IR 05000528/1994012

Revises Commitment Conpletion Date & Date of Full Compliance for Notice of Violation from Insp Repts 50-528/94-12, 50-529/94-12 & 50-530/94-12 to 941130

ML17311A436
Person / Time
Site:	Palo Verde
Issue date:	11/21/1994
From:	Stewart W ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
102-03185-WLS-A, 102-3185-WLS-A, NUDOCS 9412050088
Download: ML17311A436 (6)

Text

(I't L AWAMlXI J.I I I (ACCI'.LI'.RATED Ikll)S I'ICOCI:.SSIX REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ESSION'BR:9412050088 DOC.DATE: 94/11/21 NOTARIZED-NO DOCKET N IL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 STN-50-529 Palo Verde Nuclear Station, Unit 2i Arizona Publi 05000529 STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH.NAME AUTHOR AFFILIATION STEWART,W.L.

Arizona Public Service Co.(formerly Arizona Nuclear Power RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)SUBJECT: Revises commitment conpletion date&date of full compliance for notice of violation from insp repts 50-528/94-12, 50-529/94-12

&50-530/94-12 to 941130.DISTRIBUTION CODE: IEOID COPIES RECEIVED:LTR ENCL 0 SIZE: 2 TITLE: General (50 Dkt)-Insp Rept/Notice of Vio ation Response NOTES:STANDARDIZED PLANT Standardized plant.Standardized plant.RECIPIENT ID CODE/NAME PD4-2 PD TRAN,L INTERNAL: ACRS AEOD/SPD/RAB OD/~C LE C,El~TER 02 NRR/DRCH/HHFB NUDOCS-ABSTRACT OGC/HDS2 EXTERNAL L I TCO BRYCE i J H NRC PDR COPIES LTTR ENCL RECIPIENT ID CODE/NAME HOLIAN, B AEOD/DEIB AEOD/SPD/RRAB DEDRO NRR/DORS/OEAB NRR/PMAS/IRCB-E OE DIR RGN4 FILE 01 NOAC COPIES LTTR ENCL 05000528 05000529 I 05000530 T D 0 U NO'I'E TO AI.L"RIDS" RECIPIENT I': PLE:KSE IIEI.P l'S IO REDL'CE KKS'fE!COSTA(f'l'IIE DOCI.'iffLi'I'COiTROI.

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5N-2083)IO l:.LI 1IIXAI'I YOI.R X'AifE I ROTI DISTRI III."I'IOi'.IS'I'S I'OR DOCl if I'.i'I'S Y()l.')Oi"II:I'.D'.

TAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL~0 0 I Arizona Public Service Company~0 BOX 53999~>HOEVI'Y ARIzONA 555 2 3999 WILLIAM L STEWART EXECU'IIVE

/ICE+RESIDE'.JI hUClEAR 102-031 85-WLS/AKK/DLK November 21, 1994 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555 Reference:

Letter 102-03091, dated August 23, 1994, W.L Stewart, APS, to U.S.Nuclear Regulatory Commission, Document Control Desk,"Reply to Notice of Violations 50-528/529/530/94-12-01, 50-530/94-12-03, 50-530/94-12-04, and 50-528/529/530/94-12-05"

Dear Mr.Gwynn:

Subject: Palo Verde Nuclear Generating Station (PVNGS)Units',2, and 3 Docket Nos.STN 50-528/529/530 Revised Commitment Completion Date and Date of Full Compliance for Notice of Vlolatlon (NOV)50-528/529/530/94-12%5 File: 94-076426 On August 23, 1994, Arizona Public Service Company (APS)provided the referenced letter in response to NOV 50-528/529/530/94-12-05.

In the sections titled"Corrective Actions That Will Be Taken To Avoid Further Violations" and"Date When Full Compliance Will Be Achieved" (on pages 17 and 18)APS committed to revise the 10 CFR 50.59 evaluations for the auxiliary feedwater pump steam admission valves (SGA-UV0134 and SGA-UV01 38)and achieve full compliance by September 13, 1994.Prior to September 13, 1994, APS recognized that the committed-to date would not be met.On September 10, 1994, APS telephoned Mr.Bradley Olson of the Region IV Walnut Creek Field Office to inform the NRC that the commitment date would not be met.APS agreed to provide this foltowup letter revising the corrective action completion date and the date of full compliance.

The 10 CFR 50.59 discussed above will be revised and full compliance will be achieved by November 30, 1994.The revision to the original 10 CFR 50.59 was delayed when a separate but related safety evaluation discovered a problem with an emergency operating procedure that depressurized the secondary on a Large Break Loss Of Coolant Accident (LOCA).No data or analysis was available that addressed the off-site dose impact of any radioactive release from the secondary side due to a fuel failure with the primary (which in the case of a LOCA would include the containment building)being at a potentially higher pressure than the secondary.

This scenario needed to be evaluated prior to completing the 9412050088 cII41121 PDR ADQCK 05000528 PDR gQ()i'

'

U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Page 2 revision to the 10 CFR 50.59 associated with auxiliary feedwater pump steam admission valves.Should you have any questions, please contact Angela Krainik at (602)393-5421.

Sincerely, WLS/AKK/DLK/pv cc: L.J.Callan K.E.Perkins B.E.Holian K.E.Johnston I