ML17285A412

LER 89-007-00:on 890316,discovered That Two Tech Spec Surveillance Procedures Re Fire Protection Zones for Standby Svc Water Pump Houses & Power Generation Control Cabinet Inconsistent.Action Statements implemented.W/890413 Ltr

ML17285A412
Person / Time
Site:	Columbia
Issue date:	04/13/1989
From:	DAVISON W S, POWERS C M WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-007, LER-89-7, NUDOCS 8904280007
Download: ML17285A412 (9)

Text

gC CELE RATED DISTKBUTI ON DEMON STRXTION SYSTEM REGULATORY1EORMATZON DZSTRZBUTZON SYjEM (RZDS)~ACCESSION NBR:8904280007 DOC.DATE: 89/04/13 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 POWERS,C.M.

Washington Public Power Supply System RECIP.NAME RECIPIENT AFFXLIATION

SUBJECT:

LER 89-007-00:on 890316,failure to comply w/fire protection sys detector surveillance TS requirement.W/890413 ltr.W/8 ltr.DISTRIBUTION CODE: ZE22D COPIES RECEIVED:LTR I ENCL I SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME PD5 LA SAMWORTHER INTERNAL: ACRS MZCHELSON ACRS WYLZE AEOD/DSP/TPAB DEDRO NRR/DEST/ADE 8H NRR/DEST/CEB 8H NRR/DEST/ICSB 7 NRR/DEST/MTB 9H NRR/DEST/RSB 8E NRR/DLPQ/HFB 10 NRR/DOEA/EAB 11 RR IS/SIB 9A REG FI E 02 DSR/PRAB EXTERNAL: EG&G WILLIAMSES L ST LOBBY WARD NRC PDR NSIC MURPHYEG.A COPIES XTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1-1 1'1 1 1 1 1 1 1 4 4 1 1 1 1 1 1 RECIPIENT ID CODE/NAME PD5 PD ACRS MOELLER AEOD/DOA AEOD/ROAB/DSP ZRM/DCTS/DAB NRR/DEST/ADS 7E NRR/DEST/ESB 8D NRR/DEST/MEB 9H NRR/DEST/PSB 8D NRR/DEST/SGB 8D NRR/DLPQ/QAB 10 NRR/DREP/RPB 10 NUDOCS-ABSTRACT RES/DSIR/EIB RGN5 FXLE 01 FORD BLDG HOYEA LPDR NSIC MAYS,G COPIES LTTR ENCL 1 1 2 2 1 1 2 2 1 1 1 0 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 NOTE IO ALLRXDS" RECIPZIKIS PLEASE HELP US'IO REDOCE HASTE.CGMIRCT IHE DOCUMEKZ CXRXIRL DESK, RXM Pl-37 (EXT.20079)I ElaIM33468 KKR NAME HKH DZPQKBUZZCN LISTS P3R DOCUMENXS KRJ DON'T NEEDk TOTAL NUMBER OF COPIES REQUIRED: LTTR 44 ENCL 43 NAC Form 355 (943)LICENSEE EVENT REPORT (LER)U.S.NUCLEAR REGULATORY COMMISSION APPROVED OMB NO.3150-0104 EXPIRES: 8/31/88 FACILITY NAME (ll DOCKFT NUMSEA 12I PAGE 3)Washi to Nuclear Plant-Unit 2 o 5 o o o3 7 t OFQ"'"'"Failure to Comply with Fire Protection System Detector Surveillance Technical S ecification Re uirement-Cause Indeterminate EVENT DATE (5)MONTH OAY YEAR YEAR LEA NUMBER (SI PIxOI SEQUENTIAL idyl NUMBER REVISION NUMBER REPORT DATE (7)OAY YEAR MONTH FACILITY NAMES DOCKET NUMBER(S)0 5 0 0 0 OTHER FACILITIES INVOLVED (8)0 3 1 6 898 9 0 7 0 0 4 1 3 8 9 0 5 0 0 0 OPE RATING MODE (8)POWER LEVEL 20.402(el 20.405(e I (11(il 20.405(e)(1)(8)20.405(el)1)(iiil 20A05(e l)1 1(iv)20.405(~l(11(vl 20.405(cl 50.38(el)1) 50.38 le)(21 50.73(el (2 IS)50.7 3(e I (2)(ii)50.73(el(2)(iii)LICENSEE CONTACT FOR THIS LER (12I 50.73(~l(2)(iv)50.73(~l(2)(v)50.73(~l(2)(vill 50.73(~l(2)(viii)(Al 50.73(~I (2)(viii l(BI 50,73(~l(2)(x I THIS REPORT IS SUBMITTED PURSUANT T 0 THE REGUIREMENTs oF 10 cFR (): (cere>>onr or mo~ol thr Iolloxnnp)

(11 73.71(5)73.71(c)OTHEA ISprcify sn Aestrrct Orlow rnd In Trxr, HIIC Form 366AI NAME ee TELEPHONE NUMBFR AREA CODE 50 3-2 50 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANUFAC.TURER%YWkk!: I~~o'P(~YQ+5gP;

