LER-1981-031, /03X-1:on 810512,following Reactor Trip,Rcs Radioiodine Content Exceeded Limit.Caused by Gas Leakage Through Fuel Cladding.Levels Decayed Off Below Limits.Tech Spec Revision Being Evaluated |
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l (NP-33-81-37) On May 12,1981 at 1457 hours0.0169 days <br />0.405 hours <br />0.00241 weeks <br />5.543885e-4 months <br /> following a reactor trip, a Reactor 3 2 f-T~} l Coolant System (RCS) samp1' was collected in accordance with Technical Speci l
The analysis of the sample showed that the radio-iodine content j
- 3 ;4; j 3.4.8, Table 4.4-4.
At 2037 hours0.0236 days <br />0.566 hours <br />0.00337 weeks <br />7.750785e-4 months <br />, the level peaked at 1.52 uCi/gm dose equi-l
[ :Til I was approaching the limit.
There was no danger to the 1
lell valent iodine I-131 with the limit being 1.0 uCi/gm.
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DVR 81.-072 NAug Or PREPAnER _
O TOLEDO EDISON COMPANY DAVIS-BESSE. NUCLEAR POWER STATION UNIT ONE PACE 2 SUPPLEMENTAL INFORMATION FOR LER NP-33-81-37 The dose equivalent I-131 exceeded 1.0 uCi/gm at 2037 hours0.0236 days <br />0.566 hours <br />0.00337 weeks <br />7.750785e-4 months <br /> on May~ 12, 1981, and was below that limit at 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> on May 13, 1981. The total time dura-tion was approximately 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br />. The maximum level was 1.52 uci/go.
Specific Activity Analysis:
Date Time Activity (uCi/gm) Dose Equivalent I-131 5/12/81 0500 0.132 1845 0.94 2037 1.52 1.14 5/13/81 0013
. ~
0350 0.99 0555 0.74 0815 0.16 Designation of Apparent Cause of Occurrence: A reactor trip typically causes an iodine spike in the RCS. This is caused by a slight amount of gas leakage through the' fuel rod cladding due to transient conditions. The gas leak is a result of in-creased compression of gas by the contracting cladding. Any small defects would allow some gas to escape.
Analysis of Occurrence: There was no danger to the health and safety of the public or to station 1.arsonnel. There was no venting of containment gases until the levels had decayed. The highest levels found in any sample were still well below the allowa-ble limit of 60 uCi/gm per Figure 3.4-1 of Technical Specification 3.4.8.
Corrective Action
A corrective action is not applicable. Iodine spikes are typical following a reactor trip. No damage is indicated to the fuel. Monitoring of I-131 level was continued until it dropped below Technical Specification limit of 1 uCi/gm.
At 0555 hours0.00642 days <br />0.154 hours <br />9.176587e-4 weeks <br />2.111775e-4 months <br />.on May 13, 1981, the level dropped to.74 uCi/gm. A Technical Specifi-cation revision to change the limit is being evaluated per Facility Change Request 81-163.
Failure Data: There have been two previous reports of high iodine levels - see Licensee Event Reportis NP-33-80-114 (80-088) and NP 33-81-15 (81-016).
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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. 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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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