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| %iiP-2, OPERATING LICENSE NO.NPF-21 SPECIAL REPORT: REACTOR BUILDING EFFLUENT MONITORING SYSTEM This special report is submitted pursuant to the requirements of WNP-2 Technical Specification Section 3.3.7.5,"Accident Monitoring Instrumentation." This Technical Specification includes Table 3.3.7.5-1, Item 31,"Reactor Building Effluent Monitoring System." Item 31 references Action 81 which states: "With the number of OPERABLE accident monitoring instrumentation channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel(s) to OPERABLE status within 72 hours, or:...In lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification | | %iiP-2, OPERATING LICENSE NO.NPF-21 SPECIAL REPORT: REACTOR BUILDING EFFLUENT MONITORING SYSTEM This special report is submitted pursuant to the requirements of WNP-2 Technical Specification Section 3.3.7.5,"Accident Monitoring Instrumentation." This Technical Specification includes Table 3.3.7.5-1, Item 31,"Reactor Building Effluent Monitoring System." Item 31 references Action 81 which states: "With the number of OPERABLE accident monitoring instrumentation channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel(s) to OPERABLE status within 72 hours, or:...In lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken', the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status." At 0854 hours on November 29, 1993, the Reactor Building Effluent Monitoring System was inoperable for 72 hours requiring the submittal of this special report.~EE E~D On November 26, 1993 at 0854 hours, the Main Control Room received a"Stack Monitor='System Trouble" annunciator. |
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| ====6.9.2 within====
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| 14 days following the event outlining the action taken', the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status." At 0854 hours on November 29, 1993, the Reactor Building Effluent Monitoring System was inoperable for 72 hours requiring the submittal of this special report.~EE E~D On November 26, 1993 at 0854 hours, the Main Control Room received a"Stack Monitor='System Trouble" annunciator. | |
| The.Stack Monitor Status Display indicated that the high range channel (PRM-RE-1C) had failed its self-test. | | The.Stack Monitor Status Display indicated that the high range channel (PRM-RE-1C) had failed its self-test. |
| The stack monitor is part of the Reactor Building Effluent Monitoring System which is required to be in service during Operating Conditions 1, 2, and 3 in accordance with Technical Specification Table 3.3.7.5-1 (Item 31).210064 9312230135 931210 PDR ADOCK 05000397 S PDR i Page Two SPECIAL REPORT: REACTOR BUILDING EFFLUENT MONITO~G SYSTEM Action Taken" Immediate corrective action was taken to declare the stack mohitor inoperable. | | The stack monitor is part of the Reactor Building Effluent Monitoring System which is required to be in service during Operating Conditions 1, 2, and 3 in accordance with Technical Specification Table 3.3.7.5-1 (Item 31).210064 9312230135 931210 PDR ADOCK 05000397 S PDR i Page Two SPECIAL REPORT: REACTOR BUILDING EFFLUENT MONITO~G SYSTEM Action Taken" Immediate corrective action was taken to declare the stack mohitor inoperable. |
