LER-1977-091, /03L-0:on 771107,containment Radiation Monitor RIS 2006 Spiked & Reset Twice Causing Safety Features Actuation Sys Incident Level 1 Trips.Caused by Design Error |
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U. S. NUCLEAR Ht.GULA f un v GL. men.v.e NRC FCM 366 17 77I
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'ia L3 EVENT DATE 74 75 RE* ORT CATE 80 8
EVENT DEScalPTION AND PROBABLE CO.*ASECUENCES h On November. 7,.1977, Containment Radiation Monitor RIS 2006 spiked and was reset on I 1012 l l 70,3, ; - twoociasrions causing SFAS Incident Level l Trips at 0336 and 0615 hours0.00712 days <br />0.171 hours <br />0.00102 weeks <br />2.340075e-4 months <br />. This-l-
go,,p.l..placaA the _ station in;ths Action _S_tatement.of Technical. Specification (TS) 3.4.6.1 l
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DAVIS-EESSEUNITONENUCLEARPCWERSTATION
\\ j SUPPLEMENTAL INFORMATION FOR LER NP-33-77-91 DATE OF EVENT:
November 7, 197_7_ _.
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FACILITY: Davis-Besse Unit 1 IDENTIFICATTON OF OCCURRENCE:- - Saf ety Features Actuation System (SFAS) -Level 1 Trip due to High Radiation Irtp from Containment Radiation Monitor RIS 2006c Conditions 3.s.ior to Occurr.nce:, The plant was in Mode.1, with Power. (5'I) = 700
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and Load (MWE) < 240
- - Description of Occurrence:
OrcNovember. 7,1977 at 0336 houts,.s Radiation }ionitor
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RIS "2006 sptked-giving 2 S. iS -15cident-Level-1 Trip. - STAS Channel 4 Contain=ent-Ju %
Radiatiott-war-declared ino_:rald e.and-manually tripped., prey,iouslypt 0130- hours (see. --u.
- - NP 77-89); to give ::he o pat-of fcur-trip. - This.placedythe _ station -in the.
.s ActhStatement of Technic it Specification (TS) 3.4.&L-on _ Reactor..C.colant System Leakage Detection.
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At -0445-hotrrs, r he load was drgppeds tosl3-SeMWE...- RIS.2006 -fpil_ owed:. power reduc- :
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- - At 06I5"If6ursf MIS 2006 sp.kedsancerippedeSFAS Channel-3-Containment Radiation.-.- _,..
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~sgairr whi~ch pre SFAS Level 1 Trip-and-placed the station irr the Action S::atement 6f TS~ -3.h6.I?" STAS-Channel 3 Containment Radiatiotr-.was resetat._0&lS hours when __.
RIS 2006-staitVd'eo read nor: nits ~nich-removedu:he station, f. rom. Act; ion Statement.
Plant' operation was reduced ':o: Mo.de 2. a.t 1245 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.737225e-4 months <br /> _ foe work _ on RIS 2007 and
- --RIS' 200 6 ; -SFAS' Chatinel -3 Cc sesinment-Radiation-was =anually-tripped which placed --.. :_.
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- - the' station i*-the Action Statement. of:TS 3.3.2.1-at 1200. hours on November 8,.
-- 1977"a'feerWFAS'-Channel 4-ContainmentaRadiation was-declared.. operable. _..
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Ues-is nation--of -Accarent Cause of-Occurrence: The apparent. cause was due-to-
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sdesign/fabricatior. error, specifically imprqger electrifil iioTalion' between detector (instrument) ground and..c.ouduit.( tation), ground _.
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" L ' - Analvsis-$f 4ceifrrence: Thenaivas.< no danger-:to-rhe health and safety.- of-. the publig_.; :
c or to station personnel. SFAS 4.evel -L-Incident-Tr.ip occurted as. the systen,isc.de e.
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-- = signed etr. -' There-was always three+SFAS -Containme_nt Radiatioq,Jfonicors.cperab,lan throughout the occurrence.
