ML17304A790

Special Rept 23-SR-88-008:on 881108,7 Day Limit for Inoperability of Post Accident Sampling Sys Exceeded.Caused by Inadequate Flow Measuring Unit.Inlet Isolation Valve Reinstalled

ML17304A790
Person / Time
Site:	Palo Verde
Issue date:	12/06/1988
From:	Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
192-00436-JGH, 192-436-JGH, 23-SR-88-008, 23-SR-88-8, NUDOCS 8812130306
Download: ML17304A790 (6)

Text

1 ACCELERATED DIS1%BUTION DEMONSTRk ION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8812130306 DOC.DATE: 88/12/06 NOTARIZED: NO DOCKET FACIL:STN-50-529 Palo Verde Nuclear Station, Unit 2, Arizona Publi 05000529 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 23-SR-88-008:on 881108 7 day limit for inoperability of post accident sampling sys exceeded.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR I ENCL TITLE: 50.73 Licensee Event Report (LER), Incident Rpt, etc.. 2 SIZE:

NOTES:Standardized plant. 05000529 ~

8 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 '1 PD5 PD 1 1 CHAN,T 1 1 DAVIS,M 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DS P 1 1 ARM/DCTS/ DAB 1 1 DEDRO 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB 8H 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB 8D 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D NRR/DLPQ/QAB 10 NRR/DREP/RAB 10 1

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Arizona Nuclear Power Project P.O. BOX 82034 ~ PHOENIX. ARIZONA85072-2034 192-00436-JGH/TDS/JEM December 6, 1988 U. S. Nuclear Regulatory Commission NRC Document Control Desk Washington, D.C. 20555

Dear Sirs:

'ubject:

Palo Verde Nuclear Generating Station (PVNGS)

Unit 2 Docket No. STN 50-529 (License No. NPF-51)

Special Report 2-SR-88-008 File: 88-020-404 Attached please find Special Report 2-SR-88-008 prepared and submitted pursuant to Technical Specifications 3.3.3. 1 and 6.9.2. This report discusses the Post Accident Sampling System being inoperable for greater than 7 days.

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

Very trul yours, P4i J. G. Haynes Vice President Nuclear Production JGH/TDS/JEM/kj Attachment cc: D. B. Karner (all w/a)

E. E. Van Brunt, Jr.

J. B. Martin T. J. Polich M. J. Davis A. C. Gehr INPO Records Center

~@z 8812130306 881206 PDR ADOCK 05000529 IP 8 PDC

I' LO VERDE NUCLEAR GENERATING S ION PASS INOPERABLE FOR GREATER THAN 7 DAYS License No. NPF-51 Docket No. 50-529 Special Report 2-SR-88-008 This Special Report is being submitted in accordance with Technical Specifications 3.3.3. 1 ACTION 28-2 and 6.9.2 to report an event in which the Post Accident Sampling System (PASS) was inoperable for a period greater than 7 days. The 7 day limit for inoperability was exceeded at approximately 0900 MST on November 8, 1988.

At approximately 0900 HST on November 1, 1988, Palo Verde Unit 2 was in Mode 1 (POWER OPERATION) at 100 percent power when PASS was declared inoperable to perform an authorized Preventative Maintenance Work Order (PHWO) to calibrate the PASS gas sample flow loop. In accordance with Technical Specification 3.3.3. 1 ACTION 28-1 the Preplanned Alternate Sampling Program was initiated at 0725 HST on November 8, 1988.

During performance of the PHWO the PASS Gas Sample Flow Transmitter (FT-52) as found data was unsatisfactory and appeared to be non-linear. All attempts to calibrate FT-52 were unsuccessful. A new flow measuring unit was obtained'rom the warehouse. The new flow measuring unit had the signal conditioner attached to the flow. element (FE) wher eas the old flow measuring unit had the signal conditioner in a local panel which is approximately 6 feet from the FE. The flow measuring unit is first bench calibrated before placing it into the system. Calibration of FT-52 could not be successfully performed with the new flow measuring unit. The flow measuring unit was then sent to the vendor for adaption to current plant design and calibration. Upon receipt of the flow loop system from the vendor, it was installed in accordance with an approved work order. The PH was then completed satisfactorily at 1530 HST on November 7, 1988.

During performance of the operating procedure, to verify that adequate containment sample flow could be established, it was determined that the containment sample flow would not meet the requirements of the surveillance test. An authorized work order to troubleshoot rework/replace components to correct the low flow condition was initiated. Troubleshooting in accordance with the work order identified air leaks at various fittings. Fittings were either tightened or replaced as necessary. During troubleshooting, inlet isolation valve (V-56) for the local atmospheric sample was removed and then reinstalled. During the reinstallation, the tightness of the mounting bolts caused V-56 to be slightly misaligned preventing the valve from opening completely. The valve was reinstalled with close attention to detail in tightening the mounting bolts. Valve V-56 then operated smoothly and sufficient sample flow was achieved.

The appropriate surveillance test (74ST-2SS04) was performed satisfactorily and PASS was returned to an operable status at 0935 HST on November 23, 1988.

PASS was inoperable for approximately 22 days.