ML18011B146
| ML18011B146 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 04/20/1995 |
| From: | Berg W, Green W DAIRYLAND POWER COOPERATIVE |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| LAC-13480, LER-95-001, LER-95-1, NUDOCS 9505080020 | |
| Download: ML18011B146 (5) | |
Text
RIORITY 1 ACCELERATED RIDS PROCI'.SSliC)
~REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9505080020 DOC.DATE: 95/04/20 NOTARIZED:
NO FACIL:50-409 La Crosse Boiling Water Reactor, Dairyland Power Coop AUTH.NAME AUTHOR AFFILIATION GREEN,W.R.
Dairyland Power Cooperative BERG,W.L.Dairyland Power Cooperative RECIP.NAME RECIPIENT AFFILIATION DOCKET N 05000409
SUBJECT:
LER 95-001-00:on 950412,noted that HPSW to containment building isolated.Caused by momentary LOP due to operational test of 1A EDG.Procedures for test being modified to include instructions to verify value being open.W/950420 ltr.DISTRIBUTION CODE: IE22T COPIES RECEIVED'LTR i ENCL l SIZE'3 TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.NOTES:License Exp date in accordance with 10CFR2,2.109(1/28/75).
Conversion App 5/25/72.FCLB/Gaskin,C.
1cy.05000409 RECIPIENT ID CODE/NAME ONDD PD INTERNAL:~O BRD/RAB aM wRmz/DE/EEL NRR/DISP/PIPB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DSSA/S PS B/B RES/DSIR/EIB EXTERNAL: L ST LOBBY WARD NOAC MURPHY,G.A NRC PDR NOTES: COPIES LTTR ENCL 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 RECIPIENT ID CODE/NAME FAIRTILE,M AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DOPS/OECB NRR/DRCH/HICB NRR/DSSA/SPLB NRR/DSSA/SRXB RGN3 FILE 01 LITCO BRYCE,J H NOAC POORE,W.NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 1 VOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP I.'S TO REDUCE iVASTE!CONTACT'I'I IE DOCL'iIEYT CONTROL DES~K.ROON!Pl-37(EAT.
504-2033)TO FLIC!I%ATE 0'01'R iAi!I: PROil DISTRIBUTION LIS'I S I:OR DOC!.'iIEi'I'S 5'OU DOi"I'l I'.I)!FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED: LTTR 27 ENCL 27 OA/RYLANO t7 COOPERATIVE 3200 EASTAVE.SO.~PO.BOX817~LACROSSE, WISCONSIN54602-0817 (608)788-4000 FAX NO.(608)787-1420 WILLIAM L.BERG General Manager April 20, 1995 In reply, please refer to LAC-13480 DOCKET NO.50-409 Document Control Desk U.S.Nuclear Regulatory Commission Washington, DC 20555 Gentlemen:
SUBJECT:
Dairyland Power Cooperative La Crosse Boiling Water Reactor (LACBWR)Possession-Only License No.DPR-45 Licensee Event Re ort No.95-001
REFERENCES:
(1)10 CFR 50.73 In accordance with 10 CFR 50.73, attached is Licensee Event Report No.95-001.If there are any questions, please contact us.Sincerely, DAIRYLAND POWER COOPERATIVE WLB:WRG:dh William L.Berg, General Manager cc: John Martin, Regional Administrator U.S.Nuclear Regulatory Commission, Region III Morton Fairtile, Project Manager Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission 9505080020 950420 PDR ADOCK 05000409 g WA i@~i NRC Form 365 (043 I e LICENSEE EVENT REPORT (LER)UA.NUCLEAR AEOULATOAY COMMISSION APPROVED OMB NO.31600(BI EXPIRES: 6/31/SS FACILITY NAME (I)LA CROSSE BOILING WATER REACTOR LACBWR DOCKET NUMBER (2)PA E 0 5 0 0 0 4 0 9 1 OF 0 2 TITLE (i)LOSS OF CONTAINMENT BUILDING BASEMENT FIRE HOSE STATION OPERABILITY EVFNT DATE (SI LEA NUMBER (6)REPORT DATE (7)OTHER FACILITIES INVOLVED (6)MONTH DAY YEAR YEAR BEOUBNT/AL AX NUMBER S MONTH OAY NUMBER YEAR FACILITY NAMES DOCKET NUMBER(SI 0 5 0 0 0 0 4 12 95 95 001 00 04 17 9 5 0 5 0 0 0 OPERATINO MODE (6)POWER LEYEL 0 0 0 r.".Ã%%r:,?..Ã4<'.....
