ML17289A596

LER 92-018-00:on 920428,determined That Six Locations Not Provided W/Emergency Lighting Capacity & Operator Actions Required for Fire Outside Main CR Not in Procedures.Caused by Inadequate Design.Lighting provided.W/920528 Ltr

ML17289A596
Person / Time
Site:	Columbia
Issue date:	05/28/1992
From:	Arbuckle J, John Baker WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GO2-92-131, LER-92-018, LER-92-18, NUDOCS 9206030310
Download: ML17289A596 (8)

Text

ACCELERATED DIQ>RIBUTION DEMONSTRATION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9206030310 DOC.DATE: 92/05/28 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH. NAME AUTHOR AFFILIATION ARBUCKLE,J.D. Washington Public Power Supply System BAKER,J.W. Washington Public Power Supply System RECIP.NAME RECIPIENT AFFILIATION

SUBJECT:

LER 92-018-00:on 920428,determined that six locations not provided w/emergency lightinq capacity & operator actions required for fire outside maxn CR not in procedures. Caused D by inadequate design. Lighting provided.W/920528 ltr.

DISTRIBUTION CODE: IE22T COPIES RECEIVED:LTR ENCL ( SIZE:

TITLE: 50.73/50.9 Licensee Event Report (LER), 3 Incident Rpt, etc.

NOTES: A RECIPIENT COPIES RECIPIENT COPIES D ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD5 LA 1 1 PD5 PD 1 1 D DEAN, W. 1 1 INTERNAL: ACNW 2 2 ACRS 2 2 AEOD/DOA 1 '1 AEOD/DS P/TPAB 1 1 AEOD/ROAB/DSP 2 2 NRR/DET/EMEB 7E 1 1 NRR/DLPQ/LHFB10 1 1 1 1 NRR/DLPQ/LPEB10'RR/DREP/PRPB11 NRR/DOEA/OEAB 1 1 2 2 NRR/DST/SELB 8D 1 1 NRR/DST/SICB8H3 1 1 N /J3 PLB8D1 1 1 NRR/DST/SRXB 8E 1 1 REG FILE 02 1 1 RES/DSIR/EIB 1 1 LE 01 1 1 EXTERNAL EG &G BRY CE i J ~ H 3 3 L ST LOBBY WARD 1 1 NRC PDR 1 1 NSIC MURPHY,G.A 1 1 NSIC POORE,W. 1 1 NUDOCS FULL TXT 1 1

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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 32 ENCL 32

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WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 May 28, 1992 G02-92-131 Docket No. 50-397 Document Control Desk U. S. Nuclear Regulatory Commission Washin g ton D. C. 20555

SUBJECT:

NUCLEAR PLANT WNP-2, OPERATING LICENSE NPF-21 LICENSEE EVENT REPORT NO.92-018 Transmitted herewith is Licensee Event Report No.92-018 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.

Sincerely, J..B r WNP-2 Plant Manager (Mail Drop 927M)

Enclosure CC: Mr. John B. Martin, NRC - Region V Mr. C. Sorensen, NRC Resident Inspector (Mail Drop 901A, 2 Copies)

INPO Records Center - Atlanta, GA Mr. D. L. Williams, BPA (Mail Drop 399) s igloo~

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LICENSEE EVEN EPORT (LER)

AGILITY NAHE (1) DOCKET HUHB R ( ) PAGE (3)

Washington Nuclear Plant Unit 2 0 5 0 0 0 3 9 7 I OF ITLE (4)

INADEQUATEEMERGENCY LIGHTING AND ALL REQUIRED OPERATOR ACTIONS FOLLOWING A FIRE OUTSIDE OF THE CONTROL ROOM NOT INCLUDED IN PROCEDURES - LESS THAN ADEQUATE DESIGN/COMMUNICATIONS EVENT DATE (5) LER NUMBER 6) REPORT DATE (7 OTHER FACILITIES INVOLVED (8)

HOHTH OAY YEAR YEAR Ã, SEQUENTIAL EV I SION HOHTH DAY YEAR FACILITY NAHES CKET NUHB R (5) ji NUMBER UHBER 50 0 4 2 8 9 2 9 2 0 I 8 0 0 0 5 2 8 9 2 50 PERATIHG MIS REPORT IS SUBHITTEO PURSUANT TO THE REQUIREMENTS OF IOCFR 5: (Check one or more of the following) (11)