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DAVIS-BESSE UNIT ONE NUCLEAR POWER STATION dSUPPLEMENTAL INFORMATION FOR LER NP-33-77-91 PAGE 2 Cor~recTfve Action: Corrective action con:menced on November 8,1977 at 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />.
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The problem was determined to be a grounding problem between the detectnr_ (instru-mene) and. station ground. Tho detector was then electrically isolated by removal of tih'e rocating bracket #903416 from within the detector containment housing-assem-
-- bly-(Victoreen Print #905194). This was done in conjunction with and approval from the vendor, Victoreen.
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- - SFAS Channel 4 containment Rad 4ation was placed back in service on November 8, _
1977 at 1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />, which removed the station from the Action Statement of TS 3.3.2.1.
This modification will be performed on all four SFAS Radiation Detectors per Facility Change Request 77-~462..
4 11ura? Data: One previous incident occur 1_ed,qn October 24.g l9.77 when a fault occurred between the Radiation Module in the Control Room.and the cabinet it was
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| 05000289/LER-1977-016-01, /01T-0:on 770924,RCS Temp & Pressure Rose.Caused by Half Trip Condition from Steam & Feedwater Rupture Control Sys.Possible Cause of Half Trip Attributed to Loose Connection at Terminal Boards | /01T-0:on 770924,RCS Temp & Pressure Rose.Caused by Half Trip Condition from Steam & Feedwater Rupture Control Sys.Possible Cause of Half Trip Attributed to Loose Connection at Terminal Boards | | | 05000289/LER-1977-016, Forwards Supplemental Info to LER 77-016/01T-0 Re Half Trip in Steam Feedwater Rupture Control Sys | Forwards Supplemental Info to LER 77-016/01T-0 Re Half Trip in Steam Feedwater Rupture Control Sys | | | 05000320/LER-1977-016, /01T-0 on 770924:half Trip of Steam & Feedwater Rupture Control Sys Resulted in Opening of Pressurizer Power Relief Valve.Possibly Caused by Loose Connections at Terminal Boards | /01T-0 on 770924:half Trip of Steam & Feedwater Rupture Control Sys Resulted in Opening of Pressurizer Power Relief Valve.Possibly Caused by Loose Connections at Terminal Boards | | | 05000346/LER-1977-017, Forwards LER 77-017/01T-0 | Forwards LER 77-017/01T-0 | | | 05000346/LER-1977-017-01, /01T-0:on 771020,both Auxiliary Feed Pump Suctions Lined Up to Deaerator Storage Tanks W/O Cooling Water Supply Shifting to Svc Water,Resulting in Water Greater than 200 F as Cooling Water for Auxiliary Feed Pump Bearings | /01T-0:on 771020,both Auxiliary Feed Pump Suctions Lined Up to Deaerator Storage Tanks W/O Cooling Water Supply Shifting to Svc Water,Resulting in Water Greater than 200 F as Cooling Water for Auxiliary Feed Pump Bearings | | | 05000346/LER-1977-018, Forwards LER 77-018/01T-0 | Forwards LER 77-018/01T-0 | | | 05000346/LER-1977-018-01, /01T-0:on 771108,station Review Board Found Auxiliary Feed Pump Turbine Governor Valve Vibrational Closure Design Deficiency.Caused by Lack of Force to Hold Valve Open.Requests Design Mod for Pump Turbines | /01T-0:on 771108,station Review Board Found Auxiliary Feed Pump Turbine Governor Valve Vibrational Closure Design Deficiency.Caused by Lack of Force to Hold Valve Open.Requests Design Mod for Pump Turbines | | | 05000346/LER-1977-019-01, /01T-0:on 771117,auxiliary Feedwater Valves AF 