LER-1980-001, /01T-0:on 800106,Unit 1 Caustic Addition Valves CA-1-2 & CA-1-4 Mistakenly Closed & Secure Cards Attached. Caused by Personnel Error & Procedural Inadequacies. Administrative Procedures Modified |
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SUPPLEMENTAL INFORMATION FOR LER 80-1 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Description of Occurrence On January 6,1980 a check of the safeguard hold cards was being performed in accordance with SWI-0-3, Safeguards Hold Cards, and SP 1658, Monthly Safeguards Hold Verification.
At approximately 0600, the operator perform-ing these checks found that two unit I caustic addition valves, CA-1-2 and CA-1-4, were closed with SECURE cards attached.
Since the required position of these valves was open, the operator immediately reported the condition to the Unit 1 Shift Supervisor who directed the operator to immediately open CA-1-2 and CA-1-4.
Designation of the Apparent Cause of the Occurrence At about 2300 on January 3rd the unit 2 Lead Plant Equipment & Reactor Operator (LPE&RO) issued SECURE cards to be hung according to C1.3, Unit Shutdown procedure, Step 37b (Step 37b isolates caustic to the containment spray system on unit cooldown).
When these cards were filled out, the LPE&RO copied the unit I caustic addition valve numbers from the procedure, rather than unit 2 (numbers for both units are given in the procedure).
The Plant Equipment and Reactor Operator 0?E&RO ) then placed the unit i valves in the position specified by the SECURE cards and attached the cards to the valves without realizing that he was isolating the caustic addition valves on the operating unit, rather than the shutdown unit.
The basic cause of this occurrence is personnel error, with the procedure contributing.
Analysis of Occurrence The caustic addition system fulfills two purposes, neither of which is required to meet 10CFR100 release limits nor for immediate operation of engineered safety systems.
One of these functions is removal of iodine in the containment by the containment spray system. The analysis in the FSAR (Section 14) shows that 10CFR100 guidelines are not exceeded with or without taking credit for iodine removal.
NRC calculations in the Prairie Island SER do assume some iodine removal. ilowever, these calculations allow only a little credit for this removal (only 11% from 24 minutes to 30 days, and higher values prior to 24 minutes). Taking no credit for caustic addition should not increase these doses much (11-20%) and should remain within the guidelines of 10CFR100.
The second function the caustic addition system fulfills is to provide pH control to inhibit stress corrosion cracking in a post accident environment.
The FSAR, section 6.4.3, shows that it is not credible for the chloride concentration in the recirculated post-LOCA fluid to reach the levels that might cause stress corrosion.
Nevertheless, the caustic addition system provides a means of pH control to inhibit stress corrosion.
An even more conservative view is that the pH control might be required after the RHR system is placed in tervice for long term post-LOCA recircula-tion. Approximately 30 minutes would be available to manually initiate caustic addition before entering the recirculation mode.
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SUPPLEMENTAL INFORMATION FOR LER 80-1 (cont}
The re fo re, it is believed that the risk to the health and safety of the public as a result of this occurrence was minimal.
Corrective Action
Administrative Controls have been strengthened in the following manner:
1.
The requirement that " Safeguards Hold" tags be returned to the Shif t Supervisor (Ref SWI-0-3) has been re-emphasized. An exemption to logging requirements upon installation and removal of the tag has been deleted.
2.
SWI-0-10 has been changed to require that, when using a procedure that can apply to either unit, a line be drawn through the numbers not applicable to the unit under consideration.
This occurrence and its significance has been discussed with the individuals involved.
