ML17303A696

Special Rept 2-SR-87-028:on 871014,post-accident Sampling Sys (PASS) Inoperable Due to Radioactive Water Leak.Caused by Leakage Through PASS Sample Isolation Valve.Pass Sample Isolation Valve & Liquid Septum Replaced

ML17303A696
Person / Time
Site:	Palo Verde
Issue date:	11/18/1987
From:	Haynes J ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
192-00314-JGH-T, 192-314-JGH-T, 2-SR-87-028, 2-SR-87-28, NUDOCS 8711250185
Download: ML17303A696 (3)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR: 8711250185 DOC. DATE: 87/11/18 NOTARIZED: NO DOCKET F*CIL: STN-50-529 Palo Verde Nuc lear Stations Unit 2> Ari zona Pub AUTH. NAME AUTHOR AFFILIATION li 05000529 HAYNES'. G. Arizona Nuclear Power Prospect (formerly Arizona Public Serv RECIP. NAME RECIPIENT AFFILlATION Document Control Branch (Document Control Desk)

SUBJECT:

RO 2-SR-87-028: on 871014'ost-accident sampling sos (PASS) inoperable due to small leak of radioactive water. Caused bg leakage through PASS sample isolation valve. PASS sample isolation valve 5 liquid septum replaced.

DISTRIBUTION CODE: IE22D COPIES RECEIVED: LTR I ENCL J TITLE: 50. 73 Licensee Event Report (LER)i Incident Rpti SIZE:

etc.

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NOTES: Standardi zed plant. 0500052'7 RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD f 1 LICITRAiE 1 1 DAVIS' 1 INTERNAL: *CRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEOD/DSP/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 DEDRO 1 NRR/DEST/ADS 1 0 NRR/DEST/CEB 1 f 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/DEST/RSB 1 1 NRR/DEST/SGB 1 1 NRR/DLPG/HFB 1 1 NRR/DLPG/GAB 1 1 NRR/DOEA/EAB 1 '1 NRR/DREP/RAB NRR/

EG 8/SIB ILE 02 1

1 1

1 1

f NRR/DREP/RPB NRR/PMAS/ILRB RES DEPY GI 1,

2 1

2 1

1 FORDS J 1 1 RES/DE/EIB 1 1 RGN5 FILE 01 1 1 EXTERNAL: EG8cG GROH M 5 5 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS' f 1 NSIC MAYS> G ~ 1 NOTES:

TOTAL NUMBER OF COPIES REQUIRED: LTTR 47 ENCL 46

Arizona Nuclear Power Project P.O. BOX 52034 ~ PHOENIX. ARIZONA85072-2034 192-00314- JGH/TRB/KCP November 18, 1987 U.S. Nuclear Regulatory Commission NRC Document Control Desk Washington, D.C. 20555

Subject:

Palo Verde Nuclear Generating Station (PVNGS)

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

Special Report 2-SR-87-028 Fi 1 e: 87-020-404 Attached please find Special Report 2-SR-87-028 prepared and submitted pursuant to Technical Specifications 3.3.3. I and 6.9.2. This report discusses an event in which the Post Accident Sampling System (PASS) was inoperable for greater than 7 days.

If you have any questions, please contact T. R . Bzadish, Compl.iance .Lead at (602) 393-3531.

Very truly. yours, J. G. Haynes Vice Presi'dent Nuclear Production JGH/TRB/JEN/kj Attachment cc: 0. H. Dewichele (all w/a)

E. E. Van Brunt, Jr.

J. B. l1artin J. R. Ball E. A. Licitra A. C. Gehr INPO Records Center 87 i f +50185 87i~ii85~q PDR ADOCK 05000529'

PALO VERDE NUCLEAR GENERATING STATION PASS INOPERABLE FOR GREATER TMAN 7 DAYS License No. NPF-51 Docket No. 50-529 Special Report 2-SR-87-028 This Special Report is being submitted in accordance with Technical Specifications 3.3.3. ACTION 28(2) and 6.9.2 to report an event in which the 1

Post Accident Sampling System (PASS) was inoperable for a period greater than 7 days. The 7 day limit for inoperability was exceeded at approximately 1000 MST on October 21, 1987.

At approximately 1000 MST on October 14, 1987, Palo Verde Unit 2 was in Mode 1.

.(POWER OPERATION) at 100 percent power when PASS was declared inoperab1e due to a small leak of radioactive water coming from behind the shield bricks in the PASS sample area.

Subsequent investigation revealed that the PASS liquid septum was seeping radioactive water due to leakage through a PASS samp'1e isolation valve located on the 76 foot elevation of the Auxiliary Building in the West Wrap Around Room. This leakage was due to leakage from the Reactor Coolant System through 2 nuclear sampling system isolation valves, at a leak rate of approximately 100 ml/min. Due to the location of the Nuclear Sampling System isolation-"

valyes (2JSSBUV200 and 2JSSAU$ 0203) corrective action to evaluate and- rework

" or replace these valves will be performed during a scheduled outage. This leakage is within the-allowable leakage permitted under the Technical Specifications.

As immediate corrective action, the PASS sample isolation valve and the liquid septum were replaced and functionally tested to verify that the leak was stopped. This work was completed on October 19, 1987, however additional time was required to properly restack the lead brick shielding for the PASS hot sample sink area prior to declaring the system operable. At 1000 MST, October 21, 1987 the 7 day limit for inoperability was exceeded and the Pre-planned Alternate Sampling System was initiated per T.S. 3.3.3.1 ACTION 28(1).

PASS was.declared operable at approximately 1409 MST on October 26, 1987, following satisfactory testing in accordance with 74ST-2SS04, "PASS FUNCTIONAL Test." The duration of this event was approximately 12 days.