ML17285B332

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LER 90-010-00:on 900517,secondary Containment Isolation Occurred During Reactor Refueling Outage.Caused by Inadequate Work Control.Work Control Procedures Will Be Reviewed to Determine If Addl Steps needed.W/900613 Ltr
ML17285B332
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 06/13/1990
From: FIES C L, POWERS C M
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-90-010, LER-90-10, NUDOCS 9006200446
Download: ML17285B332 (16)


Text

ACCELERATED THJBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR: 9006200446 DOC.DATE: 90/06/13 NOTARIZED:

NO FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe AUTH.NAME AUTHOR AFFILIATION FIES,C.L.Washington Public Power Supply System POWERS,C.M.

Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000397

SUBJECT:

LER 90-010-00:on 900517,secondary containment ESF actuation caused by inadequate work control.W/9 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), ncident Rpt, etc.NOTES RECIPIENT ID CODE/NAME PD5 LA SAMWORTH,R INTERNAL: ACNW AEOD/DOA AEOD/ROAB/DSP NRR/DET/ECMB 9H NRR/DLPQ/LHFB11 NRR/DOEA/OEAB11 NRR/DST/SELB SD NRR DST/SPLBSD1 EG 2 GN5 FILE 0 EXTERNAL: EGGG STUART,V.A LPDR NSIC MAYS,G NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 2 2 1 1 2 2 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 AEOD/DS P/TPAB DEDRO NRR/DET/EMEB9H3 NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7E NRR/DST/SRXB SE RES/DSIR/EIB L ST LOBBY WARD NRC PDR NSIC MURPHY,G.A COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1~H~S OOCUMFN HP,g PPFN SCANNED NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 36 ENCL 36 ii WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George Washington Way~Richland, Washington 99352 Docket No.50-397 June 13, 1990 Document Control Desk U.S.Nuclear Regulatory Commission Washington, D.C.20555

Subject:

NUCLEAR PLANT NO.2 LICENSEE EVENT REPORT NO.90-010

Dear Sir:

Transmitted herewith is Licensee Event Report No.90-010 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, C.H.Powers (H/D 927M)WNP-2 Plant Hanager CMP:lr

Enclosure:

Licensee Event Report No.90-010 cc: Hr.John B.Hartin, NRC-Region V Hr.C.J.Bosted, NRC Site (M/D 901A)INPO Records Center-Atlanta, GA Hs.Dottie Sherman, ANI Hr.D.L.Williams, BPA (H/D 399)VOaC200~O6 S 00SZ3 PDR ADOCK 05000397 S PDC YjP~

N<<~GEIM 366 (BEET U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)APPROVED OMB NO.3(504H04 EXP IR ESI'4/30/92 ESTIMATED BURDEN PEA AESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 50.0 HAS, FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P630), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, OC 20555, AND TO THE PAPE4WORK REDUCTION PROJECT (31500104).

OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.FACILITY NAME (Il Washington Nuclear Plant-Unit 2 econ ary on a)nmen ngineere a e y ea ure Caused by Inadequate Work Control DOCKET NUMBER (2I PAGE 3 0 5 0 0 03 97>oFO c ua son EVENT DATE (SI LER NUMBE4 (6)AEPOAT DATE (7)OTHF 4 FACILITIES INVOLVED (8)MONTH DAY YEAR YEAR rr'Sex SEQVBNTIAL

6/A NUMBER~tr%REVISION MONTH WP: NUMBER OAY YEAR FACILITY NAMES DOCKET NUMBER(S)0 5 0 0 0 0 517 909 0 010 00 06 139 0 0 5 0 0 0 OPERATING MODE (8)POW6 R LEVEL P P P (10)20A02(b)20.405(~)(1)(I)20.405(rill)(ill 20A05(el(1)(iiil 20.405(e)(I)(Ivl 20A05(e I (1)(v I 20.405 (c)50.38 I c)(1l 60.38(cl(2) 50.73(~)(2)(Il 50.73(~)(2)(ii)50.73(el(2)(IIB LICENSEE CONTACT FOR THIS LER (12)50.73(e)(2)(ivl 60.73(eH2)(v) 50.73(e)(2)(vEI 60.73(~)(2)(villi(A) 50.73(e)(2)(villi(B) 60.73(e)(2)(x)THIS REPORT IS SUBMITTED PURSUANT TO THE REQUIREMENTS OF 10 CF 4 ()I (Check onr or more ol the IollowinFI (11)73.7)(B)73.71(c)OTHER ISprcify ln Abstrrct brlowrrxtin Trxt, HRCForm 366AI NAME C.L.Fies, Compliance Engineer TELEPHONE NUMBER AREA CODE 50 937 7-203 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBEO IN THIS REPO4T (13)CAUSE SYSTEM COMPONENT MANUFAC.TUAER EPORTABLE P~x$x~CAUSE SYSTEM COMPONENT MANUFAC.TURER REPORTABLE

