LER-1980-021, /01T-0:on 800425,combinations of 3A Target Rock Valve & 3B,3C & 3E Electromatic Relief Valves Failed to Open at Rated Reactor Pressure.Caused by Improper Bolted Air Operator,Pilot Valve Problems & Jammed Cutout Switch |
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| 2491980021R01 - NRC Website |
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o:2i lDuring startup follocag refueling outage. combinations of the 3A Targe: Rock Valve l
c 13 I land 33, 3C and 3E Electromatic Relief Valves f ailed to open at rated reactor pressure 1
o 3, ; iwhile performing operability surveillance in six unsuccessful startup attemots.
I o isI iMinimal effect on public health and safety because HPCI system i= mediately proven j
c is I loperable and orderly shutdown initiated in each event.
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- ,oj l 3A Target Rock had an i= properly bolted air operator, 3B electromatic had various l
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AT"'ACuMENT TO LICENSEE EVEW ?HORT 80-21/01T-0 CO3010NWEAL H EDISON CO36ANY (CWE)
DRISDEN UNIT ILDRS-3 DOCIGT # 050-249 During initial startup on April 25, 1980, following the refueling outage, the 3A Target Rock and the 3E Electromatic Relief Valves failed to open at rated reactor pressure while performing a relief valve operability surveillance.
All other electromatic relief valves operated successfully. All of the relief valves had operated correctly at 300 psi reactor pressure prior to reaching rated pressure. HPCI was immediately proven operable and an orderly shutdown comenced.
Subsequent inspection of the Target Rock revealed missing nuts on the air opera-tor.
Since the air opertter was not attached-properly to the valve, actuation was not possible.
3e problem was corrected by properly bolting the operator on the valve.
The 3E Electromatic was found to have the leak off line restricted by the gasket.
The gasket was replaced.
Unit startup was again attempted. All relief valves successfully functioned at 250 psi reactor pressure.
The 3B and 3E Electromatics failed to open at rated reactor pressure during the surveillance en 4-26-80.
All of the remaining relief valves operated successfully. HPCI was proven operable and an orderly shutdown was begun.
Pressure was dropped to about 200 psi. Adjustments were made to the pilot valves, and the valves functioned correctly at 450 psi reactor pressure.
Reactor pressure was increased to the rated pressure, and the relief valves were tested.
The 3B valve failed to open again.
The unit was brought to a cold shutdown as required by Technical Specifications.
The 3B valve was repaired by replacing the pilot valve gasket and adjusting the stroke of the adjustment ar= of the pilot valve.
Unit startup was again atte=pted. All of the relief valves were operable at 300 psi reactor pressure. However, the 3B Electromatic relief valve failed to open at the rated pressure on 4-28-80.
All other relief valves functioned successfully.
HPCI was i= mediately proven operable and an orderly shutdown coc=ienced.
The 3B valve was exa=ined, and the pilot valve mechanis= vas replaced with a new pilot assembly whose disk to stem clearance gave greater effective pilot valve stroke.
Unit startup begun. All of the relief valves functioned correctly at 400 psi reactor pressure.
The 3B Electromatic failed to open at rated pressure during the operability surveillance on 4-29-80.
HPCI was 1:nciediately proven operable and an orderly shutdown comenced. The entire 3B Electromatic Relief valve was replaced to correct the problem.
Starup was begun and all relief valves were functional at low pressure. However, 3B and 3C Electromatic Relief Valves failed to open at rated reactor pressure. All remaining relief valves were operable. HPCI was imediately proven operable and an orderly shutdown comenced.
The 3C Electromatic was found to have a binding cutout switch for the solenoid coils. Necessary cleaning and adjusting was performed e
to provide proper clearances on all electromatic solenoids.
The 3B valve was reexa=ined, measurements made, pilot valve readjustments made, dis-charge line aligned with one of the discharge ports, and a final corrective measure was made, as suggested by the Dresser Representative, consisted of changing the pilot valve bleed off discharge line from 3/4" to 1" diameter.
Unit str.rtup begun and all valves were successfully tested on May 3, 1980. There was mini =al effect on public health or safety because the HPCI system was immediately proven operable in all cases, and an orderly shut-down initiated.
Improved valve design and system configurations are being evaluated and will be implemented at the next refueling outage if deemed necessary.
The 3A Target Rock modcl number is 67F and the Dresser Electroma ic Relief valves :nodel numbers are 1525VI.
