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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARGO2-98-111, 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 Rooms1998-06-30030 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 GO2-98-006, 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%1998-01-14014 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% GO2-97-068, Ro:On 970327,reactor Scrammed.Evaluation Results,Conclusions & Corrective Actions Will Be Shared W/Nrc Prior to Plant Startup from Maint & Refueling Outage1997-04-0909 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 GO2-96-221, 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 Generated1996-11-0808 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 GO2-95-238, 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 Refurbishment1995-11-0808 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 GO2-95-156, 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 Work1995-08-18018 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 GO2-95-053, 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 9503141995-03-16016 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 GO2-94-223, 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 Removed1994-09-26026 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 GO2-93-293, 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 Necessary1993-12-17017 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 GO2-93-290, 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 Progress1993-12-10010 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 GO2-93-156, 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 9306071993-06-11011 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 GO2-93-012, 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 Channels1993-01-11011 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 GO2-92-234, 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 Channel1992-10-0707 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 GO2-92-129, 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 Startup1992-05-22022 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 GO2-91-135, 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 Operational1991-07-15015 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 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 GO2-84-528, RO Re Use of Fan Motor W/O Performing Seismic Qualification. Caused by Motor Failure on Fan WWA-FN-53A.Motor to Be Reinstalled,Qualification Obtained & Spare Motor Ordered1984-10-0202 October 1984 RO Re Use of Fan Motor W/O Performing Seismic Qualification. Caused by Motor Failure on Fan WWA-FN-53A.Motor to Be Reinstalled,Qualification Obtained & Spare Motor Ordered ML20090B2281984-07-0606 July 1984 Ro:On 840602,w/reactor Operating in Mode 1,increase in Coolant Conductivity Noted & Measures Taken to Reduce Levels.Caused by Steam Impingement.Condenser Repaired. Preparations Made for Startup 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 GO2-99-180, Monthly Operating Rept for Sept 1999 for WNP-2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for WNP-2.With GO2-99-170, Monthly Operating Rept for Aug 1999 for WNP-2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for WNP-2.With GO2-99-156, Monthly Operating Rept for July 1999 for WNP-2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for WNP-2.With ML17284A8691999-07-31031 July 1999 Monthly Operating Rept for July 1999 for WNP-2.With 990813 Ltr ML17284A8331999-07-30030 July 1999 Safety Evaluation Supporting Proposed Alternative of Direct or Remote VT-1 Visual Exam of Pump Casing Welds Will Be Capable of Detecting Any Known Degradation in Carbon Steel Welds,Therefore Provides Assurance of Pressure Integrity 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 05000397/LER-1999-001, :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. with1999-07-20020 July 1999
- 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
ML17292B7271999-06-30030 June 1999 Monthly Operating Rept for June 1999 for WNP-2.With 990707 Ltr GO2-99-124, Monthly Operating Rept for June 1999 for WNP-2.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for WNP-2.With GO2-99-106, Monthly Operating Repts for May 1999 for WNP-2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for WNP-2.With ML17292B6961999-05-31031 May 1999 Monthly Operating Repts for May 1999 for WNP-2.With 990608 Ltr GO2-99-089, Monthly Operating Rept for Apr 1999 for WNP-2.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for WNP-2.With ML17292B6391999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for WNP-2.With 990413 Ltr GO2-99-069, Monthly Operating Rept for Mar 1999 for WNP-2.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for WNP-2.With ML17292B6061999-03-25025 March 1999 Safety Evaluation Accepting Relief Request RV02 GO2-99-048, Monthly Operating Rept for Feb 1999 for WNP-2.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for WNP-2.With ML17292B5871999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for WNP-2.With 990311 Ltr GO2-99-028, Monthly Operating Rept for Jan 1999 for WNP-2.With1999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for WNP-2.With 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. LD-99-003, 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-CE1999-01-15015 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 LD-99-002, 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 Error1999-01-15015 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 GO2-99-006, Monthly Operating Rept for Dec 1998 for WNP-2.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for WNP-2.With GO2-99-041, WNP-2 1998 Annual Operating Rept. with1998-12-31031 December 1998 WNP-2 1998 Annual Operating Rept. with GO2-98-211, Washington Public Power Supply Sys 1998 Annual Rept. with1998-12-31031 December 1998 Washington Public Power Supply Sys 1998 Annual Rept. with ML17292B5351998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for WNP-2.With 990112 Ltr GO2-98-204, Monthly Operating Rept for Nov 1998 for WNP-2.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for WNP-2.With ML17284A8081998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for WNP-2.With 981110 Ltr GO2-98-188, Monthly Operating Rept for Oct 1998 for WNP-2.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for WNP-2.With 05000397/LER-1998-012, :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.With1998-10-27027 October 1998
- 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
GO2-98-174, Monthly Operating Rept for Sept 1998 for WNP-2.With1998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for WNP-2.With 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 05000397/LER-1998-013, :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.With1998-09-0303 September 1998
- 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
05000397/LER-1998-014, :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.With1998-09-0202 September 1998
- 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
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 05000397/LER-1998-015, :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.With1998-09-0202 September 1998
- 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
GO2-98-166, Monthly Operating Rept for Aug 1998 for WNP-2.With1998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for WNP-2.With 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 GO2-98-144, Monthly Operating Rept for July 1998 for WNP-21998-07-31031 July 1998 Monthly Operating Rept for July 1998 for WNP-2 05000397/LER-1998-006, :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 Changes1998-07-23023 July 1998
- 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
05000397/LER-1998-011, :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 Conducted1998-07-17017 July 1998
- 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
05000397/LER-1998-010, :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 Tubing1998-07-15015 July 1998
- 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
05000397/LER-1998-009, :on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in Preparation1998-07-0101 July 1998
- on 980606,nuclear Steam Supply Shutoff Sys Group 3 & 4 Isolations During Testing Was Noted.Caused by Procedural Deficiency.Counseled Individuals Involved in Preparation
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 GO2-98-119, Monthly Operating Rept for June 1998 for WNP-21998-06-30030 June 1998 Monthly Operating Rept for June 1998 for WNP-2 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 1999-09-30
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Text
ACCELERATED DTRIBUTION DEMONS~TION SYSTEM h
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9401190007 DOC.DATE: 93/12/17 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 931116,loose parts detection sys channel 5
did not pass daily channel surveillance. Exact cause not determined.
