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NRC form 3ee U 8. NUCLE AR 5.EGULATOAV COMMISSION APPROVED OMB NO.3160 010e LICENSEE EVENT REPORT (LER)
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F ACILITY NAME til DOCKET NUMSER III PAGEi3a D.
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COOK NUCLEAR PLANT, UNIT 1 015 l 0101013 1115 1 lOFl 013 TITLE 141 FAILURE TO CALIBRATE PRIMARY SENSORS EVENT DATE 15)
LIR NUM.ER 161 REPORT DATE 17)
OTHER FACILITIES INVOLVED (Si MONTM DAY vtAR YEAR
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0 1 5 1 0 1 0 1 0 1 I I THis REPORT 18 SueulTTED PURSUANT TO THE REQU8MEMENTS OF 10 CFR l (Chece orie or enore of the feiten a,1 (116 OPE R ATING MODE W q
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THIS IS A SUPPLEMENTAL REPORT TO LER 85-043 SUBMITTED ON 9-30-85.
THE PURPOSE IS TO REPORT COMPLETION OF CORRECTIVE ACTIONS AND THE PREVENTIVE ACTIONS THAT HAVE BEEN IMPLEMENTED.
WITH UNITS 1 AND 2 IN MODE 5 (COLD SHUTDOWN) AN IE HEADQUARTERS TEAM INSPECTION WAS CONDUCTED IN THE AREA OF INSTRUMENT SURVEILLANCES FROM AUGUST 19 TO AUGUST 28, 1985.
A CONFIRMATORY ACTION LETTER WAS ISSUED ON AUGUST 30, 1985 BECAUSE OF A DIFFERENCE IN INTERPRETATION OF PRIMARY SENSOR REQUIREMENTS.
AS PART OF THE REQUIRED ACTION, A REVIEW OF TECHNICAL SPECIFICATION SURVEILLANCES INVOLVING CALIBRATION OF PROCESS SENSORS WAS CONDUCTED TO ENSURE THAT TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS, AS A RESULT OF THE NEW INTERPRETATION, ARE MET.
THIS REVIEW DISCLOSED SEVERAL APPARENT DISCREPANCIES.
ACTION HAS SUBSEQUENTLY BEEN TAKEN TO ENSURE ALL OF THE ABOVE EQUIPMENT IS IN COMPLIANCE WITH TECHNICAL SPECIFICATION REQUIREMENTS.
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NRC Form 3e4A U 8. 9tuCLEAR F.E2ULATCAV COMMISSION UCENSEE EVENT REPORT (LER) TEXT CONTINUATION AreaovEO ows No siso-oioa EXPIRES: 8/314 FactLITY NAME Of DOCKET NUMSER (2)
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D. C. 000K, UNIT 1 0 [5 l o l 0 l 0 l3 1115 8I5 0 l 41 3 Oli of 2 F nh
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c we,., ass.w nn THIS IS A SUPPLEMENTAL REPORT TO LER 85-043 SUBMITTED ON 9-30-85.
THE PURPOSE IS TO REPORT COMPLETION OF CORRECTIVE ACTIONS AND THE PREVENTIVE ACTIONS THAT HAVE BEEN IMPLEMENTED.
WITH UNITS 1 AND 2 IN MODE 5 (COLD SHUTDOWN) AN IE HEADQUARTERS TEAM INSPECTION WAS CONDUCTED IN THE AREA OF INSTRUMENT SURVEILLANCES FROM AUGUST 19 TO AUGUST 28, 1985.
A CONFIRMATORY l
ACTION LETTER WAS ISSUED ON AUGUST 30, 1985 BECAUSE OF A DIFFERENCE IN INTERPRETATION OF PRIMARY SENSOR REQUIREMENTS.
AS PART OF THE REQUIRED ACTION, A REVIEW OF TECHNICAL SPECIFICATION SURVEILLANCES INVOLVING CALIBRATION OF PROCESS SENSORS WAS CONDUCTED TO ENSURE THAT TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS, AS A RESULT OF THE NEW INTERPRETATION, ARE MET.
