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LER-1980-015, During Radiation Monitoring Test,Radiation Alarm Setpoint for Component Cooling Sys Found Greater than Twice Background.Caused by Instrument Drift.Activity Levels Verified |
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| 2801980015R03 - NRC Website |
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I During the performance of PT-26.1, Radiation Monitoring Equipment Test, with the unit at 100% power, the Radiation Alarm Setpoint for the Component Cooling System t[Il]
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- Operating.in this condition, the
- Component Cooling Syst.em' s surge tank vent valve would not have automatically closed at. twice background.
This event is reportable* in accordance with Tech. Spec.
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CAUSE
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The activity levels in the ]
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UPDATED REPORT-PREVIOUS REPORT DATED 3-14-80 A'ITACHMENT, PAGE 1 OF 1 SURRY POWER STATION, UNIT 1 DOCKET NO:
50-280 REPORT NO:
80-015/03X-1 EVENT DATE:
2-17-80 TITLE OF EVENT:
RADIATION MONITOR (RM-'CC-106) SETPOTNT: ABOVE ESTABLISHED LIMIT
- 1.
DESCRIPTION OF EVENT
During the performance of PT-26.1, Radiation Monitoring Equipment Test, with the Unit at 100% power, the Radiation Alarm Setpoint*for the Component Cooling Sys tern was found to be greater than twice li-ackground as* listed in Tech. Spec.
3.7, Table 3.7-5 (6.4 x 10 4 CPM vs.6.0 x 10 4 CPM).
Operating in this condition, the Component Cooling System's* surge tank vent valve would not have automatically closed at twice background.
This event is reportable in accordance with Tech. Spec. 6.6.2.b.(4).
- 2.
PROBABLE CONSEQUENCES AND STATUS OF *REDUNDANT* SYSTEMS:
Upon discovery of the improper setpoint, the activity levels were checked, and verified to be within, allowable setpoints.
. the automatic operation of the-surge tank vent valve was not health and safety of the public were not affected,
- 3.
CAUSE
The improper setpoint was attributed to instrument drift.
- 4.
IMMEDIATE CORRECTIVE ACTION
in the CC system Consequently, required and the Activity levels in the CC system were verified to be within allowable limits and a maintenance* report initiated to recalibrate the monitor.
- 5.
SCHEDULED CORRECTIVE ACTION:
The monitor, RM-CC-106, was recalibrated to the proper setpoint,
- 6.
ACTION TAKEN TO PREVENT RE CURRENCE:
None required,
- 7.
GENERIC IMPLICATIONS:
This was considered a random event and poss*esses no generic implications,
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| 05000281/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000281/LER-1980-001-01, /01T-0:on 800310,review of Delta Flux Computer Program Revealed Deficiency in Periodic Test 28.9, Incore- Excore Hi Calibr. Caused by Failure to Extend Calibr of Control Board Delta Flux Meters to 120% Power Range | /01T-0:on 800310,review of Delta Flux Computer Program Revealed Deficiency in Periodic Test 28.9, Incore- Excore Hi Calibr. Caused by Failure to Extend Calibr of Control Board Delta Flux Meters to 120% Power Range | | | 05000280/LER-1980-001-03, /03L-0:on 800101,w/unit at Cold Shutdown,Snubber 1-WFPD-HSS-14 Found W/Empty Reservoir & Declared Inoperable Per Tech Spec.Caused by Leakage Around Pipe Nipple Threads on Valve Block & Extended Seal Washers.Snubber Replaced | /03L-0:on 800101,w/unit at Cold Shutdown,Snubber 1-WFPD-HSS-14 Found W/Empty Reservoir & Declared Inoperable Per Tech Spec.Caused by Leakage Around Pipe Nipple Threads on