599 & AF 608 Found Closed,Rendering Steam & Feedwater Rupture Control Sys Pressure Switch Inputs Inoperable.Caused by Procedural Deficiency.Tests Revised | /01T-0:on 771117,auxiliary Feedwater Valves AF 599 & AF 608 Found Closed,Rendering Steam & Feedwater Rupture Control Sys Pressure Switch Inputs Inoperable.Caused by Procedural Deficiency.Tests Revised | | | 05000346/LER-1977-019, Forwards LER 77-019/01T-0 | Forwards LER 77-019/01T-0 | | | 05000346/LER-1977-077-03, /03L-0:on 771010,decay Heat Valve Pit Cover Removed to Inspect Decay Heat Isolation Valves DH11 & DH12 & to Perform Wiring Change on DH12.Insp Required for Leakage & Preventive Maint | /03L-0:on 771010,decay Heat Valve Pit Cover Removed to Inspect Decay Heat Isolation Valves DH11 & DH12 & to Perform Wiring Change on DH12.Insp Required for Leakage & Preventive Maint | | | 05000346/LER-1977-077, Forwards LER 77-077/03L-0 | Forwards LER 77-077/03L-0 | | | 05000346/LER-1977-078-03, /03L-0:on 771011,during Functional Test,Reactor Protection Sys Channel 1 Accidentally de-energized.Caused by Error in Maint Work Order.Personnel Instructed | /03L-0:on 771011,during Functional Test,Reactor Protection Sys Channel 1 Accidentally de-energized.Caused by Error in Maint Work Order.Personnel Instructed | | | 05000346/LER-1977-078, Forwards LER 77-078/03L-0 | Forwards LER 77-078/03L-0 | | | 05000346/LER-1977-079-03, /03L-0:on 771011,source Range Defector NI-1 Indication Failed Low Twice,Then Returned to Normal Operation by Itself.Cause Unknown | /03L-0:on 771011,source Range Defector NI-1 Indication Failed Low Twice,Then Returned to Normal Operation by Itself.Cause Unknown | | | 05000346/LER-1977-079, Forwards LER 77-079/03L-0 | Forwards LER 77-079/03L-0 | | | 05000346/LER-1977-080, Forwards LER 77-080/03L-0 | Forwards LER 77-080/03L-0 | | | 05000346/LER-1977-080-03, /03L-0:on 771016,governor Valve on Auxiliary Feed Pump 1-2 Found Closed During Auxiliary Feedwater Sys Monthly Test Performance.Caused by Possible Design Deficiency. Excessive Vibration Under Investigation by Maint Personnel | /03L-0:on 771016,governor Valve on Auxiliary Feed Pump 1-2 Found Closed During Auxiliary Feedwater Sys Monthly Test Performance.Caused by Possible Design Deficiency. Excessive Vibration Under Investigation by Maint Personnel | | | 05000346/LER-1977-081, Forwards LER 77-081/03L-0 | Forwards LER 77-081/03L-0 | | | 05000346/LER-1977-081-03, /03L-0:on 771018,during Miscellaneous Instrument Shift Checks,Containment to Annulus Differential Pressure Exceeded Water Gauge Tech Spec Limit.Caused by Procedure & Personnel Error.Startup Procedure Modified | /03L-0:on 771018,during Miscellaneous Instrument Shift Checks,Containment to Annulus Differential Pressure Exceeded Water Gauge Tech Spec Limit.Caused by Procedure & Personnel Error.Startup Procedure Modified | | | 05000346/LER-1977-082-03, /03L-0:on 771019,discharge & Recirculation Dampers of Emergency Ventilation Sys 2 Failed to Open When Fan Started.Caused by Loose & Dirty Controller Contacts.Module Removed & Reinserted, & Contacts Cleaned | /03L-0:on 771019,discharge & Recirculation Dampers of Emergency Ventilation Sys 2 Failed to Open When Fan Started.Caused by Loose & Dirty Controller Contacts.Module Removed & Reinserted, & Contacts Cleaned | | | 05000346/LER-1977-082, Forwards LER 77-082/03L-0 | Forwards LER 77-082/03L-0 | | | 05000346/LER-1977-083, Forwards LER 77-083/03L-0 | Forwards LER 77-083/03L-0 | | | 05000346/LER-1977-083-03, /03L-0:on 771025,stop