1783 324
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| 05000282/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000282/LER-1980-001-01, /01T-0:on 800106,Unit 1 Caustic Addition Valves CA-1-2 & CA-1-4 Mistakenly Closed & Secure Cards Attached. Caused by Personnel Error & Procedural Inadequacies. Administrative Procedures Modified | /01T-0:on 800106,Unit 1 Caustic Addition Valves CA-1-2 & CA-1-4 Mistakenly Closed & Secure Cards Attached. Caused by Personnel Error & Procedural Inadequacies. Administrative Procedures Modified | | | 05000282/LER-1980-002-03, /03L-0:on 800107,during Surveillance Test of Diesel Generator D-1,relay Misoperation Occurred Which Would Have Prevented Automatic Synchronization of Generator Onto Bus 15.Caused by Stuck Relay Plunger.Plunger Freed | /03L-0:on 800107,during Surveillance Test of Diesel Generator D-1,relay Misoperation Occurred Which Would Have Prevented Automatic Synchronization of Generator Onto Bus 15.Caused by Stuck Relay Plunger.Plunger Freed | | | 05000282/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000306/LER-1980-003, Forwards LER 80-003/01T-0 | Forwards LER 80-003/01T-0 | | | 05000306/LER-1980-003-01, /01T-0:on 800109,while Conducting Eddy Current Examination of Steam Generator,Row 1 Column Hot Leg Tube Found Defective.Caused by Wearing of Tube Lane Blocking Device Against Tube.Device Modified to Prevent Movement | /01T-0:on 800109,while Conducting Eddy Current Examination of Steam Generator,Row 1 Column Hot Leg Tube Found Defective.Caused by Wearing of Tube Lane Blocking Device Against Tube.Device Modified to Prevent Movement | | | 05000282/LER-1980-004-03, /03L-0:on 800118,discovered That Loop a Steam Flow Transmitter Had Drifted Out of Spec.Caused by Failure of Differential Pressure Unit in Barton Flow Transmitter Model 384.Pressure Unit Replaced,Transmitter Recalibr | /03L-0:on 800118,discovered That Loop a Steam Flow Transmitter Had Drifted Out of Spec.Caused by Failure of Differential Pressure Unit in Barton Flow Transmitter Model 384.Pressure Unit Replaced,Transmitter Recalibr | | | 05000282/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000282/LER-1980-005-03, /03L-0:on 800121,during Surveillance Test of D1 Diesel Generator,Lockout Occurred While Engine Was Being Prelubed.Caused by Abnormally Cold Generator Room.Caution Will Be Added to Procedure to Monitor Lube Oil Pressure | /03L-0:on 800121,during Surveillance Test of D1 Diesel Generator,Lockout Occurred While Engine Was Being Prelubed.Caused by Abnormally Cold Generator Room.Caution Will Be Added to Procedure to Monitor Lube Oil Pressure | | | 05000282/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000282/LER-1980-006-01, /01T-0:on 800123,during Testing of Diesel Generator D-21,ability to Reduce Generator Load from Control Room Was Lost.Caused by Loose Front End Shield on Governor Synchronizing Motor.Motor Replaced | /01T-0:on 800123,during Testing of Diesel Generator D-21,ability to Reduce Generator Load from Control Room Was Lost.Caused by Loose Front End Shield on Governor Synchronizing Motor.Motor Replaced | | | 05000282/LER-1980-006, Forwards LER 80-006/01T-0 | Forwards LER 80-006/01T-0 | | | 05000282/LER-1980-007-03, /03L-0:on 800218,during Surveillance Test,Load on Diesel Generator D1 Could Not Be Increased Above 1,400 Kw. Caused by Trainee Operator Error.Setpoint Returned to Normal & Test Completed Satisfactorily | /03L-0:on 800218,during Surveillance Test,Load on Diesel Generator D1 Could Not Be Increased Above 1,400 Kw. Caused by Trainee Operator Error.Setpoint Returned to Normal & Test Completed Satisfactorily | | | 05000282/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000306/LER-1980-008-03, /03L-0:on 800219,during Startup After Refueling, One Steam Flow Meter on Each Steam Line Did Not Come on Scale.Both Transmitters Drifted Low.Caused by Zero Adjustment Shift in Barton Model 384 Transmitters | /03L-0:on 800219,during Startup After Refueling, One Steam Flow Meter on Each Steam Line Did Not Come on Scale.Both Transmitters Drifted Low.Caused by Zero Adjustment Shift in Barton Model 384 Transmitters | | | 