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| 05000249/LER-1980-001-03, /03L-0:on 800116,loss of Sampling Point Automatic Advance for Drywell Oxygen Analyzer Noted During Normal Operation.Caused by Electrical Failure of Stepping Switch Motor Part 808376.Motor Replaced & Advance Restored | /03L-0:on 800116,loss of Sampling Point Automatic Advance for Drywell Oxygen Analyzer Noted During Normal Operation.Caused by Electrical Failure of Stepping Switch Motor Part 808376.Motor Replaced & Advance Restored | | | 05000237/LER-1980-001, /03L-0 for Dresden, Unit 2 Re While Performing Weekly Turbine Control Valve Exercising, the 1/2 Scram on RPS Channel a Received from the Closure of 3 Turbine Control Valve Would Not Reset | /03L-0 for Dresden, Unit 2 Re While Performing Weekly Turbine Control Valve Exercising, the 1/2 Scram on RPS Channel a Received from the Closure of 3 Turbine Control Valve Would Not Reset | | | 05000010/LER-1980-001-03, /03L-0:on 800303,capacity in Unit 1 Fire Pump Found to Be in Need of Updating in Order to Be Equal to Unit 2/3 Fire Pump.Commitment Made to NRC to Increase Capacity.New Fire Pump Will Be Installed | /03L-0:on 800303,capacity in Unit 1 Fire Pump Found to Be in Need of Updating in Order to Be Equal to Unit 2/3 Fire Pump.Commitment Made to NRC to Increase Capacity.New Fire Pump Will Be Installed | | | 05000010/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000237/LER-1980-002, /03X-1 for Dresden Unit 3 Regarding During Normal Operation While Performing LPCI Monthly Surveillance, MO-3-1501-118 Valve Would Not Close | /03X-1 for Dresden Unit 3 Regarding During Normal Operation While Performing LPCI Monthly Surveillance, MO-3-1501-118 Valve Would Not Close | | | 05000249/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000010/LER-1980-002, Forwards LER 80-002/01T-0 | Forwards LER 80-002/01T-0 | | | 05000010/LER-1980-002-01, /01T-0:on 800405,while in Shutdown Mode W/Fuel Removed,Contaminated Demineralized Water Was Being Heated & Added to Primary Sys.Tube Leaks in Heat Exchanger Were Found Leaking Water Into River.Caused by Unloader Tube Failure | /01T-0:on 800405,while in Shutdown Mode W/Fuel Removed,Contaminated Demineralized Water Was Being Heated & Added to Primary Sys.Tube Leaks in Heat Exchanger Were Found Leaking Water Into River.Caused by Unloader Tube Failure | | | 05000249/LER-1980-002-03, /03L-0:on 800122,while Performing LPCI Monthly surveillance,MO-3-1501-11B Valve Would Not Close. Reoccurrence on 800213.Investigation Revealed No Cause | /03L-0:on 800122,while Performing LPCI Monthly surveillance,MO-3-1501-11B Valve Would Not Close. Reoccurrence on 800213.Investigation Revealed No Cause | | | 05000010/LER-1980-003-02, Has Been Cancelled | Has Been Cancelled | | | 05000249/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000249/LER-1980-004-03, /03L-0:on 800202,while Increasing Load by 2 Mwe Per Hour,Alarms Received in Control Room Indicating Failed Jet Pump.Jet Pump 13 Failed.Cause & Corrective Action Will Be Described in Supplemental Rept | /03L-0:on 800202,while Increasing Load by 2 Mwe Per Hour,Alarms Received in Control Room Indicating Failed Jet Pump.Jet Pump 13 Failed.Cause & Corrective Action Will Be Described in Supplemental Rept | | | 05000010/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000010/LER-1980-004-03, /03L-0:on 800724,during Outage,While Processing Water in Holdup tank,98-h Elapsed W/O Sampling.Caused by Personnel Failure to Follow Procedure for Sampling Radwaste Storage Tanks.Personnel Reinstructed | /03L-0:on 800724,during Outage,While Processing Water in Holdup tank,98-h Elapsed W/O Sampling.Caused by Personnel Failure to Follow Procedure for Sampling Radwaste Storage Tanks.Personnel Reinstructed | | | 