ML17279A873

LER 88-004-00:on 880204,standby Liquid Control Pump 1B Inoperable for Longer than 7-day Period Allowed by Tech Specs.Caused by Procedural Inadequacy.Tech Specs Reviewed to Identify Any Similar Remaining situations.W/880304 Ltr

ML17279A873
Person / Time
Site:	Columbia
Issue date:	03/04/1988
From:	Davison W, Powers C WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
LER-88-004, LER-88-4, NUDOCS 8803140153
Download: ML17279A873 (6)

Text

I

~g ACCELERATED D1SRBUTJON DEMONSTRRON SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8803140153 DOC.DATE: 88/03/04 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION DAVISON,W.S. Washington Public Power Supply System POWER,C.M. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 88-004-00:on 880204,standby liquid control sys inoperable longer than allowed by Tech .Specs.

W/8 DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR ENCL SIZE:

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

NOTES:

ID RECIPIENT PD5 LA CODE/NAME ~

COPIES LTTR ENCL 1 1 ID RECIPIENT PD5 PD CODE/NAME COPIES LTTR ENCL 1 1 I

SAMWORTH,R 1 1 h INTERNAL ACRS MICHELSON 1 1 ACRS MOELLER 2 2 AEOD/DOA 1 1 AEOD/DS P/NAS 1 1 AEOD/DSP/ROAB 2 2 AEOD/DSP/TPAB 1 1 ARM/DCTS/DAB 1 1 DEDRO 1 1 NRR/DEST/ADS7E4 1 0 NRR/DEST/CEB8H7 1 1 NRR/DEST/ESB 8D 1 1 NRR/DEST/ICSB7A 1 1 NRR/DEST/MEB9H3 1 1 NRR/DEST/MTB 9H 1 1 NRR/DEST/PSB8D1 1 1 NRR/DEST/RSB 8E 1 1 NRR/DEST/SGB 8D 1 1 NRR/DLPQ/HFB10D 1 1 NRR/DLPQ/QAB10A 1 1 NRR/DOEA/EAB11E 1 1 NRR/DREP/RAB10A 1 1 NRR/DREP/RPB10A 2 2 RIN~IB9A1 1 1 NRR/PMAS/ILRB12 1 1 R G &4 02 1 1 RES TELFORD,J 1 1 RES/DE/EIB 1 1 RES/DRPS DIR 1 1 RGN5 FILE 01 1 1 EXTERNAL EGGG GROH I M 5 5 FORD BLDG HOY,A 1 1 H ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC HARRIS,J 1 1 NSIC MAYS,G 1 1 S

A TOTAL NUMBER OF COPIES REQUIRED: LTTR 46 ENCL 45

NRC Form 386 U.S. NUCLEAR REQULATORY COMMISSION (943)

APPROVED OMB NO. 31600(04 LICENSEE EVENT REPORT (LER) EXPIRES: 8/3(l88 FACILITY NAME (I) DOCKET NUMBER (2) PAO8 3 Washin ton Nuclear Plant - Unit 2 0 s 00 0 397 ioFO 4

"'"tandby L)quand Contro ystem nopera e onger an owe y Technical S ecifications Caused By Inadequate Procedure EVENT DATE (5) LER NUMBER (8) REPORT DATE (7) OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR SEQUENTIAL )FQ: REVISION MONTH DAY YEAR FACILITYNAMES DOCKET NUMBER(SI NUMBER <.Rl NUMBER 0 5 0 0 0 0 2 4 8 8 0 0 4 0 0 0 04 88 0 5 0 0 0 THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CFR (): (Check one Or more Of the follovflnP) (11)

OPERATINO MODE (9) 20.402(bl 1 20AOS(c) 50.73(e) (2Hiv) 73.71(b)

POWER 20.40S(e) (1((il 5028(c) (1) 50.73(e) (2) (v) 73.71(c)

LEVEL 1 p p 20AOS(e) (I l(8) 60.38(c) (2) 50.73(e) (2) (vii) OTHER (Specify ln Abttrect below enrf ln Text, NRC Form 20.406(e l(1) (iiil 60.73(e) (2((il 50.73(e)(2)(vill)(A) BBBA) 20AOS(e l(1) (iv) 60.73(e) (2) (ii) 50.73(e) (2) (viii l(8)

((:. -..... X ...i&a'4 20.405(e) (1)(vl 50.73(e ) (2) (i ii) 50.73( ~ ) 12) (xl I.ICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA CODE W.S. Davison, Compliance fngineer 50 93 77- 250 1 co PLETE oNE LINE Fo EAGH coMPQNENT FAILURE DEscRIBED IN THIB REPQRT (13) f te '(o 26 CAUSE SYSTEM COMPONENT MANUFAC REPORTABLE TO NPRDS (3

'<3 MANUFAC.