%8~/<~~g44 CAUSE SYSTEM COMPONENT MANUFAC TURER SUPPLEMENTAL REPORT EXPECTED (141 YES Ill yrL complrrr fXPECTfD SV84IISSIOH OATfi ABBTAAcT ILimit to lc00 sprees, I.r., rppioximrtrly lilrrrn sinplr.specs typrvvn'ttrn linrsi 118)EXPECTED SUBMISSION OATS (ISI MONTH DAY YEAR gQ2-On March 16, 1989, during a check of the Fire Protection System technical specification surveillance procedures, a plant maintenance engineer discovered that two technical specification surveillance procedures did not agree with the requirements of WNP-2 Technical Specification 3.3.7.9.During this check of the surveillance procedures two problems wete found: 1)Fire Protection Zones 35 and 36, for Standby Service Water Pump Houses A and B, each contain one thermal fire detector and one ionization fire detector.Technical Specification Table 3.3.7.9-1 lists the required fire detectors for these two zones as being two ionization detectors in each zone.The surveillance procedure for these two zones agrees with the physical installation and does not agree with the Technical Specification requirement, 2)Power Generation Control Cabinet (PGCC)U679, located in the Hain Control Room, contains seven ionization fire detectors.

Technical Specification Table 3.3.7.9-1 lists the required number of fire detectors for PGCC U679 as eight.The surveillance procedure for this cabinet agrees with the physical installation and does not agree with the Technical Specification requirement.

The areas in question were placed on a one hour fire tour.Corrective action will consist of doing a thorough walkdown of the areas covered by the Technical Specifications to discover additional areas of disagreement.

Since an Amendment has been submitted to remove this portion of the Fire Protection System from the WNP-2 Technical Specifications, no attempt will be made to change the Technical Specifications.

The current configuration provides sufficient detection for the areas monitored and therefore a modification is not necessary.

No safety significance is associated with this event.8904280007'90413 PDR ADOCK 0500039'PNU NRC Form 355 (94)3)

NRg Form 388A (943)U.S.NUCLEAR REOULATORY COMMISSION LICENSEE EVEPIEPORT (LER)TEXT CONTINUATIO~

APPRDVED DMS NO.3I50WID4 EXPIRES: 8/31/88 FACILITY NAME l(I OOCKET NUMBER (2)LER NUMBER 18)PACE (3)YEAR gj SEOUENTIAL NUMBER~XSI'EVISION NUMBER Washin ton Nuclear Plant-Unit 2 TEXT///more 8/Moe/I required, Iree edd/dooe/HRC Fomr 38849/(17)0 5 0 0 0 3 9 7 8 9 0 0 7-0 0 2 OF P lant Conditions a)Plant Mode-I (Power Operation) b)Power Level-78ÃEvent Descri tion On March 16, 1989, during a check of the Fire Protection System technical specification surveillance procedures, a plant electrical maintenance engineer discovered that two technical specification surveillance procedures did not agree with the requirements of WNP-2 Technical Specification 3.3.7.9.During this check of the surveillance procedures the following two problems were found: 1.Fire Protection Zones 35 and 36, for Standby Service Water Pump Houses A and B, each contain one thermal fire detector and one ionization fire detector.Technical Specification Table 3.3.7.9-1 lists the required fire detectors for these two zones as being two ionization detectors in each zone.The surveillance procedure for these two zones agrees with the physical installation and does not agree with the Technical Specification requirement.

2.Power Generation Control Cabinet (PGCC)U679, located in the Main Control Room, contains seven ionization fire detectors.

Technical Specification Table 3.3.7.9-1 lists the required number of fire detectors for PGCC U679 as eight.The surveillance procedure for this-cabinet agrees with the physical installation and does not agree with the Technical Specification requirement.

Immediate Corrective Action The requirements of WNP-2 Technical Specification 3.3.7.9 LCO Action Statement were implemented to declare the questionable fire detectors inoperable and place each of the associated Fire Protection Zones on a one hour fire tour.Further Evaluation and Corrective Action Further Evaluation 1.The LER is written to document this event as reportable per the requirements of IOCFR50.73(a)

(2)(i)(B)"Any operation or condition prohibited by the plant's Technical Specification

..." 2.Due to a lack of detailed historical information, the root causes for this event are indeterminate.

The root cause investigation did, however, result in the identification of below listed contributing factors: A.The design for the number and type of fire detectors for the Standby Service Water Pump Houses (SSWPPH)has not changed since 1982.NRC FORM SBBA (983)AU.ST CPOr 1988 S20 SESI000)0 r

NRC Form 388A (943)US.NUCLEAR REOULATORY COMMISSION LICENSEE EVEOREPORT (LERI TEXT CONTINVATIO ooooovooooooo,oioowtoo EXPIRES: 8/31/88 c+CILITY NAME (I)OOCKET NUMBER (2)YEAR LER NUMBER (8)SEQUENTIAL NVM ER IIEVISION NVMSER PACE (3)Washin ton Nuclear Plant-Unit 2 0 s 0 0 o 3 9 7 TEXT///more FFece/8 rtu/rerL uee er//I/orre/HRC

%%drm 38549/()7)0 0 7 00 3oF 0 4 This is well prior to the initial submittal of the WNP-2 Technical Specification.

