LER-1980-064, /04T-0:on 800804,environ Radiological Monitoring Surveillance Revealed Periphyton Activity Greater than 10 Times Control Sample.Review of Sample Results Indicates No Significant Environ Impact |
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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT 4
DOCKET NO.50-333 ATTACHMENT TO LER 80-064/04T-0 Page 1, of 2
The following Environmental Radiological Monitoring sa:ple is an acamalous measurement based on criteria outlined in the James A. Fit:-
Patrick Nuclear Power Plant Technical Specifications, Append.'.x B, Para-graph 5.6.2.b:
Periphyton Samples pCi/gm (Wet)
Sample Location
- Sample Date Co-60 Activity 1.
Control Oswego Harbor 6/12/80
<0.0047 Recount (7/31/80) 6/12/80
<0.0047 2.
On-Site 6/12/80 0.0077 j; 0.0031 NMPP 3.
On-Site 6/12/80 0.047 1 0.0057 JAF Recount (7/26/80) 6/12/80 0.049 i 0.0053 Recount (7/31/80 6/12/80 0.052 1 0.0068 See Technical Specifications, Appendix 3, Figure 4.1.1-1 for location details.
The activity level of Co-60 in the JAF on-site sample is greater than 10 ti=es the control station value for the same sa=ple period based on sample re-analysis.
l The JAF samples were collected off shore from the power plant in l
approximately one to three feet of water. The sample location was 1,000 feet from the discharge structure and was located outside the near field dilution area (5 dilutions).
The total liquid release of Co-60 for the period of January 1, 1980 to June 12, 1980 was 0.20 C1.
An integrated release of this quantity of Co-60 should not produce a significant environmental impact. The release l
of Co-60 during this period was well within the discharge limits required by the plant's Technical Specifications, Appendix 3.
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POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DCCKET NO. 50-333 ATTACHMENT TO LER CO- 064/04!-0 Page 2
of 2
A dose calculation fro: activity fround in JAF periphyton sa=ple is di#ficult as these crganis=s are not in the human food chain.
For the purpose of illustration a dose calculation can be =ade using unrealistic assu=ptions.
If an adult were to censu=e 64 kg/yr of periphyton (an a=ount equal to the =axi=u: annual adult censu=ption of green leafy vegetables) the dose frc= the Co-60 concentration of 0.052 pC1/g (wet) would be equal to 0.30 =re: to the whole body and 2.57 =re to the GI tract (critical organ). The significance of thesa greatly over-esti=ated dosas to =an are very low with respect to natural background radiation.
Because periphyton sa=ples are near the base of some aquatic food chains, a review of the analytical results for other aquatic sa=ples taken in the vicinity of the site during this sa=e period was =ade.
Mollusk sa=ples collected on June 12, 1980 shewed no detectable Co-60 activity.
In addition, no detectable levels of Cc-60 were found in fish sa=ples collected during May 1980, which would indicate that the activity found in the JAF periphyten sa ple is not being transferred and re-concentrated in the upper levels of the aquatic food chain.
An exa=ination and analysis of si=ilar sa=ple data (Dece=ber 1974 to present) shows a decreasing trend of sa ple activity in the periphyton sa=ples taken in the vacinity of Nine Mile Point. A second collection of periphyton sa:ples is scheduled for August 4, 1980.
SOTE: LER 78-068,73-072, 78-077,78-037 and 79-114 are related events.