Valve Block & Extended Seal Washers.Snubber Replaced | | | 05000280/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000280/LER-1980-002-03, /03L-0:on 800106,during Routine Release of Lwtt 80-95,LW Effluent Flow Recorder Paper Did Not Rotate & Thus No Record of Flow Note Was Obtained.Caused by Inadequate Mesh Between Recorder Drive Gears & Recorder Paper Roll | /03L-0:on 800106,during Routine Release of Lwtt 80-95,LW Effluent Flow Recorder Paper Did Not Rotate & Thus No Record of Flow Note Was Obtained.Caused by Inadequate Mesh Between Recorder Drive Gears & Recorder Paper Roll | | | 05000280/LER-1980-002-01, /01T-0:on 800320,insp of Containment Following Type a Leak Rate Revealed Eight 1/4 Inch Holders Drilled Through Containment Liner.Caused by Improper Interpretation of Procedure During Design Change 78-48.Repair Planned | /01T-0:on 800320,insp of Containment Following Type a Leak Rate Revealed Eight 1/4 Inch Holders Drilled Through Containment Liner.Caused by Improper Interpretation of Procedure During Design Change 78-48.Repair Planned | | | 05000281/LER-1980-003, Forwards Updated LER 80-003/03L-1 & LER 80-046/03L-0 | Forwards Updated LER 80-003/03L-1 & LER 80-046/03L-0 | | | 05000280/LER-1980-003-03, /03L-0:on 800107,during Prestartup Testing, Feedwater Bypass Valve HCV-FW-155B Did Not Fail Closed Upon Loss of Instrument Air as Per Design.Caused by Sticking, Dirty Pilot Valve.Valve Cleaned & Returned to Svc | /03L-0:on 800107,during Prestartup Testing, Feedwater Bypass Valve HCV-FW-155B Did Not Fail Closed Upon Loss of Instrument Air as Per Design.Caused by Sticking, Dirty Pilot Valve.Valve Cleaned & Returned to Svc | | | 05000281/LER-1980-003-03, MOV-CW-200B Found Inoperable.Caused by Electrical Malfunction Due to Mechanical Repair in Progress.Redundant Water Box Inlet Valve MOV-CW-206B Was Shut | MOV-CW-200B Found Inoperable.Caused by Electrical Malfunction Due to Mechanical Repair in Progress.Redundant Water Box Inlet Valve MOV-CW-206B Was Shut | | | 05000280/LER-1980-004-01, /01T-0:on 800108,during Routine Startup,Check Valve 1-FW-89 in Discharge Line of Auxiliary Feed Pump Stuck Open.Cause to Be Evaluated by Vendor.Feed Pump & Motor Operated Valves Cycled to Close Valve | /01T-0:on 800108,during Routine Startup,Check Valve 1-FW-89 in Discharge Line of Auxiliary Feed Pump Stuck Open.Cause to Be Evaluated by Vendor.Feed Pump & Motor Operated Valves Cycled to Close Valve | | | 05000280/LER-1980-004, Forwards LER 80-004/01T-0 | Forwards LER 80-004/01T-0 | | | 05000281/LER-1980-004, Forwards LER 80-004/01T-0 | Forwards LER 80-004/01T-0 | | | 05000281/LER-1980-004-01, /01T:on 800521,during Cold Shutdown,Pressure Transmitter 458 Inoperable Due to Wiring Problem & Isolation Valve for Pressure Transmitter 403 Found Closed,Negating Overpressure Mitigating Sys.Caused by Cable Problem | /01T:on 800521,during Cold Shutdown,Pressure Transmitter 458 Inoperable Due to Wiring Problem & Isolation Valve for Pressure Transmitter 403 Found Closed,Negating Overpressure Mitigating Sys.Caused by Cable Problem | | | 05000280/LER-1980-005-03, /03L-0:on 800120,while Conducting PT 27D Heat Tracing Sys,Discovered That Circuit 17A Panel 9 Was Inoperative.Caused by Thermostat Failure.Maint Rept Initiated.Defective Thermostat Replaced | /03L-0:on 800120,while Conducting PT 27D Heat Tracing Sys,Discovered That Circuit 17A Panel 9 Was Inoperative.Caused by Thermostat Failure.Maint Rept Initiated.Defective Thermostat Replaced | | | 05000281/LER-1980-005-01, Type a Testing Revealed Leakage Through Recirculation Spray Diaphragm Plate Seal Welds.Caused by Lack of Fusion & Slag Inclusion in Weld Areas.Defects Repaired | Type a Testing Revealed Leakage Through Recirculation Spray Diaphragm Plate Seal Welds.Caused by Lack of Fusion & Slag Inclusion in Weld Areas.Defects Repaired | | | 05000280/LER-1980-006, Forwards Updated LER 80-006/03X-1 | Forwards Updated LER 80-006/03X-1 | | | 05000280/LER-1980-006-03, /03L-0:on 800115,during Routine Surveillance of Liquid Waste Release,Discovered That Unsampled Waste from Tank 5A Was Being Pumped to Tank 5B.Caused by Inadvertent Operation of Transfer Pump.Waste Release Terminated | /03L-0:on 800115,during Routine Surveillance of Liquid Waste Release,Discovered That Unsampled Waste from Tank 5A Was Being Pumped to Tank 5B.Caused by Inadvertent Operation of Transfer Pump.Waste Release Terminated | | | 05000281/LER-1980-006-03, /03L-0:on 800527,contrary to Tech Spec 3.1.G.2.b. (1),Containment 2 Pressurizer Level Exceeded 33% W/O Mitigation Protection.Caused by Addition of Water to Primary Sys to Maintain Level Indication.Rcs Drained | /03L-0:on 800527,contrary to Tech Spec 3.1.G.2.b. (1),Containment 2 Pressurizer Level Exceeded 33% W/O Mitigation Protection.Caused by Addition of Water to Primary Sys to Maintain Level Indication.Rcs Drained | | | 05000281/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000280/LER-1980-007-03, /03L-0:on 800116,during Normal Operation,Heat Tracing Circuit 4 on Line 1-CH-56-152,boric Acid Supply to Blender Failed.Caused by Water Penetration of Heat Tracing Tape.Tape Replaced W/Higher Water Resistant Tape | /03L-0:on 800116,during Normal Operation,Heat Tracing Circuit 4 on Line 1-CH-56-152,boric Acid Supply to Blender Failed.Caused by Water Penetration of Heat Tracing Tape.Tape Replaced W/Higher Water Resistant Tape | | | 05000280/LER-1980-007, Forwards Updated LER 80-007/03X-1 | Forwards Updated LER 80-007/03X-1 | | | 05000281/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000281/LER-1980-007-03, /03L-0:on 800606,w/unit in Cold Shutdown,Smoke Detectors Found Inoperable.Caused by Breaker Trip at Motor Control Ctr Which Feeds Detectors.Cause of Breaker Trip Unknown | /03L-0:on 800606,w/unit in Cold Shutdown,Smoke Detectors Found Inoperable.Caused by Breaker Trip at Motor Control Ctr Which Feeds Detectors.Cause of Breaker Trip Unknown | | | 05000280/LER-1980-008, Forwards LER 80-008/01T-0 | Forwards LER 80-008/01T-0 | | | 05000281/LER-1980-008-03, /03L-0:on 800623,while Performing Periodic Test 26.1,found Air Ejector Monitor Alarm Setpoint Above Tech Spec Requirement.Caused by Instrument Drift.Alarm Setpoint Recalibr | /03L-0:on 800623,while Performing Periodic Test 26.1,found Air Ejector Monitor Alarm Setpoint Above Tech Spec Requirement.Caused by Instrument Drift.Alarm Setpoint Recalibr | | | 05000280/LER-1980-008-01, /01T-0:on 800116,during Power Operation,Valve Inadvertently Closed,Preventing Boric Acid Flow in One of Two Flow Paths to Core for Approx 3-h.Caused Not Stated. Valve Opened & Boric Acid Flow Verified | /01T-0:on 800116,during Power Operation,Valve Inadvertently Closed,Preventing Boric Acid Flow in One of Two Flow Paths to Core for Approx 3-h.Caused Not Stated. Valve Opened & Boric Acid Flow Verified | | | 05000281/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000280/LER-1980-009-01, Westinghouse LOCA-ECCS Reanalysis Indicated Residual Penalty of 0.007 in Fq Exists from Fuel Rod Burst Model.Caused by Reduction in Clad Heatup Rate Which Shifts Fuel Clad Burst Curve | Westinghouse LOCA-ECCS Reanalysis Indicated Residual Penalty of 0.007 in Fq Exists from Fuel Rod Burst Model.Caused by Reduction in Clad Heatup Rate Which Shifts