The March 1984 issue of Technical Specifications was in error since it listed in Table 3.3.7.9-1 that the requirement for the SSWPH fire detectors was two ionization detectors.

The surveillance procedure has contained the correct information since its original issue.B.PGCC U679 in the Main Control Room was originally designed with seven ionization detectors.

A General Electric design change (FDDR KKI-1120 Rev.I)added an additional ionization detector and a thermal detector in May of 1983.A subsequent G.E.design change (FDDR KKI-1120 Rev.6)removed these detectors in August of 1983, leaving"seven" as the correct number of ionization detectors designed for PGCC U679.In November of 1983 the number"eight" was incorrectly submitted as the number to be included in the submittal of WNP-2 Technical Specificatons.

Therefore, in December of 1983, the WNP-2 Technical Specification was issued with an incorrect number in Table 3.3.7.9-1 for PGCC U679 ionization detectors.

The applicable Technical Specification Surveillance Procedure has contained the correct number of"seven" since its original issue in December of 1983.3.There were no structures, components or systems that were inoperable at the start of this event that contributed to the event.Corrective Actions I.A walkdown of the Fire Protection System in the areas covered by the Technical Specifications has been conducted.

No additional areas of disagreement between Technical Specifications, the designed configuration of the Fire Detection System, and the content of the Technical Specification Surveillance Procedures were discovered.

2.In light of the impending issuance of the Technical Specification Amendment which was submitted to remove the Fire Protection section from the WNP-2 Technical Specifications, no action will be taken to submit corrections to this section of the Technical Specification.

These areas will be maintained on the Technical Specification fire tour until the pending Technical Specification Amendment is issued.At that time, they will be controlled via plant procedures.

NRC EORM 388A (983)~U.S~CPOr (988 510$89r000)0

'i i~

NRC Form 366A (6-83)U.S.NUCLEAR REOULATORY COMMISSION LICENSEE EVE EPORT (LER)TEXT CONTINUATIO~

APPRQYEooMBN0.3160-0104 EXPIRES: 6/3)/SS FACILITY NAME ()I'OOCKET NUMBER (1)YEAR LER NUMBER (6)i%%SEQUENTIAL NUMSER I??$REVISION PACE (3)Washington Nuclear Plant-Unit 2 TEXT f/I more s/?Ace/s ootu/ref, uro///orre/HRC

%%d'or??3654'e/(IT)0 s 0 0 03 97 89-0 0 7 0 0 0 4o" 0 4 Safet Si nificance There is no safety significance associated with this event.Both of the conditions documented by this LER are the result of administrative errors in the writing of the WNP-2 Technical Specifications.

The design configuration of the Fire Protection System was not impacted in any way.The safety of the plant equipment and personnel due to the Fire Protection System was maintained in compliance with the bases for the Technical Specifications during the entire period covered by this event as documented by the correct completion of the Fire Protection System Surveillance Procedures.

Similar Events LER 85-039"Fuse Size Inconsistency With Technical Specifications" documents a condition during which it was discovered that the plant design and the installed configuration did not agree with the Technical Specification.

The corrective actions for LER 85-039 were focused on the Plant Modification program and preventing emerging design changes from bypassing the Technical Specification update process.This LER.(89-007) addresses the discovery of administrative errors in the'nitial writing of the WNP-2 Technical Specifications.

LER 88-036-01 RFailure to Perform Division One 4.16 KV Emergency Bus Undervoltage Degraded Voltage Protection Techtn'cal Specification Surveillance Due to Inadequate Procedure" documents a condition during which it was discovered that Technical Specification surveillance procedures did not contain all the testing requirements specified by the Technical Specifications.

The corrective action focused on the correction of the specific procedures involved and the submittal of an emergency Technical Specification Amendment.

EI IS Information Text Reference EIIS Reference System Component Thermal Fire Detector Ionization Fire Detector Power Generation Control Cabinet KP KP ID DET DET CAB NRC FORM SSSA (643)~U.S, CPOr ISSS 510 5SSI000)0 WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George Washington Way~Richland, Washington 99352 Docket No.50-397 Apr il 13, 1989 Document Control Desk U.S.Nuclear Regulatory Commission Washington, D.C.20555

Subject:

NUCLEAR PLANT NO.2 LICENSEE EVENT REPORT NO.89-007

Dear Sir:

Transmitted herewith is Licensee Event Report No.89-007 for the WNP-2 Plant.This report is submitted in response to the report requirements of 10CFR50.73 and discusses the items of reportability, corrective action taken, and action taken to preclude recurrence.

Very truly yours,/I C.M.Powers (H/D 927M)WNP-2 Plant Manager CMP: 1 g

Enclosure:

Licensee Event Report No.89-007 cc: Hr.John B.Martin, NRC-Region V Hr.C.J.Bosted, NRC Site (M/D 901A)INPO Records Center-Atlanta, GA Hs.Dottie Sherman, ANI Mr.D.L.Williams, BPA (H/D 399) 0