'N'kjpjQ TQ NPADS:+c M~gpss@.o>R NB'EIQNN SUPPLEMENTAL REPORT EXPECTED (14)YES III yrr, compte tr EXPECTED SUSIyIISSIOII DA TEI NO ABSTRACT ILlmlt to lr00 sprcrs, I r., rpproxlmrtrly Ilftren slnolrrpecr typewritten linrsl 118)EXPECTED SUBMISSION DATE IIS)MONTH DAY YEAR During the reactor refueling outage on May 17, 1990, at 1438 hours0.0166 days <br />0.399 hours <br />0.00238 weeks <br />5.47159e-4 months <br /> a Secondary Containment isolation occurred.This Engineered Safety Feature (ESF)actuation resulted in the shutdown of non-safety related HVAC equipment, the actuation of containment isolation valves, and the startup of various safety related systems such as Standby Gas Treatment.

Plant maintenance workers were replacing auxiliary relays as part of the normal preventative maintenance program when they inadvertently placed two channels in the tripped condition which initiated the ESF actuation.

The root cause for this event was inadequate work control which allowed work to proceed simultaneously on two safety-related divisions when no provisions had been made for such an activity.Immediate corrective action was taken to place the Secondary Containment systems in their normal configuration.

There is no safety significance associated with this event.ESF isolations and actuations occurred as designed for the plant configuration at the time of the event.'ccordingly, this event posed no threat to the health and safety of the public or plant personnel.

NRC Form 368 (569)

I l~~~I It It II~4 II r c Ik Ir I t>~I\ll~j NRC FORM 366A (64)9)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVEO 0M B NO.31600104 EXPIRES: 4/30/92 ES ATEO BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION AEQVEST: 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND AEPORTS MANAGEMENT BRANCH (P4)30), U.S.NUCLEAR REGULATOAY COMMISSION, WASHINGTON, OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31600)04), OFFICE OF MANAGEMENT ANO BUDGET, WASHINGTON, OC 20503.FACILI'TY NAME (1)Washington Nuclear Plant-Unit 2 TEXT/ll rrroro 4/rooo/4 ror)o/rod, rrro oddldono/NRC%%drrrr 38549/(I 2)DOCKET NUMBER (2)o s o o o 397 9 0 LER NUMBER (6)"'EOVENTIAL M NUMBER-0 0"eg?REVISION NVMBER 0 0 PAGE (3)oF0 3 Plant Conditions Power Level-0%Plant Mode-5 Event Descri tion During the reactor refueling outage on May 17, 1990, at 1438 hours0.0166 days <br />0.399 hours <br />0.00238 weeks <br />5.47159e-4 months <br /> a Secondary Con-tainment Isolation Engineered Safety Feature (ESF)Actuation occurred.At the time of the actuation maintenance work was being performed by Plant Maintenance workers on General Electric Model HFA auxiliary relays.This ESF Actuation initiated a Balance of Plant (BOP)isolation involving Group 3 (Primary and Secondary Contain-ment Ventilation and Purge Systems)and part of Group 4 (Miscellaneous Balance of Plant Systems).These two Groups are part of the Nuclear Steam Supply Shutoff System (NSSSS)that provides overall isolation of plant systems in response to various process parameters.

During refueling (Mode 5)the Primary Containment can be open to the Secondary Containment and this isolation function is limited to Secondary Containment although Primary Containment isolations will occur if com-ponents have not been deactivated.

In addition to the isolations, the Secondary Containment ESF actuation causes the normal Reactor Building (Secondary Containment) heating and ventilating supply and exhaust fans to stop and Reactor Building pressure control is transferred to the safety-related Standby Gas Treatment (SGT)system which was initiated by this event.Immediate Corrective Action Plant operators took imediate corrective action to place the systems back in their normal configuration.

The restoration of systems, including the shutdown of SGT, was completed at 1520 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.7836e-4 months <br />.Further Evaluation and Corrective Action A.Further Evaluation 1.This event is being reported per the requirements of 10CFR50.73(a)(2

)(iv)as an"......event or condition that resulted in manual or automatic actuation of an Engineered Safety Feature (ESF)......".

2.Further evaluation showed work was in progress on the Division I manual actuation relay (MS-RLY-K35A) which put the HAH channel in the tripped condition.