ODE (9) 5 ONER LEVEL 0.402(b) 20.405(C) 50.73(a)(2)(iv) 77.71(b)

(i0) 20.405(a)(1)(i) 50.36(c)(1) 50.73(a)(2)(v) 73.73(c) 20.405(a)(l)(ii) 50.36(c)(2) 50.73(a)(2)(vii) THER (Specify in Abstract 20.405(a)(1)(iii) 50.73(a)(2)(i) 50.73(a)(2)(viii)(A) elow and in Text, NRC 20.405(a)(1)(iv) 50.73(a)(2)(ii) 50.73(a)(2)(viii)(B) orm 366A) 0.405(a)(1)(v) 50.73(a)(2)(iii) 50.73(a)(2)(x)

LICENSEE CONTACT FOR THIS LER (12)

TELEPHONE NUHBER J. D. Arbuckle, Licensing Engineer REA CODE 5 0 9 7 7 - 4 1 4 5 COMPLETE OHE LIHE FOR EACH COMPONENT FAILURE DESCRIBED IH THIS REPORT (13)

CAUSE SYSTEH COMPONENT HANUFACTURER EPORTABLE CAUSE SYSTEH COHPOHEHT HANUFACTURER REPORTABLE 0 NPRDS TO HPRDS SUPPLEMENTAL REPORT EXPECTED (14) EXPECTED SUBMISSION MONTH DAY YEAR ATE (15)

YES (If yes, compiete EXPECTED SUBMISSION DATE) HO TIIACT ed)

On April 28, 1992, following a review of concerns identified during a Quality Assurance audit of the fire protection program, it was determined that concerns pertaining to the adequacy of fixed lighting supplied for fire protection considerations and operator actions required for fires outside of the main control room were reportable in accordance with 10CFR50.73. Specifically, it was determined that six locations where components were located had not been provided with the emergency lighting capacity specified by 10CFR50, Appendix R. Plant Operator actions are required to reposition these components during the event of a fire. In addition, it was determined that not all operator actions required for fires outside of the main control room had been incorporated into procedures.

Immediate corrective action consisted of initiating action to provide portable emergency lighting in the areas affected and revising the procedure for fires outside of the control room to include required operator actions.

The causes of this event are 1) Less than Adequate Design in that emergency lighting was not provided in the locations required, and 2) Less than Adequate Communication in that all procedures were not revised following direction from Engineering. Further corrective actions consist of 1) staging portable lighting within the Plant for use in the event of a fire in the areas, 2) performing a 10CFR50.59 Safety Evaluation pertaining to the use of portable lighting in these areas, and 3) performing an additional review of procedures to ensure that operator actions pertaining to the WNP-2, Appendix R, Shutdown Evaluation have been addressed.

This, event did not affect the health and safety of either the public or Plant personnel.

LICENSEE EVENT REPORT )

TEXT CONTINUATION AGILITY NANE (1) DOCKET NUMBER (2) LER NUNBER (B) AGE (3) ear umber ev. No.

Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 2 1 B 0 2 F 5 ITLE (4)

INADEQUATE EMERGENCY LIGHTING AND ALL'EQUIRED OPERATOR ACTIONS FOLLOWING A FIRE OUTSIDE OF THE CONTROL ROON NOT INCLUDED IN PROCEDURES - LESS THAN ADEQUATE DESIGN COMMUNICATIONS P~IC Ch i Power Level - 0%

Plant Mode - 5 (Refueling)

Event Descri tion

=-

On April 28, 1992, following a review of concerns identified during the Quality Assurance triennial audit of the Fire Protection Program (Audit 92-595), it was determined that concerns pertaining to the adequacy of fixed emergency lighting supplied for fire protection considerations and operator actions for fires outside of the Main Control Room were reportable in accordance with the requirements of 10CFR50.73.