THIS REVIEW DISCLOSED THE FOLLOWING APPARENT DISCREPANCIES:
INCORE THERMOCOUPLES, (IEEE = 26),USED AS BACK-UP TO SATURATION MARGIN MONITOR, T.S. TABLE 3.3-10, ITEM 11 WIDE RANGE REACTOR COOLANT SYSTEM RESISTANCE TEMPERATURE DETECTORS, (IEEE = 26), T.S. 4.3-7, ITEMS 2 AND 3 NARROW RANGE REACTOR COOLANT SYSTEM RESISTANCE TEMPERATURE DETECTORS, (IEEE = 26),
T.S. TABLE 4.3-1, ITEMS 7 AND 8 HYDROGEN RECOMBINER THERMOCOUPLES, (IEEE = 26), T.S. 4.6.4.2b1 CONTAINMENT DEWPOINT HYGROMETER, (IEEE = 45),
T.S. 4.4.6.lc METEOROLOGICAL INSTRUMENTATION, (IEEE = 45),
T.S. 4.3.3.4, TABLE 4.3-5 SEISMIC SENSORS, (IEEE = XE),
T.S. 4.3.3.3.1, TABLE 4.3-4 THE INCORE THERMOCOUPLES AND BOTH THE WIDE RANGE AND NARROW RANGE REACTGR COOLANT SYSTEM RESISTANCE TEMPERATURE DETECTORS HAVE BEEN i
SUCCESS 7ULLY CROSS-CALIBRATED BY USE OF A NEW SURVEILLANCE PROCEDURE.
PLANT PRACTICES HAVE BEEN MODIFIED TO ASSURE RESICIANCE TEMPERATURE DETECTORS AND INCORE THERMOCOUPLES ARE INCLUDED IN FUTURE CALIBRATIONS.
THE HYDROGEN RECOMBINER THERMOCOUPLE ACCURACY HAS HISTORICALLY BEEN DOCUMENTED IN THE SURVEILLANCE TEST OF THE HYDROGEN RECOMBINER.
BASED ON THE MANUFACTURER'S CRITERIA, THE CURRENT PROCEDURE INCORPORATES AN ACCEPTABLE METHOD OF TESTING THE THERMOCOUPLES, AND HAS BEEN CHANGED TO INCLUDE A SIGN-OFF DOCUMENTING THERMOCOUPLE ACCURACY.
THE CONTAINMENT DEWPOINT HYGROMETERS WERE REMOVED AND RECALIBRATED BY THE MANUFACTURER.
PREVIOUSLY, THEY HAD BEEN SUBJECT TO RECALIBRATION BY THE MANUFACTURER EVERY THREE YEARS, AND WERE RECALIBRATED BY PLANT TECHNICIANS EVERY EIGHTEEN MONTHS.
HOWEVER, THE EIGHTEEN MONTH CALIBRATION, WHIT WAS PERFORMED IN ACCORDANCE WITH 'IHE MANUFACTURER'S TECHNICAL MANUAL, DID NOT INCLUDE THE TEMPERATURE SENSOR.
REMOVAL AND RECALIBRATION OF THE SENSOR HAS BEEN ESTABLISHED ON AN EIGHTEEN MONTH BASIS.
NRC FORM 364A
NRC Form 368A U $ NUCLEAR EEGULATCKY COMMISSION LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Aremoveo ous No asso-oia EXPtRES. 0< 31 88 FACILITY NAME til DOCKET NUMSER (E LER NUMetR 156 PAGE431 "R'.1;'.
0'Jo*.70 vsaa D. C. COOK, UNIT 1 o l5 g o j o l 0 l 31115 BI 5 014l1 0l 1 01 3 OF 0l3 rnrr w
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_ncr anne,mn THE METEOROLOGICAL INSTRUMENTATION HAS HISTORICALLY BEEN CALIBRATED IN ACCORDANCE WITH THE MANUFACTURER'S RECOMMENDATIONS.