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| 05000333/LER-1980-001-03, /03L-0:on 800101,during Surveillance Testing, Average Power Range Monitor E Downscale Trip Found at 2.0/125 Compared to Tech Spec Limit of Equal to or Greater than 2.5/125.Caused by Instrument Drift.Instrument Calibr | /03L-0:on 800101,during Surveillance Testing, Average Power Range Monitor E Downscale Trip Found at 2.0/125 Compared to Tech Spec Limit of Equal to or Greater than 2.5/125.Caused by Instrument Drift.Instrument Calibr | | | 05000333/LER-1980-001, Forwards LER 80-001/03L-0 | Forwards LER 80-001/03L-0 | | | 05000333/LER-1980-002, Forwards LER 80-002/04L-0 | Forwards LER 80-002/04L-0 | | | 05000333/LER-1980-002-04, /04L-0:on 800102,failure of Makeup Water Sys Neutralizer Tank Discharge Valve Allowed Release of Approx 50,000 Gallons Regeneration Waste Water W/Ph Outside Tech Spec Limit.Caused by Solenoid Valve Sticking.Valve Cleaned | /04L-0:on 800102,failure of Makeup Water Sys Neutralizer Tank Discharge Valve Allowed Release of Approx 50,000 Gallons Regeneration Waste Water W/Ph Outside Tech Spec Limit.Caused by Solenoid Valve Sticking.Valve Cleaned | | | 05000333/LER-1980-003-03, /03L-0:on 800106,during Surveillance Testing of torus-to-drywell Vacuum Breakers,Torus Water Level Decreased Approx 1 Inch Below Tech Spec Limit.Caused by Testing of Breakers,Allowing Torus Water to Fill Downcomer Pipes | /03L-0:on 800106,during Surveillance Testing of torus-to-drywell Vacuum Breakers,Torus Water Level Decreased Approx 1 Inch Below Tech Spec Limit.Caused by Testing of Breakers,Allowing Torus Water to Fill Downcomer Pipes | | | 05000333/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000333/LER-1980-004, Forwards LER 80-004/03L-0 | Forwards LER 80-004/03L-0 | | | 05000333/LER-1980-004-03, /03L-0:on 800107,during Surveillance Testing,One of Four Core Spray Injection Permissive Switches Found to Be Set Approx 10 Psi Below Tech Spec Limit.Caused by Instrument Drift.Switch Recalibr | /03L-0:on 800107,during Surveillance Testing,One of Four Core Spray Injection Permissive Switches Found to Be Set Approx 10 Psi Below Tech Spec Limit.Caused by Instrument Drift.Switch Recalibr | | | 05000333/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000333/LER-1980-005-03, /03L-0:on 800107,during Review of Reactor Water Chemistry Data,Noted That Some Required Samples Were Not Obtained.Technicians Did Not Take Samples Due to Low Level Conductivity & Chloride Ion Concentrations | /03L-0:on 800107,during Review of Reactor Water Chemistry Data,Noted That Some Required Samples Were Not Obtained.Technicians Did Not Take Samples Due to Low Level Conductivity & Chloride Ion Concentrations | | | 05000333/LER-1980-006-03, Core Spray Injection Valve 14-MOV-12A Improperly Operated During 791221 Surveillance Test.Caused by Misoperation of Valve Circuit Breaker Overload Trip Device | Core Spray Injection Valve 14-MOV-12A Improperly Operated During 791221 Surveillance Test.Caused by Misoperation of Valve Circuit Breaker Overload Trip Device | | | 05000333/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000333/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000333/LER-1980-007-03, /03L-0:on 800109,during Normal Operation,B Loop of RHR Declared Inoperable While Hanger H10-28 Was Inoperable for IE Bulletin 79-02 Testing.Caused by Failure of Concrete Anchors Under Pull Test.Repairs Made | /03L-0:on 800109,during Normal Operation,B Loop of RHR Declared Inoperable While Hanger H10-28 Was Inoperable for IE Bulletin 79-02 Testing.Caused by Failure of Concrete Anchors Under Pull Test.Repairs Made | | | 05000333/LER-1980-008-03, /03L-0:on 800109,while Performing Surveillance, Core Spray Valve 14-MOV-12B Failed to Open as Required. Caused by Torque Switch Not Being Bypassed for Sufficient Time Period.Adjusted Torque & Limit Switches | /03L-0:on 800109,while Performing Surveillance, Core Spray Valve 14-MOV-12B Failed to Open as Required. Caused by Torque Switch Not Being Bypassed for Sufficient Time Period.Adjusted Torque & Limit Switches | | | 05000333/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000333/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000333/LER-1980-009-03, /03L-0:on 800110,during Normal Operation,Diesel Fire Pump Made Inoperable to Correct Minor Boil Over of Engine Following Shutdown.Boil Over Caused by Defective Coolant Sys