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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML17284A6751998-06-30030 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 ML17292B2281998-01-14014 January 1998 Informs of Unexpected Change in Feedwater Temperature & Flow Indication Used to Calculate Plant Heat Balance During Routine Trending of Plant Computer Feedwater Temperatures on 980112.Corrective Actions Reduced Reactor Power to 99% ML17292A7921997-04-0909 April 1997 Ro:On 970327,reactor Scrammed.Evaluation Results,Conclusions & Corrective Actions Will Be Shared W/Nrc Prior to Plant Startup from Maint & Refueling Outage ML17292A5901996-11-0808 November 1996 Special Rept:On 961023,intermediate & High Range Stack Monitors PRM-RE-1B & PRM-RE-1C Declared Inoperable.Caused by Monitor Output Had Upward Trend Due to Electronic Noise Interference.Work Request Generated ML17291B0981995-11-0808 November 1995 Special Rept:On 951026,RB Effluent Monitoring Sys Inoperable for 72 H Due to Failure of Mid Range Stack Monitor.Cryostat Cooling Assemblies for Mid & High Range Stack Monitors Returned to Vendor for Refurbishment ML17291A9781995-08-18018 August 1995 Special Rept:On 950712,loose Part Detection Sys Channel 4 Failed Due to Electrical Noise During Daily Check.Channel 4 Will Remain Inoperable Until Next Forced or Scheduled Outage When Primary Containment de-inerted for Other Work ML17291A6961995-03-16016 March 1995 Special Rept:On 950305,reactor Bldg Effluent Monitoring Sys Was Inoperable for 72 Hrs.Caused by Failure of Stack Monitor Detector.Stack Monitor Returned to Svc on 950314 ML17291A4131994-09-26026 September 1994 Special Rept:On 940825,loose Part Detection Sys Channel Number Eight Actuated Associated MCR Alarm & on 940908 Subj Channel Began Alarming Due to Electronic Noise Originating in Drywell.Electronic Module of Channel Removed ML17290A8871993-12-17017 December 1993 Special Rept:On 931116,loose Parts Detection Sys Channel 5 Did Not Pass Daily Channel Surveillance.Exact Cause Not Determined.Need to Provide Addl Notifications Should Other Channels Become Inoperable Not Necessary ML17290A8381993-12-10010 December 1993 Special Rept:On 931126,main Control Room Received Stack Monitor Sys Trouble Annunciator & Status Display Indicated High Range Channel Failed self-test.Caused by Component Failure of Stack Monitor Detector.Replacement in Progress ML17290A5301993-06-11011 June 1993 Special Rept:On 930503,space Frame & Attached Seismic Triaxial Peak Accelorograph (SEIS-TPA-1) Removed to Allow for Refueling of Reactor Core.Instrument Returned to Svc on 930607 ML17289B1281993-01-11011 January 1993 Update to 921007 Special Rept Re Inoperability of Loose Parts Detection Instrumentation Following Failure of Channel 1 on 921113.On 921128,constant Alarm Received on Channel 8. Maint Work Request Initiated to Repair Failed Channels ML17289A9161992-10-0707 October 1992 Special Rept:On 920905,channel 1 on Main Steam Line D Nozzle in Drywell Did Not Pass Surveillance & Inoperable for More than 30 Days.Caused by Faulty Equipment in Drywell. Maint Work Request Initiated to Repair Failed Channel ML17289A6001992-05-22022 May 1992 Special Rept:On 920420,seismic Triaxial Peak Accelerograph & Space Frame Removed to Allow Refueling of Reactor Core. Accelerometer Will Be Returned to Svc When Space Frame Reattached to Reactor Vessel Prior to Startup ML17286A9401991-07-15015 July 1991 Special Rept:On 910604,time History Triaxial Acceleration Sensor Found Malfunctioning During Performance of Seismic Sys Maint Activities.Failed Unit Returned Under Warranty to Supplier for Repair.Sys Now Fully Operational ML17285A8001989-10-19019 October 1989 Special Rept:On 891009,valve PSR-V-104 Isolated to Repair Leaking PASS Sample Valve PSR-V-616,resulting in PASS Being Inoperable.Plan Made to Replace Valve PSR-V-616 to Restore Sys by Jan 1990 ML17285A7331989-09-14014 September 1989 Special Rept:On 890821,leakage Discovered in post-accident Sampling Sys Containment Valves When in Closed Position. Maint Work Requests Prepared to Repair post-accident Sampling Sys Containment Isolation Valves ML17285A3511989-03-22022 March 1989 Special Rept:On 890306,post-accident Sampling Primary Coolant Radiation Monitor Inoperable.Caused by Excess Moisture.Pass Vacuum Pump PSR-P-702 Replaced W/New Pump & Bulkhead Fitting Repaired ML17285A2931989-02-16016 February 1989 Special Rept:On 890203,plant Personnel Unable to Obtain Sample from PASS Due to Lack of Compression in Vacuum Pump. Caused by Broken Pump Shaft.Replacement Parts Currently on Order & Pump Will Be Repaired as Soon as Possible 1998-06-30