SENSOR CALIBRATION OF THE METEOROLOGICAL INSTRUMENTS IS NOT SPECIFIED IN THE MANUFACTURER'S TECHNICAL MANUAL.
AS A COVSERVATIVE MEASURE, NEW SENSORS WITH CERTIFICATES OF CALIBRATION WERE PURCHASED AND INSTALLED.
THE METEOROLOGICAL INSTRUMENTATION CALIBRATION PROCEDURE HAS BEEN CHANGED TO REQUIRE SENSOR CALIBRATION ON A SEMIANNUAL BASIS IN ACCORDANCE WITE TECH SPEC REQUIREMENTS.
THE SEISMIC SENSORS WERE ALSO INVESTIGATED.
IT WAS FOUND THAT THESE SENSORS HAVE HISTORICALLY BEEN SURVEILLANCE TESTED IN ACCORDANCE WITH TECHNICAL SPECIFICATIONS.
IN ALL CASES DESCRIBED ABOVE, PAST SIMSOR CALIBRATIONS HAD BEEN PERFORMED IN ACCORDANCE WITH OUR INTERPRETATION OF TECHNICAL SPECIFICATION REQUIREMENTS AT THE TIME.
THE SURVEILLANCE CONCERNS DESCRIBED HEREIN DID NOT PRESENT A SIGNIFICANT SAFETY CONCERN.
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| 05000315/LER-1985-001, :on 850105,fire Watch Failed to Conduct 2330 Hourly Insp of Inoperable Fire Barrier Penetration Seals & Dampers in Unit 1 & 2 Charging Pump Rooms.Caused by Inadequate Turnover of Tour Assignments |
- on 850105,fire Watch Failed to Conduct 2330 Hourly Insp of Inoperable Fire Barrier Penetration Seals & Dampers in Unit 1 & 2 Charging Pump Rooms.Caused by Inadequate Turnover of Tour Assignments
| | | 05000316/LER-1985-001-01, :on 850111,automatic ESF Actuation Occurred, Providing Start Signal to Motor Driven Auxiliary Feedwater Pumps.Caused by Personnel Error in Manual Control of Feedwater Regulator Valves |
- on 850111,automatic ESF Actuation Occurred, Providing Start Signal to Motor Driven Auxiliary Feedwater Pumps.Caused by Personnel Error in Manual Control of Feedwater Regulator Valves
| | | 05000316/LER-1985-002, :on 850112,automatic ESF Actuation Occurred, Resulting in Reactor Trip.Caused by lo-lo Level in Steam Generator 22 Due to Unexpected Increase in Steam Flow.Event Discussed W/Shift Personnel & Operating Memo Written |
- on 850112,automatic ESF Actuation Occurred, Resulting in Reactor Trip.Caused by lo-lo Level in Steam Generator 22 Due to Unexpected Increase in Steam Flow.Event Discussed W/Shift Personnel & Operating Memo Written
| | | 05000315/LER-1985-002-01, :on 850118,discovered That Required Daily Auxiliary Bldg Vent Sample Not Taken on 850111-17.Required Daily Samples Collected on 850118 & 19.Surveillance Requirement Added & Procedures Revised |
- on 850118,discovered That Required Daily Auxiliary Bldg Vent Sample Not Taken on 850111-17.Required Daily Samples Collected on 850118 & 19.Surveillance Requirement Added & Procedures Revised
| | | 05000315/LER-1985-003, :on 840116,Train a Battery Not Declared Inoperable Per Tech Spec 4.8.2.4.2.Caused by Misunderstanding Between Personnel.Requirement Will Be Added to Surveillance Procedure |
- on 840116,Train a Battery Not Declared Inoperable Per Tech Spec 4.8.2.4.2.Caused by Misunderstanding Between Personnel.Requirement Will Be Added to Surveillance Procedure
| | | 05000316/LER-1985-003, :on 850126,while in Mode 1,reactor Tripped. Caused by Failure of Vital Bus III Inverter.Inverter Repaired.Accelerated Testing Program Implemented |
- on 850126,while in Mode 1,reactor Tripped. Caused by Failure of Vital Bus III Inverter.Inverter Repaired.Accelerated Testing Program Implemented
| | | 05000316/LER-1985-004-01, :on 850125,RCS Loop 2 Cold Leg Temp Found Not Environmentally Qualified.On 850126,unit Trip Occurred. Caused by Unrelated Component Failure.Loop Replaced W/Qualified Spare |