Cap.Cap Replaced | /03L-0:on 800110,during Normal Operation,Diesel Fire Pump Made Inoperable to Correct Minor Boil Over of Engine Following Shutdown.Boil Over Caused by Defective Coolant Sys Cap.Cap Replaced | | | 05000333/LER-1980-010, Forwards LER 80-010/03L-0 | Forwards LER 80-010/03L-0 | | | 05000333/LER-1980-010-03, /03L-0:on 800110,recirculation Loop Temp Instruments Found Out of Calibr.Caused by Use of Wrong Type of Test Signal in Previous Calibr.Problem Corrected by Recalibr | /03L-0:on 800110,recirculation Loop Temp Instruments Found Out of Calibr.Caused by Use of Wrong Type of Test Signal in Previous Calibr.Problem Corrected by Recalibr | | | 05000333/LER-1980-011-03, /03L-0:on 800110,during Surveillance Testing, Hydraulic Snubber Found Inoperable.Caused by Snubber Accumulator Cocked & O-ring Leakage.Overhaul & post-repair Testing Restored Snubber to Operable Status as Spare | /03L-0:on 800110,during Surveillance Testing, Hydraulic Snubber Found Inoperable.Caused by Snubber Accumulator Cocked & O-ring Leakage.Overhaul & post-repair Testing Restored Snubber to Operable Status as Spare | | | 05000333/LER-1980-011, Forwards LER 80-011/03L-0 | Forwards LER 80-011/03L-0 | | | 05000333/LER-1980-012, Forwards LER 80-012/03L-0 | Forwards LER 80-012/03L-0 | | | 05000333/LER-1980-012-03, /03L-0:on 800111,during Surveillance Testing, Emergency Diesel Generator a Tripped on Low Lube Oil Pressure.Caused by Partial Failure of Engine Immersion Heater Resulting in Cold Lube Oil.Heater Replaced | /03L-0:on 800111,during Surveillance Testing, Emergency Diesel Generator a Tripped on Low Lube Oil Pressure.Caused by Partial Failure of Engine Immersion Heater Resulting in Cold Lube Oil.Heater Replaced | | | 05000333/LER-1980-013, Forwards LER 80-013/03L-0 | Forwards LER 80-013/03L-0 | | | 05000333/LER-1980-013-03, /03L-0:800114,during Surveillance Testing,Reactor lo-lo-lo Level Switch a Operated Improperly.Caused by Improper Closing of Level Switch Contact at Switch Set Point.Switch Replaced | /03L-0:800114,during Surveillance Testing,Reactor lo-lo-lo Level Switch a Operated Improperly.Caused by Improper Closing of Level Switch Contact at Switch Set Point.Switch Replaced | | | 05000333/LER-1980-014, Forwards LER 80-014/03L-0 | Forwards LER 80-014/03L-0 | | | 05000333/LER-1980-014-03, /03L-0:on 800116,during Normal Operation,Torus Water Level Limits Exceeded Tech Specs for 20 Minutes. Caused by Testing of HPCI Sys,Adding Water to Torus Via Min Flow Valve.Torus Pumped Down to Tech Spec Limit | /03L-0:on 800116,during Normal Operation,Torus Water Level Limits Exceeded Tech Specs for 20 Minutes. Caused by Testing of HPCI Sys,Adding Water to Torus Via Min Flow Valve.Torus Pumped Down to Tech Spec Limit | | | 05000333/LER-1980-015, Forwards LER 80-015/03L-0 | Forwards LER 80-015/03L-0 | | | 05000333/LER-1980-015-03, /03L-0:on 800123,during Normal Operation,Lpci Independent Power Supply a Inverter Tripped for No Apparent Reason.Caused by Failed Capacitors in Inverter Control Circuit.Capacitors Replaced | /03L-0:on 800123,during Normal Operation,Lpci Independent Power Supply a Inverter Tripped for No Apparent Reason.Caused by Failed Capacitors in Inverter Control Circuit.Capacitors Replaced | | | 05000333/LER-1980-016-03, /03L-0:on 800125,during Normal Operation, Containment Isolation Valve 20-MOV-82 Was Inoperable.Caused by Ground Fault.Replaced Burned Up Motor Limit Switch Assembly,Torque Switch Assembly & Modified Termination Box | /03L-0:on 800125,during Normal Operation, Containment Isolation Valve 20-MOV-82 Was Inoperable.Caused by Ground Fault.Replaced Burned Up Motor Limit Switch Assembly,Torque Switch Assembly & Modified Termination Box | | | 05000333/LER-1980-016, Forwards LER 80-016/03L-0 | Forwards LER 80-016/03L-0 | | | 05000333/LER-1980-017, Forwards LER 80-017/03L-0 | Forwards LER 80-017/03L-0 | | | 05000333/LER-1980-017-03, /03L-0:on 800130,drywell-to-torus Differential Pressure Did Not Meet 1.7 Psi Requirements of Tech Specs for Approx 1-h.Caused by Rapid Temp Decrease in Drywell Cooling Sys.Nitrogen Added,Restoring Pressure to Normal | /03L-0:on 800130,drywell-to-torus Differential Pressure Did Not Meet 1.7 Psi Requirements of Tech Specs for Approx 1-h.Caused by Rapid Temp Decrease in Drywell Cooling Sys.Nitrogen Added,Restoring Pressure to Normal | | | 05000333/LER-1980-018-03, /03L-0:on 800201,during Normal