05000306/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000282/LER-1980-009-03, /03L-0:on 800310,during Normal Operation,Nuclear Power Range Channel 1N44 Was Inoperable for Several Minutes. Caused by latch-up of High Voltage Power Supply Due to Spike on Yellow Instrument Bus.Fuses Were Removed & Reset | /03L-0:on 800310,during Normal Operation,Nuclear Power Range Channel 1N44 Was Inoperable for Several Minutes. Caused by latch-up of High Voltage Power Supply Due to Spike on Yellow Instrument Bus.Fuses Were Removed & Reset | | | 05000282/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000282/LER-1980-010-03, /03L-0:on 800311,during Surveillance Test, Containment Isolation Valve 11 Opened at 0.57 Psi.Caused by Apparent Drift in Barton Model 288A Differential Pressure Switch.Setpoint Adjusted & Valve Retested Satisfactorily | /03L-0:on 800311,during Surveillance Test, Containment Isolation Valve 11 Opened at 0.57 Psi.Caused by Apparent Drift in Barton Model 288A Differential Pressure Switch.Setpoint Adjusted & Valve Retested Satisfactorily | | | 05000282/LER-1980-010, Updated LER 80-010/03L-1: Cause Code & Component Manufacturer Corrected | Updated LER 80-010/03L-1: Cause Code & Component Manufacturer Corrected | | | 05000306/LER-1980-011-03, /03L-0:on 800312,motor Breaker of Charging Pump 22 Would Not Stay Closed.Pump Stopped.Caused by Failed Tfk Breaker.Breaker Replaced | /03L-0:on 800312,motor Breaker of Charging Pump 22 Would Not Stay Closed.Pump Stopped.Caused by Failed Tfk Breaker.Breaker Replaced | | | 05000306/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000282/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000282/LER-1980-012-03, /03L-0:on 800331,during Review of Electrical Surveillance Program,Discovered That Individual Float Cell Voltage Measurements Were Not Done in Mar 1980 on Battery Monthly Test.Caused by Personnel Oversight | /03L-0:on 800331,during Review of Electrical Surveillance Program,Discovered That Individual Float Cell Voltage Measurements Were Not Done in Mar 1980 on Battery Monthly Test.Caused by Personnel Oversight | | | 05000306/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000306/LER-1980-013-03, /03L-0:on 800411,while Performing Maint,Workman Accidentally Tripped Overspeed Valve for turbine-driven Auxiliary Feedwater Pump 22.Valve Immediately Reset | /03L-0:on 800411,while Performing Maint,Workman Accidentally Tripped Overspeed Valve for turbine-driven Auxiliary Feedwater Pump 22.Valve Immediately Reset | | | 05000282/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000282/LER-1980-014-03, /03L-0:on 800410,during Surveillance Test,One Overpower Delta T Setpoint Was Found to Trip About 70% Above Desired Setpoint.Caused by Intermittent Capacitor.Capacitor Was Replaced | /03L-0:on 800410,during Surveillance Test,One Overpower Delta T Setpoint Was Found to Trip About 70% Above Desired Setpoint.Caused by Intermittent Capacitor.Capacitor Was Replaced | | | 05000282/LER-1980-015-01, /01T-0:on 800429,containment Maint Airlock Showed Leakage Greater than Tech Spec Limit.Caused by Degradation of Airlock Door Seal.Inner Door Seals Replaced & Leak Tested Satisfactorily | /01T-0:on 800429,containment Maint Airlock Showed Leakage Greater than Tech Spec Limit.Caused by Degradation of Airlock Door Seal.Inner Door Seals Replaced & Leak Tested Satisfactorily | | | 05000282/LER-1980-015, Forwards LER 80-015/01T-0 | Forwards LER 80-015/01T-0 | | | 05000306/LER-1980-016-03, /03L-0:on 800529,during Instrument Calibr, Instrument Was Dropped on Trip Throttle Valve Linkage, Tripping Valve & Making Pump Inoperable for 3 Minutes. Caused by Personnel Error | /03L-0:on 800529,during Instrument Calibr, Instrument Was Dropped on Trip Throttle Valve Linkage, Tripping Valve & Making Pump Inoperable for 3 Minutes. Caused by Personnel Error | | | 05000306/LER-1980-016, Forwards LER 80-016/03L-0 | Forwards LER 80-016/03L-0 | | | 05000306/LER-1980-017, Forwards LER 80-017/03L-0 | Forwards LER 80-017/03L-0 | | | 05000306/LER-1980-017-03, /03L-0:on 800615,during Normal Operation,Found One Charging Pump Out of Svc.Charge Pump 23 Started & Shut Down.Caused by Air Leaks on Speed Control Unit Due to Broken Packing