LER-1981-064, /04T-0:on 810824,following Environ Radiological Sampling,Anomalous Results in Gammarus & Periphyton Samples Exceeded Ets.Investigation of Liquid Effluents Released Underway.Findings Will Be Included in 1981 Rept |
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POWER AllTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACHMENT TO LER 81 - 064/04T-0 Page 1
of 2
The following Environmental Radlological Monitoring samples are-anamalous measurements based on criteria outlined in the James A. FitzPatrick Nuclear Power Plant Technical Specifications, Appendix B, Paragraph 5.6.2.b:
PERIPHYTON SAMPLES pCi/g (wet)
ISOTOPE
'ONTROL *(Off-Site)
NMPP *(On-Site)
SAMPLE SAMPLE RECOUNT (7/ 8/81)
(7/ 6/81)
Ce-141 0.61 1 0.15 0.75 1 0.15 0.80 1 0.19 Zr-95 0.54 1 0.05 0.88 1 0.09 0.84 1 0.086 Nd-95 1.6 1 0.16 1.8 1 0.18 2.2 1 0.22 Cs-134
< 0.043 0.54 1 0.05 0.51 1 0.051 Mn-54
< 0.033 0.16 1 0.03 0.16 1 0.034 co-60
< 0.037 0.19 1 0.02 0.19 1 0.019 Cs-137 0.14 1 0.03 4.0 1 0.4 4.1 1 0.41
- SEE TECHNICAL SPECIFICATIONS, APPENDIX B, FOR SAMPLE LOCATIONS.
The activity level of Cs-134 and Cs-137 in the NMPP sample was greater than ten times the control station value for the same sample period. As noted above, the on-site (NMPP) sample was recounted to verify the measured levels of Cs-134 and Cs-137 Also detected in the NMPP sample were lesser amounts of Ce-141, Zr-95, Nd-95, Mn-54, and Cs-60.
The Ce-141, Zr-95 and Nd-95 are the result of global fallout from recent atmospheric nuclear tests conducted by the People's Republic of China. Each of these fallout nuclides was also detected in the control station sample. The detected concentrations of Cs-134 and Cs-137 are related to recent liquid effluents discharged from the Nine Mile Point Site. An investigation of liquid effluents released from the site is underway and the findings of the study will be reported in the 1981 Radiological Environmental Surveillance Report.
There is no expected dose to man as a result of the radioactivity detected in the periphyton samples as periphyton is not directly in the human food chain. A more direct calculatior, of dose to man can be made based on possible levels of Cs-134 and Cs-137 found in fish samples collected if such activity is present.
Such calculations will be included in the 1981 Radiological Environmental Survel11ance Report, as fish sampling is not yet completed for the 1981 sampling season.
A second series of Periphyton Samples was collected during the week of 8/ 9/81.
POWER AUTH0hlTY OF THE STATE OF NEW YOT.K JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 ATTACHMENT TO LER 81-064/04T-0 Page 2 of 2 The second Environmental sample media, with radiological analytical results containing anomalous measurements, wss Gammarus:
GAMMARUS SAh/LES pCi/g (wet)
SAMPLE LOCATION
- 1) Control Oswego Harbor 7/ 9/81
< 0.14
< 0.11
< 0.16
- 2) On-site 7/ 9/81 1.4 1 0.3 0.22 1 0.1 0.40 1 0.3 RECOUNT 1.5 1 0.3 0.14 1 0.1 0.59 1 0.2
- 3) On-site JAF 7/ 9/81 8.0 1 0.8 1.3 1 0.3 2.4 1 0.5 RECOUNT 9.2 1 0.9 1.1 1 0.3 2.8 1 0.5
- SEE TECHNICAL SPECIFICATIONS, APPENDIX B, FOR SAMPLE LOCATIONS.
The activity level os Cs-137 in the NMPP on-site Gammarus sample and the activity level of Cs-137, Cs-134 and Co-60 in the JAF on-site Gammarus sample were greater than ten times the control station value for the same sample period.
As noted above the on-site samples were recounted to verify the measured levels of Cs-137, Cs-134 and Co-60.