Valve AF3872 Failed to Stroke When Given Open Signal.Caused by Component Failure. Torque Switch Replaced on 771027 | /03L-0:on 771025,stop Valve AF3872 Failed to Stroke When Given Open Signal.Caused by Component Failure. Torque Switch Replaced on 771027 | | | 05000346/LER-1977-084, Forwards LER 77-084/03L-0 | Forwards LER 77-084/03L-0 | | | 05000346/LER-1977-084-03, /03L-0:on 771025,surveillance Test ST 5080.01 Not Performed.Caused by Personnel Error.Test Performed Immediately & Computer Program Revised | /03L-0:on 771025,surveillance Test ST 5080.01 Not Performed.Caused by Personnel Error.Test Performed Immediately & Computer Program Revised | | | 05000346/LER-1977-086-03, /03L-0:on 771028,safety Features Actuation Sys Channel 4 Radiation Monitor RIS 2007 Failed to Respond to Internal Check Source.Caused by Component Failure.Low Amplifier Board Replaced & Monitor Recalibr | /03L-0:on 771028,safety Features Actuation Sys Channel 4 Radiation Monitor RIS 2007 Failed to Respond to Internal Check Source.Caused by Component Failure.Low Amplifier Board Replaced & Monitor Recalibr | | | 05000346/LER-1977-086, Forwards LER 77-086/03L-0 | Forwards LER 77-086/03L-0 | | | 05000346/LER-1977-087, Forwards LER 77-087/03L-0 | Forwards LER 77-087/03L-0 | | | 05000346/LER-1977-087-03, /03L-0:on 771024,safety Features Actuation Sys Channel 3 Containment Radiation Reaqdings Unreliable . Caused by Design/Fabrication Error.Facility Change Request 77-437 Issued for Permanent Repair | /03L-0:on 771024,safety Features Actuation Sys Channel 3 Containment Radiation Reaqdings Unreliable . Caused by Design/Fabrication Error.Facility Change Request 77-437 Issued for Permanent Repair | | | 05000346/LER-1977-088, Forwards LER 77-088/03L-0 | Forwards LER 77-088/03L-0 | | | 05000346/LER-1977-088-03, /03L-0:on 771027,source Range Detector NI-1 Indication Failed Low.Cause Unknown.Updated Rept Forthcoming | /03L-0:on 771027,source Range Detector NI-1 Indication Failed Low.Cause Unknown.Updated Rept Forthcoming | | | 05000346/LER-1977-089-03, /03L-1:on 771107,radiation Monitor RIS 2007 Was Showing Erratic Readings.Caused by Victoreen Low Range Amplifier Board 847-1-20 Failure.Board Replaced | /03L-1:on 771107,radiation Monitor RIS 2007 Was Showing Erratic Readings.Caused by Victoreen Low Range Amplifier Board 847-1-20 Failure.Board Replaced | | | 05000346/LER-1977-089, Forwards LER 77-089/03L-1.W/o Encl | Forwards LER 77-089/03L-1.W/o Encl | | | 05000346/LER-1977-090-03, /03L-0:on 771107,during Review of Deficiency in Steam & Feedwater Rupture Control Sys Monthly Test,Reactor Coolant Pump Found Inoperable.Caused by Component Failure. Voltage Regulating Diode Replaced | /03L-0:on 771107,during Review of Deficiency in Steam & Feedwater Rupture Control Sys Monthly Test,Reactor Coolant Pump Found Inoperable.Caused by Component Failure. Voltage Regulating Diode Replaced | | | 05000346/LER-1977-090, Forwards LER 77-090/03L-0 | Forwards LER 77-090/03L-0 | | | 05000346/LER-1977-091-03, /03L-0:on 771107,containment Radiation Monitor RIS 2006 Spiked & Reset Twice Causing Safety Features Actuation Sys Incident Level 1 Trips.Caused by Design Error | /03L-0:on 771107,containment Radiation Monitor RIS 2006 Spiked & Reset Twice Causing Safety Features Actuation Sys Incident Level 1 Trips.Caused by Design Error | | | 05000346/LER-1977-091, Forwards LER 77-091/03L-0 | Forwards LER 77-091/03L-0 | | | 05000346/LER-1977-092, Forwards LER 77-092/03L-0 | Forwards LER 77-092/03L-0 | | | 