The concerns pertaining to emergency lighting were limited to four areas where breakers must be repositioned and two locations where motor-operated valves may need to be manually operated. The concerns pertained to the Supply System 10CFR50, Appendix R, Calculation NE-02-85-19 which provides analysis bases, methodology, results and individual calculations for supporting the WNP-2 Safe Shutdown Analysis for a Fire Incident.

Specifically, it was noted that the calculation required certain operator actions be taken in the event of a fire outside of the Main Control Room. These actions included 1) local operator operation of the High Pressure Core Spray (HPCS) System pump'circuit breaker, 2) manual operation of Standby Service Water (SW) System Valves SW-V-224B, SW-V-225B, SW-V-227B, SW-V-822B, and SW-V-823B to provide cooling to the Control Room Chiller Units, and 3) isolation of SW to the Reactor Closed Cooling (RCC)

System to mitigate potential spurious operation of valves SW-V-187A, SW-V-187B, SW-V-188A and SW-V-188B as required to prevent flooding in the area of the RCC Surge Tank. However, upon further review, it was determined that the areas in which these components were located had not been provided with the emergency lighting required by 10CFR50, Appendix R.

Furthermore, it was also determined that existing Plant procedures did not encompass all of the operator actions that would be required for a fire outside of the Main Control Room. In May 1990, following the expanded review of the WNP-2, Appendix R, Shutdown Analysis, Supply System Engineering issued an interoffice memorandum to Plant Operations which provided a summary of operator actions required to shutdown the reactor in the event of a fire. The summary included operator actions that had been required since Plant startup (1983 time-frame) and additional actions that were identified from followup reviews.

Although these requirements were included in Plant procedures for fires within the Main Control Room, they had not been incorporated into procedures for fires outside of the Control Room.

LICENSEE EVENT REPORT TEXT CONTINUATION

+)

AGILITY NAHE (1) DOCKET NUHBER (2) LER NUHBER (8) AGE (3) ear umber ev. No.

Mashington Nuclear Plant - Unit 2 0 5 .0 0 0 3 9 7 2 18 00 3 F 5 ITLE (4)

INADEQUATE EMERGENCY LIGHTING AND ALL REQUIRED OPERATOR ACTIONS FOLLOWING A FIRE OUTSIDE OF THE CONTROL ROOM NOT INCLUDED IN PROCEDURES - LESS THAN ADEQUATE DESIGN COMMUNICATIONS Immedi te orrective Acti n Immediate corrective actions were to initiate steps to provide for temporary lighting in the critical areas and revise the procedure for a fire outside of the Main Control room to include required operator actions.

F rther Evaluation and orrective Ac i n A. F~hE This event is reportable in accordance with the requirements of 10CFR50,73(a)(2)(v) as any event or condition that alone could have prevented the fulfillment of the safety function of structures or systems that are needed to shut down the reactor and maintain it in a safe shutdown condition.

2. There were no systems, structures or components that were inoperable at the time of the event that contributed to the event.

3. Pertaining to the emergency lighting issue, the requirements of 10CFR50, Appendix R (Section III.J), are such that emergency lighting with an eight-hour battery power supply be provided in all areas where operator actions are specified to mitigate the potential effects of a fire. Although WNP-2 is a non-Appendix R Plant, the Supply System was required to review its Fire Protection Program against Appendix R and did not take exception to this section, except for certain areas where the existing normal emergency lighting has been demonstrated to remain available to support post-fire safe shutdown.

The current plan for the six areas to ensure the adequacy of lighting for fire protection considerations is to take credit for portable lighting in lieu of providing eight-hour, battery-backed lighting. These areas'include four rooms where breakers must be repositioned only one time during an event, and the potential for valve operation in another room and also at the Service Water Pumphouse (which is outside of the Plant).

The use of portable lighting in lieu of fixed lighting will be addressed by means of the 10CFR50.59 Safety Analysis Process, which would require that a summary of the safety evaluation be included in the WNP-2 Annual Operating Report. It is not anticipated that the evaluation of the use of portable lighting will result in an unreviewed safety question.

LICENSEE EVENT REPORT (Ol)

TEXT CONTINUATION

, FACILITY HAHE (I) DOCKET NUHBER (2) LER NUHBER (8) PAGE (3) umber ev. Ho.