- on 850125,RCS Loop 2 Cold Leg Temp Found Not Environmentally Qualified.On 850126,unit Trip Occurred. Caused by Unrelated Component Failure.Loop Replaced W/Qualified Spare
| | | 05000315/LER-1985-004, :on 850129,w/reactor in Mode 1,high Alarm Received on Lower Containment Radiation Monitor That Resulted in Containment Isolation.Caused by Upward Trend in Containment Airborne Activity |
- on 850129,w/reactor in Mode 1,high Alarm Received on Lower Containment Radiation Monitor That Resulted in Containment Isolation.Caused by Upward Trend in Containment Airborne Activity
| | | 05000316/LER-1985-005, :on 850130,one Cell on Train AB Battery Had Unacceptable Specific Gravity Reading.Cell Replacement Completed & Cross Tie Breaker Opened Restoring Both Dc Bus Trains |
- on 850130,one Cell on Train AB Battery Had Unacceptable Specific Gravity Reading.Cell Replacement Completed & Cross Tie Breaker Opened Restoring Both Dc Bus Trains
| | | 05000315/LER-1985-005-01, :on 850205,discovered That Sample Medium Designated in Tech Spec 3.11.2.1 Not Used.Caused by Personnel Error.Tech Spec Change Re Use of Iodine Will Be Implemented |
- on 850205,discovered That Sample Medium Designated in Tech Spec 3.11.2.1 Not Used.Caused by Personnel Error.Tech Spec Change Re Use of Iodine Will Be Implemented
| | | 05000316/LER-1985-006-01, :on 850204,8-inch by 16-inch Opening Found in Wall in Quadrant 1 of Reactor Cable Tunnel,Constituting Inoperable Fire Barrier.Opening Believed to Have Existed Since Initial Plant Const.Opening Repaired |
- on 850204,8-inch by 16-inch Opening Found in Wall in Quadrant 1 of Reactor Cable Tunnel,Constituting Inoperable Fire Barrier.Opening Believed to Have Existed Since Initial Plant Const.Opening Repaired
| | | 05000315/LER-1985-006, :on 850206,auxiliary Bldg Access Control Ventilation Duct Fire Damper Found Closed.Damper Designed as safety-related But Misidentified as nonsafety-related.Damper Reset |
- on 850206,auxiliary Bldg Access Control Ventilation Duct Fire Damper Found Closed.Damper Designed as safety-related But Misidentified as nonsafety-related.Damper Reset
| | | 05000316/LER-1985-007, :on 841228,NDE Revealed Cracks in Seven 2-inch Rockwell-Edward Globe Valves,Similar to IE Info Notice 84-48 & Suppl 1 Description.Valves Isolate Reactor Coolant Loop Resistance Temp Detector Manifolds |
- on 841228,NDE Revealed Cracks in Seven 2-inch Rockwell-Edward Globe Valves,Similar to IE Info Notice 84-48 & Suppl 1 Description.Valves Isolate Reactor Coolant Loop Resistance Temp Detector Manifolds
| | | 05000315/LER-1985-007-01, :on 850222,controlled Shutdown Initiated. Caused by Inoperable Control Room Emergency Ventilation Sys. Analysis of Potential Radiological Consequences of Operation at Higher Flow Rates Performed.Room Balanced |
- on 850222,controlled Shutdown Initiated. Caused by Inoperable Control Room Emergency Ventilation Sys. Analysis of Potential Radiological Consequences of Operation at Higher Flow Rates Performed.Room Balanced
| | | 05000315/LER-1985-007, :on 850222,control Room Pressure Could Not Be Maintained at +1/+6 Inches Wg Relative to Outside Atmosphere.Flow Rates Satisfactorily Adjusted & Unit Returned to Power.Mods Being Developed |
- on 850222,control Room Pressure Could Not Be Maintained at +1/+6 Inches Wg Relative to Outside Atmosphere.Flow Rates Satisfactorily Adjusted & Unit Returned to Power.Mods Being Developed
