LER-1995-006, Forwards LER 95-006-01 Re Reactor Scram During Surveillance Testing Due to Protective Sys Relay Failure |
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9506190315 DOC.DATE: 95/06/08 NOTARIZED: NO DOCKET FACIL:50-397 WPPSS Nuclear Project, Unit 2, Washington Public Powe 05000397 AUTH.NAME AUTHOR AFFILIATION PARRISH,J.V.
Washington Public Power Supply System RECIP.NAME RECIPIENT AFFXLIATION Document Control Branch (Document Control Desk)
SUBJECT:
Forwards LER 95-006-01.
DISTRIBUTION CODE:
IE22T COPIES RECEIVED:LTR Q ENCL g SIZE: I+
TXTLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:
RECIPIENT ID CODE/NAME PD4-2 PD INTERNAL: ACRS AEOD/SPD/RRAB NRR/DE/ECGB NRR/DE/EMEB NRR/DOPS/OECB NRR/DRCH/HXCB NRR/DSSA/SPLB NRR/DSSA/SRXB RGN4 FILE Ol EXTERNAL: L ST LOBBY WARD NOAC MURPHY,G.A NRC PDR COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME CLIFFORD,J D RAB NRR/DE/EELB NRR/DISP/PI PB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DSSA/SPSB/B RES/DSIR/EIB LITCO BRYCE,J H
NOAC POORE,W.
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WASHINGTON PUBLIC POWER SUPPLY SYSTEM I?O. Box 968
~ 3000 George iVashington iVay
~ kichlanii, 1Vashington 99352-0968
~ (509) 372-5000 June 8, 1995 G02-95-110 Docket No. 50-397 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Gentlemen:
Subject:
NUCLEAR PLANT WNP-2, OPERATING LICENSE NPF-21, LICENSEE EVENT REPORT NO.95-006, REVISION 1 Transmitted herewith is Licensee Event Report No.95-006, Revision I for the WNP-2 Plant.
This report discusses the items of reportability, corrective action taken, and action taken to preclude recurrence.
This revision incorporates a correction and clarifications to the original report.
Should you have any questions or desire additional information, please call me or D.A. Swank at (509) 377-4563.
Sincerely
. V. Parrish (Mail Drop 1023)
Vice-President, Nuclear Operations JVP/BRH Enclosure cc:
LJ Callan, NRC-RIV KE Perkins, Jr., NRC-RIV, Walnut Creek Field Office NS Reynolds, Winston & Strawn NRC Sr. Resident Inspector (Mail Drop 927N, 2 Copies)
INPO Records Center - Atlanta, GA DL Williams, BPA (Mail Drop 399) 9506190315 950608 PDR ADOCK 05000397 S
PDR pygmy'
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| 05000397/LER-1995-001, :on 950113,failed to Satisfy Single Failure Criteria for Containment Isolation Function Due to Electrical Separation Plate in Control Panel Missing. Replaced Missing Barrier |
- on 950113,failed to Satisfy Single Failure Criteria for Containment Isolation Function Due to Electrical Separation Plate in Control Panel Missing. Replaced Missing Barrier
| 10 CFR 50.73(s)(2)(ii)
10 CFR 50.73(s)(2) | | 05000397/LER-1995-002, :on 950218,automatic Reactor Scram Occurred. Caused by Erroneous Positioning of Control During Performance of Scheduled Periodic Functional Test.Control Repositioned |
- on 950218,automatic Reactor Scram Occurred. Caused by Erroneous Positioning of Control During Performance of Scheduled Periodic Functional Test.Control Repositioned
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(8) | | 05000397/LER-1995-003, :on 940817,CR Indication Lost for PASS Inboard Ci Valve & Cycling for Restoration Erratic & Showed Continuous Closed Indication.Caused by Unclear TS Requirement.Ts Bases Will Be Revised |
- on 940817,CR Indication Lost for PASS Inboard Ci Valve & Cycling for Restoration Erratic & Showed Continuous Closed Indication.Caused by Unclear TS Requirement.Ts Bases Will Be Revised
| 10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)
10 CFR 50.73(e)(2)(i)
10 CFR 50.73(s)(2)(viii) | | 05000397/LER-1995-004, :on 950226,malfunction in Main Turbine DEH Control Sys Caused All Four High Pressure Turbine Governor Valves to Rapidly Close.Caused by Blown Fuse.Suspected Faulty Circuit Card Replaced |
- on 950226,malfunction in Main Turbine DEH Control Sys Caused All Four High Pressure Turbine Governor Valves to Rapidly Close.Caused by Blown Fuse.Suspected Faulty Circuit Card Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(s)(2)(i)
