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1906 at 0304, a Ful1 Heactor Trio occurred aue to s we e t cr error.
The oiant was in Doorational Condition 5, with t ht-not' a ew t t c h in Ehuccown and all rodn inserted in the core.
1 I
A furctional t en* of the Ave *apo power Range Monitor (APRM) Logic wan t.v i r ; perfortod by Nuc16ar Annistant Station Doerators (NAGO) m i r.a Cte. tion Deocorb re 24.604.01 to catinfy Technical i
Env.iflcation re 7 u i rerne n t 1.
Th is functional teot requires the ope rn t o.- to incert 1/P 'leactor Trip nignals into the RPS Lonic at varions t i'nn u n o m.
to fully tent the circuitry.
The test alno esta u t rw that the ADAM channels which serve the "A"
Reactor Drot e c t ior=
by t.t err (PPG) Lootc train t n..
tested prior to tentina tho29 w. i ch urve the "D"
Lncic train.
1/2 trio Gignalc I
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'O' Locle train are uubseouently recet within
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t>o g a re to innert +hn first 15%
t, t e na l into the "B"
nPRM in the
'b" Logst t ra i n, a Full Aatto-Tri o ot: curred.
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Loaic trip siunal and estn u t the "D"
Lo it when t h r* ueennd onorator dialed dowi. che 15% trio uinnal ontheGDW.
Dcth ocer:rcor. involved
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i that the 1/i2 t-in i, the "n"
t-ain wan recot at two socarate locations.
T $. a s i rcur,s n t r: ncy orompted the Watch Enoineer to wthorin tne individuo3c to a t t orno t to recreato the event no as
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to we if an euuip ent r r n b is"rn was the caune.
Th i s wan a t t ornot t'd
- twice, wtt* to o lotte nerf orot rm ac deoioned both t i ronn.
Upon further inv W iet': on of the ment, it wan de t nerni ned f rora thn En?CUence D V e n t *,
b e i n t o o l, that t h t?
Sporator had ncit i
wacteufully rowt ths "H"
ap5 1/2 trio nignal an he bonan the "D"
- 6Dah, T h ta r p wat no emfet/ c. i ri r a f i r.inc e to tbe event.
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Upro challonged or PVQ u i r et s f ", * -
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Operalcon ci,rriffd out all rugettypd c Jr'r P C t I VT1 ACh1Cn5.
O l a r.t MaPla n ernt, n t was r Qt i find of thO Ovent afd t bo NHC w. rac. i r. ed at 0%D one 10CF'HLO. 72.
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- .-- m...m To brevent recurrence, the following corrective actions have or will be taken:
1)
The noerators responsible for causing this event will be recuired to review the procedure and deterrnine if it can be rnod i fied at all to prevent a future occurencu.
In addition, they will be required to update the procedure
- wording, to accurately rufluct the a l a rnt typor's printout for each cornputer phroue called out during the curveillance.
2)
The Cornout er Section will be requested to evaluatu the pc.uu i b i l it y of having the secuence cornouter list the alarrns on the CRT an well ao on the typer. This will allow the perforraance of the surveillance without an operator i
dedicated to the typor.
3)
A copy of the Final Incident Report will be placed on reauired readina for all Operations pornonnel.
4)
The I nst r utnan t and Controln Section has been dirneted to invustigate whether this RpS actuation could have buen caunod by an equiprount rna l f unct i on.
