ML17298A296

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Advises That Check Valve SG-V044 Will Not Be Relocated from Train B motor-driven Auxiliary Feedwater Pump Room (Afpr) to Train a turbine-driven Afpr Per 810306 Commitment.Steam Line Pipe Stresses Do Not Exceed Recommendation
ML17298A296
Person / Time
Site: Browns Ferry, Palo Verde  
Issue date: 04/15/1983
From: Van Brunt E
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To: Knighton G
Office of Nuclear Reactor Regulation
References
ANPP-23510-WFQ, NUDOCS 8304190507
Download: ML17298A296 (4)


Text

. REGULATO INf.ORMATION DISTRIBUTION STEM (RIDS)

AOCE'SSION NBR: 8304190507 DOC ~ DATE: 83/04/15 NOTARIZED!

NO FACIL:STN-50 528 Palo Ver de Nuclear Stationi Unit 1i Arizona Publi

'STN 50 529 Palo Verde Nuclear Station< Unit 2r Arizona Publi STN 50-530 Palo Verde Nuclear Stationi Uniit 3i Arizona Publi

'AUTH'AME AUTHOR AFFILIATION VAN BRUNTqE,E.

Arizona 'Public Service Co.

'RECIPeNAME RECIPIENT AFFILIATION KNI G H TON i G. e Licensing Branch 3

DOCKET 05000528 05000529 05000530

SUBJECT:

Advises *that check valve SG-V044 will *not be relocated from Train 8 motor"driven auxiliary feedwater pump room (AFPR) to Train A turbine-driven-AFPR per 810306'commitments Steam line pipe stresses do not exceed recommendation.

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j TITLE: Licensing Submittal:

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Arizona Public Service Company P.O. SOX 21666

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PHOENIX. ARIZONA 65036 April 15, 1983 ANPP-23510 WFQ/RJP Director of Nuclear Reactor Regulation Attention:

Mr. George Knighton, Chief Licensing Branch No.

3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, D. C.

20555

Subject:

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

Docket.Nos.

STN-50-528/529/530 File:

83-056-026; G.l.01.10

Reference:

Letter from E. E.

Van Brunt, Jr.,

APS, to H.

R. Denton,

NRC, dated March 6, 1981.

Dear Mr. Knighton:

The referenced letter provided responses to open items from the PVNGS Auxiliary Feedwater System Independent Design

Review, which was held in Phoenix on August 21 and 22, 1981.

Page 2 of the attachment to the Referenced letter states that check valve SG-V044 is being relocated from the Train B

pump room to the Train A

turbine-driven Auxiliary Feedwater pump room.

We have since evaluated this steam line in accordance with the criteria of Branch Technical Position

-(BTP)

MEB 3-1, B.2.C, and found that the pipe stresses do not exceed the 0.4(1.2Sht+SA) recommendation at any point in the Train B motor-driven Auxiliary 'Feedwater pump room.

We have also evaluated this pipe in accordance with Appendix A of BTP APCSB3-1 and do not consider it to be a high-energy or moderate-energy line.

Based on these evaluations the necessary requirements are met without moving this check valve.

Therefore, we are changing our previous commitment, and the present design will not be changed.

8304190507 830415 PDR ADOCK 05000528 PDR Very truly your E. E. Van Brunt, Jr.

APS Vice President, Nuclear Projects ANPP Project Director

~oo t EEVB/RJP/sP cc:

E. A. Licitra A. C. Gehr G. Wermiel (NRC)

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