ML17285A293

Special Rept:On 890203,plant Personnel Unable to Obtain Sample from PASS Due to Lack of Compression in Vacuum Pump. Caused by Broken Pump Shaft.Replacement Parts Currently on Order & Pump Will Be Repaired as Soon as Possible

ML17285A293
Person / Time
Site:	Columbia
Issue date:	02/16/1989
From:	Power C WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
NUDOCS 8903090053
Download: ML17285A293 (5)

Text

ACCELERATED DI BUTION DEMON STRA,TIO.'i SYSTEM REGULA I ZNEORilATZON DZSTRISUTIOiZSTEN (RIDE)

ACCESSION NBR:8903090053 DOC.DATE: 89/02/16 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION POWERiC.M. Washington Public Power Supply System RECIP. NAME RECIPIENT AFFILIATION MARTIN,J.B. Region 5, Ofc of the Director

SUBJECT:

Special rept re post-accident sampling containment atmosphere radiation monitor.

DISTRIBUTiON CODE: IE22D COPIES RECEIVED:LTR t ENCL J SIZE:

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

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 SAMWORTH,R 1 1 INTERNAL: ACRS MICHELSON 1 1 ACRS MOELLER 2 2 ACRS WYLIE 1 1 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 1 AEOD/ROAB/DSP 2 2 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADE SH 1 1 NRR/DEST/ADS 7E 1 0 NRR/DEST/CEB SH 1 1 NRR/DEST/ESB SD 1 1 NRR/DEST/ICSB 7 1 1 NRR/DEST/MEB 9H 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB SD 1 1 NRR/DEST/RSB SE 1 1 NRR/DEST/SGB SD 1 1 NRR/DLPQ/HFB 10 1 1 NRR/DLPQ/QAB 10 1 1 NRR/DOEA/EAB 11 1 1 NRR/DREP/RAB 10 1 1 NRR/DREP/RPB 10 2 2 NRR/DRIS SIB 9A 1 1 NUDOCS-ABSTRACT 1 1 R LE 1 1 RES/DSIR/EIB 1 1 RES/DSR/PRAB 1 1 RGN5 FILE 01 1 1 EXTERNAL: EG&G WILLIAMSiS 4 4 FORD BLDG HOY,A 1 1 H S,T LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC MAYSiG 1 1 NS IC MURPHY, G. A 1 1 S

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TOTAL NUMBER OF COPIES REQUIRED: LTTR 45 ENCL 44

@~i WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99362

'l ' '.c Docket No. 50-397 February 16, 1989 Nr. J.B. Martin Regional Administrator USNRC, Region V 1450 Maria Lane, Suite 210 Walnut Creek, CA 94596 Dear Nr. Martin;

Subject:

NUCLEAR PLANT NO. 2 LICENSE NO. NPF-21 SPECIAL REPORT: POST-ACCIDENT SAMPLING CONTAINMENT ATMOSPHERE RADIATION MONITOR This special report is submitted pursuant to the requirements of WNP-2 Technical Specification Table 3;3.7.5-1 (Instrument No. 24: Post Accident Sampling Containment Atmospheric Radiation Monitor), Action Statement 81 ~

Action Statement Bl 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 action taken, the cause of the inoperability and the plans and schedule for restoring the system to operable status."

id" gib 53 890 0397 050oPNU 890309o0cy,

>9 6

On february 3, 1989 during an E'mergency Preparedness Drill, Plant personnel were unable to obtain a sample from the Post Accident Sampling System (PASS).

Accordingly, a Maintenance Work Request (NMR) was written to Lrouble shoot the problem. During the trouble shooting eFforts it was discovered that vacuum pump PSR-P-702 (Suppression Pool Atmospheric Sample Return) would run freely but there was no.compression. The problem is suspected to be a broken pump shaft. As a result, the system was inoperable and Post Accident Sampling Containment Atmospheric Radiation NoniLor PSR-RI-704 was not able to perform its function as required by the Technical Specifications.

In the event. of an inoperable PASS during accident conditions, the alternate method for assessing core damage is Plant. Procedure (PPN) 9.3.22, "Core Damage Evaluation." Included in this procedure are evaluations oF water level history, installed monitor indication and hydrogen conLent in the containment atmospheres Regarding restoring the system to operable status, replacement parts for PSR-P-702 are currently on order and the pump will be repaired as soon as possible (estimated completion date is April-Nay, 1989). As part of the repair effort, an evaluation of the failure mode will be performed and the results provided in a supplemental report.

Very truly yours, C. . Powers (N/0 927M)

NNP-2 Plant Manager cc: Mr. C.J. Bosted, NRC Site (N/0 901A)

Ns. Dottie Sherman, AN1 Nr. O.L. Williams, BPA (M/0 399)

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