| | | 05000316/LER-1985-008, :on 850103,broken Control Rod Guide Tube Support Pins Found in Steam Generators 22 & 23.Failure of Pin in Generator 22 Attributed to Igscc.Cause of Pin Failure in Generator 23 Undetermined |
- on 850103,broken Control Rod Guide Tube Support Pins Found in Steam Generators 22 & 23.Failure of Pin in Generator 22 Attributed to Igscc.Cause of Pin Failure in Generator 23 Undetermined
| | | 05000315/LER-1985-008-01, :on 850314,low Pressure Carbon Dioxide Fire Suppression Sys Removed from Svc W/O Proper Fire Watch Coverage.Caused by Nonlicensed Planning Personnel Error. Individuals Counseled |
- on 850314,low Pressure Carbon Dioxide Fire Suppression Sys Removed from Svc W/O Proper Fire Watch Coverage.Caused by Nonlicensed Planning Personnel Error. Individuals Counseled
| | | 05000316/LER-1985-009, :on 850327,monthly Vent Stack Composite Sample Lost During Isotopic Extraction Procedure.Caused by Error in Lab Technician Handling Technique.Personnel Counseled Re Handling Breakable Equipment |
- on 850327,monthly Vent Stack Composite Sample Lost During Isotopic Extraction Procedure.Caused by Error in Lab Technician Handling Technique.Personnel Counseled Re Handling Breakable Equipment
| | | 05000315/LER-1985-010, :on 850112 & 0406,dose Equivalent I-131 Limit Exceeded.Fuel Sipping Performed During 10-yr Inservice Insp/Refueling Outage on 208 Fuel Assemblies |
- on 850112 & 0406,dose Equivalent I-131 Limit Exceeded.Fuel Sipping Performed During 10-yr Inservice Insp/Refueling Outage on 208 Fuel Assemblies
| | | 05000316/LER-1985-010, :on 850327,fire Watch Failed to Inspect 4 Kv Bus Room Ab.Caused by Personnel Error.Fire Watch Reinstructed Re Responsibility to Enter All Areas Assigned as Part of Fire Duties |
- on 850327,fire Watch Failed to Inspect 4 Kv Bus Room Ab.Caused by Personnel Error.Fire Watch Reinstructed Re Responsibility to Enter All Areas Assigned as Part of Fire Duties
| | | 05000315/LER-1985-010-01, :on 850112 & 0406,dose Equivalent I-131 of Reactor Coolant Exceeded Tech Spec Limit.Caused by Leaking Fuel Assemblies.Fuel Sipping Will Be Performed During 1985 Refueling Outage |
- on 850112 & 0406,dose Equivalent I-131 of Reactor Coolant Exceeded Tech Spec Limit.Caused by Leaking Fuel Assemblies.Fuel Sipping Will Be Performed During 1985 Refueling Outage
| | | 05000315/LER-1985-011, :on 850407,containment Purge Begun Per Approved Procedure Which Established More than on Purge Supply & Exhaust Path.Procedure Not Allowed Per Tech Spec 3.6.1.7. Procedures Changed |
- on 850407,containment Purge Begun Per Approved Procedure Which Established More than on Purge Supply & Exhaust Path.Procedure Not Allowed Per Tech Spec 3.6.1.7. Procedures Changed
| | | 05000316/LER-1985-011-01, :on 850520,alarm Signals Received on Three Lower Containment Area Radiation Monitors Resulting in Containment Purge/Exhaust Isolation Signal |
- on 850520,alarm Signals Received on Three Lower Containment Area Radiation Monitors Resulting in Containment Purge/Exhaust Isolation Signal
| | | 05000316/LER-1985-012, :on 850603,while Process Radiation Monitoring Instrumentation Inoperable,Auxiliary Bldg Ventilation Grab Sample Not Obtained within Specified Time Restraints.Caused by Personnel Error.Technicians Counseled |
- on 850603,while Process Radiation Monitoring Instrumentation Inoperable,Auxiliary Bldg Ventilation Grab Sample Not Obtained within Specified Time Restraints.Caused by Personnel Error.Technicians Counseled