When work started on the HBA channel relay (MS-RLY-81B) this caused a full trip on the outboard relay cabinet (RC-1)which resulted in the Secondary Containment Isolation.

NRC Form 366A (669) 0~~I I I," IMI~'$l bl~'lk<>~4 t H>.',J.><1~c~~~~~0<<E NRC FORM 366A (84)9)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVED 0 M 6 NO.31500104 EXPIRES: 4/30/92 ES ATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUEST: 50J)HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P4)30), U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31504)104), OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILI'TY NAME (1)DOCKET NUMBER (2)LER NUMBER (8): : SEOUENTIAL P4I'EVISION NR.w NUMBER'tee'UMBER PAGE (3)Washin ton Nuclear Plant-Unit 2 TEXT//I moro tptot it r//I/rtd, Iree odd/1/one/P/RC Form 386A'4/07)0500039790

-01 0-00 OF 0 3.The root cause was inadequate work control which allowed work to proceed simultaneously on two safety related divisions when no provisions had been made for such an activity.4.There were no structures, components or systems that were inoperable prior to the start of this event which contributed to the event.B.Further Corrective Action 1.Work control procedures will be reviewed to determine if additional steps need to be added to control Division related work.2.The current work control administrative process will be reviewed with Plant Maintenance Department Supervisor and Engineering personnel.

Safety Si nificance There is no safety significance associated with this event.ESF isolations and actuations occurred as designed for the plant configuration at the time of the event.Accordingly, this event posed no threat to the health and safety of the public or plant personnel.

Similar Events None EIIS Information Text Reference EIIS Reference Secondary Containment Nuclear Steam Supply Shutoff System Primary Containment Standby Gas Treatment Main Steam Relay K35A (MS-RLY-K35A)

Main Steam Relay K81B (MS-RLY-K81B)

System C BH SB SB~Com onent RLY RLY NRC Form 368A (84)9) v I l II~tl ll4 d~v drrd-4144~~4 4 I 1,, I I ll II I)d, r I v I,v I lt I" d'.!~II d I I~4 4 IIII r i" Idh 4 I~" It I~li V 4.t I, I~II II t ttI , I Id 4'I.tt"4,'I I tl'td tl!I 4 tI 4 II I I>~4 r"dr i Id I'l I II'I dd 14'.rh'I I, IOl>>I I I v~I II I vll ldV I Id!Id 3 4.)hdI)4 I I V 41 I 4 4 I It 4 tl ACCELERATED D>TRIBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR: 9006200446 DOC.DATE: 90/06/13 NOTARIZED:

NO FACIL:50-397 WPPSS Nuclear Project, Unit, 2, Washington Public Powe AUTH.NAME AUTHOR AFFILIATION FIES,C.L.Washington Public Power Supply System POWERS,C.M.

Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION DOCKET 05000397

SUBJECT:

LER 90-010-00:on 900517,secondary containment ESF actuation caused by inadequate work control.W/9 ltr.DISTRIBUTION CODE: IE22T.COPIES RECEIVED:LTR ENCL SIZE: TITLE: 50.73/50.9 Licensee Event Report (LER), ncident Rpt, etc.NOTES: RECIPIENT ID CODE/NAME PD5 LA SAMWORTH,R INTERNAL: ACNW AEOD/DOA AEOD/ROAB/DS P NRR/DET/ECMB 9H NRR/DLPQ/LHFB1 1 NRR/DOEA/OEAB1 1 NRR/DST/SELB 8 D PLBSD1 R ILE 01 EXTERNAL EG&G STUART I V~A LPDR NSIC MAYS,G NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 2 2 1 1 2 2 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 AEOD/DS P/TPAB DEDRO NRR/DET/EMEB9H3 NRR/DLPQ/LPEB10 NRR/DREP/PRPB11 NRR/DST/SICB 7E NRR/DST/SRXB SE RES/DSIR/EIB L ST LOBBY WARD NRC PDR NSIC MURPHY I G A COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 2 2 1 1 1 1 1 1 1 1 1.1 1'NOTE TO ALL"RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 36 ENCL 36 I

c ti WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Box 968~3000 George Washington Way~Richland, Washington 99352 Docket No.50-397 June 13, 1990 Document Control Desk U.S.Nuclear Regulatory Commission Washington, D.C.20555

Subject:

NUCLEAR PLAN1 NO.2 LICENSEE EVENT REPORT NO.90-010

Dear Sir:

Transmitted herewith is Licensee Event Report No.90-010 for the WNP-2 Plant.This report is submitted in response to the report requirements of 10CFR50.73 and discusses the items of reportabi lity, corrective action taken, and action taken to preclude recurrence, Very truly yours, C.H.Powers (H/D 927H)WNP-2 Plant Hanager CHP:lr

