Letter Sequence Other |
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Results
Other: 05000346/LER-1980-089, Forwards LER 80-089/03L-0, 05000346/LER-1980-089-03, /03L-0:on 801203,following Reactor Trip,Rcs Sample Revealed Dose Equivalent I-131 Level Was Greater than Tech Specs.Caused by Gas Leakage Through Fuel Cladding.Levels Monitored to Ensure That Gas Decayed to Below Limits, 05000346/LER-1981-016, 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, ML20049A784
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MONTHYEAR05000346/LER-1980-089, Forwards LER 80-089/03L-01981-01-0202 January 1981 Forwards LER 80-089/03L-0 Project stage: Other 05000346/LER-1980-089-03, /03L-0:on 801203,following Reactor Trip,Rcs Sample Revealed Dose Equivalent I-131 Level Was Greater than Tech Specs.Caused by Gas Leakage Through Fuel Cladding.Levels Monitored to Ensure That Gas Decayed to Below Limits1981-01-0202 January 1981 /03L-0:on 801203,following Reactor Trip,Rcs Sample Revealed Dose Equivalent I-131 Level Was Greater than Tech Specs.Caused by Gas Leakage Through Fuel Cladding.Levels Monitored to Ensure That Gas Decayed to Below Limits Project stage: Other 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 Monitored1981-04-0303 April 1981 /03L-0:on 810308,dose Equivalent I-131 Level Exceeded Tech Spec Limit.Caused by Gas Leakage Through Fuel Cladding.Levels Monitored Project stage: Other 05000346/LER-1981-016, Forwards LER 81-016/03L-01981-04-0303 April 1981 Forwards LER 81-016/03L-0 Project stage: Other ML20049A7691981-09-25025 September 1981 Forwards Application for Amend to License NPF-3,revising App a Tech Specs.Class III Amend Fee Encl Project stage: Request ML20049A7841981-09-25025 September 1981 Proposed Tech Specs 3/4.3,4.4.6.2.1,3.4.8 & 3/4.4.7 Re Instrumentation Surveillance Requirements,Limiting Condition for Operation & Bases,Respectively Project stage: Other ML20049A7761981-09-25025 September 1981 Application for Amend to License NPF-3,revising App a Tech Specs Re Steam Generator Containment Isolation Valves, Chlorine Detector & Control Room Ventilation & I-131 Dose Equivalent.Safety Evaluations Encl Project stage: Request ML20095A3751984-08-13013 August 1984 Withdraws Item 4 of 810925 Application for Amend to License NPF-3,per Project stage: Request 1981-04-03
[Table View] |
LER-1981-016, /03L-0:on 810308,dose Equivalent I-131 Level Exceeded Tech Spec Limit.Caused by Gas Leakage Through Fuel Cladding.Levels Monitored |
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| 3461981016R03 - NRC Website |
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EVm f DESCRIPTION AND PROBASLE CONSEQUENCES h I; ! 21 l (NP-33-81-15) on 3/S/81 at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> following a power reduction, a Reactor Coolant l lc (3 l l System (RCS) sample revealed that the Dose Equivalent Iodine I-131 level was greater l Wgl than the 1.0 uCi/gn limit of Technical Specification 3.4.8, Table 4.4-4.
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At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> onj j r le ] ] 3/9/81 the level returned to below the limit. There was no danger to the health and j j r. J 7 j i safety of the public or station personnel. The highest level was still well below l
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TOLEDO EETSON COM'AW DAVIS-BESSE NUCLEAR POUER STATION UNIT ONE SUPPLEME!T/AL INFORMATION FOR LER NP-33-81-15 DATE OF EVENT: March 8, 1981 FACILITY: Davis-Ee se Unit 1 IDENTIFICATION OF OCCURRENCE: Reactor Coolant System (RCS) Dose E uivalete I-131 3
Exceeded Technical Specification Limits After a Power Reduction The unit was in Mode 1 with Power (IMT) = 195 Conditions Prior to Occurrence:
and Load (Cross tf4E) = G.
Description of Occurrence: At 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> on March 8, 1981 following a power reduction an RCS sample was collected in accordance with Technical Specification 3.4.S, Tabic 4.4-4.
The analysis of the sample by Chemistry and Health Physics personnel showed that the radio-iodine content excee led the Technical Specification 3.4.8 limit of 1.0 uCi/ gram Dose Equivalent of I-l31.
At 1501 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.711305e-4 months <br /> on March 9,1981, the level peaked at 1.31 uCi/gm Dose Equivalent Iodine I-131.
The following information is supplied per reporting requirements:
Syecific Activity Analysis:
Date Time Activity (uC1/P) 3/7/81 0810 0.075 3/8/81 0830 1.25 1220 1.30 1501 1.51 1821 1.34 2200 1.35 3/9/81 0200 1.15 0600 1.13 0815 1.00 1200 1.04 1500 0.77 Power History:
Reactor power was constant at approximately 99.6% until 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on March 7, 1981.
Date Time Reactor Power 3/7/81 2300 93.58%
3/8/81 0000 82.98%
0100 75.94%
0200 62.12%
0300 46.80%
0400 34.71%
0500 26.62%
LER #81-016 i
TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER 5TATION UNIT ONE SUPPLEMENTAL INFORMATION FJR LER NP-33-81-15 PACE 2 Date Time Reactor Power 3/8/81 0600 21.77%
0700 11.93%
0800 8.52%
0830 7.5%
Fuel Burnup By Core Region - See attached computer printout Cleanup Flow History - 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first limit exceeding sample:
The letdown flow during this time period was kept constant at approximately 79.5 gpm.
There was no degassing operation.
The Dose Equivalent I-131 exceeded 1.0 uC1/gm at 0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br /> on March 8, 1981, and was below that limit at 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on !! arch 9,1981. The total time dura-tion was 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> and 30 minutes. The maximum measured level was 1.51 uCi/gm Dose Equivalent I-131.
Designation of Apparent Cause of Occurrence: The cause of the 1.51 uCi/gm Dose Equi-valent I-131 level in the RCS was a slight amount of leakage of gas through the fuel rod cladding. Some leakage is normal following a power transient when the gases in the fuel rods are further compressed 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 statien personnel. There was nu venting of containment gases until the levels had decayed. The highest levels found in any sample was still well below the allowa-ble limit of 60 uCi/gm per Figure 3.4-1 of Technical Specification 3.4.8.
Corrective Action
The action that was taken was to monitor the level of I-131 to ensure that it did return to below the Technical Specit'ication limit of 1 uC;'gm.
At 1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br /> on March 9, 1981, the level dropped to 0.77 uCi/gm.
Failure Data: There has been one previous report of high iodine levels on December 3,1980, see Licensee Event Report NP-33-80-114 (80-088).
LER #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. 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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