| | | 05000316/LER-1985-013, :on 850726,frost Accumulation in Excess of Tech Spec Found within Ice Condenser Flow Passages.Caused by Excessive Moisture in Air or Sublimation of Ice.Frost Buildup Removed on 850728 |
- on 850726,frost Accumulation in Excess of Tech Spec Found within Ice Condenser Flow Passages.Caused by Excessive Moisture in Air or Sublimation of Ice.Frost Buildup Removed on 850728
| | | 05000315/LER-1985-013, :on 850407,w/RCS in Mode 3,spray Additive Tank Room Fire Door 529 Found Blocked Open W/O Fire Watch Coverage.Caused by Personnel Error.Blockage Removed |
- on 850407,w/RCS in Mode 3,spray Additive Tank Room Fire Door 529 Found Blocked Open W/O Fire Watch Coverage.Caused by Personnel Error.Blockage Removed
| | | 05000316/LER-1985-013-01, :on 850726,accumulation of Excessive Frost within Ice Condenser Flow Passages Discovered.Condition May Have Existed Prior to Cold Shutdown.Frost Buildup Removed on 850728.Investigation Underway |
- on 850726,accumulation of Excessive Frost within Ice Condenser Flow Passages Discovered.Condition May Have Existed Prior to Cold Shutdown.Frost Buildup Removed on 850728.Investigation Underway
| | | 05000316/LER-1985-014, :on 850728,w/unit in Mode 5,inadvertent Safety Injection Signal Generated During Installation of Design Change.Caused by Voltage Drop Resulting in Reduction of Power to Vital Instrument Buses III & IV |
- on 850728,w/unit in Mode 5,inadvertent Safety Injection Signal Generated During Installation of Design Change.Caused by Voltage Drop Resulting in Reduction of Power to Vital Instrument Buses III & IV
| | | 05000315/LER-1985-014, :on 850407,fire Watch Unable to Conduct Insps of Seismic Gap Fire Barrier Seals.Caused by Broken Locking Mechanism on Fire Door 325 |
- on 850407,fire Watch Unable to Conduct Insps of Seismic Gap Fire Barrier Seals.Caused by Broken Locking Mechanism on Fire Door 325
| | | 05000316/LER-1985-014-01, :on 850728,during Replacement of Inverters, Safety Injection Signal Inadvertently Generated.Caused by Reactor Coolant Pump 3 Startup,Resulting in Momentary Power Reduction from Channels 3 & 4 |
- on 850728,during Replacement of Inverters, Safety Injection Signal Inadvertently Generated.Caused by Reactor Coolant Pump 3 Startup,Resulting in Momentary Power Reduction from Channels 3 & 4
| | | 05000315/LER-1985-015, :on 850408,09 & 11,several Spurious High Alarms Received on Lower Containment Radiation Monitor Particulate Channels Ers 1301 & Ers 1401.Caused by Jump in Rate Count. New Program Chips Purchased |
- on 850408,09 & 11,several Spurious High Alarms Received on Lower Containment Radiation Monitor Particulate Channels Ers 1301 & Ers 1401.Caused by Jump in Rate Count. New Program Chips Purchased
| | | 05000316/LER-1985-015-01, :on 850803,ESF Actuation Occurred.Caused by Level Deviation Due to Excessive Leakage Through Loop 4 Auxiliary Feedwater Valve.Loop 4 Removed from Svc & Will Be Repaired Prior to Startup |
- on 850803,ESF Actuation Occurred.Caused by Level Deviation Due to Excessive Leakage Through Loop 4 Auxiliary Feedwater Valve.Loop 4 Removed from Svc & Will Be Repaired Prior to Startup
| | | 05000315/LER-1985-016, :on 850412,w/RCS in Mode 3,vent Inside Containment Opened to Drain Header & Vent Outside Containment Opened to Drain Hxs,Creating Flow Path from Inside to Outside Containment.Procedure Revised |
