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| issue date = 06/09/1988
| issue date = 06/09/1988
| title = Forwards Justification for Continued Operation of Auxiliary Feedwater Pump.Continued Operation of Plant Does Not Pose Undue Risk Based on Listed Considerations
| title = Forwards Justification for Continued Operation of Auxiliary Feedwater Pump.Continued Operation of Plant Does Not Pose Undue Risk Based on Listed Considerations
| author name = VAN BRUNT E E
| author name = Van Brunt E
| author affiliation = ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
| author affiliation = ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
| addressee name =  
| addressee name =  
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:REGULAT'NFORMATION DISTRIBUTION
{{#Wiki_filter:REGULAT     'NFORMATION DISTRIBUTION 'TEM (RIDS) ly ACCESSION NBR: 8806220134           DOC. DATE: 88/06/09   NOTARIZED: NQ         DOCKET FACIL: STN-50-528 Palo Verde Nuclear Stations           Unit ii Arizona Pub li 05000528 STN-50-529 Palo Verde Nuclear Stations           Unit 2i Arizona Publi 05000529 STN-50-530 Palo Ver de Nuclear Stations AUTH. NAME              AUTHOR AFFILIATION Uni t 3i Arizona Pub li   05000530 VAN BRUNTi E. E.       Arizona Nuclear Poujer ProJect     (formerly Arizona P ub lic Serv RECIP. NAME             RECIPIENT AFFlLIATIQN Document Control Branch     (Document Control Desk )
'TEM (RIDS)ly ACCESSION NBR: 8806220134 DOC.DATE: 88/06/09 NOTARIZED:
NQ FACIL: STN-50-528 Palo Verde Nuclear Stations Unit ii Arizona Pub li STN-50-529 Palo Verde Nuclear Stations Unit 2i Arizona Publi STN-50-530 Palo Ver de Nuclear Stations Uni t 3i Arizona Pub li AUTH.NAME AUTHOR AFFILIATION VAN BRUNTi E.E.Arizona Nuclear Poujer ProJect (formerly Arizona P RECIP.NAME RECIPIENT AFFlLIATIQN Document Control Branch (Document Control Desk DOCKET 05000528 05000529 05000530 ub lic Serv)


==SUBJECT:==
==SUBJECT:==
Forwards Justification for continued operation of auxiliary feedujater pump.Continued operation of plant does not pose undue risk based on listed considerations.
Forwards Justification for continued operation of auxiliary feedujater pump. Continued operation of plant does not pose undue   risk     based on   listed considerations.
DIBTRIBUTION CODE:*OOID DOPIER RECEIVED: LTR J ENCL Q SIZE: TITLE: OR Submittal:
DIBTRIBUTION CODE: *OOID           DOPIER RECEIVED: LTR   J   ENCL Q SIZE:
General Distribution NOTES: Standardized plant.Stand ar d i z e d p lant.Standardi zed plant.05000528 05000529 05000530 RECIPIENT ID CODE/NAME PD5 LA LICITRAz E INTERNAL: ACR 8 NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/RSB 8E NRR/PMAS/ILRB12 QGC 15-B-18 RES/DE/EIB EXTERNAL: LPDR NSIC COPIES LTTR ENCL 1 0 1 1 6 6 1 1 1 1 1 1 1 1 0 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD5 PD DAVIS>M ARM/DAF/LFMB NRR/DEST/CEB 8H NRR/DEST/MTB 9H NRR/DOEA/TSB 11 NUDO-TRACT FIL 01 NRC PDR COPIES LTTR ENCL 5 5 1 1 1 0 1 1 1 1 1 1 1 1 1 1 1 1 NOTES: TOTAL NUMBER OF CQP IES REQUIRED: LTTR 30 ENCL 27 lQ I 4 P (1 Arizona Nuclear Power Project P.O.BOX 52034~PHOENIX.ARIZONA 85072-2034 Docket Nos.STN 50-528/529/530 161-01094-EEVB/BJA June 9, 1988 Document Control Desk U.S.Nuclear Regulatory Commission Hail Station Pl-137 Washington, D.C.20555  
TITLE: OR Submittal: General Distribution NOTES: Standardized plant.                                                         05000528 Stand ar d i z e d p lant.                                                 05000529 Standardi zed plant.                                                       05000530 RECIPIENT             COPIES            RECIPIENT        COPIES ID CODE/NAME           LTTR ENCL      ID CODE/NAME      LTTR ENCL PD5 LA                     1      0    PD5 PD                5    5 LICITRAz E                   1      1    DAVIS> M              1    1 INTERNAL: ACR 8                         6      6    ARM/DAF/LFMB          1    0 NRR/DEST/ADS 7E             1      1    NRR/DEST/CEB 8H      1    1 NRR/DEST/ESB 8D             1      1    NRR/DEST/MTB 9H      1    1 NRR/DEST/RSB 8E             1      1    NRR/DOEA/TSB 11      1    1 NRR/PMAS/ILRB12             1      1    NUDO      TRACT    1    1 QGC 15-B-18                       0        FIL      01    1    1 RES/DE/EIB                 1      1 EXTERNAL: LPDR                           1     1   NRC PDR               1     1 NSIC                        1     1 NOTES:
TOTAL NUMBER OF CQP IES REQUIRED: LTTR             30   ENCL   27
 
