ML17285B332

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
Issue date:	06/13/1990
From:	Fies C, Powers C 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 DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION FIES,C.L. Washington Public Power Supply System POWERS,C.M. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION

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 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: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DSP 2 2 DEDRO 1 1 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB9H3 1 1 NRR/DLPQ/LHFB11 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB11 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB SD 1 1 NRR/DST/SICB 7E 1 1 NRR DST/SPLBSD1 1 1 NRR/DST/SRXB SE 1 1 EG 2 1 1 RES/DSIR/EIB 1 1 GN5 FILE 0 1 1 EXTERNAL: EGGG STUART,V.A 4 4 L ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY,G.A 1 1 NUDOCS FULL TXT 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 ELIMINATEYOUR 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 PDR S

ADOCK S 00SZ3 05000397 YjP~

PDC

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FACILITY NAME (Il DOCKET NUMBER (2I PAGE 3 Washington Nuclear Plant - Unit 2 0 5 0 0 03 97>oFO econ ary on a)nmen ngineere a e y ea ure c ua son Caused by Inadequate Work Control EVENT DATE (SI LER NUMBE4 (6) AEPOAT DATE (7) OTHF 4 FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR rr'Sex SEQVBNTIAL ~tr% REVISION MONTH OAY YEAR FACILITYNAMES DOCKET NUMBER(S)

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LICENSEE CONTACT FOR THIS LER (12)

NAME TELEPHONE NUMBER AREA CODE C. L. Fies, Compliance Engineer 50 937 7- 203 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBEO IN THIS REPO4T (13)

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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)

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EXPIRES: 4/30/92 ES ATEO BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION AEQVEST: 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND AEPORTS MANAGEMENT BRANCH (P4)30), U.S. NUCLEAR REGULATOAY COMMISSION, WASHINGTON, OC 20555, AND TO THE PAPERWORK REDUCTION PROJECT (31600)04), OFFICE OF MANAGEMENTANO BUDGET, WASHINGTON, OC 20503.

FACILI'TY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

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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)

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EXPIRES: 4/30/92 ES ATED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REOUEST: 50J) HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P4)30), U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31504)104), OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILI'TYNAME (1) DOCKET NUMBER (2) LER NUMBER (8) PAGE (3)

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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 System ~Com onent Secondary Containment Nuclear Steam Supply Shutoff System Primary Containment C Standby Gas Treatment BH Main Steam Relay K35A SB RLY (MS-RLY-K35A)

Main Steam Relay K81B SB RLY (MS-RLY-K81B)

NRC Form 368A (84) 9)

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ACCELERATED D> TRIBUTION DEMONS TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR: 9006200446 DOC. DATE: 90/06/13 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit, 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION FIES,C.L. Washington Public Power Supply System POWERS,C.M. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION

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 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: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DS P 2 2 DEDRO 1 1 NRR/DET/ECMB 9H 1 1 NRR/DET/EMEB9H3 1 1 NRR/DLPQ/LHFB1 1 1 1 NRR/DLPQ/LPEB10 1 1 NRR/DOEA/OEAB1 1 1 1 NRR/DREP/PRPB11 2 2 NRR/DST/SELB 8 D 1 1 NRR/DST/SICB 7E 1 1 PLBSD1 1 1 NRR/DST/SRXB SE 1 1 1 1 RES/DSIR/EIB 1 1 R ILE 01 1 1 EXTERNAL EG&G STUART I V ~ A 4 4 L ST LOBBY WARD 1 1 LPDR 1 1 NRC PDR 1 1 NSIC MAYS,G 1 1 NSIC MURPHY I G A 1' .