- on 850412,w/RCS in Mode 3,vent Inside Containment Opened to Drain Header & Vent Outside Containment Opened to Drain Hxs,Creating Flow Path from Inside to Outside Containment.Procedure Revised
| | | 05000316/LER-1985-016-01, :on 850808,flux Mapping Sys (Fms) Frame Assembly Restraint Devices Not Installed Per Design Specs. Installation of Restraint Devices & Mods Authorized by Design Changes (RFC-12-2778) Completed 850817 |
- on 850808,flux Mapping Sys (Fms) Frame Assembly Restraint Devices Not Installed Per Design Specs. Installation of Restraint Devices & Mods Authorized by Design Changes (RFC-12-2778) Completed 850817
| | | 05000315/LER-1985-017, :on 850417,accumulated Leakage Exceeded Tech Spec Limits Found While Performing Type B & C Leak Rate Tests.Cause Unknown.Penetrations Repaired |
- on 850417,accumulated Leakage Exceeded Tech Spec Limits Found While Performing Type B & C Leak Rate Tests.Cause Unknown.Penetrations Repaired
| | | 05000316/LER-1985-017-01, :on 850819 & 22,listed ESF Actuation Signals Received While Unit in Mode 3.Caused by Increasing Containment Radioactivity During Startup.Containment Purge Procedure Revised |
- on 850819 & 22,listed ESF Actuation Signals Received While Unit in Mode 3.Caused by Increasing Containment Radioactivity During Startup.Containment Purge Procedure Revised
| | | 05000315/LER-1985-018, :on 850416,fire Barrier Inoperable.Caused by Lack of Fire Sealant Matl in Two Floor Penetrations. Penetrations Sealed,Declared Operable & Added to Surveillance Program |
- on 850416,fire Barrier Inoperable.Caused by Lack of Fire Sealant Matl in Two Floor Penetrations. Penetrations Sealed,Declared Operable & Added to Surveillance Program
| | | 05000316/LER-1985-018-01, :on 850820,ESF Actuation Occurred.Caused by Opening of Reactor Trip Breakers During Instrumentation Checks.Surveillance Test Procedure Thp 4030 STP.180 Revised |
- on 850820,ESF Actuation Occurred.Caused by Opening of Reactor Trip Breakers During Instrumentation Checks.Surveillance Test Procedure Thp 4030 STP.180 Revised
| | | 05000315/LER-1985-019, :on 850420,ice Inventory within Ice Condenser Determined to Be Below Tech Spec Limits.Cause Unknown.Ice Weight of Deficient Rows Increased by Ice Replenishment Program |
- on 850420,ice Inventory within Ice Condenser Determined to Be Below Tech Spec Limits.Cause Unknown.Ice Weight of Deficient Rows Increased by Ice Replenishment Program
| | | 05000316/LER-1985-019-01, :on 850821,determined That Seismic Qualification of Governors for turbine-driven Auxiliary Feed Pumps Inadequate for Approx 4 Yrs.Cause Not Stated.Governors as Installed Meet Current Seismic Requirements |
- on 850821,determined That Seismic Qualification of Governors for turbine-driven Auxiliary Feed Pumps Inadequate for Approx 4 Yrs.Cause Not Stated.Governors as Installed Meet Current Seismic Requirements
| | | 05000315/LER-1985-020, :on 850429,low Pressure CO2 Fire Suppression Sys for Quadrant 1 of Reactor Cable Tunnel Isolated W/O Fire Watch Coverage.Caused by Personnel Error.Personnel Counseled |
- on 850429,low Pressure CO2 Fire Suppression Sys for Quadrant 1 of Reactor Cable Tunnel Isolated W/O Fire Watch Coverage.Caused by Personnel Error.Personnel Counseled