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| 05000322/LER-1986-001, :on 860116,discovered That Primary Containment Air Sampling Procedure Did Not Adequately Meet Requirement of Tech Specs.Procedure Sp 74.020.04 Will Be Revised to Meet Surveillance Requirements |
- on 860116,discovered That Primary Containment Air Sampling Procedure Did Not Adequately Meet Requirement of Tech Specs.Procedure Sp 74.020.04 Will Be Revised to Meet Surveillance Requirements
| | | 05000322/LER-1986-002, :on 860124,hourly Fire Watch Patrol Late by 13 Minutes for LPCI MG Set Room 11.Caused by Malfunctioning Door Preventing Access to Room.Door Repaired |
- on 860124,hourly Fire Watch Patrol Late by 13 Minutes for LPCI MG Set Room 11.Caused by Malfunctioning Door Preventing Access to Room.Door Repaired
| | | 05000322/LER-1986-004, :on 860225,discovered That Three Individuals Not Properly Logged Into Primary Containment Area Personnel Hatch.Caused by Security Guard Error.Security Supervisors Will Conduct Random Checks to Ensure Logging |
- on 860225,discovered That Three Individuals Not Properly Logged Into Primary Containment Area Personnel Hatch.Caused by Security Guard Error.Security Supervisors Will Conduct Random Checks to Ensure Logging
| | | 05000322/LER-1986-005, :on 860208,control Room Air Conditioning Sys/ Reactor Bldg Standby Ventilation Sys B Side Initiation & Partial Nuclear Steam Supply Shutoff Sys Isolation Occurred. Caused by Procedural Deficiency |
- on 860208,control Room Air Conditioning Sys/ Reactor Bldg Standby Ventilation Sys B Side Initiation & Partial Nuclear Steam Supply Shutoff Sys Isolation Occurred. Caused by Procedural Deficiency
| | | 05000322/LER-1986-007, :on 860212,split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Into Accident Configuration Occurred Due to lo-lo RBCLCW Head Tank a Level.Caused by Inadequate Station Procedure for Filling Hxs.Procedure Being Revised |
- on 860212,split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Into Accident Configuration Occurred Due to lo-lo RBCLCW Head Tank a Level.Caused by Inadequate Station Procedure for Filling Hxs.Procedure Being Revised
| | | 05000322/LER-1986-008, :on 860214,during Surveillance Procedure,Split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Sys Occurred.Caused by Technician Accidentally Bumping RBCLCW Head Tank B lo-lo Level Switch.Procedure Revised |
- on 860214,during Surveillance Procedure,Split of Reactor Bldg Closed Loop Cooling Water (RBCLCW) Sys Occurred.Caused by Technician Accidentally Bumping RBCLCW Head Tank B lo-lo Level Switch.Procedure Revised
| | | 05000322/LER-1986-009, :on 860217,during APRM Functional Test,Full Reactor Trip Occurred.Caused by Technician Failure to Reset Reactor Protection Sys Trip Signal a Before Initiating Test of Logic Train B.Procedures Being Reviewed |
- on 860217,during APRM Functional Test,Full Reactor Trip Occurred.Caused by Technician Failure to Reset Reactor Protection Sys Trip Signal a Before Initiating Test of Logic Train B.Procedures Being Reviewed
| | | 05000322/LER-1986-011, :on 860318,results of Annual Sounding of Intake Canal Initiated Limiting Condition for Operation Rept.Public Hearings Were Held & Util Granted Last of Three Permits to Dredge on 881220 |
- on 860318,results of Annual Sounding of Intake Canal Initiated Limiting Condition for Operation Rept.Public Hearings Were Held & Util Granted Last of Three Permits to Dredge on 881220
| | | 05000322/LER-1986-011-02, Forwards LER 86-011-02,Station Procedure 84.122.01 & Intake Canal Soundings. W/One Oversize Drawing | Forwards LER 86-011-02,Station Procedure 84.122.01 & Intake Canal Soundings. W/One Oversize Drawing | | | 05000322/LER-1986-012, :on 860303,loss of Continuous Monitoring of Station Ventilation Exhaust Occurred Resulting from Panel 1D11-PNL-041 Sample Pump Being Shut Off for Maint.Caused by Personnel Miscommunication |
