LER-1981-034, /03L-0:on 810601,found That When Unit Experienced Power Swing During Turbine Generator Control Valve Test, Main Steam Line Code Safety Valves Lifted Early.Cause Unknown.Investigation Will Be Done in Upcoming Outage |
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CCYT 68 69 EVENT DATE 74 7b REPORT DATE 80 60 61 DOCKET NUMBER 7
8 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h Turbine Generator control l
10121 l (NP 33-81-39) on 5/31/81 at 0300 knn,.= W 1. p o,. r,,,. q., g Valve Test, the station experienced a power swing. During the swing, one of the Main, pl Steam Line code safety valves lifted. After reviewing data, it was determined On 6/1/81 at 1555 hours0.018 days <br />0.432 hours <br />0.00257 weeks <br />5.916775e-4 months <br />, one safety valve l
that one of the valves lifted early..
30j5j l The station entered the action statement of T.S. 3.7.1.1.
g l0 l6 l l was declared inoperable.
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l There was no danger to public or station personnel.
Icl7j intended function of relieving pri.sure had'a trip occurred.
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Testing and ex-l l The cause for the apparent early lifting is unknown at this time.
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safety valves will be done durine the upcominc 1
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Any problems found at that time will be evaluated and l
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% POWER oTHER STATUS iSCO RY DISCOVERY DESCRIPT.vN l
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PERSONNEL EXPOSURES NuYBER TYPE
DESCRIPTION
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TYPE DESCRIPflON
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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-81-39 DATE OF EVENT: June 1, 1981 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: One code safety valve on Main Steam Line 1 declared inoperable The unit was in Mode 1 with Power (MWT) = 2018 and Conditions Prior to Occurrence:
Load (Gross MWE) = 672 Description of Occurrence: On May 31,1981 at 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> while performing Turbine Generator Control Valve Test, PT 5193.01, the station experienced a power swing down to 550 MWe.
During the swing, one of the main steam safety valves lifted on the After reviewing all of the available data from the swing, it was deter-No. 1 side.
mined that one of the safety valves lif ted early. On June 1,1981 at 1555 hours0.018 days <br />0.432 hours <br />0.00257 weeks <br />5.916775e-4 months <br />, one The station entered the safety valve on Main Steam Line 1 was declared inoperable.
action statement of Technical Specification 3.7.1.1 which allows power operation to proceed provided that within four hours the high flux trip settnint be reduced to 4m92.91% full power. As the station.was already in a three reactor coolant pump the high flux trip setpoint had previously been reduced to 80%
operating condition,
' full power. The conditions of the action statement were being met.
The cause for the apparent early lifting Designation of Apparent Cause of Occurrence:
is unknown at this time. Testing and examination of some main steam line safety
~
valves will be donc during the current Reactor Coolant Pump seal repair outage.
There was no danger to the health and safety of the public Analysis of Occurrence:
or to station personnel. The power swing was not severe and was controlled without difficulty after suspending turbine control valve testing. The safety valve apperently lifted only 4% 1cuer than its setpoint. The valve would still have served its intended function of relieving pressure had a trip occur. red.
The setpoints for some safety valves will be checked during the Corrective Act' or :
8,y p-oblems found at that time will be evaluated and corrective action next outage taken.
Previous safety setpoint problems were reported in Licensee Event Failure Data:
Reports NP-33-79-51 (79-049), NP-33-79-34 (79-032), NP-33-79-25 (79-020),
NP-33-79-23 (79-018) and NP-33-78-145 '~8-124).