05000346/LER-1977-092-03, /03L-0:on 771101,facility Review Board Meeting Revealed That Surveillance Requirement of Venting Hpis Valve HP 72 Not Performed.Caused by Personnel Error.High Point Valve Vented & Modified | /03L-0:on 771101,facility Review Board Meeting Revealed That Surveillance Requirement of Venting Hpis Valve HP 72 Not Performed.Caused by Personnel Error.High Point Valve Vented & Modified | | | 05000346/LER-1977-093, Forwards LER 77-093/03L-0 | Forwards LER 77-093/03L-0 | | | 05000346/LER-1977-093-03, /03L-0:on 771114,reactor Protection Sys Daily Heat Balance Check Not Completed When Station Above 15% Rated Thermal Power During Oct-Nov 1977.Caused by Personnel Error. Surveillance Test Placed on Daily Testing Schedule | /03L-0:on 771114,reactor Protection Sys Daily Heat Balance Check Not Completed When Station Above 15% Rated Thermal Power During Oct-Nov 1977.Caused by Personnel Error. Surveillance Test Placed on Daily Testing Schedule | | | 05000346/LER-1977-094-03, /03L-0:on 771116,emergency Ventilation Sys Dampers Pdv 5014A & B Failed to Modulate Correctly to Draw Down Annulus.Caused by Defective Pressure Differential Controller.Dampers Replaced & Sys Retested | /03L-0:on 771116,emergency Ventilation Sys Dampers Pdv 5014A & B Failed to Modulate Correctly to Draw Down Annulus.Caused by Defective Pressure Differential Controller.Dampers Replaced & Sys Retested | | | 05000346/LER-1977-094, Forwards LER 77-094/03L-0 | Forwards LER 77-094/03L-0 | | | 05000346/LER-1977-095-03, /03L-0:on 771127,control Room Ventilation Isolation Damper HV 5311A Failed to Close on Radiation Monitor Trip.Caused by Component Failure.Damper Dismantled & Sealing Surfaces Cleaned & Lubricated | /03L-0:on 771127,control Room Ventilation Isolation Damper HV 5311A Failed to Close on Radiation Monitor Trip.Caused by Component Failure.Damper Dismantled & Sealing Surfaces Cleaned & Lubricated | | | 05000346/LER-1977-095, Forwards LER 77-095/03L-0 | Forwards LER 77-095/03L-0 | | | 05000346/LER-1977-097, Forwards LER 77-097/03L-0 | Forwards LER 77-097/03L-0 | | | 05000346/LER-1977-097-03, /03L-0:on 771129,radiation Monitor Re 2006 Tripped Safety Features Actuation Sys Channel 3 Containment Radiation Due to Sporadic Spiking.Caused by Component Failure in Radiation Detector.Detector Replaced | /03L-0:on 771129,radiation Monitor Re 2006 Tripped Safety Features Actuation Sys Channel 3 Containment Radiation Due to Sporadic Spiking.Caused by Component Failure in Radiation Detector.Detector Replaced | | | 05000346/LER-1977-100-03, /03L-0:on 771201 & 05,source Range Neutron Detector NI-1 Indication Dropped to Zero & Returned to Normal Operation W/O Assistance.Cause Unknown.After First Failure,Detector Replaced & Retested | /03L-0:on 771201 & 05,source Range Neutron Detector NI-1 Indication Dropped to Zero & Returned to Normal Operation W/O Assistance.Cause Unknown.After First Failure,Detector Replaced & Retested | | | 05000346/LER-1977-100, Forwards LER 77-100/03L-0 | Forwards LER 77-100/03L-0 | | | 05000346/LER-1977-101-03, /03L-0:on 771201,diesel Generator 1-1 Inoperable Due to Failure to Perform Required Surveillance Testing on Diesel Generator 1-2 within Required Tech Spec Interval. Caused by Personnel Error | /03L-0:on 771201,diesel Generator 1-1 Inoperable Due to Failure to Perform Required Surveillance Testing on Diesel Generator 1-2 within Required Tech Spec Interval. Caused by Personnel Error | |
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