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LER-1980-037, While Performing Periodic Test 26.1,radiation Monitor RM-SV-111 Found Inoperative. Caused by Spare Lug Short Causing Erroneous Indications. Lug Removed.Monitor Returned to Svc |
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| 2801980037R03 - NRC Website |
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While* performing Periodic Test 26. l, Radiatign Monitor BH:SY-J J J was found to J;,e inoperative.
This is contrary to Technical Specification 3. 7.E Table 3. 7-5 and is
((ill! reportable as per Technical Specification 6.6.2.b.(4).
The re1.ease limits of_Technici_l_
Specification 3.11.A were not exceeded.
The health.and safety of the public were
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not affected.
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CAUSE OESCAIPTION ANO CORFIECilVE ACilONS @
[JJ]J I A spare lug on the monitor shorted the 16
- volt power supply causing erroneous [I!Il I indications.
The lug was removed* and the monitor returned to service.
- 47.
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"UPDATED REPORT-PREVIOUS REPORT DATED 08""'.06-80 ATTACHMENT l -(PAGE l of 1)
SURRY POWER STATION, UNIT 1 DOCKET NO:
50-280 *'
REPORT NO:
80-037/JJ3X-l EVENT DATE:
7-11-80 TITLE OF EVENT:
RADIATION MONITOR (RM~sv~111) "INOPERATIVE
- 1.
DESCRIJ;'TION OF *EVENT:
While perfonning PT-26.1, (Air* Ejecto:r Discharge Monitor), RM-SV-111 was found to be inoperative.
This is contrary to Technical Specification 3. 7.E Table 3.7-5 and is reportable as per Technical Specification 6.6.2,b.(4).
- 2.
PROBABLE CONSEQUENCES AND
- STATUS OF *""REDUNDANT *SYSTEMS:
The release limits delineated in Technical Specification 3.11.A and 10 CFR 20 were not exceeded.
The health. and safety of the pu6lic were not affected.
There is no redundant monitor.
- 3.
CAUSE
The radiation monitor failed because a wire lug-shorted the terminals-for the 16V power supply.
Y!
~
- 4.
IMMEDIATE CORRECTIVE ACTION
Health Physics sampled the Air Ejector discharge and found it within the limits of Technical Specification 3.11.A.
The monitor was repaired and returned to service.
- 5.
SUBSEQUENT CORRECTIVE *ACTION:
- :No!l~~ ~~-ons!_d~!~_d_;_;_!:.c~s~aE_y: *
- 6.
ACTION TAKEN TO PREVENT RECURRENCE:
The Periodic Testing program is* designed t.o locate this type of failure in a timely manner, therefore, no further action is required.
- 7.
GENERIC IMPLICATIONS:
None.
-*- -~----- ******-**-~-*-~~
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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. 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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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