LER #81-034
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| 05000346/LER-1981-001, Forwards LER 81-001/01X-1 | Forwards LER 81-001/01X-1 | | | 05000346/LER-1981-001-01, /01X-1:on 810107,discovered Contractor Personnel on 801204 Disassembled Restraints Other than Those Requested & Failed to Perform Reassembly in Timely Manner. Caused by Inadequate Procedural Control | /01X-1:on 810107,discovered Contractor Personnel on 801204 Disassembled Restraints Other than Those Requested & Failed to Perform Reassembly in Timely Manner. Caused by Inadequate Procedural Control | | | 05000346/LER-1981-002-03, /03L-0:on 810102,reactor Coolant Pump 1-2 Was Shutdown Due to High Seal Return Temp & Deteriorating Seal Staging & on 810106,pump 2-1 Was Shutdown for Deteriorating Seal Staging.Caused by Seal Degradation.Seals Replaced | /03L-0:on 810102,reactor Coolant Pump 1-2 Was Shutdown Due to High Seal Return Temp & Deteriorating Seal Staging & on 810106,pump 2-1 Was Shutdown for Deteriorating Seal Staging.Caused by Seal Degradation.Seals Replaced | | | 05000346/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000346/LER-1981-003-03, /03L-0:on 810106,breaker HX02B Tripped, de-energizing Bus B Which Reduced Electrical Distribution Less than Tech Specs Required.Caused by Personnel Error. Breakers Restored.Operators Counselled Re Attentiveness | /03L-0:on 810106,breaker HX02B Tripped, de-energizing Bus B Which Reduced Electrical Distribution Less than Tech Specs Required.Caused by Personnel Error. Breakers Restored.Operators Counselled Re Attentiveness | | | 05000346/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000346/LER-1981-004, Forwards LER 81-004/03X-1 | Forwards LER 81-004/03X-1 | | | 05000346/LER-1981-005-03, /03L-0:on 810114,RCS Chloride Concentration Exceeded Tech Spec Limit.Caused by Use of Spotcheck in Cleaning Reactor Coolant Pump Seal Cavities.Instructions Issued for Use of Solvents in RCS | /03L-0:on 810114,RCS Chloride Concentration Exceeded Tech Spec Limit.Caused by Use of Spotcheck in Cleaning Reactor Coolant Pump Seal Cavities.Instructions Issued for Use of Solvents in RCS | | | 05000346/LER-1981-005, Forwards LER 81-005/03L-0 | Forwards LER 81-005/03L-0 | | | 05000346/LER-1981-006-03, /03L-0:on 810119,power Lost to Safety Features Actuation Sys Channel 1 Cabinet.Caused by Blown Supply Fuse from Panel Y-1 Due to Procedure Deficiency.Fuse Replaced & Procedure Modified | /03L-0:on 810119,power Lost to Safety Features Actuation Sys Channel 1 Cabinet.Caused by Blown Supply Fuse from Panel Y-1 Due to Procedure Deficiency.Fuse Replaced & Procedure Modified | | | 05000346/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000346/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000346/LER-1981-007-03, /03L-0:on 810122,door 306 Found Partially Open,So That Spent Fuel Pool Emergency Ventilation Sys Could Not Have Maintained Area at Correct Pressure.Caused by Maladjusted Door Closure.Maint Work Order Issued | /03L-0:on 810122,door 306 Found Partially Open,So That Spent Fuel Pool Emergency Ventilation Sys Could Not Have Maintained Area at Correct Pressure.Caused by Maladjusted Door Closure.Maint Work Order Issued | | | 05000346/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000346/LER-1981-008-03, /03L-0:on 810127,345 Kv Switchyard Bus K Tripped & Locked out,de-energizing Startup Transformer 02.Caused by Action from Directional Ground Current Relay & Charred Phase Lightning Arrestor C on Startup Transformer | /03L-0:on 810127,345 Kv Switchyard Bus K Tripped & Locked out,de-energizing Startup Transformer 02.Caused by Action from Directional Ground Current Relay & Charred Phase Lightning Arrestor C on Startup Transformer | | | 05000346/LER-1981-009-03, /03L-0:on 810128,diesel Generator 1-2 Could Not Be Started W/Left Side Set of Air Start Motors During Diesel Generator Surveillance Test 5081.01.Caused by Failure of One Air Start Motor Due to Broken Solenoid Drive Shaft | /03L-0:on 810128,diesel Generator 1-2 Could Not Be Started W/Left Side Set of Air Start Motors During Diesel Generator Surveillance Test 5081.01.Caused by Failure of One Air Start Motor Due to Broken Solenoid Drive Shaft | | | 05000346/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000346/LER-1981-010, Forwards LER 81-010/03L-0 | Forwards LER 81-010/03L-0 | | | 05000346/LER-1981-010-03, /03L-0:on 810202,MSIV Bypass Valve Ms 100 a Failed to Close.Probably Caused by Component Failure.Actuator Spring Adjusted to Increase Tension Until Valve Would Close | /03L-0:on 810202,MSIV Bypass Valve Ms 100 a Failed to Close.Probably Caused by Component Failure.Actuator Spring Adjusted to Increase Tension Until Valve Would Close | | | 05000346/LER-1981-011, Forwards LER 81-011/03L-0 | Forwards LER 81-011/03L-0 | | | 05000346/LER-1981-011-03, /03L-0:on 810205,post-accident Monitoring Instrument HPI Flow 1-2 Was Declared Inoperable.Caused by Bad Current Buffer.Current Buffer Was Repaired,Recalibr & Reinstalled.Hpi Flow 1-2 Was Returned to Operable Status | /03L-0:on 810205,post-accident Monitoring Instrument HPI Flow 1-2 Was Declared Inoperable.Caused by Bad Current Buffer.Current Buffer Was Repaired,Recalibr & Reinstalled.Hpi Flow 1-2 Was Returned to Operable Status | | | 05000346/LER-1981-012-03, /03L-0:on 810212,control Rod 1-3 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals Causing Asymmetric Rod Alarms.Exact Cause Undetermined,But Absolute Position Indication Leads Picking Up Noise | /03L-0:on 810212,control Rod 1-3 Absolute Position Indication Declared Inoperable Due to Fluctuating Signals Causing Asymmetric Rod Alarms.Exact Cause Undetermined,But Absolute Position Indication Leads Picking Up Noise | | | 05000346/LER-1981-012, Forwards LER 81-012/03L-0 | Forwards LER 81-012/03L-0 | | | 05000346/LER-1981-013-03, /03L-0:on 810218,control Room Normal Ventilation Dampers Tripped Shut Resulting in No Power Available to Chlorine Detector 1 Above Control Room or in Block House. Caused by Failure of 10 Amp Fuse of Circuit Y111 | /03L-0:on 810218,control Room Normal Ventilation Dampers Tripped Shut Resulting in No Power Available to Chlorine Detector 1 Above Control Room or in Block House. Caused by Failure of 10 Amp Fuse of Circuit Y111 | | | 05000346/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | | | 05000346/LER-1981-014-03, /03X-1:on 810226,decay Heat Valve 64 Would Not Open During Testable ECCS Valves Quarterly Test.Caused by Loose Set Rod Bushing,Allowing Gear Box Set Rod to Move Which Unlocked Limit Switches from Adjusted Position | /03X-1:on 810226,decay Heat Valve 64 Would Not Open During Testable ECCS Valves Quarterly Test.Caused by Loose Set Rod Bushing,Allowing Gear Box Set Rod to Move Which Unlocked Limit Switches from Adjusted Position | | | 05000346/LER-1981-014, Forwards LER 81-014/03X-1 | Forwards LER 81-014/03X-1 | | | 05000346/LER-1981-015-03, /03L-0:on 810227,access Door 107 Found Propped Open from ECCS 2 Pump Room 115 to Miscellaneous Waste Monitor Tank & Pump Room 114.Caused by Failure to Follow Posted Signs While Clearing Odor from Room | /03L-0:on 810227,access Door 107 Found Propped Open from ECCS 2 Pump Room 115 to Miscellaneous Waste Monitor Tank & Pump Room 114.Caused by Failure to Follow Posted Signs While Clearing Odor from Room | | | 05000346/LER-1981-015, Forwards LER 81-015/03L-0 | Forwards LER 81-015/03L-0 | | | 05000346/LER-1981-016, Forwards LER 81-016/03L-0 | Forwards LER 81-016/03L-0 | | | 05000346/LER-1981-016-03, /03L-0:on 810308,dose Equivalent I-131 Level Exceeded Tech Spec Limit.Caused by Gas Leakage Through Fuel Cladding.Levels Monitored | /03L-0:on 810308,dose Equivalent I-131 Level Exceeded Tech Spec Limit.Caused by Gas Leakage Through Fuel Cladding.Levels Monitored | | | 05000346/LER-1981-017-03, /03L-0:on 810309,train 2 Hpi/Low Pressure Injection cross-connect Isolation Valve Dh 63 Would Not Open from Control Room During Quarterly Valve Surveillance Test 5051.13.Caused by Faulty Torque Switch in Valve Operator | /03L-0:on 810309,train 2 Hpi/Low Pressure Injection cross-connect Isolation Valve Dh 63 Would Not Open from Control Room During Quarterly Valve Surveillance Test 5051.13.Caused by Faulty Torque Switch in Valve Operator | | | 05000346/LER-1981-017, Forwards LER 81-017/03L-0 | Forwards LER 81-017/03L-0 | | | 05000346/LER-1981-018-03, /03L-0:on 810322 & 0401,chlorine Detector Ae 5358B Tripped.First Trip Probably Caused by Fouled Detector. Detector Cleaned.Detector & Circuit Board Replaced After Second Failure | /03L-0:on 810322 & 0401,chlorine Detector Ae 5358B Tripped.First Trip Probably Caused by Fouled Detector. Detector Cleaned.Detector & Circuit Board Replaced After Second Failure | | | 05000346/LER-1981-018, Forwards LER 81-018/03L-0 | Forwards LER 81-018/03L-0 | | | 05000346/LER-1981-019-03, /03L-0:on 810323,fluctuating Signals W/Numerous Asymmetric Rod Alarms Received,Resulting in Control Rod 4-7 Absolute Position Indication Inoperability.Probably Caused by Electrical Penetration Module Deficiency | /03L-0:on 810323,fluctuating Signals W/Numerous Asymmetric Rod Alarms Received,Resulting in Control Rod 4-7 Absolute Position Indication Inoperability.Probably Caused by Electrical Penetration Module Deficiency | | | 05000346/LER-1981-019, Forwards LER 81-019/03L-0 | Forwards LER 81-019/03L-0 | | | 05000346/LER-1981-020-03, /03L-0:on 810324,valve CV5011A,on Containment Air Sample Inlet Line to Hydrogen Analyzer,Would Not Stroke Closed W/Monitor Operator.Caused by Badly Worn Tripper in Motor Operator.Tripper Levers Replaced | /03L-0:on 810324,valve CV5011A,on Containment Air Sample Inlet Line to Hydrogen Analyzer,Would Not Stroke Closed W/Monitor Operator.Caused by Badly Worn Tripper in Motor Operator.Tripper Levers Replaced | | | 05000346/LER-1981-020, Forwards LER 81-020/03L-0 | Forwards LER 81-020/03L-0 | | | 05000346/LER-1981-021-03, /03L-0:on 810401,half Trip Occurred from Steam & Feedwater Rupture Control Sys Channel 1 Low Steam Generator Level Trip.Caused by Power Supply Failure.Power Supply Replaced Per Work Order on 810402 | /03L-0:on 810401,half Trip Occurred from Steam & Feedwater Rupture Control Sys Channel 1 Low Steam Generator Level Trip.Caused by Power Supply Failure.Power Supply Replaced Per Work Order on 810402 | | | 05000346/LER-1981-021, Forwards LER 81-021/03L-0 | Forwards LER 81-021/03L-0 | | | 05000346/LER-1981-022, Forwards LER 81-022/03L-0 | Forwards LER 81-022/03L-0 | | | 05000346/LER-1981-022-03, /03L-0:on 810316,NRC Site Inspector Reported Finding Four 0.5-inch Holes Through Control Room Equipment Room East Fire Wall.On 810403,two Holes Found in Wall of Room 427B.Caused by Personnel Error | /03L-0:on 810316,NRC Site Inspector Reported Finding Four 0.5-inch Holes Through Control Room Equipment Room East Fire Wall.On 810403,two Holes Found in Wall of Room 427B.Caused by Personnel Error | | | 05000346/LER-1981-023-03, /03L-1:on 810403,decay Heat Cooler Outlet Valve CC1467 Stroked Closed During Component Cooling Water Monthly Test & Would Not Reopen.Caused by Excessive Wear on Actuator Due to Design Deficiency.Actuator Rebuilt | /03L-1:on 810403,decay Heat Cooler Outlet Valve CC1467 Stroked Closed During Component Cooling Water Monthly Test & Would Not Reopen.Caused by Excessive Wear on Actuator Due to Design Deficiency.Actuator Rebuilt | | | 05000346/LER-1981-023, Forwards LER 81-023/03L-1 | Forwards LER 81-023/03L-1 | | | 05000346/LER-1981-024, Forwards LER 81-024/03L-0 | Forwards LER 81-024/03L-0 | | | 05000346/LER-1981-024-03, /03L-0:on 810418,bus J Was Rapidly Taken Out of Svc W/O Providing for Alternate Power Supply for Decay Heat Pump 1-1.Caused by Personnel Error.Procedure Modified & Operator Informed of Mods | /03L-0:on 810418,bus J Was Rapidly Taken Out of Svc W/O Providing for Alternate Power Supply for Decay Heat Pump 1-1.Caused by Personnel Error.Procedure Modified & Operator Informed of Mods | | | 05000346/LER-1981-025, Forwards LER 81-025/03L-0 | Forwards LER 81-025/03L-0 | | | 05000346/LER-1981-025-03, /03L-0:on 810423,during Review of Safety Tagging Log,Unit Entered Mode 4 W/O Required Two Makeup Pumps Operable.Caused by Personnel Error.Pumps Restored to Operation.Personnel Reinstructed in Procedures | /03L-0:on 810423,during Review of Safety Tagging Log,Unit Entered Mode 4 W/O Required Two Makeup Pumps Operable.Caused by Personnel Error.Pumps Restored to Operation.Personnel Reinstructed in Procedures | | | 05000346/LER-1981-026-03, /03L-0:on 810428,reactor Protection Sys Channel 1 Tripped on Flux/Delta Flux/Flow.Caused by Failure of Flow Differential Pressure Transmitter Primary Power Transformer Shorting to Ground.New Amplifier Installed & Calibr | /03L-0:on 810428,reactor Protection Sys Channel 1 Tripped on Flux/Delta Flux/Flow.Caused by Failure of Flow Differential Pressure Transmitter Primary Power Transformer Shorting to Ground.New Amplifier Installed & Calibr | |
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