TURER

m. '. o)

CAUSE SYSTEM COMPONENT TVRER TO NPAD)

WNM .m. Rcc SUPPLEMENTAL REPORT EXPECTED (14) MONTH DAY YEAR EXPECTED SUBMISSION DATE 05)

YES (if yet, complete EXPECTED SVBMISSIDlY DATE) NO ABSTRACT (Limit to 1400 tpecel, l 8, epproximetely fifteen tfnpreepece typewritten lined (18)

While dispositioning a Nonconformance Report concerning the Standby Liquid Control (SLC) System on February 4, 1988, an engineer deterrained that one of the two pur)p relief valves, SLC-RV-29B, was set 25 psig below the allowab'le value listed in Plant Technical Specifications. Further investigation revealed that SLC pump 1B (SLC-P-1B) was inoperable for longer than the seven-day period allowed by Technica'l Specifications. The relief valve setpoint was ir(rmediately readjusted to within the allowable value. The root cause was determined to be procedural inadequacy. The Relief Valve Setpoint Control and Logging Procedure did not contain adequate direction concerning Technical Specification requirements. Corrective actions include a review of Plant Technical Specifications to identify any similar remaining situations and the modification of the Relief Valve Setpoint Control and Logging Procedure to include Technical Specification requirements. This event posed no threat to the safety of Plant personnel or the public.

(7 () i q@$

SS03140153 SS0304 PDR ADDCK 05000M'7 1 8 DCD r

NRC Form 388 (9 83)

~

'RC US. NUCLEAR REGULATORY COMMISSION Form 3SSA 1943 I LICENSEE EVENT REPORT ILERI TEXT CONTINUATION APPROVFO OM8 NO. 3150&10S EXPIRES: 8/31/88 FACILITYNAME (11 OOCKET NUMBER (21 LER NUMBER (5) PAGE (3I SECUENT/AL ~" KEYED/orr NUM E4 ~ 3 rrvMssR Washin ton Nuclear Plant

'TEXT /I/ more s/>>ce ie eoe/kred, use adainel iYRC Anrs

- Unit

~'s/ (I T) 2 0500039788 0 0 4 0 0 OF Plant Conditions a) Power Level - 100K b) Plant IIode - 1 (Power Operation)

Event Descri tion Whi le dispositioning a Nonconformance Report which documented a problem with the Standby Liquid Control (SLC) system pump number 18 relief valve (SLC-RV-298) on February 4, 1988, a Plant Technical Staff engineer determined that the relief valve was set 25 psig below the a'llowable value, listed in Plant Technical Specifications.

Further investigation revealed that, due,to the improper relief valve setpoint, SLC-P-18 was inoperable for longer than the seven-day period allowed by Technical Specification requirement 3. 1.5.a. 1.

On January 26, 1988, during plant operation at approximately 100 percent power, SLC-P-18 was declared inoperable at 0758 hours0.00877 days <br />0.211 hours <br />0.00125 weeks <br />2.88419e-4 months <br /> to allow repair of SLC-RV-29B which was leaking during pump operation. Entry was made into Technical Specification LCO Action Statement (TSAS) 3. 1.5.a.l which allowed seven days to return the pump to operable status.

On January 28, 1988, after repair of SLC-RV-298 was completed, the valve was set and tested at a lift setpoint of 1375 psig as directed by the Relief Valve Setpoint-Data Sheet section of the work package. At 2215 hours0.0256 days <br />0.615 hours <br />0.00366 weeks <br />8.428075e-4 months <br />, after the relief valve was reinstalled, the SLC System was declared operable and the pla'nt exited TSAS 3.1.5.a. l.

On February 4, 1988, during evaluation of Nonconformance written to lift within tolerance Report a

document the failure of SLC-RV-29B to specified by the Plant Maintenance Procedures, the Technical Staff SLC System engineer determined that the final setpoint of the relief valve was not within values specified by Technical Specification 3.1.5. The minimum allowable value specified was 1400 psig. The relief valve setpoint, as recorded in the work package, was 1375 psig.

Investigation determined that the Relief Valve Setpoint Data Sheet supplied to the hIaintenance group by Plant Technical Staff was in error,. listing the setpoint as 1400 psig + 3 percent.

