Arizona Public Service will submit evaluations and other plant specific data consistent with the schedule transmitted by letter on December 15, 1980 from Mr. Youngdahl to yourself.

If you have any questions, please contact me or my staff.

Very truly

ours, EEVBJr/KWG/av cc:

J. Kerrigan R.

Youngdahl B. Myerson B107170244 B10/10 PDR ADQCK 0500052B A

PDR P. Hourihan A. Gehr E.

E.

Van Brunt, Jr.

APS Vice President, Nuclear Projects ANPP Project Director Goal

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