LER-1981-028, /03L-0:on 810505,log Review Showed That Liquid Release Had Been Made While Radiation Monitors Re 1878A & B Were Inoperable Due to Testing Date Being Exceeded.Caused by Personnel Error.Personnel Will Be Counseled |
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U. S. NUCLE AR REGULATORY COMMISSION hPC FORM 36G (7-??)
LICENSEE EVENT REPORT p CONTROL DLOCK: l l
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8 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h I (NP-33-81-36) On 5/ 5/81 it was confirmed by reviewing the Unit Log and the surveillancp la12l j test computer schedule that a liquid release had been made from the Miscellaneous l
,,,,3, g g g., l Waste Monitor Tank while the Radwaste Monitors RE1878A.and RE1878B were inoperable Release 706 was made on 5/1/81 but the test l
l g7-] ; to their testing date being exceeded.
l c le 1 l late date was 4/28/81. There was no danger to the poblic or station personnel.
l the monitors had, in fact, been operable]
g l When the test was performed, it verified that l
l o 181 i and that no release limits had been exceeded.
80 COMP.
VALVE SYSTEM
CAUSE
CAUSE CODE CODE SUBCODE COUPONENT CODE SUSCODE SUSCOOE l Ml Cl@
@l Al@ lI lN lS lT lR lU l@ W@ W @-
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10 11 12 IJ 18 19 20 REVISION SEQUENTIAL OCCURRENCE REPORT EVENT YE AR REPORT NO.
CODE TY'E N O.
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_ 21 22 23 24 26 27 28 29 30 31 32 AK ACTO CN PL *T
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40 41 33 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l"gO ] l The cause was personnel error on tite part of the Shif t Supervisor who permitted the l
that the monthly functional test had exceeded its I g l release without remaining cognizant l late date.
Therefore, the monitor was technically inoperable. A memo will be written l g l to the appropriate supervisory personnel reinforcing their responsibility to review l
g l the test schedule and ensure the equipment 5 properly tested.
l 80 7
8 9 ST S
% POWER OTHER STATUS ISCO RY DISCOVERY DESCRIPTION 11 l5 l W@ l 0 l 9 l 9 lhl NA l
l Al@l Unit Log Review l
ACTIVITY CONTENT LOCATION OF RELE ASE AMOUNT OF ACTIVITY l
RELEASE @D OF RELEASE @lNA l
l NA 1 6 7
8 9 to 11 44 45 80 PERSONNEL EXPOSURES NUMBER TYPE
DESCRIPTION
l 10101 Ol@l Zl@l NA i 7 PERSONNE L INJURIES DE SCRIP TIO'.@
l NUMBER [LL1j l 0101 Ol@l NA 80 8 9 11 12 LOSS OF OR DAMAGE TO FACILITY h l
TYPE
DESCRIPTION
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l lllllllllllll2 ISSUE DESCRIP TION l
[110_] LN hl NA 8106090 % O t MW an Mot 2 PHONE: (419) 259-5000, Ext. 2s DG S1-071 NAME Of-PHEPARER
TOLCD0' EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE.
SUPPLEMENTAL INFORMATION FOR LER NP-33-81-36 DATE OF EVENT: May 5, 1981 FACILITY: Davis-Besse Unit 1.
Liquid release made while radiation monitors RE1878A IDENTIFICATION OF OCCURRENCE:
dd tnd RE1878B were inoperable due to their testing date being excee e The unit was in Mode 1 with Power (MWT) - 2750 Conditions Prior to Occurrencer End Load (Gross MWE) = 915 On May 5, 1981, it was confirmed by reviewing the Unit computer schedule that a liquid release had been made Description of Occurrence:
Log and the surveillance testfrom the Fuscellaneous Waste Monitor Tank while the Misce The Monthly Functional Test RE1878A and RE1878B were technically inoperable.
ST 5032.01 late date passed at 0455 hours0.00527 days <br />0.126 hours <br />7.523148e-4 weeks <br />1.731275e-4 months <br /> on April 28, 1981. Environmental Technical Specification 2.4.2.d states that if these monitors are inoperable for a period ex-d ceeding 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, no release from a radioactive liquid waste tank shall be made an
.The release was started at 0405 hours0.00469 days <br />0.113 hours <br />6.696429e-4 weeks <br />1.541025e-4 months <br /> any releas'e in progress shall be terminated.
This finding is being on May 1, 1981 and was completed at 0610 hours0.00706 days <br />0.169 hours <br />0.00101 weeks <br />2.32105e-4 months <br /> the same day.
reported under Environmental Technical Specification 5.4.2 for exceeding a limiting 3
condition for operation.
The cause is a personnel error on the Designation of Apparent Cause of Occurrence:
part of the Shif t Supervisor who permitted the release without remaining cognizant which.is performed by operations personnel, had that the monthly functional test,Therefore, the monitor was technically inoperable.
The test exceeded its late date.
was shown on the operations section of the schedule as overdue, i
1 i
There was no danger to the health and safety of the public Analysis of Occurrence:
laten the calibration test and functional test was performed-or to station personnel.
in fact, operable during later on May 1, 1981, it verified that the monitor had been, the release. No release Ibnits had been exceeded.
A memo will be written' to the appropriate. supervisory personnel
Corrective Action
reinforcing their responsibility of reviewing the Surveillance Test Schedule and see-Tests not being performed on ing that tests are performed within the deadline.
Administrative controls schedule will render the equipment technically inoperable.
will also be modified to establish better controls of Technical Specification re-i quired radiation monitor surveillance testing.
i I
There have been no previous reports of releases being made with Failure Data:
inoperable monitors in excess of Environmental Technical Soecification limits.
l LER #81-028 t
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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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