'.Nn:..THIS REPORT IS SUBMITTED PURSUANT T 0 THE REQUIREMENTS OF 10 CFA ():/Cher/t onr or more of the follorflnP)
(11 20A05(cl 60.73(e)(2)(Iv)50.73(e)(2)(v)50.73(el(2)(ril)60.73(e)12)(rill)IA)60.73(el(2)(vill)
(6)60.73(e)l2)(x I 20A02(B)20A05(e)(I I (ll 20A05(e)(I l(QI 20A05(e)(1)(ill I 20AOS(e)(I l(lv)20A05(el(1
)(vl 50.35(c)(I)50.36 (c)(2)50.73(~)(2)(ll 50.73(e)(2)(ll) 50.7 3 4 H2)(Ill)73.7((B)73.71(cl OTHER ISprclfy In Ahttrrct IN/ow rnd In Text, HRC Form JEEAI NAME LICENSEE CONTACT FOR THIS LER (12)WILLIAM R.GREEN, TECHNICAL SUPPORT ENGINEER TELEPHONE NUMBER AREA CODE 6 0 8 689-4 210 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE OESCRISEO IN THIS REPORT (13)CAUSE SYSTEM COMPONENT MANU FAC.TURER{".N CAUSE SYSTEM COMPONENT.?.B MAM PN..XN..erne...'ANUFAC TURER EPOATABLE TO NPADS I'M SUPPLEMENTAL REPORT EXPECTED (Ill X NO YES/If yet, complete EXPECTED SCII/htISSIOH DATE/ABSTRACT/Limit to 1400 tpecet, I.r., oppress/metrly I/Item t/nprr.tpece typrwr/tten liner/(16)EXPECTED SUBMISSION DATE (15)MONTH DAY YEAR The La Crosse Boiling Mater Reactor (LACBMR)Technical Specifications (T.S.)4.4.5 states,"The fir e hose stations in the following-locations shall be operable." This statement is followed by a list of five stations that includes the"Containment Building Basement." This requirement is applicable at all times.The action step of this T.S.states."Mi th a hose station inoperable, establish a 1-hour fire watch.or route an additional hose of equivalent capacity to the unprotected area within one hour." On April 12, 1995, it was noted by a LACBMR staff member that the High Pressure Service Mater to the Containment Building, which supplies water pressure to the Containment Building Basement hose station, was isolated.
'j~~NRC Form 366A (9431 LICENSEE EVENT REPORT{LER)TEXT CONTINUATION U.S.NUCLEAR REOULATORY COMMISSION APPROVED OMB NO.3150&)06 EXPIRES: 8/31/88 FACILITY NAME (11 LA CROSSE BOILING WATER REACTOR TEXT/I/moro E/Nco lr rrr/rorL vro a%I/E/rvN//Y/IC Frvm SEBA'r/(17)DOCKET NUMBER (3)o s o o o 409 LER NUMBER (6)SEQUENTIAL NUMBER 0 0 1 PP'EVISION NUM ER 0 0 PAGE (31 0 2oFO 2 The La Crosse Boiling Mater Reactor (LACBWR)Technical Specifications (T.S.)require that several fire hose stations be operable at all times.Included in the list of hose stations is the Containment Building Basement hose station.On the morning of Wednesday, April 12, 1995, a LACBWR operator discovered the High Pressure Service Mater (HPSM)Containment Building automatic isolation valve shut.which render ed the Containment Building hose station inoperable.
At the time of this discovery, the operators on duty were unsure of when the isolation had occurred, or what caused the isolation.
The shift super visor was informed and the valve was opened.Further investigation of the incident revealed that the valve had probably closed on the morning of April 10, 1995.On this date we had performed an operational test of the 1A Emergency Diesel Generator (EDG)which caused momentary loss of power to the 120 VAC regulated bus during the Power Supply transfer~.This caused a momentary loss of control power to the HPSW auto isolation valve and caused the valve to fail closed.This condition went unnoticed until April 12, 1995.Portions of the operational test of the 1A EDG were repeated on April 18, 1995, to confirm our analysis of this incident.The effect of this situation in Plant Safety was minimal.Numerous fire extinguishers are located throughout the Containment Building to be used in the event of a fir e.The HPSM auto isolation valve had the capability of being unisolated in the event of d fire and routine tours (every 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />)are conducted in the Containment Building to identify possible hazardous conditions such as fire hazards.To ensure this situation doesn't occur again, the procedure for the operational test of the 1A EDG that was performed on April 10, 1995, is being modified to include a statement that instructs operators to verify open, and reopen as necessary, the HPSW auto isolation valve during this procedure.