- on 860303,loss of Continuous Monitoring of Station Ventilation Exhaust Occurred Resulting from Panel 1D11-PNL-041 Sample Pump Being Shut Off for Maint.Caused by Personnel Miscommunication
| | | 05000322/LER-1986-013, :on 860305,fire Watch in Relay Room Found Asleep.Caused by Personnel Error.Individual Terminated |
- on 860305,fire Watch in Relay Room Found Asleep.Caused by Personnel Error.Individual Terminated
| | | 05000322/LER-1986-015, :on 860310,in Shutdown Mode,Continuous Fire Watch Patrol Required by Tech Spec 3.7.8 Not Kept.Caused by Watch Being Stuck in Elevator for 25 Minutes.Elevator Repaired & Fire Watch Resumed |
- on 860310,in Shutdown Mode,Continuous Fire Watch Patrol Required by Tech Spec 3.7.8 Not Kept.Caused by Watch Being Stuck in Elevator for 25 Minutes.Elevator Repaired & Fire Watch Resumed
| | | 05000322/LER-1986-016, :on 860304,seismic Monitoring Instrumentation Rendered Inoperable.Caused by Removal of Scratch Plates to Avoid Damage During Implementation of Portion of tie-in for Colt Diesel Engines |
- on 860304,seismic Monitoring Instrumentation Rendered Inoperable.Caused by Removal of Scratch Plates to Avoid Damage During Implementation of Portion of tie-in for Colt Diesel Engines
| | | 05000322/LER-1986-018, :on 860410,nonradioactive Water Discharged from Condensate Storage Tank Sump W/O Prior Analysis.Caused by Personnel Error.Water & Ground Samples Acceptable. Training Procedures Revised |
- on 860410,nonradioactive Water Discharged from Condensate Storage Tank Sump W/O Prior Analysis.Caused by Personnel Error.Water & Ground Samples Acceptable. Training Procedures Revised
| | | 05000322/LER-1986-019, :on 860509,unplanned Automatic Initiation of Reactor Bldg Standby Ventilation/Control Room Air Conditioning Sys Occurred.Caused by Low Reactor Bldg Differential Pressure.Procedure Sp 24.203.04 Revised |
- on 860509,unplanned Automatic Initiation of Reactor Bldg Standby Ventilation/Control Room Air Conditioning Sys Occurred.Caused by Low Reactor Bldg Differential Pressure.Procedure Sp 24.203.04 Revised
| | | 05000322/LER-1986-020, :on 860510,full Reactor Trip Occurred Due to Personnel Error During Performance of Operations Surveillance Test on Emergency Diesel Generator 101.Maint Work Request Generated to Inspect Detector |
- on 860510,full Reactor Trip Occurred Due to Personnel Error During Performance of Operations Surveillance Test on Emergency Diesel Generator 101.Maint Work Request Generated to Inspect Detector
| | | 05000322/LER-1986-021, :on 860512,reactor Trip Occurred Due to Perturbation in Ref Leg While Technicians Valving in Level Transmitter.Possibly Caused by Air Entrapment in Instrument Lines Downstream of Valves |
- on 860512,reactor Trip Occurred Due to Perturbation in Ref Leg While Technicians Valving in Level Transmitter.Possibly Caused by Air Entrapment in Instrument Lines Downstream of Valves
| | | 05000322/LER-1986-022, :on 860515,discovered That Particulate Sample Filters from Station Ventilation Exhaust Monitor Discarded Prior to Being Analyzed for Gross Alpha Activity.Procedure Revised to Include Sign Off Steps |
- on 860515,discovered That Particulate Sample Filters from Station Ventilation Exhaust Monitor Discarded Prior to Being Analyzed for Gross Alpha Activity.Procedure Revised to Include Sign Off Steps
| | | 05000322/LER-1986-023, :on 860520,Action Statement 120 of Tech Spec 3.3.7.11 Requiring Noble Gas Grab Samples Not Met.Caused by Poor Communication Between Technicians During Shift Change. Mgt Notified & Shift check-off List Revised |
- on 860520,Action Statement 120 of Tech Spec 3.3.7.11 Requiring Noble Gas Grab Samples Not Met.Caused by Poor Communication Between Technicians During Shift Change. Mgt Notified & Shift check-off List Revised