[Table view] Category:LER)
MONTHYEARML17284A6751998-06-30030 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 ML17292B2281998-01-14014 January 1998 Informs of Unexpected Change in Feedwater Temperature & Flow Indication Used to Calculate Plant Heat Balance During Routine Trending of Plant Computer Feedwater Temperatures on 980112.Corrective Actions Reduced Reactor Power to 99% ML17292A7921997-04-0909 April 1997 Ro:On 970327,reactor Scrammed.Evaluation Results,Conclusions & Corrective Actions Will Be Shared W/Nrc Prior to Plant Startup from Maint & Refueling Outage ML17292A5901996-11-0808 November 1996 Special Rept:On 961023,intermediate & High Range Stack Monitors PRM-RE-1B & PRM-RE-1C Declared Inoperable.Caused by Monitor Output Had Upward Trend Due to Electronic Noise Interference.Work Request Generated ML17291B0981995-11-0808 November 1995 Special Rept:On 951026,RB Effluent Monitoring Sys Inoperable for 72 H Due to Failure of Mid Range Stack Monitor.Cryostat Cooling Assemblies for Mid & High Range Stack Monitors Returned to Vendor for Refurbishment ML17291A9781995-08-18018 August 1995 Special Rept:On 950712,loose Part Detection Sys Channel 4 Failed Due to Electrical Noise During Daily Check.Channel 4 Will Remain Inoperable Until Next Forced or Scheduled Outage When Primary Containment de-inerted for Other Work ML17291A6961995-03-16016 March 1995 Special Rept:On 950305,reactor Bldg Effluent Monitoring Sys Was Inoperable for 72 Hrs.Caused by Failure of Stack Monitor Detector.Stack Monitor Returned to Svc on 950314 ML17291A4131994-09-26026 September 1994 Special Rept:On 940825,loose Part Detection Sys Channel Number Eight Actuated Associated MCR Alarm & on 940908 Subj Channel Began Alarming Due to Electronic Noise Originating in Drywell.Electronic Module of Channel Removed ML17290A8871993-12-17017 December 1993 Special Rept:On 931116,loose Parts Detection Sys Channel 5 Did Not Pass Daily Channel Surveillance.Exact Cause Not Determined.Need to Provide Addl Notifications Should Other Channels Become Inoperable Not Necessary ML17290A8381993-12-10010 December 1993 Special Rept:On 931126,main Control Room Received Stack Monitor Sys Trouble Annunciator & Status Display Indicated High Range Channel Failed self-test.Caused by Component Failure of Stack Monitor Detector.Replacement in Progress ML17290A5301993-06-11011 June 1993 Special Rept:On 930503,space Frame & Attached Seismic Triaxial Peak Accelorograph (SEIS-TPA-1) Removed to Allow for Refueling of Reactor Core.Instrument Returned to Svc on 930607 ML17289B1281993-01-11011 January 1993 Update to 921007 Special Rept Re Inoperability of Loose Parts Detection Instrumentation Following Failure of Channel 1 on 921113.On 921128,constant Alarm Received on Channel 8. Maint Work Request Initiated to Repair Failed Channels ML17289A9161992-10-0707 October 1992 Special Rept:On 920905,channel 1 on Main Steam Line D Nozzle in Drywell Did Not Pass Surveillance & Inoperable for More than 30 Days.Caused by Faulty Equipment in Drywell. Maint Work Request Initiated to Repair Failed Channel ML17289A6001992-05-22022 May 1992 Special Rept:On 920420,seismic Triaxial Peak Accelerograph & Space Frame Removed to Allow Refueling of Reactor Core. Accelerometer Will Be Returned to Svc When Space Frame Reattached to Reactor Vessel Prior to Startup ML17286A9401991-07-15015 July 1991 Special Rept:On 910604,time History Triaxial Acceleration Sensor Found Malfunctioning During Performance of Seismic Sys Maint Activities.Failed Unit Returned Under Warranty to Supplier for Repair.Sys Now Fully Operational ML17285A8001989-10-19019 October 1989 Special Rept:On 891009,valve PSR-V-104 Isolated to Repair Leaking PASS Sample Valve PSR-V-616,resulting in