ML17285A800

Special Rept:On 891009,valve PSR-V-104 Isolated to Repair Leaking PASS Sample Valve PSR-V-616,resulting in PASS Being Inoperable.Plan Made to Replace Valve PSR-V-616 to Restore Sys by Jan 1990

ML17285A800
Person / Time
Site:	Columbia
Issue date:	10/19/1989
From:	POWERS C M WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	MARTIN J B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
NUDOCS 8910250229
Download: ML17285A800 (4)

Text

tw ACCELERATED DIS1%BUTION DEMONS'ON SYSTEM REGULATORY XNFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:8910250229 DOC-DATE: 89/10/19 NOTARIZED:

NO DOCKET g FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH NAME AUTHOR AFFXLIATION POWERS,C.M.

'ashington Public Power Supply System RECIP.NAME

, RECIPIENT AFFILIATION MARTIN,J.B.

Region 5, Ofc of the Director

SUBJECT:

Special rept:on 890928&1009.post-accident sampling primary coolant radiation monitor inoperable.

DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR I ENCL Q SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES RECIPIENT XD CODE/NAME PD5 LA SAMWORTH,R INTERNAL: ACRS MICHELSON ACRS WYLIE AEOD/DSP/TPAB DEDRO NRR/DEST/ICSB 7 NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 NUDOCS-ABSTRACT RES/DSXR/EIB CL COPIES LTTR EN 1 1'ECIPIENT ID CODE/NAME PD5 PD ACRS MOELLER AEOD/DOA AEOD/ROAB/DSP NRR/DEST/ESB 8D NRR/DEST/MEB 9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/PEB 10 NRR DREP/RPB 10 G~-&a GN5 FILE 01.COPIES LTTR ENCL EXTERNAL: EG&G WXLLIAMS,S LPDR NSIC MAYS,G NUDOCS FULL TXT L ST LOBBY WARD 1 NRC PDR 1 NSIC MURPHY,G.A 1 NOTE TO ALL"RIDS" RECIPIENTS:

P~HELP US TO REDUCE WAS'ONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEEDlTOTAL NUMBER OF COPIES REQUXRED: LTTR 38 ENCL 0 1a 1 ti WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George N'ashington EVay~Richland, Washington 99352 Docket No.50-397 October 19, 1989 Hr.J.8.Hartin Regional Administrator USNRC, Region V 1450 Haria Lane, Suite 210 Walnut Creek, CA 94596

Subject:

NUCLEAR PLANT NO.2 LICENSE NO.NPF-21 SPECIAL REPORT: POST-ACCIDENT SAHPLING PRIHARY COOLANT RADIATION HONITOR

Reference:

Letter, C.H.Powers (SS)to J.8.Hartin (NRC), dated September 14, 1989 This special report is submitted pursuant to the requirements of WNP-2 Technical Specification Table 3.3.7.5-1 (Instrument No.29: Post-Accident Sampling Primary Coolant Radiation Honitor), 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'ithin 14 days following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status." S&i02~022y gyg0>>PDRl"-lDOCK 05000397 8 PDC ((ggfgt/Pf pzpP lu J.B.Hartin Page 2 October 19, 1989 SPECIAL REPORT'OST-ACCIDENT SAMPLING PRIMARY COOLANT RADIATION MONITOR The referenced letter described a condition where part oF the Post-Accident Sampling System (PASS)was isolated due to leaking PASS Containment Isolation Valves PSR-V-X77A/3 and PSR-V-X77A/4; The valves were isolated by closing PSR-V-104 (Jet Pump 20 Sample Line Isolation Valve).Valve PSR-V-107, the Jet Pump 10 Sample Line Isolation Valve, had previously been closed due to leakage from PASS Containment Isolation Valves PSR-V-X77A/1 and PSR-V-X77A/2.

On September 28, 1989, during Plant startup from a forced outage due to main condenser problems, PSR-V-104 was opened and the PASS declared operable.On October 9, 1989, PSR-V-104 was again isolated to repair'eaking PASS sample valve PSR-V-616.

By having both PSR-V-104 and PSR-V-107 isolated, the system is considered inoperable and 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 (PPH)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, current plans are to replace valve PSR-V-616.

Due to the long lead time required to procure a replacement valve, it is anticipated that the new valve will be installed and the system declared operable by mid-January, 1990.Maintenance Work Requests (HWRs)have also been prepared to repai r PASS Containment Isolation Valves PSR-V-X77A/1, A/2, A/3 and A/4.As stated in the referenced letter, current plans are to repair these valves during the next maintenance and refueling outage (Spring 1990).Very truly yours, C.H.Powers (.H/D 927M)WNP-2 Plant Hanager CHP:lr cc: Mr.C.J.Bosted, NRC Site (M/D 901A)Ms.Dottie Sherman, ANI Hr.D.L.Williams, BPA (H/D 399)Document Control Desk, NRC