ML17285A733

Special Rept:On 890821,leakage Discovered in post-accident Sampling Sys Containment Valves When in Closed Position. Maint Work Requests Prepared to Repair post-accident Sampling Sys Containment Isolation Valves

ML17285A733
Person / Time
Site:	Columbia
Issue date:	09/14/1989
From:	POWERS C M WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	MARTIN J B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
NUDOCS 8909250014
Download: ML17285A733 (6)

Text

<CCELERATED DlgR1BU'TlON DEMONST+TlON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8909250014 DOC.DATE: 89/09/14.NOTARIZED:

NO FACIAL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe AUTH.NAME AUTHOR AFFILIATION POWERS,C.M.

Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION MARTIN,J.B.

Region 5, Ofc of the Director

SUBJECT:

Special rept:on 890821,post-accident sampling primary coolant radiation monitor.DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR J ENCL/SIZE'TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: DOCKET I 05000397 I R'D'RECIPIENT ID CODE/NAME PD5 LA SAMWORTH,R COPIES LTTR EN 1 1 CL RECIPIENT ID CODE/NAME PD5 PD COPIES LTTR ENCL INTERNAL: ACRS MICHELSON ACRS WYLIE AEOD/DSP/TPAB DEDRO NRR/DEST/CEB 8H NRR/DEST/ICSB 7 NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NUDOCS-ABSTRACT RES/DSIR/EIB EXTERNAL: EG&G WILLIAMS,S LPDR NSIC MAYS,G NUDOCS FULL TXT NOZE'IO ALLRIBS" RECIPIIRIS:

ACRS MOELLER AEOD/DOA AEOD/ROAB/DSP

" IRM/DCTS/DAB NRR/DEST/ESB 8D NRR/DEST/MEB 9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/PEB 10 NRRtBBB RPB 10 EG FILE 02 RGN5 LE Ol L ST LOBBY WARD NRC PDR NSIC MURPHYIG~A 8 I D D D S PIZASE HELP US'IO REEVE HASTE!CGHIMT'IHE DOI.'X3KKI'KNIBOL DESK, RXM Pl-37 (EXT.20079)K)EEiZKMQR KXK NAKE FR%DIBTRZBUZICN TOTAL NUMBER%PVOVRP%+%%8P

%M%5 ENCL~0

WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.o.Box 968~3000 George Washington Way~Richland, Washington 99352 Docket No.50-397 September 14, 1989 V Mr.J.8.Hartin Regional Administrator USNRC, Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596

Subject:

NUCLEAR PLANT NO.2 LICENSE NO.NPF-21 SPECIAL REPORT: POST-ACCIDENT SAMPLING PRIMARY COOLANT RADIATION MONITOR This special report is submitted pursuant to the requirements of WNP-2 Tech-nicall Specification Table 3.3.7.5-1 (Instrument

'o.29: Post-Accident Sampling Primary Coolant Radiation Monitor), Action Statement 81.Action Statement 81 requires","with the number of operable accident monitoring instrumentation channels less than required by the minimum channels operable requirement,, either restore the inoperable channel(s) to operable status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or: (a)Initiate the preplanned alternate method of monitoring the appropriate parameter(s), and (b)In lieu of any other report required by Specification

6.9.1 prepare

and submit a Special Report to the commission pursuant to Specification

6.9.2 within

14 days following the event outlining the'ction taken, the cause of.the inoperability and the plans and schedule for restoring the system to operable status."

J.B.Hartin Page 2 September 14, 1989 SPECIAL REPORT: POST-ACCIDENT SAMPLING PRIMARY COOLANT RADIATION MONITOR On August 21, 1989, during routine Post-Accident Sampling System (PASS)train-ing for Plant Chemistry Personnel, it was noted that PASS Containment Isola-tion Valves PSR-V-X77A/3 and PSR-V-X77A/4 appeared to leak when in the closed~position.Accordingly, the valves were isolated by closing PSR-V-104 (Jet Pump 20 Sample Line Isolation Valve)and the LCO was entered.On August 24, 1989 PSR-V-104 was opened and the system returned to service, within the 72-hour LCO time frame.After further review of the situation, the decision was made to manually isolate the valves to prevent back leakage of Jet Pumps 10 and 20 to the Demineralized Water System., On August 31, 1989, the valves were again isolated by closing PSR-V-104 (PSR-V-107, Jet Pump 10 Sample Line Isolation Valve, had previously been closed due to leakage from PASS Contain-ment Isolation Valves PSR-V-X77A/1 and PSR-V-X77A/2).

Because the system is inoperable, Post-Accident Sampling Primary Coolant Radiation Monitor PSR-RI-665 is unable to perform its intended function as required by the Technical Specifications.

In the event of an inoperable PASS during accident conditions, the alternate preplanned method for assessing core damage is Plant Procedure (PPM)9,3.22."Core Damage Evaluation." Included in this procedure are evaluations of water level history, installed radiation monitor indication and hydrogen content in the containment atmosphere.

Regarding restoring the system to operable status, Maintenance Work Requests-(HWRs)have been prepared to repair PASS Containment Isolation Valves PSR-V-X77A/1, A2, A3 and A4.Current plans are to repair the valves during the next maintenance and refueling outage (Spring 1990).Very truly yours, i'.u(/)..~C.H.Powers (H/D 927M)WNP-2 Plant Manager CHP:lr cc: Hr.C.J.Bosted, NRC Site (H/0 901A)Hs.Dottie Sherman, ANI Hr.D.L.Williams, BPA (H/D 399)Document Control Desk, NRC