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=Text=
=Text=
{{#Wiki_filter:.REGULATO INf.ORMATION DISTRIBUTION STEM (RIDS)AOCE'SSION NBR: 8304190507 DOC~DATE: 83/04/15 NOTARIZED!
{{#Wiki_filter:. REGULATO     INf.ORMATION DISTRIBUTION         STEM (RIDS)
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.
AOCE'SSION NBR: 8304190507           DOC ~ DATE: 83/04/15     NOTARIZED!   NO         DOCKET FACIL:STN-50 528 Palo Ver de Nuclear Stationi Unit 1i Arizona Publi                     05000528
Arizona'Public Service Co.'RECIPeNAME RECIPIENT AFFILIATION K N I G H TON i G.e Licensing Branch 3 DOCKET 05000528 05000529 05000530
          'STN 50 529 Palo Verde Nuclear Station< Unit 2r Arizona Publi                   05000529 STN 50-530 Palo Verde Nuclear Stationi Uniit 3i Arizona Publi                 05000530
    'AUTH'AME               AUTHOR AFFILIATION VAN   BRUNTqE,E.         Arizona 'Public Service Co.
    'RECIPeNAME             RECIPIENT AFFILIATION KN IG H TON i G. e         Licensing Branch 3


==SUBJECT:==
==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.
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.
DISTRIBUTION CODE!8001S COPIES RECEIVEDSLTR ENCL SIZE:, j TITLE: Licensing Submittal:
DISTRIBUTION CODE! 8001S           COPIES RECEIVEDSLTR     j  ENCL       SIZE:,
PSAR/FSAR Amdts&Related Correspondence NOTES:Standardi'zed plant.-Standardized, plant.Standardized.plant~05000528 05000529 05000530 RECIPIENT ID-CODE/NAME NRR/DL/ADL NRR L83 LA INTERNAL;..ELD/HDS3 IE/DEPER/EPB
TITLE: Licensing Submittal:           PSAR/FSAR Amdts &     Related Correspondence NOTES:Standardi'zed       plant.                                                       05000528
'36 IE/DEQA/QAB 21 NRR/DE/CEB 11 NRR/DE/EQ8 13 NRR/DE/HGEB 30 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/LQB 32 NRR/DS I/AEB 26 NRR/DSI/CPB 10 NRR/DSI/I CSB 16 NRR/DSI/PSB 19 NRR/DS I/RSB 23" RGN5 EXTERNALS ACRS 41 DMB/DSS (At1DTS)LPDR 03 NSIC 05 COPIES LTTR ENCL 1 0 1 0 1 0 3 1 1 1 2 2 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 3 R3.6 6 1 1 1 1 1 1 REC IP IENT ID CODE/NAt<E NRR LB3 BC LICITRAi E~01 IE FILE IE/DEPER/I RB 35 NRR/DE/AEA8 NRR/DE/EHEB NRR/DE/GB 28 NRR/DE/MEB 18 NRR/DE/SAB 24 NRR/DHFS/HFE840 NRR/DL/SSP8 NRR/DS I/ASB NRR/DSI/CS8 09 NRR/DSI/tlETB 12 N RAB 22 G F 04 M/DDAMI/MI8 BNL(AMDTS ONLY)FEMA REP DIV 39 NRC PDR 02 NTIS COPIES LTTR ENCL 1 0.1 1.1 1 1 ,1 0 1 1 2 2 1 1 1 1 1 0 1 1 ,1 1~1 1 1 1 1 1 0 1,1 1 1 1 1 1 1~TOTAL NUMBER OF COPIES REQUIRED: LTTR 54 ENCL 47 R ti v R I r,l tv lt R l h II It, tv tl itvt, I I'v l tr'T'1 j Lnli v f w F ci r,$I FI I'I J Wkt IRv ff hl'1 if)lltf)j f'n'1 JI cj.I-jr}IW Ill I',I i Frit'1t li"'ll'j ti')I hit'Itr'lli ic''1RH F1 i n II R,hi I,', icif Ih j~cr&I vrf-lvr'I/h'ljri'f'tl rh I}l ttl,t k yk>>ttj l f'lt'I v j''lit i'X fk j II lr I I ijp'vW R il Iijt R ih II 4 ,(li'l, II, ill il Ci I'r f Ih I n r R'il l'f I'(tg rt r i'RAX jh III'Rl,,lt 4, gr f)h j Arizona Public Service Company P.O.SOX 21666~PHOENIX.ARIZONA 65036 April 15, 1983 ANPP-23510
          -Standardized, plant.                                                           05000529 Standardized .plant     ~                                                     05000530 RECIPIENT           COPIES            REC IP IENT            COPIES ID -CODE/NAME         LTTR ENCL        ID CODE/NAt<E          LTTR ENCL NRR/DL/ADL                 1    0    NRR  LB3  BC              1      0 NRR L83 LA                 1    0    LICITRAiE ~      01      .1      1 INTERNAL;..ELD/HDS3                       1    0    IE FILE                    .1      1 IE/DEPER/EPB     '36             3    IE/DEPER/I RB 35                  1 IE/DEQA/QAB       21       1          NRR/DE/AEA8                ,1      0 NRR/DE/CEB       11       1    1    NRR/DE/EHEB                1      1 NRR/DE/EQ8       13       2    2    NRR/DE/GB        28        2      2 NRR/DE/HGEB       30       1    1    NRR/DE/MEB        18        1      1 NRR/DE/MTEB       17       1    1    NRR/DE/SAB        24              1 NRR/DE/SGEB       25       2    2    NRR/DHFS/HFE840            1 NRR/DHFS/LQB     32       1    1    NRR/DL/SSP8                1      0 NRR/DS I/AEB     26       1    1    NRR/DS I/ASB                1      1 NRR/DSI/CPB       10       1    1    NRR/DSI/CS8 09            ,1 NRR/DSI/I CSB     16       1    1    NRR/DSI/tlETB 12            1    ~ 1 NRR/DSI/PSB       19             1    N          RAB    22        1      1 NRR/DS I/RSB     23"           1        G F            04        1      1 RGN5                       3    R3      M/DDAMI/MI8              1      0 EXTERNALS ACRS DMB/DSS (At1DTS) 41      .6 1
-WFQ/RJP Director of Nuclear Reactor Regulation Attention:
6 1
Mr.George Knighton, Chief Licensing Branch No.3 Division of Licensing U.S.Nuclear Regulatory Commission Washington, D.C.20555  
BNL(AMDTS ONLY)
FEMA REP     DIV 39 1,1 1     1 LPDR              03      1     1     NRC PDR          02        1     1 NSIC              05      1     1     NTIS                        1     1
~TOTAL NUMBER OF COPIES         REQUIRED: LTTR     54   ENCL     47
 