Fuel Clad Burst Curve | | | 05000280/LER-1980-009, Forwards LERs 82-049/03L-0,82-080/03L-0 & Updated LER 80-009/01X-1 | Forwards LERs 82-049/03L-0,82-080/03L-0 & Updated LER 80-009/01X-1 | | | 05000280/LER-1980-009-03, /03L-0:on 800123,during Normal Operation,Boric Acid Transfer Pump 1-CH-P-2A Lost Flow.Caused by Broken Pump Shaft Inside Pump Casing.Caused by Improper Installation.Pump a Replaced & Maint Procedures Revised | /03L-0:on 800123,during Normal Operation,Boric Acid Transfer Pump 1-CH-P-2A Lost Flow.Caused by Broken Pump Shaft Inside Pump Casing.Caused by Improper Installation.Pump a Replaced & Maint Procedures Revised | | | 05000281/LER-1980-009, Forwards LER 80-009/01T-0 | Forwards LER 80-009/01T-0 | | | 05000281/LER-1980-009-01, /01T-0:on 800718,Westinghouse LOCA ECCS Reanalysis Indicated Error in Fuel Clad Burst Model.Caused by Reduction in Clad Heatup Rate Which Shifts Fuel Clad Burst Curve & Results in Earlier Clad Burst.Limit Will Be Controlled | /01T-0:on 800718,Westinghouse LOCA ECCS Reanalysis Indicated Error in Fuel Clad Burst Model.Caused by Reduction in Clad Heatup Rate Which Shifts Fuel Clad Burst Curve & Results in Earlier Clad Burst.Limit Will Be Controlled | | | 05000281/LER-1980-010-01, Containment Gaseous & Particulate Radiation Monitor Found to Have One Automatic Function Incapable of Operating During Fuel Movement.Caused by Bypass of Containment Exhaust Fan Relay in Design Change | Containment Gaseous & Particulate Radiation Monitor Found to Have One Automatic Function Incapable of Operating During Fuel Movement.Caused by Bypass of Containment Exhaust Fan Relay in Design Change | | | 05000280/LER-1980-010, Forwards LER 80-010/01T-0 | Forwards LER 80-010/01T-0 | | | 05000280/LER-1980-010-01, Overstress on 18-inch Line CC-9-121,unit 2 Supply to RHR Exchanger,Found During Pipe Stress Reanalysis on Show Cause Lines.Caused by Supports Installed to Prevent Overstress During DBE | Overstress on 18-inch Line CC-9-121,unit 2 Supply to RHR Exchanger,Found During Pipe Stress Reanalysis on Show Cause Lines.Caused by Supports Installed to Prevent Overstress During DBE | | | 05000280/LER-1980-011-03, /03L-0:on 800128,during Normal Operations,Heat Tracing Strip Heater on 1-CH-P-2A Circuit 25A (Panel 9) Failed.Caused by Penetration of Water Leakage from Pump Flange.Strip Heater Replaced & Leak Repair Requested | /03L-0:on 800128,during Normal Operations,Heat Tracing Strip Heater on 1-CH-P-2A Circuit 25A (Panel 9) Failed.Caused by Penetration of Water Leakage from Pump Flange.Strip Heater Replaced & Leak Repair Requested | | | 05000281/LER-1980-011-01, /01T-0:on 800819,at 12% Power,Steam Flow Transmitters (FI-474,475,484,485,494 & 495) Isolated Contrary to Tech Spec-3.7.B.Caused by Transmitters Being Isolated Following Containment Integrated Leak Rate Test | /01T-0:on 800819,at 12% Power,Steam Flow Transmitters (FI-474,475,484,485,494 & 495) Isolated Contrary to Tech Spec-3.7.B.Caused by Transmitters Being Isolated Following Containment Integrated Leak Rate Test | | | 05000280/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000281/LER-1980-011, Forwards LER 80-011/01T-0 | Forwards LER 80-011/01T-0 | | | 05000281/LER-1980-012-03, /03L-0:on 800815,review of Unit 2 Pipe Support Showed That Seismic Support for Charging Pump 2-CH-P-1B Had Not Been Installed.Caused by Administrative Error.Support Installed | /03L-0:on 800815,review of Unit 2 Pipe Support Showed That Seismic Support for Charging Pump 2-CH-P-1B Had Not Been Installed.Caused by Administrative Error.Support Installed | | | 05000280/LER-1980-012-03, /03L-0:on 800202,while