| | | 05000322/LER-1986-024, :on 860522,unplanned Automatic Reactor Bldg Closed Loop Cooling Water Side a Isolation Occurred.Caused by Technician Placing Wrench on Lower Isolation Valve Piping.Investigation in Progress |
- on 860522,unplanned Automatic Reactor Bldg Closed Loop Cooling Water Side a Isolation Occurred.Caused by Technician Placing Wrench on Lower Isolation Valve Piping.Investigation in Progress
| | | 05000322/LER-1986-025, :on 860611,two Noble Gas Grab Samples Discarded Prior to Being Analyzed.Caused by Personnel Error. Instructions Given to Technicians to Obtain Foreman Approval Prior to Disposal of Samples |
- on 860611,two Noble Gas Grab Samples Discarded Prior to Being Analyzed.Caused by Personnel Error. Instructions Given to Technicians to Obtain Foreman Approval Prior to Disposal of Samples
| | | 05000322/LER-1986-026, :on 860703,automatic Initiation of Reactor Bldg Standby Ventilation Sys a Side Occurred.Caused by Technician Dropping Screwdriver in Panel & Deenergizing Relay During Surveillance Test.Test Procedure Revised |
- on 860703,automatic Initiation of Reactor Bldg Standby Ventilation Sys a Side Occurred.Caused by Technician Dropping Screwdriver in Panel & Deenergizing Relay During Surveillance Test.Test Procedure Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000322/LER-1986-027, :on 850815,reactor Power Excursions Occurred Due to Failure of Mechanical Linkage Between Position Feedback Arm & Controller on Startup Level Control Valve. Retaining Screw Replaced W/Locking Washer |
- on 850815,reactor Power Excursions Occurred Due to Failure of Mechanical Linkage Between Position Feedback Arm & Controller on Startup Level Control Valve. Retaining Screw Replaced W/Locking Washer
| | | 05000322/LER-1986-028, :on 860710,environmentally Unqualified Jumper Wires Installed in Valve Operators Contrary to License Condition.Caused by Inability to Provide Documentation for Jumpers.Faulty Valve Operators Replaced |
- on 860710,environmentally Unqualified Jumper Wires Installed in Valve Operators Contrary to License Condition.Caused by Inability to Provide Documentation for Jumpers.Faulty Valve Operators Replaced
| | | 05000322/LER-1986-030, :on 860727 & 0811,ESF Automatic Actuations Occurred.Caused by Thunderstorms Producing Power Spikes. Engineering Requested to Evaluate Events to Determine If Common Mode Failure Exists |
- on 860727 & 0811,ESF Automatic Actuations Occurred.Caused by Thunderstorms Producing Power Spikes. Engineering Requested to Evaluate Events to Determine If Common Mode Failure Exists
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000322/LER-1986-031, :on 860716,seismic Monitoring Instrumentation (Triaxial response-spectrum Recorders) Became Inoperable. Caused by Removal of Scratch Plates to Avoid Activation Due to Vibration from Const Activities |
- on 860716,seismic Monitoring Instrumentation (Triaxial response-spectrum Recorders) Became Inoperable. Caused by Removal of Scratch Plates to Avoid Activation Due to Vibration from Const Activities
| | | 05000322/LER-1986-033, :on 860806,emergency Diesel Generator 101 Manually Shut Down During Surveillance Test Due to High Lube Oil & Jacket Water Temps.Caused by Insufficient Response of Jacket Water Temp Valve |
- on 860806,emergency Diesel Generator 101 Manually Shut Down During Surveillance Test Due to High Lube Oil & Jacket Water Temps.Caused by Insufficient Response of Jacket Water Temp Valve
| | | 05000322/LER-1986-034, :on 860811,containment Isolation Reactor Vessel wide-range Level Indicator Switch 1B21*LIS-155B Declared Inoperable.Possibly Caused by Error in Calibr of Transmitter 1B21*LT-155B.Unit Shut Down |