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Arizona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX. ARIZONA85072-2034 161-01094-EEVB/BJA June 9, 1988 Docket Nos. STN 50-528/529/530 Document Control Desk U. S. Nuclear Regulatory Commission Hail Station Pl-137 Washington, D.C.       20555


==Reference:==
==Reference:==
 
Letter from J.     G. Haynes,     ANPP,   to USNRC Document Control Desk dated June 3, 1988 (192-00379).            
Letter from J.G.Haynes, ANPP, to USNRC Document Control Desk dated June 3, 1988 (192-00379).


==Subject:==
==Subject:==
Licensee Event Report 88-013-00.
Licensee Event Report 88-013-00.


==Dear Sirs:==
==Dear Sirs:==
Subj ect: Palo Verde Nuclear Generating Station (PVNGS)Units 1, 2, and 3 Auxiliary Feedwater Pumps-Justification for Continued Operation File: 88-A-056-026 The NRC was notified by telephone call on June 3, 1988, that ANPP had determined that the recent Auxiliary Feedwater (AFW)pump degradation event was considered to be reportable under 10CFR21.The event was characterized by the loss of the pump's fourth stage impeller and was detected during surveillance testing.Subsequent to the telephone notification, NRC Region V requested that ANPP provide a Justification for Continued Operation (JCO)to address the AFW pump problems.The requested JCO is provided as an attachment to this letter.To summarize the material presented in the attached JCO, ANPP believes that the continued operation of the PVNGS units does not pose an undue risk based on the following considerations:
 
i)Calculations have shown that the reduced AFW pump flow (caused by the potential loss of a fourth stage impeller)is sufficient, to meet safety analysis requirements for decay heat removal.ii)To correct the cause of the AFW pump degradations that have been experienced, ANPP will pursue the rework of the pump's rotating elements in an expeditious manner.The primary constraint in the rotating element rework is the pump vendor's capabilities to support the effort.iii)For the interim period, AFW system reliability is not significantly degraded by this pump design deficiency due to the extremely low probabi.lity that this event would occur simultaneously in all three pump trains.8806220134 880609 PDR ADOCK 05000528 P PDR.
Subj ect:     Palo Verde Nuclear Generating Station (PVNGS)
I IQ ii f P Document Control Desk Page 2 161-01094-EEVB/BJA June 9, 1988 If you have any additi.'onal questions on this matter, please contact Mr.A.C.Rogers at (602)371-404l.Very truly yours, EEVB/B JA/j le Attachment E.E.Van Brunt, Jr.Executive Vice President Project Director cc: J.B.'Martin T.J.Polich G.W.Knighton M.J.Davis A.C.Gehr (all w/a) 0 4k I'}}
Units 1, 2,     and   3 Auxiliary Feedwater Pumps         - Justification for Continued Operation File: 88-A-056-026 The   NRC was     notified by telephone call on June 3, 1988, that ANPP had determined that the recent Auxiliary Feedwater (AFW) pump degradation event was considered to be reportable under 10CFR21.                   The event was characterized by the loss of the pump's fourth stage impeller and was detected during surveillance testing.           Subsequent to the telephone notification, NRC Region V requested that ANPP provide a Justification for Continued Operation (JCO) to address     the AFW pump problems. The requested JCO is provided as an attachment to this   letter.
To summarize     the material presented in the attached JCO, ANPP believes that the   continued operation of the PVNGS units does not pose an undue risk based on the following considerations:
i)   Calculations have shown that the reduced AFW pump flow (caused by the potential loss of a fourth stage impeller) is sufficient, to meet safety analysis requirements for decay heat removal.
ii)   To correct the cause of the AFW pump degradations that have been experienced,       ANPP will pursue           the rework of the pump's rotating elements in an expeditious manner. The primary constraint in the rotating element rework is the pump vendor's capabilities to support the effort.
iii)   For the interim period, AFW system reliability is not significantly degraded by this pump design deficiency due to the extremely low probabi.lity that this event would occur simultaneously in all three pump trains.
8806220134 880609 PDR   ADOCK 05000528 P                     PDR.
 