05000249/LER-1980-005-01, /01T-0:on 800213,while in S/D Mode,Msiv Scram Limit Switches Were Checked & of 16 Limit Switches,Two Found to Have Setpoints Greater than 10%.Caused by Switch Out of Calibr.Limit Switches Readjusted | /01T-0:on 800213,while in S/D Mode,Msiv Scram Limit Switches Were Checked & of 16 Limit Switches,Two Found to Have Setpoints Greater than 10%.Caused by Switch Out of Calibr.Limit Switches Readjusted | | | 05000249/LER-1980-005, Forwards LER 80-005/01T-0 | Forwards LER 80-005/01T-0 | | | 05000249/LER-1980-006-03, /03L-0:on 800215,during Local Leak Rate Test Performed on a Feedwater Inboard Check Valve 3-220-58A Measured Leakage Exceeded Tech Specs.Caused by Worn Seat/ Disc Assembly Pins | /03L-0:on 800215,during Local Leak Rate Test Performed on a Feedwater Inboard Check Valve 3-220-58A Measured Leakage Exceeded Tech Specs.Caused by Worn Seat/ Disc Assembly Pins | | | 05000249/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000249/LER-1980-007-03, /03L-0:on 800209,during Local Leak Rate Test of Containment Vent Line,Measured Leakage Exceeded Tech Specs. Investigation Showed Valve AO-3-1601-23 Leaking Through. Caused by Normal Expected Wear of Rubber Seats | /03L-0:on 800209,during Local Leak Rate Test of Containment Vent Line,Measured Leakage Exceeded Tech Specs. Investigation Showed Valve AO-3-1601-23 Leaking Through. Caused by Normal Expected Wear of Rubber Seats | | | 05000249/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000249/LER-1980-008-03, /03L-0:on 800307,during Refueling Outage While Performing Temp Switch Calibr Surveillance,Three Temp Switches Failed to Trip Per Specs.Caused by Drift,Excessive Gap Between Actuator & Switch Plunger or Dirty Contacts | /03L-0:on 800307,during Refueling Outage While Performing Temp Switch Calibr Surveillance,Three Temp Switches Failed to Trip Per Specs.Caused by Drift,Excessive Gap Between Actuator & Switch Plunger or Dirty Contacts | | | 05000237/LER-1980-008, /03L-0 for Dresden, Unit 2 Re Equipment Operator Discovered Level in the 2/3 Diesel Generator Coolant Water Expansion Head Tank Overflowing Thru the Vent Line | /03L-0 for Dresden, Unit 2 Re Equipment Operator Discovered Level in the 2/3 Diesel Generator Coolant Water Expansion Head Tank Overflowing Thru the Vent Line | | | 05000249/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000249/LER-1980-009-03, /03L-0:on 800306,during Refueling Outage,While Performing LPCI Logic Tests,Injection Valve Mo 3-1501-22A Failed to Open.Caused by Loose Wire on Terminal Block in MCC-38-7 Due to Stripped Brass Screw | /03L-0:on 800306,during Refueling Outage,While Performing LPCI Logic Tests,Injection Valve Mo 3-1501-22A Failed to Open.Caused by Loose Wire on Terminal Block in MCC-38-7 Due to Stripped Brass Screw | | | 05000249/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000249/LER-1980-010, /03L-0 for Dresden Unit 3 Regarding Relief Valves Rv 1105A and 1105B Actuating at 1525 and 1520 PSIG Respectively | /03L-0 for Dresden Unit 3 Regarding Relief Valves Rv 1105A and 1105B Actuating at 1525 and 1520 PSIG Respectively | | | 05000249/LER-1980-011-03, /03L-0:on 800305,while Conducting Steam Line Area Temp Switch Calibr Surveillance,Temp Switch TS 3-261-17B Tripped Above Tech Specs.Caused by Dirt Deposits on Switch Actuation Plunger.Switch Cleaned,Adjusted & Tested | /03L-0:on 800305,while Conducting Steam Line Area Temp Switch Calibr Surveillance,Temp Switch TS 3-261-17B Tripped Above Tech Specs.Caused by Dirt Deposits on Switch Actuation Plunger.Switch Cleaned,Adjusted & Tested | | | 05000249/LER-1980-011, /03L-0 for Dresden Unit 3 Regarding Temperature Switch TS 3-261-17B Tripping at 203.1 Degrees Fahrenheit Which Is Above the Technical Specification | /03L-0 for Dresden