10 CFR 50.73(e)(2)
10 CFR 50.73(s)(2)(x)
10 CFR 50.73(s)(2)(v)
10 CFR 50.73(e)(2)(viii) | | 05000397/LER-1995-005, :on 950222,inoperable IRM Had Been Relied Upon to Meet TS Requirements During Reactor Startup.Caused by Lack of Neutron Source to Test Instrumentation. Sys Knowledge Gained Will Be Incorporated |
- on 950222,inoperable IRM Had Been Relied Upon to Meet TS Requirements During Reactor Startup.Caused by Lack of Neutron Source to Test Instrumentation. Sys Knowledge Gained Will Be Incorporated
| 10 CFR 50.73(a)(2)(i)
10 CFR 50.73(e)(2)(i)
10 CFR 50.73(e)(2)(vii)
10 CFR 50.73(e)(2)
10 CFR 50.73(e)(2)(iv)
10 CFR 50.73(e)(2)(v)
10 CFR 50.73(e)(2)(viii) | | 05000397/LER-1995-006-01, Forwards LER 95-006-01 Re Reactor Scram During Surveillance Testing Due to Protective Sys Relay Failure | Forwards LER 95-006-01 Re Reactor Scram During Surveillance Testing Due to Protective Sys Relay Failure | | | 05000397/LER-1995-006, :on 950405,reactor Scram Occurred During Surveillance Testing Due to Protective Sys Relay Failure. Replaced Failed Relay Before Plant Startup |
- on 950405,reactor Scram Occurred During Surveillance Testing Due to Protective Sys Relay Failure. Replaced Failed Relay Before Plant Startup
| 10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(s)(2)(i)
10 CFR 50.73(s)(2)(ii)
10 CFR 50.73(s)(2)(x)
10 CFR 50.73(s)(2)(v)
10 CFR 50.73(s)(2)
10 CFR 50.73(s)(2)(viii) | | 05000397/LER-1995-007, :on 950222,emergency Diesel Start Occurred Due to Voltage Transient on BPA Grid.Confirmation Was Received at 17:51 H That Disturbance Had Originated in BPA Grid |
- on 950222,emergency Diesel Start Occurred Due to Voltage Transient on BPA Grid.Confirmation Was Received at 17:51 H That Disturbance Had Originated in BPA Grid
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1995-008, :on 940125,TS Wording Lead to Potential TS Violation.Caused by Lack of Clarity in Ts.Submitted Improved TS for Plant to Provide Addl Clarity |
- on 940125,TS Wording Lead to Potential TS Violation.Caused by Lack of Clarity in Ts.Submitted Improved TS for Plant to Provide Addl Clarity
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1995-009, :on 950907,unexpected Closure of Inboard & Outboard MSIV Occurred During Performance of Surveillance Test.Caused by Activity Performed Under Procedure That Did Not Define Necessary Steps.Updated Procedure |
- on 950907,unexpected Closure of Inboard & Outboard MSIV Occurred During Performance of Surveillance Test.Caused by Activity Performed Under Procedure That Did Not Define Necessary Steps.Updated Procedure
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(x)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition
10 CFR 50.73(a)(2)(viii)(A)
10 CFR 50.73(a)(2)(viii)(B) | | 05000397/LER-1995-010, :on 950609,HPCS DG Declared Inoperable Due to Discovery That TS Test Method Incomplete.Caused by Inadequate Testing Procedure.Test Procedure for HPCS DG Reviewed & Special Test Procedures Written |
- on 950609,HPCS DG Declared Inoperable Due to Discovery That TS Test Method Incomplete.Caused by Inadequate Testing Procedure.Test Procedure for HPCS DG Reviewed & Special Test Procedures Written
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)
10 CFR 50.73(e)(2)(x)
10 CFR 50.73(e)(2) | | 05000397/LER-1995-011, :on 950919,failed to Comply W/Ts SR for RCIC Sys Due to Analysis Deficiency That Resulted in Inadequate Surveillance Test Procedure.Surveillance Procedure Revised to Correct Deficiency |
- on 950919,failed to Comply W/Ts SR for RCIC Sys Due to Analysis Deficiency That Resulted in Inadequate Surveillance Test Procedure.Surveillance Procedure Revised to Correct Deficiency
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function
10 CFR 50.73(a)(2)(vii), Common Cause Inoperability
10 CFR 50.73(a)(2)(iv), System Actuation
10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
10 CFR 50.73(a)(2)(i)
10 CFR 50.73(a)(2)(iii)
10 CFR 50.73(a)(2)(viii)(A) |
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