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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARGO2-99-177, LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With1999-10-0101 October 1999 LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With 05000397/LER-1984-027, Revised LER 84-027-01:on 840322,main Steam Relief Valve Solenoids Failed Due to Grounding in Solenoid Coils.Voltage Spike Suppression Diodes Installed Across Each Solenoid Circuit.Ge Conducting Review of Failures1984-07-19019 July 1984 Revised LER 84-027-01:on 840322,main Steam Relief Valve Solenoids Failed Due to Grounding in Solenoid Coils.Voltage Spike Suppression Diodes Installed Across Each Solenoid Circuit.Ge Conducting Review of Failures 05000397/LER-1984-008, Revised LER 84-008-01:on 840128,suppression Pool Level Indicator & Pool Level Fell Below Tech Spec Limits.Caused by Simultaneous Loss of Control Room Indication & Operation of Loop a of RHR Sys.Indication Reenergized1984-07-19019 July 1984 Revised LER 84-008-01:on 840128,suppression Pool Level Indicator & Pool Level Fell Below Tech Spec Limits.Caused by Simultaneous Loss of Control Room Indication & Operation of Loop a of RHR Sys.Indication Reenergized 05000397/LER-1984-026, Revised LER 84-026-01:on 840419 & 27,water Found in Train B of Standby Gas Treatment Sys.Caused by Pressure Surges in Preaction & Deluge Portions of Fire Protection Sys.Design Change in Progress1984-05-18018 May 1984 Revised LER 84-026-01:on 840419 & 27,water Found in Train B of Standby Gas Treatment Sys.Caused by Pressure Surges in Preaction & Deluge Portions of Fire Protection Sys.Design Change in Progress 05000397/LER-1983-003, Updated LER 83-003-01:on 831222,walk Down Revealed Fire Dampers Not Meeting Fire Rating Requirements,Violating Tech Specs.Caused by Personnel Error.Defective Dampers Replaced1984-03-28028 March 1984 Updated LER 83-003-01:on 831222,walk Down Revealed Fire Dampers Not Meeting Fire Rating Requirements,Violating Tech Specs.Caused by Personnel Error.Defective Dampers Replaced 05000397/LER-1984-010, Supplemental LER 84-010-00 Providing Corrective Actions Inadvertently Omitted from Original Ler.All Five Excess Flow Check Valves Removed,Modified & Reinstalled.Drawings Revised Indicating Water or Gas Svc1984-03-28028 March 1984 Supplemental LER 84-010-00 Providing Corrective Actions Inadvertently Omitted from Original Ler.All Five Excess Flow Check Valves Removed,Modified & Reinstalled.Drawings Revised Indicating Water or Gas Svc 1999-10-01
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML17284A9001999-10-31031 October 1999 Rev 0 to COLR 99-15, WNP-2 Cycle 15,COLR GO2-99-177, LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With1999-10-0101 October 1999 LER 99-S01-00:on 990903,failure to Take Compensatory Measure within Required Time Upon Failure of Isolation Zone Microwave Unit,Was Noted.Caused by Personnel Error.Provided Refresher Training on Compensatory Measures.With ML17284A8941999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for WNP-2.With 991012 Ltr ML17284A8801999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for WNP-2.With 990910 Ltr ML17284A8691999-07-31031 July 1999 Monthly Operating Rept for July 1999 for WNP-2.With 990813 Ltr ML17292B7421999-07-20020 July 1999 LER 99-001-00:on 990628,ESF Signal Closed All Eight MSIVs While Plant Was Shutdown.Caused by Failure of Relay RPS-RLY-K10D.Subject Relay Was Replaced & Tested on 990630. with 990720 Ltr ML17292B7271999-06-30030 June 1999 Monthly Operating Rept for June 1999 for WNP-2.With 990707 Ltr ML17292B6961999-05-31031 May 1999 Monthly Operating Repts for May 1999 for WNP-2.With 990608 Ltr ML17292B6641999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for WNP-2.With 990507 Ltr ML17292B6391999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for WNP-2.With 990413 Ltr ML17292B5871999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for WNP-2.With 990311 Ltr ML17292B5571999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for WNP-2.With 990210 Ltr ML17292B5621999-01-31031 January 1999 Rev 1 to COLR 98-14, WNP-2 Cycle 14 Colr. ML17292B5341999-01-15015 January 1999 Part 21 Rept Re Incorrect Modeling of BWR Lower Plenum Vol in Bison.Defect Applies Only to Reload Fuel Assemblies Currently in Operation at WNP-2.BISON Code Model for WNP-2 Has Been Revised to Correct Error ML17292B5331999-01-15015 January 1999 Part 21 Rept Re XL-S96 CPR Correlation for SVEA-96 Fuel. Defect Applies Only to WNP-2,during Cycles 12,13 & 14 Operation.Evaluations of Defect Performed by ABB-CE ML17292B4791998-12-31031 December 1998 Washington Public Power Supply Sys 1998 Annual Rept. with 981215 Ltr ML17292B5351998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for