The detected levels of Cs-137, Cs-134 and co-60 are related to recent liquid effluents discharged from the Nine Mile Point Site. An investigation of liquid effluent discharges from the site is underway and the findings of the study will be reported in the 1981 Radiological Environmental Surveillance Report.
There is no expected dose to man as a re sult of radioactivity dete.ted in the Gammarus samples, as Gammarus is not directly in the human food chain. A more di rect dose to man can be made based on possible levels of Cs-137, Cs-134 and Co-60 found in fish samples collected if such activity is present.
Such calculations will be included in the 1981 Radiological Environmental Surveillance Report, as fish sampling is not yet completed for the 1981 sampling season.
A second series of Gammarus samples was collected during the week of 8/16/81.
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| 05000333/LER-1981-001-01, /01T-0:on 810121,problems Re IE Bulletin 80-25 Found in safety-relief Valve Solenoids.Probably Caused by Solenoid Valve Vendor Inadequacy.Eleven Solenoid Pairs Disassembled,Inspected & Cleaned | /01T-0:on 810121,problems Re IE Bulletin 80-25 Found in safety-relief Valve Solenoids.Probably Caused by Solenoid Valve Vendor Inadequacy.Eleven Solenoid Pairs Disassembled,Inspected & Cleaned | | | 05000333/LER-1981-001, Forwards LER 81-001/01T-0 | Forwards LER 81-001/01T-0 | | | 05000333/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000333/LER-1981-002-03, /03L-0:on 810106,condensate Storage Tank Level Switches 23-LS-74B & 75B Did Not Operate as Required.Caused by Incorrect Setpoint Due to Moisture.Switches Cleaned, Lubricated & Recalibr | /03L-0:on 810106,condensate Storage Tank Level Switches 23-LS-74B & 75B Did Not Operate as Required.Caused by Incorrect Setpoint Due to Moisture.Switches Cleaned, Lubricated & Recalibr | | | 05000333/LER-1981-003, Forwards LER 81-003/03L-0 | Forwards LER 81-003/03L-0 | | | 05000333/LER-1981-003-03, /03L-0:on 810106,containment Isolation Valve 16-1-AOV-102A Would Not Close.Caused by Natural End of Life. Valve Will Be Replaced | /03L-0:on 810106,containment Isolation Valve 16-1-AOV-102A Would Not Close.Caused by Natural End of Life. Valve Will Be Replaced | | | 05000333/LER-1981-004, Forwards LER 81-004/03L-0 | Forwards LER 81-004/03L-0 | | | 05000333/LER-1981-004-03, /03L-0:on 810110,emergency Diesel Generator D Exhibited Load Swings (Hunting) & Tripped on High Circulating Current.Caused by Defective Regulator Droop Switch.Switch Replaced in Both Emergency Power Sys | /03L-0:on 810110,emergency Diesel Generator D Exhibited Load Swings (Hunting) & Tripped on High Circulating Current.Caused by Defective Regulator Droop Switch.Switch Replaced in Both Emergency Power Sys | | | 05000333/LER-1981-005, Forwards LER 81-005/04L-0 | Forwards LER 81-005/04L-0 | | | 05000333/LER-1981-005-04, /04L-0:on 810112,annual Test of Offgas Automatic Isolation Not Performed as Required by Ets.Caused by Missed Surveillance Due to Conflict Between ETS & Operating Tech Specs.Surveillance Test Revised to Reflect ETS Requiremen | /04L-0:on 810112,annual Test of Offgas Automatic Isolation Not Performed as Required by Ets.Caused by Missed Surveillance Due to Conflict Between ETS & Operating Tech Specs.Surveillance Test Revised to Reflect ETS Requirement | | | 05000333/LER-1981-006-03, /03L-0:on 810112,during Normal Operation,Rod Block Monitor B Failed to Null When Control Rod