A Immediate Corrective Action Since the plant was in the Shutdown condition, no action was required to cor/Iply with Technical Specification 3.1.5. The relief setpoint was iII/iediately readjusted to within the allowable value and at 0110 hours0.00127 days <br />0.0306 hours <br />1.818783e-4 weeks <br />4.1855e-5 months <br /> on February 5, 1988, the SLC System was declared operable.

NRC SO/IM SSOA *U S GPO;1988.0.824 538/455 (9831

U.S. NUCLEAR REGULATORY COMMISSION NRC FPIm SSSA 1583l LICENSEE EVENT REPORT (LER) TEXT CONTINUATION APPROVED OMS NO. 3150&IOd EXPIR ES: 8/31/88 FACILITY NAME 111 DOCKET NUMSER ISI LER NUMSER 151 PAGE 131 gm SSOVSNTIAL rP+: IISVISION K/P NVM SII NVM dll Washin ton Nuclear Plant - Unit 2 TEXT /// morP dpdcd /d /Pdvkwf. IIPP ~ AI/IC Foml 358A 8/ II7 I

- o 3 9 7 8 8 0 0 4 0 OF Further Evaluation and Corrective Action o Further Evaluation

1. This event is being reported as a condition prohibited by the Plant's Technical Specifications in accordance with 10CFR50.73(a)(2)(i)(B).'.

SLC-P-1B was inoperable from January 26, 1988, to February 4, 1988. This period totals nine days, which is two days in excess of the seven days allowed by Technical Specification 3.1.5. This constitutes noncompliance with the Plant Technical Specifications.

3. The immediate cause of the event was determined to be an error as a direct result of an approved procedure in that the incorrectly set relief valve was reinstal led in the SLC System as operable as a result of the incorrect Relief Valve Setpoint Data Sheet.

4. The root cause of this event was determined to be procedu'ral inadequacy in that the Relief Valve Setpoint Control and Logging Procedure did not contain adequate direction concerning Technical Specification requirements to enable the engineer to correctly complete the Relief Valve Setpoint Data Sheet.

o Corrective Action

1. A review of the Plant Technical Specifications will be performed to identify any sii/Iilar limitations which may-be more restrictive than the ASIIE Code for relief valve setpoints.

2. The Relief Valve Setpoint Control and Logging procedure will be modified to strengthen the setpoint verification process to specifically include Technical Specification requirements.

Safet Si nificance-Technical Specifications allow operation of the SLC system with one of the redundant components inoperable for a period of seven days. The fact that SLC-P-1B (redundant to SLC-P-lA) was technically inoperable for a slightly longer period did not decrease the system's ability to perform its design function. As shown by testing, the highest pressure expected to be seen at this relief valve during accident conditions is less than 1300 psig. With SLC-RV-29B set at 1375 psig, sufficient margin existed to ensure system injection capability at full capacity. This event posed no threat to the safety of Plant personnel or the public.

NIIC SOIIM SSSA *U.S GPO:1985 0.52d 538/455 19 83 I

s ~I NRC Form 366A V.S. NUCLEAR REGULATORY COMMISSION (94)3)

LICENSEE EVENT REPORT (LER) TEXT CONTINUATION " APPROVEO OMS NO. 3)50M)04 EXPIRES: 8/31/88 FACILITYNAME (1) OOCKET NUMBER (3) LER NVMSER (6) PAGE I3)

YEAR SEQUENTIAL REVISION NVM ER NVMSER Washin ton Huc1ear P1ant TEXT /// more tptoe /I Ieqo)ed, ote e//oeot ~

- Unit

//RC /or/II 3(()r('t/ ()3) 2 o >> <<3 7 8 8 0 0 4 0 OF Simi1ar Events

'one.

EIIS Information Text Reference EI IS Reference System Component SLC BR SLC-RV-29B BR RV SLC-P-1A BR P SLC-P-lB BR P NRC FORM ESSA e V S GPO 19' (943)

WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 9935Z Docket No. 50-397 March 7, 1988 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

NUCLEAR PLANT NO. 2 LICENSEE EVENT REPORT NO. 88-04

Dear Sir:

Transmitted herewith is Licensee Event Report No. 88-04 for the WNP-2 Plant.

This report is submitted in response to the report requirements of 10CFR50.73 and action and discusses the items of reportability, corrective action taken, taken to preclude recurrence.

Very truly yours, 5/4 A~

C.H. Powers (H/D 927M)

WNP-2 Plant Manager CHP:sm

Enclosure:

Licensee Event Report No. 88-04 cc: Hr. John B. Martin, NRC Region V Hr. C.J. Bosted, NRC Site (H/D 901A)

INPO Records Center' Atlanta, GA Ms, Dottie Sherman, ANI Hr. D. L. Williams, BPA (M/D 399)