ML17303A731

Special Rept 3-SR-87-008,on 871217,containment Vessel Structural Integrity Not Verified within Required Time Frame.Caused by Surveillance Test 73ST-32CO1 Not Completed. Containment Vessel Declared Operable on 871218

ML17303A731
Person / Time
Site:	Palo Verde
Issue date:	01/12/1987
From:	Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
192-00335-JGH-T, 192-335-JGH-T, 3-SR-87-008, 3-SR-87-8, NUDOCS 8801190102
Download: ML17303A731 (6)

Text

ACCELERATED IHSIRIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)'CCESSION NBR:8801190192 DOC.DATE: 87/01/12 NOTARIZED: NO DOCKET FACIL:STN-50-530 Palo Verde Nuclear Station, Unit 3, Arizona Publi 05000530 AUTH. NAME AUTHOR AFFILIATION HAYNES,J.G. Arizona Nuclear Power Project (formerly Arizona Public Serv RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Special Rept 3-SR-87-008,on 871217,containment vessel integrity not verified within required time fra e.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL SIZE:

TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.

NOTES:Standardized plant. 05000530t)

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 LICITRA,E 1 1 DAVIS,M 1 1 A

INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DS P/ROAB 2 2 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 1 NRR/DEST/ELB 1 1 NRR/DEST/ICSB 1 1 NRR/DEST/MEB 1 1 NRR/DEST/MTB 1 1 NRR/DEST/PSB 1 1 NRR/DE ST/RS B 1 1 NRR/DEST/SGB 1 1 NRR/DLPQ/HFB 1 1 NRR/DLPQ/QAB 1 1 NRR/DOEA/EAB 1 1 NRR/DRE P/RAB 1 1 NRR/DREP/RPB 2 2

~NRR~RIS/ IB 1 1 NRR/PMAS/ILRB 1 1

~EG FI RE~SDE/EIB 02 1 1 RES TELFORD i J 1 1 1 1 RES/DRPS DIR 1 1 RGN5 FILE 01 1 1 EXTERNAL: EG&G GROH,M 5 5 FORD BLDG HOY i A 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS,J 1 1 NSIC MAYS,G 1 1 NOTES: 1 1 8

A

~n D TOTAL NUMBER OF COPIES REQUIRED: LTTR 48 ENCL 47

Arizona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX, ARIZONA 85072-2034 192-00335-JGH/TDS/JEM January 12, 1987 U.S. Nuclear Regulatory Commission NRC Document Control Desk Washington, D.C. 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 3 Docket No. STN 50-530 (License No. NPF-74)

Special Report 3-SR-87-008 Fi le: 88-020-404 Attached please find Special Report 3-SR-87-008 prepared and submitted pursuant to Technical Specification 3.6. 1.6 Action Statement "a" and 6.9.2.

This report discusses Containment Vessel Structural Integrity.

If you have any questions, please contact T. D. Shriver, Compliance l1anager at (602) 393-2521.

Very truly yours, vxd~~~

J. G. Haynes Vice President Nuclear Production JGH/TDS/JEH/kj Attachment cc: 0. M. DeHichele (all w/a)

E. E. Van Brunt, Jr.

J. B. Hartin J. R. Ball E. A. Licitra A. C. Gehr INPO Records Center 880il90i0> 870ii2 FOR AOOCR 0S0005zo 8 DCD

l PALO VERDE NUCLEAR GENERATING STATION CONTAINMENT VESSEL STRUCTURAL INTEGRITY License No. NPF-74 Docket No. 50-530 Special Report No. 3-SR-87-008 This Special Report is being submitted pursuant to Technical Specification 3.6. 1.6 ACTION "a" and Technical Specification 6.9.2. This reports an event where the containment vessel structural integrity was not verified within the required time frame as specified in Specification 4.6. 1.6.

At 0645 MST on December 17, 1987, Palo Verde Unit 3 was in Mode 3 (HOT STANDBY) when the containment vessel was declared inoperable due to surveillance test 73ST-3ZC01 (Tendon Integrity) not being fully completed.

The surveillance test was performed satisfactorily with the exception of receiving the results of the grease sample analysis.

The grease samples were sent to an approved, out of state laboratory on November 19, 1987. Due to delays at the laboratory the results of the analysis were not received by ANPP until December 18, 1987. Based upon the r eceipt of the satisfactory grease analysis the surveillance test was completed in accordance with Technical Specification 4.6. 1.6.2. In accordance with Technical Specification 3.6. 1.6 ACTION "a", an Engineering Evaluation of the containment vessel structural integrity was performed on December 18, 1987 and determined th'at the structural integrity of the containment was within acceptable limits throughout the event.

At 1830 MST on December 18, 1987, the containment vessel was declared operable. The containment vessel was therefore considered administratively inoperable for 35 hours4.050926e-4 days <br />0.00972 hours <br />5.787037e-5 weeks <br />1.33175e-5 months <br /> and 45 minutes.

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