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the Radioencmictry Department d:ncovcred tnat the ce;:aary containmen: air samplina procedure cic not adeo uat ely raee t tne reaulrements set forth in the Technical Eccc ficationc.
The alant was in Doerational Condition 5
witn the
- ce witch in s h ut c' ow n during an outace and all contrc' roic a nnert ed in trm core.
Ermaling of orimary cont a i rmr.t air requirec by Technical Boecification sectionc
- 3. i 1. 3. I and 3.11. 2. Ei nust be analyred for ncble
- gases, carticulates end icdines.
However, the air carples were analyzed after tne air had nassec t*ough oartaculate ad charcoal filterc.
Tne sa'mling anc analysis was nerfor aed by raolochemistry aersonnel in accordance with an aoorovec ntation procedure, 53 74.020.04 (Containment Drywell Exhaust and Air Renoval PL :w Enaust Ar.alysis and Discharge Aut hori zat. ar,).
Thta procecure wi'I be rev;ced t o rm e t the surve:3 lance recuirementc of tne Technical 3aecifications crior to tne cer t ormar.ce of the BOXt te5t.
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0 l0 h op ne e m. ~ _ _ __ _ =a: s ama,nm On January 16.
1986 at 1500, the Radiochemistry Department discovered that the or1 mary containment air sampling procedure dic not adecuately meet the requirements set forth in the Technical Speci f icat ionn.
The plant was in Operational Condition i
5 with the mode switch in shutdown curing an outage and all control rods inserted in the core Primary cont ainment was ooen at the time to perform plant modifications.
Plant Manacement was notified of the event and tne NRC was notified at 1437 the next day.
Technical Specification 3,11.2.1 requires that the containment air ce namoled and analyzed on a monthly basis for particulates, iocines anc noble gases.
- However, in accordance with the sampling procedure, Sp74.020.04, the analysis was performcd by takinc an air samole downstream of the RMS skid (1D11*PNL-061)
I af t er cassing tnrouch a carticulate filter and a charcoal filter.
Tne samole is then placed in a Geli recorder for a
complete isotopic analycio.
Although the grab samples were
- ov in and analyzed in accordance with the Tech Specs (as indicated in table 4.11.2.1.7) ttey die not fully meet the recuirements au w e the iocinec anc pa r1 I'cu l at es hac been fiitered out p'ic to the analysis.
This procedure nad been used for p r e v i o i, monthly somoling per Tech.
Spec.
3.11.2.1 and for swpling cova prior to anc curing purging ano venting as required by Tech.
Spec.
3.11.2.8.
The noble gas analysis was done au required.
Upon cisccvery of the event, grab air namples were taken and analyzed for oart i cul at es anc iodines in accordance with an approved st, tion prncedure, Sp
- 62. 20.01 (Airborne Activity Survey Tecnnicures ene Deteroination).
There is no safety signi ficance to tnis event, because the drywell air is continuously monitored.
Any t ime containment was purgec or vented, the air was exnausted through tne Reactor Builcing Ventilation Exhaust System (RDNVE) and was also sampled by the normal station vent monitors.
These are Particulate, Iodine and Ganeous (PIG) mon i t orn.
No abnovval readince have occurred.
The samoling and analysis was performed by radchemintry personnel in accordance with an approved station arocedure.
Sampl;ng and analysis for noble gases will remain the same, by procedure, but the station proce ure will be revised to change the method of sampling and analysis for particulates and iodines.
The existing filters (charcoal and part icu l at e) in the sample ukid will be roolaced with " grab sample" filters.
After the sample air passes throuch the filters for a specified collection time, the filters are removed and analyzed for particulaten and
- iodines, ibis crocedure channe will be incorporated into t h:' procedura prior to 1
the performance of the next surveillance test as required b; the Technical Scecification.
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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 |
|