WNP-2.With 990112 Ltr ML17292B5741998-12-31031 December 1998 WNP-2 1998 Annual Operating Rept. with 990225 Ltr ML17284A8231998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for WNP-2.With 981207 Ltr ML17284A8081998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for WNP-2.With 981110 Ltr ML17292B4451998-10-27027 October 1998 LER 98-012-01:on 980715,failure to Comply with Requirements of TS SR 3.8.4.7 Was Noted.Caused by Inadequate Work Practices.Training Session Was Held with Personnel.With 981027 Ltr ML17284A7831998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for WNP-2.With 981007 Ltr ML17284A7491998-09-10010 September 1998 WNP-2 Inservice Insp Summary Rept for Refueling Outage RF13 Spring,1998. ML17284A7561998-09-0303 September 1998 LER 98-013-00:on 980805,ESF Actuations Were Noted Due to Deenergization of Vital Electrical Bus SM-8.Caused by Inadequate Direction in Troubleshooting Plan.Will Conduct Training for Engineering Personnel.With 980903 Ltr ML17284A7571998-09-0202 September 1998 LER 98-014-00:on 980807,completion of TS 3.8.1.F Required Shutdown Due to Inoperability of EDG-2 Was Noted.Caused by Degraded Voltage Regulator for DG-2.Replaced Voltage Regulator & Associated Scrs.With 980902 Ltr ML17284A7551998-09-0202 September 1998 LER 98-015-00:on 980808,discovered Reactor Coolant Pressure Boundary Leak During Shutdown Conditions.Caused by Leakage from Socket Weld (Fwb 63) on Elbow Connection.Failed Piping Connection Was Replaced.With 980902 Ltr ML17284A7681998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for WNP-2.With 980915 Ltr ML17284A7311998-08-17017 August 1998 LER 98-012-00:on 980716,determined That 24-month SR 3.8.4.7 Had Not Been Fulfilled within Specified Frequency.Caused by Inadequate Work Practices.License Requested & Received Enforcement Discretion Re Battery Svc test.W/980817 Ltr ML17284A7261998-07-31031 July 1998 Monthly Operating Rept for July 1998 for WNP-2.W/980810 Ltr ML17284A7121998-07-23023 July 1998 LER 98-006-01:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of 10CFR50,App R Calculations for High Impedance Faults.Caused by Inadequate Work Practices.Implemented Procedural Changes ML17284A6951998-07-17017 July 1998 LER 98-011-00:on 980617,ECCS Pump Room Flooding Was Noted Due to FP Sys Pipe Break.Caused by Inadequate Design of FP Sys.Detailed Review of FP Sys Design Was Conducted. W/980717 Ltr ML17284A6961998-07-15015 July 1998 LER 98-010-00:on 980615,TS Required Shutdown Due to Inoperability of TIP Sys Isolation Valve Was Noted.Caused by Improper Installation of TIP Tubing.Reattached Affected Tubing & Inspected Other TIP tubing.W/980715 Ltr ML17284A6731998-07-0101 July 1998 LER 98-009-00:on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in preparation.W/980701 Ltr ML17284A6751998-06-30030 June 1998 Ro:On 980617,flooding of RB Northeast Stairwell with Consequential Flooding of Two ECCS Pump Rooms.Caused by Inadequate Fire Protection Sys Design.Pumped Out Water from Affected Areas to Point Below Berm Areas of Pump Rooms ML17284A6641998-06-24024 June 1998 LER 98-008-00:on 980531,inadvertent Full Scram During RPV Leak Testing in Mode 4 Was Noted.Caused by Change in Mgt Techniques.Revised Procedures to Take Into Account Addl Water Head in Pressure Sensing lines.W/980624 Ltr ML17284A6651998-06-24024 June 1998 LER 98-007-00:on 980530,inadvertent Full Scram & Division 1 ECCS Injection Was Noted.Caused by Failure to Meet Mgt Work Practice Expectation When Encountering Deficient Procedure. Incident Review Board Convened to Review event.W/980624 Ltr ML17284A6631998-06-19019 June 1998 LER 98-006-00:on 980520,discovered Discrepancies in Low Voltage Bus Calculations During Review of App R Calculations for High Impedance Fault Analysis.Caused Indeterminate. Implemented Procedural Changes Involving Operator Action ML17284A6551998-06-0404 June 1998 LER 98-005-00:on 980506,potential for Failure of RHR Sys Valve to Close on Isolation Signal Was Noted.Caused by Design Deficiency.Caution Tag Was Placed on RHR-V-40 Control Switch to Inform Plant Operators of limitation.W/980604 Ltr ML17284A6421998-06-0101 June 1998 LER 98-004-00:on 980502,determined That Primary Containment Penetration Overcurrent Protection Does Not Meet Reg Guide 1.63 Requirements.Caused by Inadequate Design Changes. Installed Addl Fuse in RHR-MO-9 circuit.W/980601 Ltr ML17284A6491998-05-31031 May 1998 Rev 0 to COLR 98-14, WNP-2,Cycle 14 Colr. ML17292B4031998-05-31031 May 1998 Monthly Operating Rept for May 1998 for WNP-2.W/980608 Ltr ML17292B3921998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for WNP-2.W/980513 Ltr ML17292B3291998-04-0909 April 1998 LER 98-003-00:on 980311,WNP-2 Experienced SCRAM Signal as Result of