Performing PT-27D,amperage Readings for Circuit 25A,panels 1 & 2,were Below Acceptance Criteria.Repairs to Tape Not Completed within 2-h Limit.Unit Rampdown Intiated.Caused by Water Penetration | /03L-0:on 800202,while Performing PT-27D,amperage Readings for Circuit 25A,panels 1 & 2,were Below Acceptance Criteria.Repairs to Tape Not Completed within 2-h Limit.Unit Rampdown Intiated.Caused by Water Penetration | | | 05000280/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000280/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000281/LER-1980-013-03, /03L-0:on 800815,during Startup Testing,Boric Acid Concentration of 13.8% Was Reported in 1-CH-TK-1C & 2-SI-TK- 2.Caused by Pumping Boric Acid from Boron Evaporator Bottoms Tank to Boric Acid Storage Tank W/O Sampling | /03L-0:on 800815,during Startup Testing,Boric Acid Concentration of 13.8% Was Reported in 1-CH-TK-1C & 2-SI-TK- 2.Caused by Pumping Boric Acid from Boron Evaporator Bottoms Tank to Boric Acid Storage Tank W/O Sampling | | | 05000280/LER-1980-013-03, Valve HCV-1852A to Tank 1-SI-TK-1A Delayed Closing 30-50 Secs,Resulting in Tank Draining Below Tech Spec Level.Caused by Moisture in Air Lines Feeding Valve Operator.Tank Filled to Tech Spec Level | Valve HCV-1852A to Tank 1-SI-TK-1A Delayed Closing 30-50 Secs,Resulting in Tank Draining Below Tech Spec Level.Caused by Moisture in Air Lines Feeding Valve Operator.Tank Filled to Tech Spec Level | | | 05000280/LER-1980-014-01, /01T-0:on 800320,informed by Westinghouse That Incident of Stress Corrosion Cracking in Control Rod Support Pins & Flexures Noted in Foreign Plant.Vendor Testing & Assessment Program in Progress.Appropriate Action Planned | /01T-0:on 800320,informed by Westinghouse That Incident of Stress Corrosion Cracking in Control Rod Support Pins & Flexures Noted in Foreign Plant.Vendor Testing & Assessment Program in Progress.Appropriate Action Planned | | | 05000280/LER-1980-014-03, /03L-0:on 800816,w/reactor Critical,Discovered Level in Refueling Water Storage Tank & Cat Below Min Set by Tech Specs.Caused by Excessive Makeup to B SI Accumulator W/O Refilling | /03L-0:on 800816,w/reactor Critical,Discovered Level in Refueling Water Storage Tank & Cat Below Min Set by Tech Specs.Caused by Excessive Makeup to B SI Accumulator W/O Refilling | | | 05000280/LER-1980-015-03, During Radiation Monitoring Test,Radiation Alarm Setpoint for Component Cooling Sys Found Greater than Twice Background.Caused by Instrument Drift.Activity Levels Verified | During Radiation Monitoring Test,Radiation Alarm Setpoint for Component Cooling Sys Found Greater than Twice Background.Caused by Instrument Drift.Activity Levels Verified | | | 05000281/LER-1980-015-03, /03L-0:on 800816,after Pressurization of Accumulator Tanks,Level Indicator for B SI Accumulator Indicated 61% Level,Above Tech Spec Max of 58.3%.Caused by Condensation & High Pressure in Nitrogen Feed Line | /03L-0:on 800816,after Pressurization of Accumulator Tanks,Level Indicator for B SI Accumulator Indicated 61% Level,Above Tech Spec Max of 58.3%.Caused by Condensation & High Pressure in Nitrogen Feed Line | | | 05000280/LER-1980-016-03, /03L-0:on 800916,w/unit Operating Steady State at 100% power,TV-SS-201B Would Not Remain Closed When Control Switch Was Released.Cause Undetermined.Inside Trip Valve Closed & Air Secured to TV-SS-201B | /03L-0:on 800916,w/unit Operating Steady State at 100% power,TV-SS-201B Would Not Remain Closed When Control Switch Was Released.Cause Undetermined.Inside Trip Valve Closed & Air Secured to TV-SS-201B | |
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