Operation,Core Spray Sys Pipe Break Detector Was Outside of Tech Spec Limits for Nine Days.Caused by Change in Tech Specs.Detector Recalibr to New Tech Spec Value | /03L-0:on 800201,during Normal Operation,Core Spray Sys Pipe Break Detector Was Outside of Tech Spec Limits for Nine Days.Caused by Change in Tech Specs.Detector Recalibr to New Tech Spec Value | | | 05000333/LER-1980-018, Forwards LER 80-018/03L-0 | Forwards LER 80-018/03L-0 | | | 05000333/LER-1980-019-03, /03L-0:on 800205,during Normal Operation,Rod Sequence Control Sys Failed to Come Into Svc at Expected Power Level.Caused by Calibr Procedure Error.Procedure Corrected,Instrument Recalibr & Returned to Svc | /03L-0:on 800205,during Normal Operation,Rod Sequence Control Sys Failed to Come Into Svc at Expected Power Level.Caused by Calibr Procedure Error.Procedure Corrected,Instrument Recalibr & Returned to Svc | | | 05000333/LER-1980-019, Forwards LER 80-019/03L-0 | Forwards LER 80-019/03L-0 | | | 05000333/LER-1980-020, Advises That Date on Transmittal Ltr for LER 80-020/04L-0 Should Be 800305,instead of 800205 | Advises That Date on Transmittal Ltr for LER 80-020/04L-0 Should Be 800305,instead of 800205 | | | 05000333/LER-1980-020-04, /04L-0:on 800205,during Routine Shutdown & Cooldown Operations,Plant Stack Gas Monitoring Sys Was Inoperable Due to Freeze Up of Sample Line.Caused by Cold Weather & Purge of Humid Containment Atmosphere | /04L-0:on 800205,during Routine Shutdown & Cooldown Operations,Plant Stack Gas Monitoring Sys Was Inoperable Due to Freeze Up of Sample Line.Caused by Cold Weather & Purge of Humid Containment Atmosphere | | | 05000333/LER-1980-021, Forwards LER 80-021/03L-0 | Forwards LER 80-021/03L-0 | | | 05000333/LER-1980-021-03, /03L-0:on 800207,during Normal Shutdown Operations Intermediate Range Monitor B Was Made Inoperable to Repair Signal Cable Connector.Reactor Protections Sys B Placed in Tripped Condition.Caused by Normal Wear | /03L-0:on 800207,during Normal Shutdown Operations Intermediate Range Monitor B Was Made Inoperable to Repair Signal Cable Connector.Reactor Protections Sys B Placed in Tripped Condition.Caused by Normal Wear | | | 05000333/LER-1980-022, Forwards LER 80-022/03L-0 | Forwards LER 80-022/03L-0 | | | 05000333/LER-1980-022-03, /03L-0:on 800208,during Normal Startup Operations, Drywell Atmosphere Monitor a Was Made Inoperable While B Was Out of Svc Resulting in Operation in Degraded Mode.Caused by Need to Investigate Noise from Sample Pump | /03L-0:on 800208,during Normal Startup Operations, Drywell Atmosphere Monitor a Was Made Inoperable While B Was Out of Svc Resulting in Operation in Degraded Mode.Caused by Need to Investigate Noise from Sample Pump | | | 05000333/LER-1980-023-03, /03L-0:on 800211,during Normal Startup Operations, Water Chemistry Samples Indicated Chloride Ion Concentration in Excess of Tech Specs.Probably Caused by Sample Contamination.Second Water Cleanup Filter Placed in Svc | /03L-0:on 800211,during Normal Startup Operations, Water Chemistry Samples Indicated Chloride Ion Concentration in Excess of Tech Specs.Probably Caused by Sample Contamination.Second Water Cleanup Filter Placed in Svc | | | 05000333/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000333/LER-1980-024, Forwards LER 80-024/03L-0 | Forwards LER 80-024/03L-0 | | | 05000333/LER-1980-024-03, /03L-0:on 800213,during Normal Operation,Hpci Steam Isolation Valve Closed Due to Spurious Operation Signal.Caused by Loose Wire within Thermocouple Switch Associated W/High Area Temp Isolation Logic.Wire Fastened | /03L-0:on 800213,during Normal Operation,Hpci Steam Isolation Valve Closed Due to Spurious Operation Signal.Caused by Loose Wire within Thermocouple Switch Associated W/High Area Temp Isolation Logic.Wire Fastened | | | 05000333/LER-1980-025, Forwards LER 80-025/03L-0 | Forwards LER 80-025/03L-0 | | | 05000333/LER-1980-025-03, /03L-0:on 800228,during Normal Operation While Conducting Surveillance Tests,Average Power Reactor Monitor B Remained Inoperable When Function Switch Was Returned to Operation Position.Caused by Normal Hysteresis Effect | /03L-0:on 800228,during Normal Operation While Conducting Surveillance Tests,Average Power Reactor Monitor B Remained Inoperable When Function Switch Was Returned to Operation Position.Caused by Normal Hysteresis Effect | |
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