| | | 05000316/LER-1985-020, Advises That LER 85-020-00 Re Inoperable Fire Damper, Determined Not Reportable & Being Withdrawn.Concludes That All Specified Compensatory Actions Per Tech Specs Completed & Events Did Not Constitute Unreviewed Safety Issues | Advises That LER 85-020-00 Re Inoperable Fire Damper, Determined Not Reportable & Being Withdrawn.Concludes That All Specified Compensatory Actions Per Tech Specs Completed & Events Did Not Constitute Unreviewed Safety Issues | | | 05000316/LER-1985-020-01, :on 850822,during Surveillance Testing, safety-related Fire Damper Found Inoperable.Cause Not Determined.Damper Repaired,Tested & Returned to Svc on 850823 |
- on 850822,during Surveillance Testing, safety-related Fire Damper Found Inoperable.Cause Not Determined.Damper Repaired,Tested & Returned to Svc on 850823
| | | 05000315/LER-1985-021, :on 850429,reactor Vessel Flow Requirement Not Verified Prior to RCS Boron Dilution.Procedure for Filling Reactor Refueling Cavity Revised to Include Verification/ Documentation of Reactor Vessel Flow During RCS Dilution |
- on 850429,reactor Vessel Flow Requirement Not Verified Prior to RCS Boron Dilution.Procedure for Filling Reactor Refueling Cavity Revised to Include Verification/ Documentation of Reactor Vessel Flow During RCS Dilution
| | | 05000316/LER-1985-021-01, :on 850822 & 23,discovered That Several Instrumentation Channel Functional Tests Not Performed as Required.Cause Not Stated.Testing Conducted |
- on 850822 & 23,discovered That Several Instrumentation Channel Functional Tests Not Performed as Required.Cause Not Stated.Testing Conducted
| | | 05000315/LER-1985-022, :on 850502 & 04-07,during Refueling,High Alarms Received on Lower Containment Monitor Particulate Channels ERS-1301 & ERS-1401.Caused by Fluctuation Activity Resulting in Erroneous Alarms.Value Will Be Updated |
- on 850502 & 04-07,during Refueling,High Alarms Received on Lower Containment Monitor Particulate Channels ERS-1301 & ERS-1401.Caused by Fluctuation Activity Resulting in Erroneous Alarms.Value Will Be Updated
| | | 05000316/LER-1985-022-01, :on 850825,grab Sample of Essential Svc Water Sys Not Obtained at Proper Time.Caused by Technician Error. Technician Disciplined |
- on 850825,grab Sample of Essential Svc Water Sys Not Obtained at Proper Time.Caused by Technician Error. Technician Disciplined
| | | 05000315/LER-1985-023, :on 850502,definition of Auxiliary Bldg Crane Load Block as Being Heavy Load Not Emphasized in Plant Procedures.Cautions Will Be Added to Applicable Plant Procedures by 850615 |
- on 850502,definition of Auxiliary Bldg Crane Load Block as Being Heavy Load Not Emphasized in Plant Procedures.Cautions Will Be Added to Applicable Plant Procedures by 850615
| | | 05000316/LER-1985-023-01, :on 850823,discovered That Incorrect Essential Svc Water Sample Point Being Used to Fulfill Table 3.3-12 of Tech Spec 3.3.3.9.Procedure 12 Thp 6020 LAB.037 Revised to List Specific Sample Points |
- on 850823,discovered That Incorrect Essential Svc Water Sample Point Being Used to Fulfill Table 3.3-12 of Tech Spec 3.3.3.9.Procedure 12 Thp 6020 LAB.037 Revised to List Specific Sample Points
| | | 05000316/LER-1985-024-01, :on 850906,automatic ESF Actuation Occurred, Resulting in Reactor Trip Signal.Caused by Simultaneous Tripping of Two of Three Steam Generator 2 Level Channel Bistables.No Corrective Action Taken |
- on 850906,automatic ESF Actuation Occurred, Resulting in Reactor Trip Signal.Caused by Simultaneous Tripping of Two of Three Steam Generator 2 Level Channel Bistables.No Corrective Action Taken
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