Low Rpv.Caused by Less than post-SCRAM Operational Strategy for Resetting SCRAM Signal in Conditions.Changes in post-SCRAM Operational Strategy implemented.W/980409 Ltr ML17292B3281998-04-0909 April 1998 LER 98-002-00:on 980311,reactor Scram & Plant Transient Occurred,Due to Failed Closed Main Steam Isolation Valve. Caused by Loss of Pneumatic Actuating Supply Pressure. Problem Evaluation Request Written for Failure of MS-V-22D ML17292B3371998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for WNP-2.W/980409 Ltr ML17292B2641998-03-0404 March 1998 Performance Self Assessment,WNP-2. ML17292B2661998-03-0404 March 1998 LER 98-001-00:on 980203,automatic Start of HPCS EDG Was Noted.Caused by Operator Error.Operations Crew Stabilized Plant at Approximately 75% Reactor Power & Investigation of Event Was initiated.W/980304 Ltr ML17292B2911998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for WNP-2.W/980313 Ltr ML17284A7971998-02-17017 February 1998 Rev 28 to Operational QA Program Description, WPPSS-QA-004.With Proposed Rev 29 ML17292B3591998-02-12012 February 1998 WNP-2 Cycle 14 Reload Design Rept. 1999-09-30
[Table view] |
LER-2083-003, Updated LER 83-003-01:on 831222,walk Down Revealed Fire Dampers Not Meeting Fire Rating Requirements,Violating Tech Specs.Caused by Personnel Error.Defective Dampers Replaced |
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, Update R: port - Previous Report Date 01/20/84
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- 28 Aremovto oms NO. sino.0iDe LICENSEE EVENT REPORT (LER) """"
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NAME TELEPHONE NVMSER AREA CQQE L. D. Kassakatis, Plant Compliance Engineer 5,0,9 3,7 , 7, ,2 ,5,0,1 COMPLETE ONE LINE FOR EACM COMPONENT F41 LURE DESCRISE0 IN THIS REPORT (13) [Xt. 4/27 CausE SYSTEM COM ONENT **yW;^c "$7",',',!!' CAUSE $YSTEM COMPO*iE NT **;$#^O "h["[',((' ! +
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A T Au a, . ,== es a e . see,..., ev ee .,,,e- ,,,,e., n ei A walk down was performed on fire dampers and those listed below were found which did not meet UL fire rating requirements, thus violating Tech Spec 3/4.7.7. The system remained fully functional even though the dampers were not in compliance with UL standards. Thus potential consequences were minimal. Damper identification: WMA-FD-1,
-2, -3, -6, -7, -8, -9, -10, -11, -14, and DRA-FD-34-1.
8404040190 840328 PDR S
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4 o NRC Ford 364A U S NUCLfAR REGUL ATOAV COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION AnaovEo oMe No mo-oio4 ERPIRES 8/31 =85 F ACILITV NAME III DOCKti NUMetR (21 LER NUMBER (69 PAGE13)
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Washington Nuclear Project - Unit 2 o ls j o lo lo l 31917 81 3 0l0l3 -
0 l1 012 OF Ql2 11XT (# more spece e segurmf, use sakteoner NRC Form Jti&4's/ (1M The fire dampers which were originally reported as being modified by the vendor were numbered incorrectly. This was due to personnel error when reading the associated drawings. Dampers WMA-FD-3 and 6 were originally reported as WMA-FD-18 and 15 respectively. The modification made to the dampers was minor cutting to obtain the size required to allow installation into the existing duct work. This cutting, however, voided the U.L. fire rating of the dampers, thus violating Technical Specification 3/4.7.7, which requires all fire rated assemblies to be operable at all times.
Corrective Action:
A fire watch has been established to monitor the affected areas.
Each modified damper is being removed and replaced with a U.L. approved damper.
g ,. . . . _.
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- E Washington Public Power Supply System P.O. Box 968 3000 GeorgeWashington Way Richland, Washington 99352 (509)372-5000 Docket No. 50-397 March 28, 1984 Document Control Desk U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Subject:
NUCLEAR PROJECT NO. 2 LICENSEE EVENT REPORT NO.83-003 REVISION 1
Dear Sir:
Transmitted herewith is Revision 1 to Licensee Event Report No.83-003 for WhP-2 Plant. This report is submitted in response to the report requirements of Technical Specification Section 6.9.1.7 and discusses the item of noncompliance and corrective action taken. The revision was necessary because of component misidentification in the original report.
Very truly yours, 5 $6 J.D. Martin (M/D927M)lN WNP-2 Plant Manager JDM:de
Enclosure:
Licensee Event Report No.83-003 Revision 1 cc: Mr. John B. Martin, Administrator Region V, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission 1450 Maria Lane Walnut Creek, California 94596 Mr. A. D. Toth, NRC Resident Inspector (901A)
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