NUDOCS FULL TXT 1 1 NOTE TO ALL "RIDS" RECIPIENTS:

PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR 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 YP~

PDC

NRC F,OEIM 366 V.S. NUCLEAR REGULATORY COMMISSION (63)9l 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 LICENSEE EVENT REPORT (LER) 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 MANAGELAENTAND BUDGET, WASHINGTON, DC 20503, FACILITY NAME (1I DOCKET NUMBER (2) PA 8 3l Washington Nuclear Plant - Unit 2 0 5 0 0 03 97'FO econ ary on alnmen nglneere a e y ea ure c ua ion Caused by Inadequate Work Control EVENT DATE (SI LER NUMBER (6) REPORT DATE (7I OTHER FACILITIES INVOLVED (8)

MONTH DAY YEAR YEAR SEQUENTIAL N: RSV+~ MONTH DAY YEAR FACILITYNAMES DOCKET NUMBERISI

)4:: NUMBER ...I NUMBER 0 5 0 0 0 0 517 9 0 9 0 01 0 00 06 139 0 0 5 0 0 0 OPERATING THIS REPORT IS SUBMITTED PURSUANT T 0 THE RLOUIREMENTS OF 10 CFR (I: /Check one or more of the follow/no/ (ll MODE (BI 20.402(B) 20.405(cl 50.73(e) (2)(irl 73.71(BI POWE R 20.406( ~ I (1)(i) 60.38 (cl (1) 50.73( ~ ) I LS (rl 73.71(cl LEVEL (10) P P 0 20.405(c l(1)(ill 50.38(c) (2) 50.73 (4 l(2) (rII) OTHER /Specify in Ahttrect OelOw end In Tent, IIRC form 20.405(e l(1)(ill) 50.73 I~ ) (2 I (il 50,73( ~ l(2)(r BI)(A I 366AI 20A05( ~ l(1)(lcl 50.73( ~ ) (2)(ill 50,73( ~ l(2)(rllil(BI

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LICENSEE CONTACT FOA THIS LER (12I NAME TELEPHONE NUMBER AREA CODE C. L. Fies, Compliance Engineer 50 937 7- 03 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRIBED IN THIS REPOAT (13I MANUFAC COMPONENT MANUFAC EPORTABLE CAUSE SYSTFM COMPONENT TURER TO NPADS CAUSE SYSTEM TVRER TO NPADS Iyr . S~c.

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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 U.S. NUCLEAR REGULATORY COMMISSION APPROVED OMB NO. 31500104 (689) EXPIRES: 4/30)92 ESTIM ED BURDEN PER RESPONSE TO COMPLY WTH THIS r LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REQUEST: 500 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINUATION AND REPORTS MANAGEMENT BRANCH (P830), U.S, NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31504)104). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, DC 20503.

FACILITY NAME (1) DOCKET NUMBER (2) LER NUMBER (6) PAGE (3)

SEQUENTIAL SBIS REVISION NVMSSR Srll NVMSSR Washington Nuclear Plant - Unit 2 o s o o o 397 9 0 0 0 0 0 OF 0 3 TEXT llfIIXNP <<>>4 ~ 14 nqIP)PIL u44 44'diO'O44ISRC F4'6649) (IT)

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 U.S. NUCLEAR REGULATORY COMMISSION (689) APPRQVEO 0MB NO. 31504108 EXPIRES: el30)92 ESTIMAIED BURDEN PER RESPONSE TO COMPLY WTH THIS LICENSEE EVENT REPORT (LER) INFORMATION COLLECTION REOUESTI 50.0 HRS. FORWARD COMMENTS REGARDING BURDEN ESTIMATE TO THE RECORDS TEXT CONTINuATION AND REPORTS MANAGEMENT BRANCH IP-5301. U.S. NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555, AND TO 1HE PAPERWORK REDUCTION PROJECT (31500104). OFFICE OF MANAGEMENTAND BUDGET, WASHINGTON, OC 20503.

FACILITY NAME (11 DOCKET NUMBER (21 LER NUMBER (6) PAGE (3)

SEOUENTIAL )II6 REV IS ION YEAR NUMBER ~6 NUM8EII Washin ton Nuclear Pl ant - Unit 2 0 5 0 0 0 3 9 7 9 0 0 1 0 0 0 3 OF 0 3 TEXT IIImar S>>oe JI I88II)cad, IIee ed)IPdoINJ HRC Farm 366ABJ (12)

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 need control procedures will be reviewed to determine to be added to control Division related work.

if additional steps

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 System ~Com onent Secondary Containment Nuclear Steam Supply Shutoff System Primary Containment C Standby Gas Treatment BH Main Steam Relay K35A SB RLY (MS-RLY-K35A)

Main Steam Relay K81B SB RLY (MS-RLY-K81B)

NRC Form 366A (689)

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