Enclosure:

Licensee Event Report No.90-010 cc: Hr.John B.Hartin, NRC-Region V Hr.C.J.Bosted, NRC Site (H/D 901A)INPO Records Center-Atlanta, GA Hs.Dottie Sherman, ANI Hr.D.L.Williams, BPA (H/D 399)9006200446 900613 PDR ADOCK 05000="97 PDC YP~

NRC F,OEIM 366 (63)9l V.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)APPROVEO 0MB NO.31504)104 EXP IR ES: 4/30/92 ESTIMATED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUESTt 50.0 HAS.FORWARD COMMENTS REGARDING BUADEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P4)30).U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON.

DC 20555, AND TO THE PAPERWORK REDUCTION PROJECT 131500104), OFFICE OF MANAGELAENT AND BUDGET, WASHINGTON, DC 20503, FACILITY NAME (1I Washington Nuclear Plant-Unit 2 econ ary on alnmen nglneere a e y ea ure Caused by Inadequate Work Control DOCKET NUMBER (2)PA 8 3l 0 5 0 0 03 97'FO c ua ion MONTH DAY YEAR EVENT DATE (SI YEAR LER NUMBER (6)SEQUENTIAL

)4:: NUMBER REPORT DATE (7I N: RSV+~MONTH DAY YEAR...I NUMBER DOCKET NUMBERISI 0 5 0 0 0 FACILITY NAMES OTHER FACILITIES INVOLVED (8)0 517 9 0 9 0 01 0 00 06 139 0 0 5 0 0 0 OPERATING MODE (BI POWE R LEVEL P P 0 (10)'e,.AX~4g"-.g'/9y:.NAME 20.402(B)20.406(~I (1)(i)20.405(c l(1)(ill 20.405(e l(1)(ill)20A05(~l(1)(lcl 20.405(e)(I

)(I)20.405(cl 60.38 (cl (1)50.38(c)(2)50.73 I~)(2 I (il 50.73(~)(2)(ill 50.73(e)(2)(l ill LICENSEE CONTACT FOA THIS LER (12I 50.73(e)(2)(irl 50.73(~)LS I (rl 50.73 (4 l(2)(rII)50,73(~l(2)(r BI)(A I 50,73(~l(2)(rllil(BI 60,73 I~I (2)(n)THIS REPORT IS SUBMITTED PURSUANT T 0 THE RLOUIREMENTS OF 10 CFR (I:/Check one or more of the follow/no/(ll 73.71(BI 73.71(cl OTHER/Specify in Ahttrect OelOw end In Tent, IIRC form 366AI TELEPHONE NUMBER C.L.Fies, Compliance Engineer AREA CODE 50 937 7-03 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPOAT (13I CAUSE SYSTFM COMPONENT MANUFAC TURER TO NPADS:-~8881," CAUSE SYSTEM COMPONENT MANUFAC TVRER EPORTABLE TO NPADS Iyr.S~c.b.AS.PIC.IN'9..PNM KB.M%I((SUPPLEMENTAL REPOAT EXPECTED (14)EXPECTED SUBMISSION DATE (15)MONTH DAY YEAR YES/lf yf 6 comPlete EXPECTED SVEMISSIDII DA TEI NO ABsTRAGT/Limit to/400 tpecet, l.e., eppronlmetefy II fteen tlnple tpece typewrinen hnetl 118)During the reactor refueling outage on May 17, 1990, at 1438 hours0.0166 days <br />0.399 hours <br />0.00238 weeks <br />5.47159e-4 months <br /> a Secondary Containment isolation occurred.This Engineered Safety Feature (ESF)actuation resulted in the shutdown of non-safety related HVAC equipment, the actuation of containment isolation valves, and the startup of various safety related systems such as Standby Gas Treatment.

Plant maintenance workers were replacing auxiliary relays as part of the normal preventative maintenance program when they inadvertently placed two channels in the tripped condition which initiated the ESF actuation.

The root cause for this event was inadequate work control which allowed work to proceed simultaneously on two safety-related divisions when no provisions had been made for such an activity.Immediate corrective action was taken to place the Secondary Containment systems in their normal configuration.

There is no safety significance associated with this event.ESF isolations and actuations occurred as designed for the plant configuration at the time of the event.Accordingly, this event posed no threat to the health and safety of the public or plant personnel.

NRC Form 386 (54)9)

NRC FORM366A (689)r U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINUATION APPROVED OMB NO.31500104 EXPIRES: 4/30)92 ESTIM ED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REQUEST: 500 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH (P830), U.S, NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31504)104).

OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.FACILITY NAME (1)DOCKET NUMBER (2)LER NUMBER (6)SEQUENTIAL NVMSSR SBIS REVISION Srll NVMSSR PAGE (3)Washington Nuclear Plant-Unit 2 TEXT llf IIXNP<<>>4~14 nqIP)PIL u44 44'diO'O44ISRC F4'6649)(IT)o s o o o 397 9 0 0 0-0 0 OF 0 3 Plant Conditions Power Level-OX Plant Mode-5 Event Descri tion During the reactor refueling outage on May 17, 1990, at 1438 hours0.0166 days <br />0.399 hours <br />0.00238 weeks <br />5.47159e-4 months <br /> a Secondary Con-tainment Isolation Engineered Safety Feature (ESF)Actuation occurred.At the time of the actuation maintenance work was being performed by Plant Maintenance workers on General Electric Model,HFA auxiliary relays.This ESF Actuation initiated a Balance of Plant (BOP)isolation involving Group 3 (Primary and Secondary Contain-ment Ventilation and Purge Systems)and part of Group 4 (Miscellaneous Balance of Plant Systems).These two Groups are part of the Nuclear Steam Supply Shutoff System (NSSSS)that provides overall isolation of plant systems in response to various process parameters.

During refueling (Mode 5)the Primary Containment can be open to the Secondary Containment and this isolation function is limited to Secondary Containment although Primary Containment isolations will occur if com-ponents have not been deactivated.

In addition to the isolations, the Secondary Containment ESF actuation causes the normal Reactor Building (Secondary Containment) heating and ventilating supply and exhaust fans to stop and Reactor Building pressure control is transferred to the safety-related Standby Gas Treatment (SGT)system which was initiated by this event.Immediate Corrective Action Plant operators took immediate corrective action to place the systems back in their normal configuration.

The restoration of systems, including the shutdown of SGT, was completed at 1520 hours0.0176 days <br />0.422 hours <br />0.00251 weeks <br />5.7836e-4 months <br />.Further Evaluation and Corrective Action A.Further Evaluation 1.This event is being reported per the requirements of 10CFR50.73(a)(2)(iv) as an"......event or condition that resulted in manual or automatic actuation of an Engineered Safety Feature (ESF)......".

2.Further evaluation showed work was in progress on the Division I manual actuation relay (MS-RLY-K35A) which put the"AH channel in the tripped condition.

When work started on the HBH channel relay (MS-RLY-81B) this caused a full trip on the outboard relay cabinet (RC-1)which resulted in the Secondary Containment Isolation.

NRC Form 366A (689)

NRC FORM 366A (689)U.S.NUCLEAR REGULATORY COMMISSION LICENSEE EVENT REPORT (LER)TEXT CONTINuATION APPRQVEO 0MB NO.31504108 EXPIRES: el30)92 ESTIMAIED BURDEN PER RESPONSE TO COMPLY WTH THIS INFORMATION COLLECTION REOUESTI 50.0 HRS.FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS AND REPORTS MANAGEMENT BRANCH IP-5301.U.S.NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31500104).

OFFICE OF MANAGEMENT AND BUDGET, WASHINGTON, OC 20503.FACILITY NAME (11 DOCKET NUMBER (21 YEAR LER NUMBER (6)SEOUENTIAL)II 6 NUMBER~6 REV IS ION NUM8EII PAGE (3)Washin ton Nuclear Pl ant-Unit 2 TEXT III mar S>>oe JI I88II)cad, IIee ed)IPdoINJ HRC Farm 366ABJ (12)0 5 0 0 0 3 9 7 9 0 0 1 0 0 0 3 OF 0 3 3.The root cause was inadequate work control which allowed work to proceed simultaneously on two safety related divisions when no provisions had been made for such an activity.4.There were no structures, components or systems that were inoperable prior to the start of this event which contributed to the event.B.Further Corrective Action 1.Work control procedures will be reviewed to determine if additional steps need to be added to control Division related work.2.The current work control administrative process will be reviewed with Plant Maintenance Department Supervisor and Engineering personnel.

Safety Si nificance There is no safety significance associated with this event.ESF isolations and actuations occurred as designed for the plant configuration at the time of the event.Accordingly, this event posed no threat to the health and safety of the public.or plant personnel.

Similar Events None EIIS Information Text Reference EIIS Reference Secondary Containment Nuclear Steam Supply Shutoff System Primary Containment Standby Gas Treatment Main Steam Relay K35A (MS-RLY-K35A)

Main Steam Relay K81B (MS-RLY-K81B)

System C BH SB SB~Com onent RLY RLY NRC Form 366A (689)

C 4 p!N