PASS Being Inoperable.Plan Made to Replace Valve PSR-V-616 to Restore Sys by Jan 1990 ML17285A7331989-09-14014 September 1989 Special Rept:On 890821,leakage Discovered in post-accident Sampling Sys Containment Valves When in Closed Position. Maint Work Requests Prepared to Repair post-accident Sampling Sys Containment Isolation Valves ML17285A3511989-03-22022 March 1989 Special Rept:On 890306,post-accident Sampling Primary Coolant Radiation Monitor Inoperable.Caused by Excess Moisture.Pass Vacuum Pump PSR-P-702 Replaced W/New Pump & Bulkhead Fitting Repaired ML17285A2931989-02-16016 February 1989 Special Rept:On 890203,plant Personnel Unable to Obtain Sample from PASS Due to Lack of Compression in Vacuum Pump. Caused by Broken Pump Shaft.Replacement Parts Currently on Order & Pump Will Be Repaired as Soon as Possible 1998-06-30
[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] |
Text
ACCELERATED DISTRIBUTION DEMONS~TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9312230135 DOC.DATE: 93/12/10.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 AFFILIATION FAULKENBERRY,B.
Region 5 (Post 820201)
SUBJECT:
Special rept:on 931126,main control room received stack monitor sys trouble annunciator
&status display indicated high range channel failed self-test.
Caused by component fax.lure of stack monitor detector.Replacement in progress.DISTRIBUTION CODE: IE22D COPIES RECEIVED:LTR
)ENCL I SIZE: TITLE: '50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc, NOTES'i I'RECIPIENT ID CODE/NAME PDV LA CLIFFORD,J INTERNAL: ACRS AEOD/DS P/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB RRQBSSA.SPLB.GF E 02 RGA FILE 01 EXTERNAL: EG&G BRYCE,J.H NRC PDR NSIC POORE,W.COPIES LTTR ENCL 1 1 1~1 2 2 1 1 1 1 1=1 1 1 1 1 1 1 1 1 1 1 2 2 1 1 1 l.RECIPIENT ID CODE/NAME PDV PD AEOD/DOA AEOD/ROAB/DSP NRR/DE/EMEB NRR/DRCH/HHFB NRR/DRCH/HOLB NRR/DRSS/PRPB NRR/DSSA/SRXB RES/DSIR/EIB L ST LOBBY WARD NSIC MURPHY,G.A NUDOCS FULL TXT COPIES LTTR ENCL 1 1 1-1 2 2 1 1 1.1 1'2 2 1 1 1 1 1 1 1 1 1 1 A D D NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT.20079)TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!TOTAL NUMBER OF COPIES REQUIRED: LTTR 30 ENCL 30 D D-S WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O.Bax 968 3000 Geode Washington Way Richland, Washington 993524968 0'09)372-5000 December 10, 1993 G02-93-290 Docket No.50-397 Mr.B.'H.Faulkenberry Regional Administrator VS Nuclear Regulatory Commission Region V 1450 Maria Lane Walnut Creek, CA.94596
Dear Mr.Faulkenberry:
Subject:
%iiP-2, OPERATING LICENSE NO.NPF-21 SPECIAL REPORT: REACTOR BUILDING EFFLUENT MONITORING SYSTEM This special report is submitted pursuant to the requirements of WNP-2 Technical Specification Section 3.3.7.5,"Accident Monitoring Instrumentation." This Technical Specification includes Table 3.3.7.5-1, Item 31,"Reactor Building Effluent Monitoring System." Item 31 references Action 81 which states: "With the number of OPERABLE accident monitoring instrumentation channels less than required by the Minimum Channels OPERABLE requirement, either restore the inoperable channel(s) to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or:...In lieu of any other report required by Specification 6.9.1, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 14 days following the event outlining the action taken', the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status." At 0854 hours0.00988 days <br />0.237 hours <br />0.00141 weeks <br />3.24947e-4 months <br /> on November 29, 1993, the Reactor Building Effluent Monitoring System was inoperable for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> requiring the submittal of this special report.~EE E~D On November 26, 1993 at 0854 hours0.00988 days <br />0.237 hours <br />0.00141 weeks <br />3.24947e-4 months <br />, the Main Control Room received a"Stack Monitor='System Trouble" annunciator.