Unit 3 Regarding Temperature Switch TS 3-261-17B Tripping at 203.1 Degrees Fahrenheit Which Is Above the Technical Specification | | | 05000249/LER-1980-012, /03L-0 for Dresden Unit 3 Regarding Fuel Pool Area ARM Channels a and B Tripping at Levels Exceeding the Technical Specification | /03L-0 for Dresden Unit 3 Regarding Fuel Pool Area ARM Channels a and B Tripping at Levels Exceeding the Technical Specification | | | 05000249/LER-1980-013, /03L-0 for Dresden Unit 3 Regarding B Feedwater Outboard Check Valve 3-220-62B Leakage Exceeding Limit for a Single Isolation Valve | /03L-0 for Dresden Unit 3 Regarding B Feedwater Outboard Check Valve 3-220-62B Leakage Exceeding Limit for a Single Isolation Valve | | | 05000249/LER-1980-015, /01T-0 for Dresden Unit 3 Regarding Discovery of Reactor Water Cleanup Mechanical Snubber Fully Retracted | /01T-0 for Dresden Unit 3 Regarding Discovery of Reactor Water Cleanup Mechanical Snubber Fully Retracted | | | 05000237/LER-1980-015, /03L-0 for Dresden, Unit 2 Re During Steady State Operation, Torus to Drywell Vacuum Breaker 2-1601-33A Was Found Inoperable During Routine Operability Surveillance | /03L-0 for Dresden, Unit 2 Re During Steady State Operation, Torus to Drywell Vacuum Breaker 2-1601-33A Was Found Inoperable During Routine Operability Surveillance | | | 05000237/LER-1980-016, /01T-1 for Dresden, Unit 2 Re While Shutdown and Conducting 300 Psi Primary System Hydrostatic Leak Inspection, Water Discovered Dripping from LPCI Check Valve Up Stream Drain Line | /01T-1 for Dresden, Unit 2 Re While Shutdown and Conducting 300 Psi Primary System Hydrostatic Leak Inspection, Water Discovered Dripping from LPCI Check Valve Up Stream Drain Line | | | 05000237/LER-1980-017, /03L-0 for Dresden, Unit 2 Re Double Valve Indication Was Observed on the HPCI Inboard Isolation Valve. Upon Trying to Cycle the Valve, the Valve Failed to Close | /03L-0 for Dresden, Unit 2 Re Double Valve Indication Was Observed on the HPCI Inboard Isolation Valve. Upon Trying to Cycle the Valve, the Valve Failed to Close | | | 05000249/LER-1980-017, /03L-0 for Dresden Unit 3 Regarding During Refueling Outage, While Conducting Operability Surveillance Test, U-3 Diesel Generator Failed to Start | /03L-0 for Dresden Unit 3 Regarding During Refueling Outage, While Conducting Operability Surveillance Test, U-3 Diesel Generator Failed to Start | | | 05000249/LER-1980-019-03, /03L-0:on 800420,during Switch Calibr Surveillance,Target Rock Relief Valve Press Switch PS-3-203-3A Tripped Below Tech Specs Limit.Caused by Setpoint Drift.Switch Readjusted within Tech Specs Limit | /03L-0:on 800420,during Switch Calibr Surveillance,Target Rock Relief Valve Press Switch PS-3-203-3A Tripped Below Tech Specs Limit.Caused by Setpoint Drift.Switch Readjusted within Tech Specs Limit | | | 05000249/LER-1980-019, Forwards LER 80-019/03L-0 | Forwards LER 80-019/03L-0 | | | 05000249/LER-1980-021, /01T-0 for Dresden Unit 3 Regarding During Startup Following Refueling Outage, Combinations of 3A Target Rock Valve and 3B, 3C and 3E Electromatic Relief Valves Failed to Open at Rated Reactor Pressure While Performing Operabil | /01T-0 for Dresden Unit 3 Regarding During Startup Following Refueling Outage, Combinations of 3A Target Rock Valve and 3B, 3C and 3E Electromatic Relief Valves Failed to Open at Rated Reactor Pressure While Performing Operability Surveilla | | | 05000249/LER-1980-021-01, /01T-0:on 800425,combinations of 3A Target Rock Valve & 3B,3C & 3E Electromatic Relief Valves Failed to Open at Rated Reactor Pressure.Caused by Improper Bolted Air Operator,Pilot Valve Problems & Jammed Cutout Switch | /01T-0:on 800425,combinations of 3A Target Rock Valve & 3B,3C & 3E Electromatic Relief Valves Failed