- on 860811,containment Isolation Reactor Vessel wide-range Level Indicator Switch 1B21*LIS-155B Declared Inoperable.Possibly Caused by Error in Calibr of Transmitter 1B21*LT-155B.Unit Shut Down
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(1) | | 05000322/LER-1986-035, :on 860828,unplanned Actuation of RWCU Sys Occurred During Monthly Surveillance Test.Caused by Relanding Lead Prior to Resetting Isolation Logic.Isolation Logic Reset & Sys Returned to Svc |
- on 860828,unplanned Actuation of RWCU Sys Occurred During Monthly Surveillance Test.Caused by Relanding Lead Prior to Resetting Isolation Logic.Isolation Logic Reset & Sys Returned to Svc
| | | 05000322/LER-1986-036, :on 860926,heat Trace Control Switch for Drywell Gas Particulate Radiation Monitor Discovered in Off Position,Rendering Monitor Skid Inoperable.Caused by Procedural Deficiency.Procedures Revised |
- on 860926,heat Trace Control Switch for Drywell Gas Particulate Radiation Monitor Discovered in Off Position,Rendering Monitor Skid Inoperable.Caused by Procedural Deficiency.Procedures Revised
| 10 CFR 50.73(a)(2)(i) | | 05000322/LER-1986-037, :on 860908,fire Watch Missed in Relay Room. Caused by Inadvertent CO2 Injection Into Normal Switchgear Room Forcing Evacuation of Control Bldg.Fire Watch Reestablished |
- on 860908,fire Watch Missed in Relay Room. Caused by Inadvertent CO2 Injection Into Normal Switchgear Room Forcing Evacuation of Control Bldg.Fire Watch Reestablished
| 10 CFR 50.73(a)(2)(i) | | 05000322/LER-1986-039, :on 861006,unplanned Initiation of Reactor Bldg Standby Ventilation Sys Occurred W/All Rods Inserted in Core.Caused by Faulty Design of Retaining Device.Warning Signs Attached to Valve Actuator & Valve Mod Initiated |
- on 861006,unplanned Initiation of Reactor Bldg Standby Ventilation Sys Occurred W/All Rods Inserted in Core.Caused by Faulty Design of Retaining Device.Warning Signs Attached to Valve Actuator & Valve Mod Initiated
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000322/LER-1986-040, :on 861007,nuclear Steam Supply Shutoff Sys (Nssss) Isolated & Reactor Bldg Standby Ventiliation Sys & Control Room Air Conditioning Initiated.Caused by Defective Relay Socket in Nssss Logic.Socket Replaced |
- on 861007,nuclear Steam Supply Shutoff Sys (Nssss) Isolated & Reactor Bldg Standby Ventiliation Sys & Control Room Air Conditioning Initiated.Caused by Defective Relay Socket in Nssss Logic.Socket Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000322/LER-1986-042, :on 861009,SPDES Permit Renewal Application Discovered Not Submitted on 860602 Per Section 3.2. of App B to License NPF-36.Caused by Procedural Inadequacy. Application Submitted to NRC on 861010 |
- on 861009,SPDES Permit Renewal Application Discovered Not Submitted on 860602 Per Section 3.2. of App B to License NPF-36.Caused by Procedural Inadequacy. Application Submitted to NRC on 861010
| | | 05000322/LER-1986-044, :on 861011,reactor Bldg Standby Ventilation Sys & Control Room Air Conditioning Side B Initiation Occurred. Caused by Accidently Grounded Circuit Simulating Nuclear Steam Supply Shutoff Sys Isolation Signal |
- on 861011,reactor Bldg Standby Ventilation Sys & Control Room Air Conditioning Side B Initiation Occurred. Caused by Accidently Grounded Circuit Simulating Nuclear Steam Supply Shutoff Sys Isolation Signal
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000322/LER-1986-045, :on 861127,reactor Bldg Standby Ventilation Sys/Control Room Air Conditioning Sys Inadvertently Actuated During Change in Monitor Bulb.Caused by Personnel Error.Personnel Counseled |
- on 861127,reactor Bldg Standby Ventilation Sys/Control Room Air Conditioning Sys Inadvertently Actuated During Change in Monitor Bulb.Caused by Personnel Error.Personnel Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation |
|