LER-1981-025, /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 |
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U.S. NUCLEAR KEGULATCGY COMMISSl!!N NRC FOriM 3cn (7 77)
LICENSEE EVENT REPORT CONT ROL BLOCK: l l
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lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) t 6
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7 8 9 LICENSEE CODE 14 15 LICENSE NUMSEH 25 26 LICENSE TYPE JO 57 CAT 58 lol1l S$RC lL !@l0 l 51010101314 I6 @l0 l412 l3 l8 l1 l@l 0 l 5 l 2 l 218 CON'T -
60 61 OOCKET NUYS ER 68 69 EVENT DATE 74 75 REPORT OATE 80 7
8 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES h Jo ja] l (NP-33-81-27) During a review of the Safety Tagging Log prior to entering Mode 3, a i
Shif t Supervisor discovered that Makeup (MU) Pump 2 was still tagged out from 4/11/814 lo tal l l
F5T ! LTherefore, the unit had entered Mode 4 without the required two MU pumps operable.
There was no danger to the public or station personnel. The action statement for TS l lo l5l l l
1 3.1.2.4 requires a shutdown to Hot Standby within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if less than two MU pumps 0 e 0 7 l are operable when in Modes 1-4.
The second MU pump was restored within 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> of it4 Shutdown.
l g o la l l required operability, and the unit was in Hot 80 DE CODE S BC E COMPONENT CODE SUSCOdE SU E
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9 to 11 12 f3 18 19 20 SEQUENTIAL OCCUR R ENCE REPORT REVISION
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3 36 31 40 di 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS li l o l l A t' o-ough review of the Safety Tagging Log and an absolute verification of TS requirst-h lijijl ments were not done prior to changing modes. Upon discovery, immediate action was l taken, and the second MU pump was restored by 0445 hours0.00515 days <br />0.124 hours <br />7.357804e-4 weeks <br />1.693225e-4 months <br /> on 4/23/81. The incident was i
, 7 A memorandum was written to all operaf [TTTI I reviewed with the personnel directly involved.
tions personnel to reinforce the necessity for proper procedural verifications.
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7 8 9 STA S
% POWER OTHER STATUS IS O RY OISCOVERY DESCRIPTION y y@ l 0 l 0 l 0 l@l NA l
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8 9 11 12 LOSS OF OR D AMAGE TO FACILITY -
l TYPE DESCntPTION IZi@l NA i 9 7
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DESCRIPTION
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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-81-27 DATE OF EVENT: April 23, 1981 FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE:
Changed modes without the required number of makeup pumps being operable Conditions Prior to Occurrence: The unit was in Mode 4 with Power (MWT) = 0 and Load (Gross MRE) = 0.
Description of Occurrence: As a precaution for the OTSG tube plugging outage, both makeup pump breakers were racked out and remained racked out until startup proce-dures required the Makeup and Purification' System be put in service to provide seal injection to the reactor coolcnt pumps.
The end of the shift was near and since only one makeup pump was required for this operation, the Makeup and Purification System was made operable with or e makeup pump and the reactor coolant pumps were started. Appropriate log entries were made and startup sequences continued as depicted by the Startup Mode Chec'klist and the Startup Procedure.
. When Mode 4 was approached, the Assistant Shift Supervisor reviewed the Safety Tagging Log for " outstanding items required for entering Mode 4".
He did not notice a tag for the racked out breaker of the second makeup was outstanding and signed off the requirement. The following shift, a second Assistant Shift Supervisor, realizing that the Makeup and Purification System was in service since the reactor coolant pump's had been running and the Safety Tagging Log had been reviewed, ascertained
'that Technical Specification requirements for makeup pumps for Mode 4 had been met and signed off that requirement on the Startup' Checklist. With the Startup Checklist then complete, Mode 4 was attained at 2200 hcurs on April 22, 1981.
The completion of the Startup Checklist for Mode 3 continued which included addi-tional review of the Safety Tagging Log.
The Shift Supervisor making this review noticed the outstarding tag, immediately took the necessary action, and restored the second makeup pump by 0445 hours0.00515 days <br />0.124 hours <br />7.357804e-4 weeks <br />1.693225e-4 months <br /> on April 23, 1981, approximately nine hours after entering Mode 4.
l Designation of Apparent Cause of Occurrence: Events which resulted in this occurrence included errors on the part of two Assistant Shif t Supervisors. A thorough review of the Safety Tagging Log and an absolute verification of Technical Specification require-ments were not done prior to changing modes. Either check would have prevented the occurrence.
LER #81-025
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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-81-27 PAGE 2 Analysis of Occurrence: There was no danger to the health and safety of the public or to station personnel. The action statement for Technical Specification 3.1.2.4 rsquires a shutdown to Hot Standby within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> if less than two makeup pumps are operable when in Modes 1-4.
The second makeup pump was restored within 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> of its required operability, and the unit was in Hot Shutdown.
Corrective Action
The second makeup pump was restored as required by 0445 hours0.00515 days <br />0.124 hours <br />7.357804e-4 weeks <br />1.693225e-4 months <br /> on April 23, 1981. The incident was reviewed with the peraonnel directly involved.
A memorandum was written te all operations personnel to reinforce the necessity for proper procedural verifications.
In addition, as secondary cor'rective action, two procedural modifications were prepared to further emphasize the requirement of having both makeup pumps operable as specified in the Technical Specifications.
These procedural hi-lites will further assist in preventing recurrence in the future.
Failure Data: One similar occurrence was reported in Licensee Event Report NP-32-78-13 (78-123).
LER #81-025 i
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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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