ML17312B541

Submits Request for Relief from Asme,Section XI & Applicable Addenda for Reactor Exams Involving Unit 1.Requested Relief Would Not Be Used to Credit Exam Completion for Second 10-yr ISI Interval

ML17312B541
Person / Time
Site:	Palo Verde
Issue date:	06/20/1997
From:	LEVINE J M ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
102-03962-JML-A, 102-3962-JML-A, NUDOCS 9707020396
Download: ML17312B541 (10)

Text

CATEGORY 1 REUUIAT(INFORMATION DISTRIBUTION OSTEM iRIDS)ACCESSION NBR:9707020396 DOC.DATE: 97/06/20 NOTARIZED:

NO DOCKET r~5CIL:STN-50-528 Palo Verde Nuclear Station, Unit 1, Arizona Publi 05000528 AUTH.NAME AUTHOR AFFILIATION LEVINE,J.M.

Arizona Public Service Co.(formerly Arizona Nuclear Power RECAP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Submits request for relief from ASME,Section XI&applicable.addenda for reactor exams involving Unit 1.Requested relief would not be used to credit exam completion for second ten yr ISI interval.DISTRIBUTION CODE: A047D COPIES RECEIVED:LTR ENCL<SI'ZE: l TITLE: OR Submittal:

Inservice/Testing/Relief from ASME Code-GL-89-04 NOTES:STANDARDIZED PLANT 05000528 G RECIPIENT ID CODE/NAME PD4-2 LA c THOMASiK COPIES LTTR ENCL 1 1 1 1 RECIPIENT ID CODE/NAME PD4-2 PD COPIES LTTR ENCL 1 1 0 INTERNAL: CENTER 01-'B RES/DET/EIB 1 1 1 1 1 1 1 1 AEOD/SPD/RAB NRR/DE/EMEB OGC/HDS2 RES/DET/EMMEB 1 1 1 1 1 0 1 1 EXTERNAL: LITCO ANDERSON NRC PDR 1 1 1 1 NOAC 1 1 D 0 E NOTE TO ALL MRIDS" RECZPZENTS:

PLEASE HELP US TO REDUCE WASTEI CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT~415"2083)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LZSTS FOR DOCUMENTS YOU DON'T NEEDl TOTAL NUMBER OF COPIES REQUIRED: LTTR 14 ENCL 13 FI Commitmont.

Innorntlnn.

Eaertty, Palo Verde Nuclear Generating Station James M.Levine Senior Vice President Nuclear TEL (602)3934300 FAX (602)3936077 Mail Station 7602 P.O.Box 52034 Phoenix, AZ 65072-2034 102-03962-JML/AKK/RKB June 20, 1997 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Mail Station P1-37 Washington, DC 20555-0001

Subject:

Palo Verde Nuclear Generating Station (PVNGS)Unit 1 Docket No.STN 50-528 First Inservice Inspection Interval-(Relief Request No.10)Pursuant to 10 CFR 50.55a (a)(3), enclosed please find a request for relief from American Society of Mechanical Engineers (ASME),Section XI, and applicable addenda, for reactor vessel exams involving PVNGS Unit 1.Relief is requested to delay the first ten year interval Inservice Inspection (ISI)reactor vessel exams to the eighth refueling outage, scheduled for September 18, 1999, which falls within period one of the second ten year ISI interval.This request results in an extension of approximately 110 days beyond the ASME code allowable one year extension period.The requested relief would not be used to credit exam completion for the second ten year ISI interval.Your review of the enclosed relief request prior to January 22, 1998 is requested to facilitate adequate planning prior to the start of the Unit 1 Cycle 7 Refueling Outage, scheduled for March 22, 1998.Should you have any questions, please contact Scott A.Bauer at (602)393-5978.Sincerely, JML/AKK/RKB/mah Enclosure cc: E.W.Merschoff K.E.Perkins J.W.Clifford F.L.Brush 9707020396 970620 PDR ADOCK 05000528 8'DR llllllf(fllllllflflllllllllf illlllllllll,++7

'I I I li J ENCLOSURE ASME SECTION XI RELIEF REQUEST NO.10

ASME Section XI Relief Request No.10 First Ten Year Inservice Inspection Interval Palo Verde Nuclear Generating Station, Unit 1 Reference Code: ASME Section XI, 1980 Edition including Winter 1981 Addenda I.Components for which Relief is Requested:

Component or Item Code Class Program Table Code Itesn Examen Category Pressure Retaining Welds In Reactor Vessel Full Penetration Welds of Nozzles in Vessel Interior of Reactor Vessel Interior Attachments to Reactor Vessel Removable Core Support Structures 1-3 1-13 1-13 1-13 81.00 83.00 813.00 813.00 813.00 8-A 8-D 8-N-1 8-N-2 8-N-3 II.Reference Code Requirement:

The required examinations shall have been completed during each successive inspection interval in accordance with Table IWB-2412-1.The inspection period specified may be decreased or extended by as much as one year to enable an inspection to coincide with a plant outage, within the limits of IWA-2400(c).III.Basis for Requested Relief: The last scheduled Unit One refueling outage which falls within the first ten year ISI interval is the Unit One Cycle Seven Refueling Outage (U1R7), which is to begin March 22, 1998.Currently, the first ten year interval reactor vessel ISI exams are scheduled during this outage.There are, however, a number of emergent maintenance activities which need to be performed during this outage including reactor coolant pump shaft replacements and full station battery replacement.

Therefore, to balance major maintenance activities between refueling outages, Arizona Public Service Company proposes to move the reactor vessel ISI to the Unit One Cycle 8 (U1R8)outage scheduled for the fall of 1999.In accordance with 10CFR50.55a (a)(3)(i), the Alternative Examination proposed by APS, in conjunction with the review of data from the Units 2 and 3 examinations, provides an adequate level of safety and quality.

IV.Alternative Examination:

This relief request is for the deferral of, not the exemption from, the code examination requirements.

The one year extension period allowed for the examination by the ASME Code ends on July 17, 1999 and U1R8 is currently scheduled from September 18, 1999 to November 7, 1999.Thus, performing the first ten year interval ISI reactor vessel examinations during U1R8 would delay the exams by approximately 110 days beyond the ASME Code allowable one year extension.

This relief request applies specifically to the first ten year ISI interval, no credit is being taken for these exams in the second ten year ISI interval.The first ten year ISI interval reactor vessel inspections for Units 2 and 3 will be completed during the scheduled Fall 1997 and Fall 1998 Refueling Outages, respectively.

Data collected during these examinations will provide for an assessment of the condition of the Unit 1 reactor vessel since the three reactor vessels are of the same material and design.Should relief be granted, its use will be re-evaluated against indications from Unit 2 inspection data.V.Implementation Schedule: The ASME Code examinations for the first ten year ISI interval reactor vessel exams will be conducted during U1R8 Refueling Outage scheduled to begin September 18, 1999.

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