to Open at Rated Reactor Pressure.Caused by Improper Bolted Air Operator,Pilot Valve Problems & Jammed Cutout Switch | | | 05000237/LER-1980-022, /03L-0 for Dresden Unit 3 Regarding During Normal Shutdown Conditions, IRM 12 Downscale Rod Block Was Found to Trip at 4/125 | /03L-0 for Dresden Unit 3 Regarding During Normal Shutdown Conditions, IRM 12 Downscale Rod Block Was Found to Trip at 4/125 | | | 05000237/LER-1980-023, /03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58A Tripped at Less than Tech. Spec. Limit of 144 Inches | /03L-0 for Dresden Unit 3 Regarding During Normal Operation with Reactor Level Instrument Surveillance in Progress, Level Switch LIS 3-263-58A Tripped at Less than Tech. Spec. Limit of 144 Inches | | | 05000237/LER-1980-024, /03L-0 for Dresden, Unit 2 Re Drywell Oxygen Concentration Indication Failed Downscale in Violation of Tech. Spec. 3.7.A.6.d | /03L-0 for Dresden, Unit 2 Re Drywell Oxygen Concentration Indication Failed Downscale in Violation of Tech. Spec. 3.7.A.6.d | | | 05000237/LER-1980-025, /03L-0 for Dresden Unit 3 Regarding During Normal Operation While Performing Main Steam Line High Flow Isolation Surveillance, Flow Switch DPIS 3-261-2A Was Out of Tech. Spec. Limits, Table 3.2.1 | /03L-0 for Dresden Unit 3 Regarding During Normal Operation While Performing Main Steam Line High Flow Isolation Surveillance, Flow Switch DPIS 3-261-2A Was Out of Tech. Spec. Limits, Table 3.2.1 | | | 05000237/LER-1980-027, /03L-0 for Dresden, Unit 2 Re Dropping Load in Preparation for I.E.B. 80-17 Scram Tests, Low Level of Diesel Generator Coolant Present in the Water Tank Was Noticed by Equipment Operator | /03L-0 for Dresden, Unit 2 Re Dropping Load in Preparation for I.E.B. 80-17 Scram Tests, Low Level of Diesel Generator Coolant Present in the Water Tank Was Noticed by Equipment Operator | | | 05000249/LER-1980-028, Forwards LER 80-028/03L-0 | Forwards LER 80-028/03L-0 | | | 05000249/LER-1980-028-03, /03L-0:on 800718,during Setpoint Surveillance, Solenoid Valve for Torus to Reactor Bldg Vacuum Breaker 3-1601-20A Determined Inoperative,Preventing Valve from Opening.Caused by Mechanical Failure.Valve Replaced | /03L-0:on 800718,during Setpoint Surveillance, Solenoid Valve for Torus to Reactor Bldg Vacuum Breaker 3-1601-20A Determined Inoperative,Preventing Valve from Opening.Caused by Mechanical Failure.Valve Replaced | | | 05000249/LER-1980-030, /03L-0 for Dresden Unit 3 Regarding While Reducing Power for Manual Scram Required by I.E. Bulletin 80-17, Routine Surveillance of MSIV Closure Times Showed That MSIVs 3-203-2B and 2D Closed in Less than 3 Seconds | /03L-0 for Dresden Unit 3 Regarding While Reducing Power for Manual Scram Required by I.E. Bulletin 80-17, Routine Surveillance of MSIV Closure Times Showed That MSIVs 3-203-2B and 2D Closed in Less than 3 Seconds | | | 05000249/LER-1980-032, /03L-0 for Dresden Unit 3 Regarding During Normal Operations While Performing APRM Rod Block and Scram Functional Tests, APRM 3 Failed to Initiate a Rod Block | /03L-0 for Dresden Unit 3 Regarding During Normal Operations While Performing APRM Rod Block and Scram Functional Tests, APRM 3 Failed to Initiate a Rod Block | | | 05000249/LER-1980-033, Forwards LER 80-033/03L-0 | Forwards LER 80-033/03L-0 | | | 05000249/LER-1980-033-03, /03L-0:on 800724,during Normal operations,1/4-inch through-wall Leak Discovered in 3A Component Cooling Svc Water Pump Casing.Caused by Casting Hole on Bottom of Casing.Pump Removed & Hole Plugged | /03L-0:on 800724,during Normal operations,1/4-inch through-wall Leak Discovered in 3A Component Cooling Svc Water Pump Casing.Caused by Casting Hole on Bottom of Casing.Pump Removed & Hole Plugged | |
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