DISTRIBUTION CODE:
IE22D COPIES RECEIVED:LTR L ENCL 0 SIZE:
TITLE: 50.73/50.9 Licensee Event Report (LER), Incident Rpt, etc.
NOTES:
D RECIPIENT ID CODE/NAME PDV LA CLIFFORD,J INTERNAL: ACRS AEOD/DSP/TPAB NRR/DE/EELB NRR/DORS/OEAB NRR/DRCH/HICB NRR/DRIL/RPEB N~/J3SSA/SPLB EG FILE~
02 RGN5 FILE 01 EXTERNAL: EGGG BRYCE,J.H NRC PDR NSIC POORE,W.
COPIES LTTR ENCL 2
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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,
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D NOTE TO ALL"RIDS" RECIPIENTS PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P 1-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCVMENIS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 30 ENCL
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A WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Bar 968 ~ 3000 George Wasbtngton Way ~ Rtebland, 1Pasbtngton 99352-096'8
~ (509) 372-5000 December 17, 1993 G02-93-293 li Docket No. 50-397 Mr, B, H. Faulkenberry Regional Administrator US Nuclear Regulatory Commission Region V 1450 Maria Lane Walnut Creek, Ca. 94596 LD H ~
pl
~m CD~Ay CJ CD
Dear Mr. Faulkenberry:
Subject:
WNP-2, OPERATING LICENSE NO. NPF-21 SPECIAL REPORT: LOOSE-PART DETECTION INSTRUMENTATION
'his special report is submitted pursuant to the requirements ofWNP-2 Technical Specification Section 3.3.7.2 "Loose-Part Detection Instrumentation" which requires the instruments to be operable at all times. The action statement for this specification requires that "with one or more Loose-Part Detection System (LPDS) channels inoperable for more than 30 days, 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 the next 10 days outlining the cause of the malfunction and the plans for restoring the channel(s) to OPERABLE status."
The Loose-Part Detection System has been designed and installed to detect the presence of internal loose parts in the Reactor Pressure Vessel (RPV). This system is dedicated to monitor the RPV via the use of ten permanently-mounted sensors in various locations around the Reactor Vessel.
A signal of twice the general background noise for each sensor willgenerate an alarm.
The alarm would alert the Shift Technical Advisor to listen to the signals with head phones and try to determine the cause of the alarm.
The signals causing the alarm are automatically recorded and are available for analysis.
On November 16, 1993, LPDS channel ¹5 did not pass its daily channel check surveillance.
The channel was observed to periodically driftin and out of operation.
On December 1, 1993, the channel remained out of operation for a period of time sufficient for persorinel to troubleshoot the problem.
The system engineer worked with the technicians to isolate the problem. It was determined that the channel ¹5 problem was with its associated equipment in the Drywell, and because of its location, the exact cause of the failure cannot presently be determined.
940ii90007 93i2i7 PDR ADOCK 05000397 S
PDR
Page Two SPECIAL REPORT: LOOSE-PART DETECTION INSTRUMENTATION Channel ¹5 is located on the Reactor Recirculation System B Suction in the Drywell. Analysis of the signal relationship from the 10 channels is used to determine the location of the suspected loose part.
There is one sensor located on each Reactor Recirculation line to monitor this portion of the Vessel.
Therefore determining the location of suspected loose parts at this region of the vessel willbe impacted with the loss of channel ¹5.
The alarm logic is. determined by the relationship of the background noise level gong time constant RMS average) of a channel versus the signal noise level (short time constant RMS average) of the same channel and is independent of the number ofchannels in service.
The system output is an annunciator on Board S in the Main Control Room and a magnetic tape recording of all ten signals at the time of the alarm.
There are no automatic actuations produced by this instrument.
'hile the Technical Specifications require the system to be declared inoperable, the loose parts monitor system design allows the system to be functional when less than the full ten channels are operational.
The failed equipment is located in the Drywell and is not accessible during ~
reactor operation.
An MWR has been initiated to repair the failed channel the next time the Drywell is accessible.
With the LPDS System now not operable, the Supply System does not believe that there is a requirement to provide additional notifications should other channels become inoperable while the LPDS System is still inoperable.
Sincerely,
. V. Parrish (Mail Drop 1023)
Assistant Managing Director, Operations DLO!bk CC:
BH Faulkenberry - NRC RV NS Reynolds - Winston E. Strawn JW Clifford - NRC DL Williams - BPA/399 NRC Site Inspector - 927N