Ring.Packing Ring Replaced | /03L-0:on 800615,during Normal Operation,Found One Charging Pump Out of Svc.Charge Pump 23 Started & Shut Down.Caused by Air Leaks on Speed Control Unit Due to Broken Packing Ring.Packing Ring Replaced | | | 05000282/LER-1980-018, Forwards LER 80-018/01T-0 | Forwards LER 80-018/01T-0 | | | 05000282/LER-1980-018-01, /01T-0:on 800701,unit Was Shut Down Due to Leaking Tube in Hot Leg of Vertical Steam Generator 12,Westinghouse Series 51.Cause Not Stated.Defective Tube Will Be Plugged | /01T-0:on 800701,unit Was Shut Down Due to Leaking Tube in Hot Leg of Vertical Steam Generator 12,Westinghouse Series 51.Cause Not Stated.Defective Tube Will Be Plugged | | | 05000282/LER-1980-019, Forwards LER 80-019/03L-0 | Forwards LER 80-019/03L-0 | | | 05000282/LER-1980-019-03, /03L-0:on 800630,two Power Range High Power Trip Setpoints Were Over Tech Spec Limit.Caused by Personnel Error.Rept Reviewed & Technicians Cautioned | /03L-0:on 800630,two Power Range High Power Trip Setpoints Were Over Tech Spec Limit.Caused by Personnel Error.Rept Reviewed & Technicians Cautioned | | | 05000306/LER-1980-020, Forwards LER 80-020/01T-0 | Forwards LER 80-020/01T-0 | | | 05000306/LER-1980-020-01, /01T-0:on 800715,during Severe Electrical Storm Several Breakers Operated.Main Generator Was Separated from Grid & Reactor & Reactor Coolant Pumps Tripped.Caused by Electrical Storm.Next Day Conditions Returned to Normal | /01T-0:on 800715,during Severe Electrical Storm Several Breakers Operated.Main Generator Was Separated from Grid & Reactor & Reactor Coolant Pumps Tripped.Caused by Electrical Storm.Next Day Conditions Returned to Normal | | | 05000282/LER-1980-021-03, Replacement of Inverter 13 Was Stopped Due to Lack of Seismic Analysis for Inverter Mount.Caused by Personnel Error.Improvement in Design Change Process Initiated | Replacement of Inverter 13 Was Stopped Due to Lack of Seismic Analysis for Inverter Mount.Caused by Personnel Error.Improvement in Design Change Process Initiated | | | 05000282/LER-1980-021, Forwards LER 80-021/03L-0 | Forwards LER 80-021/03L-0 | | | 05000306/LER-1980-022-03, /03L-0:on 800805,during Surveillance test,fan-coil Unit Dome Damper 23 Could Not Be Positioned Properly.Caused by Leaking Air Supply Line to Damper Actuator.Air Supply Line Replaced | /03L-0:on 800805,during Surveillance test,fan-coil Unit Dome Damper 23 Could Not Be Positioned Properly.Caused by Leaking Air Supply Line to Damper Actuator.Air Supply Line Replaced | | | 05000306/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000282/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000282/LER-1980-023-03, /03L-0:on 800820,during Review of Surveillance Program Annual test,SP1185 for Control Room Special Ventilation Flow Verification Found Omitted for 1978-1980. Caused by Personnel Error.Personnel Will Review Rept | /03L-0:on 800820,during Review of Surveillance Program Annual test,SP1185 for Control Room Special Ventilation Flow Verification Found Omitted for 1978-1980. Caused by Personnel Error.Personnel Will Review Rept | | | 05000282/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000282/LER-1980-024-03, /03L-0:on 800829,failure to Perform Inservice Insp of Safety Nozzle to Shell Weld of Both Reactor Vessels Was Noted.Cause Due to Equipment Unavailablilty.Rescheduling Requested for 1983 & 1984 Outages | /03L-0:on 800829,failure to Perform Inservice Insp of Safety Nozzle to Shell Weld of Both Reactor Vessels Was Noted.Cause Due to Equipment Unavailablilty.Rescheduling Requested for 1983 & 1984 Outages | | | 05000282/LER-1980-025, Forwards LER 80-025/01T-0 | Forwards LER 80-025/01T-0 | | | 05000282/LER-1980-025-01, /01T-0:on 800904,during Refueling Shutdown, Ultrasonic Exam of Steam Generator Support Bolts Revealed Crack Indications.Unit 2 Also Inspected.Caused by Environ Assisted Cracking.All Unit 1 Bolts Will Be Replaced | /01T-0:on 800904,during Refueling Shutdown, Ultrasonic Exam of Steam Generator Support Bolts Revealed Crack Indications.Unit 2 Also Inspected.Caused by Environ Assisted Cracking.All Unit 1 Bolts Will Be Replaced | |
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