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Arizona Public Service Company P.O. SOX 21666 ~ 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:==
==Subject:==
Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2 and 3 Docket.Nos.
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
STN-50-528/529/530 File: 83-056-026; G.l.01.10  


==Reference:==
==Reference:==
Letter from  E. E. Van Brunt,        Jr.,  APS,    to H. R. Denton, NRC, dated March 6, 1981.
==Dear Mr. Knighton:==


Letter from E.E.Van Brunt, Jr., APS, to H.R.Denton, NRC, dated March 6, 1981.
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.
Very    truly    your 8304190507 830415                                            E. E. Van Brunt,       Jr.
PDR ADOCK 05000528                                            Vice President, PDR APS Nuclear Projects ANPP  Project Director
                                                                                                ~oo t EEVB/RJP/sP cc:    E. A. Licitra        A. C. Gehr          G. Wermiel (NRC)


==Dear Mr.Knighton:==
M
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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Revision as of 11:23, 29 October 2019

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 DOCKET FACIL:STN-50 528 Palo Ver de Nuclear Stationi Unit 1i Arizona Publi 05000528

'STN 50 529 Palo Verde Nuclear Station< Unit 2r Arizona Publi 05000529 STN 50-530 Palo Verde Nuclear Stationi Uniit 3i Arizona Publi 05000530

'AUTH'AME AUTHOR AFFILIATION VAN BRUNTqE,E. Arizona 'Public Service Co.

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

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.

DISTRIBUTION CODE! 8001S COPIES RECEIVEDSLTR j ENCL SIZE:,

TITLE: Licensing Submittal: PSAR/FSAR Amdts & Related Correspondence NOTES:Standardi'zed plant. 05000528

-Standardized, plant. 05000529 Standardized .plant ~ 05000530 RECIPIENT COPIES REC IP IENT COPIES ID -CODE/NAME LTTR ENCL ID CODE/NAt<E LTTR ENCL NRR/DL/ADL 1 0 NRR LB3 BC 1 0 NRR L83 LA 1 0 LICITRAiE ~ 01 .1 1 INTERNAL;..ELD/HDS3 1 0 IE FILE .1 1 IE/DEPER/EPB '36 3 IE/DEPER/I RB 35 1 IE/DEQA/QAB 21 1 NRR/DE/AEA8 ,1 0 NRR/DE/CEB 11 1 1 NRR/DE/EHEB 1 1 NRR/DE/EQ8 13 2 2 NRR/DE/GB 28 2 2 NRR/DE/HGEB 30 1 1 NRR/DE/MEB 18 1 1 NRR/DE/MTEB 17 1 1 NRR/DE/SAB 24 1 NRR/DE/SGEB 25 2 2 NRR/DHFS/HFE840 1 NRR/DHFS/LQB 32 1 1 NRR/DL/SSP8 1 0 NRR/DS I/AEB 26 1 1 NRR/DS I/ASB 1 1 NRR/DSI/CPB 10 1 1 NRR/DSI/CS8 09 ,1 NRR/DSI/I CSB 16 1 1 NRR/DSI/tlETB 12 1 ~ 1 NRR/DSI/PSB 19 1 N RAB 22 1 1 NRR/DS I/RSB 23" 1 G F 04 1 1 RGN5 3 R3 M/DDAMI/MI8 1 0 EXTERNALS ACRS DMB/DSS (At1DTS) 41 .6 1

6 1

BNL(AMDTS ONLY)

FEMA REP DIV 39 1,1 1 1 LPDR 03 1 1 NRC PDR 02 1 1 NSIC 05 1 1 NTIS 1 1

~TOTAL NUMBER OF COPIES REQUIRED: LTTR 54 ENCL 47

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Arizona Public Service Company P.O. SOX 21666 ~ 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.

Very truly your 8304190507 830415 E. E. Van Brunt, Jr.

PDR ADOCK 05000528 Vice President, PDR APS Nuclear Projects ANPP Project Director

~oo t EEVB/RJP/sP cc: E. A. Licitra A. C. Gehr G. Wermiel (NRC)

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