The.Stack Monitor Status Display indicated that the high range channel (PRM-RE-1C) had failed its self-test.
The stack monitor is part of the Reactor Building Effluent Monitoring System which is required to be in service during Operating Conditions 1, 2, and 3 in accordance with Technical Specification Table 3.3.7.5-1 (Item 31).210064 9312230135 931210 PDR ADOCK 05000397 S PDR i Page Two SPECIAL REPORT: REACTOR BUILDING EFFLUENT MONITO~G SYSTEM Action Taken" Immediate corrective action was taken to declare the stack mohitor inoperable.
The System Engineer was then notified and Limiting Condition for Operation (LCO)3.3.7.5 Action Statement No.81 was entered to initiate the preplanned alternate monitoring method and submit this'pecial report.Troubleshooting by the System Engineer on November 26, 1993 indicated a failure of the cryogenically cooled stack monitor detector.Additional troubleshooting on November 28, 1993 confirmed the initial findings.The equipment vendor (EG&G ORTEC)was contacted on November 29, 1993 for assistance in determining the location of the fault.Because the stack monitor detector requires a controlled warm-up and,cooldown from 70'elvin (-333.4'), a process that takes approximately 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, the vendor recommended replacement of several components within the detector preamplifier before proceeding with detector replacement.
The vendor supplied preamplifier components were installed on December 2, 1993 but subsequent testing on December 3, 1993 indicated that the fault had not been corrected.
The vendor determined that the fault was internal to the stack monitor detector, requiring replacement.
a e of he In era ili The cause of the Reactor Building Effluent Monitoring System inoperability was a component failure of the stack monitor detector.However, the cause of the detector failure has not been determined because the fault apparently resides within the high-vacuum, sealed detector canister.The detector will be returned to the v'endor for warranty repair.lan and chedule for Rest rin the System t rable tatus The stack monitor detector replacement work is currently in progress with completion of installation.and calibration expected by December 17, 1993.Sincerely.V.Parrish (Mail Drop 1023)Assistant Managing Director, Operations CDM/bk CC: Document Control Desk NS Reynolds-Winston&Strawn'W Clifford-NRC DL Williams-BPA/399 NRC Site Inspector-927N Regulatory Agency wasNINCTCN puaLlc Pew!a A SUPPLY SYSTEM REGULATORY COMMITMENT IDENTIFICATION FORM~(FOR INTERNAL DISTRIBUTION ONLY)Source OocumenVDate S~al Gporf I/2llol93-/tobZ-93-2'utgorng Document Autttor Q.D.MCL~HACLLA Incomrng Document Reviewer Mail Drop Ext TeIs 44s I Summary ol Document Z ma(Lporf: Pitric.kv Eurfcfiu E4/0~k kfourka ru ZilW CONCURRENCE FOR COMMITMENTS LISTED BELOW.ASSIGNED TO SUPV.NAME rInt COMMITMENT wavily r'otuJtl~k~
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