Washington Nuclear Plant - Unit 2 0 5 0 0 0 3 9 7 2 018 0 4 OF 5 ITLE (4)

INADEQUATE EMERGENCY LIGHTING AND ALL REQUIRED OPERATOR ACTIONS FOLLOWING A FIRE OUTSIDE OF THE CONTROL ROOM NOT INCLUDED IN PROCEDURES - LESS THAN ADEQUATE DESIGN COMMUNICATIONS 4, The causes of this event are 1) Less than Adequate Design in that emergency lighting was not provided in the locations required, and 2) Less than Adequate Communications in that all procedures were not revised following direction from Engineering.

Although emergency lighting requirements were stipulated in Calculation NE-02-85-19, the six areas as described in this LER were inadvertently omitted as being locations that required adequate lighting to allow for operator actions to be taken in the event of a fire. These areas should have been provided with the required emergency lighting.

Although Engineering provided direction pertaining to operator actions to be taken following a fire, the interoffice memorandum was not acted upon in a timely manner by Plant Operations because it was not fully understood. These actions should have been incorporated into the procedure for fires outside of the Main Control Room.

B. her rrecive Ac i n With regard to the emergency lighting concern, a walkdown of the areas involved was performed which confirmed that the required Operator actions could be accomplished with portable lighting. In addition, the required portable lighting was obtained and has been staged at four separate locations within the Plant. Scheduled maintenance will be performed on the portable lighting to ensure that the batteries are fully charged. This activity has been entered into the computerized Scheduled Maintenance System (SMS) to track completion efforts.

2. The 10CFR50.59 Safety Evaluation pertaining to the use of portable lighting for the six locations identified in this LER will be completed prior to startup from the on-going Maintenance and Refueling Outage (currently scheduled for July 1, 1992).

3. Engineering and Plant Operations will perform an additional review of applicable procedures to ensure that operator actions required by the WNP-2, Appendix R, Shutdown Analysis have been addressed. This review will be completed prior to startup from the ongoing Maintenance and Refueling Outage.

4. An evaluation will be performed pertaining to the process of how design information is transmitted to the Plant for incorporation into Plant procedures to determine if any changes are necessary. The evaluation will be completed by August 31, 1992.

LICENSEE EVENT REPORT (L )

TEXT CONTINUATION ACILITY NAME (1) DOCKET NUMSER (2) LER NUMBER (8) AGE (3)

- Unit ear umber ev. No.

Mashington Nuclear Plant 2 0 5 0 0 0 3 9 7 2 1 8 0 5 OF 5 ITLE (4)

INADEQUATE EMERGENCY LIGHTING AND ALL REQUIRED OPERATOR ACTIONS FOLLOWING A FIRE OUTSIDE OF THE CONTROL ROOM NOT INCLUDED IN PROCEDURES - LESS THAN ADEQUATE DESIGN COMMUNICATIONS fe i nifi n During the event period no fires were experienced which would have affected the ability to safely shutdown the Plant. Furthermore, the fire detection, suppression and barrier systems either remained operable or required compensatory measures were implemented. The operability of the fire detection instrumentation ensures that adequate warning capability is available for prompt identification of fires. Operability of the fire suppression systems ensures that adequate fire suppression capability is available to confine and extinguish fires. The operability of fire barriers and barrier penetrations minimize the possibility of a single fire involving more than one fire area prior to detection and extinguishment. Accordingly, this event did not affect the health and safety of either the public or Plant personnel.

imilar Event There have been LERs associated with implementation of the Fire Protection Program; however, none pertaining to emergency lighting or operator actions required to mitigate the potential effects of a fire.

f

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~sstem E~f g~m~nen High Pressure Core Spray (HPCS) BG System HPCS Pump Circuit Breaker BG Standby Service Water (SW) System BI SW-V-224B BI V SW-V-225B BI V SW-V-227B BI V SW-V-822B BI V SW-V-823B BI V Control Room Chiller Units CHU Reactor Closed Cooling (RCC) System CC SW-V-187A, SW-V-187B BI V SW-V-188A, SW-V-188B BI V RCC Surge Tank CC TK Service Water Pump House MK BLDG