I IQ ii P f
 
Document Control Desk                             161-01094-EEVB/BJA Page 2                                            June 9, 1988 If   you have any additi.'onal questions on this matter,     please contact Mr. A. C. Rogers at (602) 371-404l.
Very truly yours, E. E. Van Brunt, Jr.
Executive Vice President Project Director EEVB/BJA/j le Attachment cc:   J. B. 'Martin     (all w/a)
T. J. Polich G. W. Knighton M. J. Davis A. C. Gehr
 
0 4k I'}}

Latest revision as of 10:52, 29 October 2019

Forwards Justification for Continued Operation of Auxiliary Feedwater Pump.Continued Operation of Plant Does Not Pose Undue Risk Based on Listed Considerations
ML17304A217
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 06/09/1988
From: Van Brunt E
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
Shared Package
ML17304A218 List:
References
REF-PT21-88 161-01094-EEVB, 161-1094-EEVB, NUDOCS 8806220134
Download: ML17304A217 (6)
v • d • e


Text

REGULAT 'NFORMATION DISTRIBUTION 'TEM (RIDS) ly ACCESSION NBR: 8806220134 DOC. DATE: 88/06/09 NOTARIZED: NQ DOCKET FACIL: STN-50-528 Palo Verde Nuclear Stations Unit ii Arizona Pub li 05000528 STN-50-529 Palo Verde Nuclear Stations Unit 2i Arizona Publi 05000529 STN-50-530 Palo Ver de Nuclear Stations AUTH. NAME AUTHOR AFFILIATION Uni t 3i Arizona Pub li 05000530 VAN BRUNTi E. E. Arizona Nuclear Poujer ProJect (formerly Arizona P ub lic Serv RECIP. NAME RECIPIENT AFFlLIATIQN Document Control Branch (Document Control Desk )

SUBJECT:

Forwards Justification for continued operation of auxiliary feedujater pump. Continued operation of plant does not pose undue risk based on listed considerations.

DIBTRIBUTION CODE: *OOID DOPIER RECEIVED: LTR J ENCL Q SIZE:

TITLE: OR Submittal: General Distribution NOTES: Standardized plant. 05000528 Stand ar d i z e d p lant. 05000529 Standardi zed plant. 05000530 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 0 PD5 PD 5 5 LICITRAz E 1 1 DAVIS> M 1 1 INTERNAL: ACR 8 6 6 ARM/DAF/LFMB 1 0 NRR/DEST/ADS 7E 1 1 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/RSB 8E 1 1 NRR/DOEA/TSB 11 1 1 NRR/PMAS/ILRB12 1 1 NUDO TRACT 1 1 QGC 15-B-18 0 FIL 01 1 1 RES/DE/EIB 1 1 EXTERNAL: LPDR 1 1 NRC PDR 1 1 NSIC 1 1 NOTES:

TOTAL NUMBER OF CQP IES REQUIRED: LTTR 30 ENCL 27

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Arizona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX. ARIZONA85072-2034 161-01094-EEVB/BJA June 9, 1988 Docket Nos. STN 50-528/529/530 Document Control Desk U. S. Nuclear Regulatory Commission Hail Station Pl-137 Washington, D.C. 20555

Reference:

Letter from J. G. Haynes, ANPP, to USNRC Document Control Desk dated June 3, 1988 (192-00379).

Subject:

Licensee Event Report 88-013-00.

Dear Sirs:

Subj ect: Palo Verde Nuclear Generating Station (PVNGS)

Units 1, 2, and 3 Auxiliary Feedwater Pumps - Justification for Continued Operation File: 88-A-056-026 The NRC was notified by telephone call on June 3, 1988, that ANPP had determined that the recent Auxiliary Feedwater (AFW) pump degradation event was considered to be reportable under 10CFR21. The event was characterized by the loss of the pump's fourth stage impeller and was detected during surveillance testing. Subsequent to the telephone notification, NRC Region V requested that ANPP provide a Justification for Continued Operation (JCO) to address the AFW pump problems. The requested JCO is provided as an attachment to this letter.

To summarize the material presented in the attached JCO, ANPP believes that the continued operation of the PVNGS units does not pose an undue risk based on the following considerations:

i) Calculations have shown that the reduced AFW pump flow (caused by the potential loss of a fourth stage impeller) is sufficient, to meet safety analysis requirements for decay heat removal.

ii) To correct the cause of the AFW pump degradations that have been experienced, ANPP will pursue the rework of the pump's rotating elements in an expeditious manner. The primary constraint in the rotating element rework is the pump vendor's capabilities to support the effort.

iii) For the interim period, AFW system reliability is not significantly degraded by this pump design deficiency due to the extremely low probabi.lity that this event would occur simultaneously in all three pump trains.

8806220134 880609 PDR ADOCK 05000528 P PDR.

I IQ ii P f

Document Control Desk 161-01094-EEVB/BJA Page 2 June 9, 1988 If you have any additi.'onal questions on this matter, please contact Mr. A. C. Rogers at (602) 371-404l.

Very truly yours, E. E. Van Brunt, Jr.

Executive Vice President Project Director EEVB/BJA/j le Attachment cc: J. B. 'Martin (all w/a)

T. J. Polich G. W. Knighton M. J. Davis A. C. Gehr

0 4k I'

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