Selected.Caused by Relay Failure Due to End of Natural Life.Relay Board Replaced & Monitor Returned to Svc | /03L-0:on 810112,during Normal Operation,Rod Block Monitor B Failed to Null When Control Rod Selected.Caused by Relay Failure Due to End of Natural Life.Relay Board Replaced & Monitor Returned to Svc | | | 05000333/LER-1981-006, Forwards LER 81-006/03L-0 | Forwards LER 81-006/03L-0 | | | 05000333/LER-1981-007-03, /03L-0:on 810113,during Normal Operation,Core Spray Pipe Break D/P Switches 14-DPIS-43A&B Found Set at 1.08 & 0.77.Caused by Instrument Drift.Switches Recalibr & Returned to Svc | /03L-0:on 810113,during Normal Operation,Core Spray Pipe Break D/P Switches 14-DPIS-43A&B Found Set at 1.08 & 0.77.Caused by Instrument Drift.Switches Recalibr & Returned to Svc | | | 05000333/LER-1981-007, Forwards LER 81-007/03L-0 | Forwards LER 81-007/03L-0 | | | 05000333/LER-1981-008-03, /03L-0:on 810114,during Normal Operation,Resident Inspector Noted That Daily Reactor Coolant Leakage Rate Not Calculated on 810113 Contrary to Tech Specs.Caused by Personnel Error.Leak Rate Calculated for 39-h Period | /03L-0:on 810114,during Normal Operation,Resident Inspector Noted That Daily Reactor Coolant Leakage Rate Not Calculated on 810113 Contrary to Tech Specs.Caused by Personnel Error.Leak Rate Calculated for 39-h Period | | | 05000333/LER-1981-008, Forwards LER 81-008/03L-0 | Forwards LER 81-008/03L-0 | | | 05000333/LER-1981-009, Forwards LER 81-009/03L-0 | Forwards LER 81-009/03L-0 | | | 05000333/LER-1981-009-03, /03L-0:on 810115,during Normal Operation, Administrative Review Noted Fire Hose Gasket Insp & Rerack Not Completed as Required by Tech Specs.Caused by Personnel Error.Improper Data Sheets Not Used After May 1980 | /03L-0:on 810115,during Normal Operation, Administrative Review Noted Fire Hose Gasket Insp & Rerack Not Completed as Required by Tech Specs.Caused by Personnel Error.Improper Data Sheets Not Used After May 1980 | | | 05000333/LER-1981-010-03, /03X-1:on 810117,HPCI Sys Did Not Automatically Operate at Rated Speed Upon Receipt of Auto Start Signal Following Reactor Scram & Isolation.Caused by Reactor Water Level Shrink.Speed & Discharge Pressure Increased | /03X-1:on 810117,HPCI Sys Did Not Automatically Operate at Rated Speed Upon Receipt of Auto Start Signal Following Reactor Scram & Isolation.Caused by Reactor Water Level Shrink.Speed & Discharge Pressure Increased | | | 05000333/LER-1981-010, Forwards LER 81-010/03X-1 | Forwards LER 81-010/03X-1 | | | 05000333/LER-1981-011, Forwards LER 81-011/03X-1 | Forwards LER 81-011/03X-1 | | | 05000333/LER-1981-012, Forwards LER 81-012/04L-0 | Forwards LER 81-012/04L-0 | | | 05000333/LER-1981-012-04, /04L-0:on 810120,found Offgas Vent Pipe (Stack) Sample Pumps Had Been Off Since Loss of Instrumentation Power Resulting in Plant Hot Shutdown Condition.Caused by Design Deficiency.Sample Pumps Started | /04L-0:on 810120,found Offgas Vent Pipe (Stack) Sample Pumps Had Been Off Since Loss of Instrumentation Power Resulting in Plant Hot Shutdown Condition.Caused by Design Deficiency.Sample Pumps Started | | | 05000333/LER-1981-013, Forwards LER 81-013/03L-0 | Forwards LER 81-013/03L-0 | | | 05000333/LER-1981-013-03, /03L-0:on 810124,HPCI Sys Flow Square Root Computation Module Found Out of Calibr.Possibly Caused by Instrument Drift.Instrument Recalibr & Returned to Svc | /03L-0:on 810124,HPCI Sys Flow Square Root Computation Module Found Out of Calibr.Possibly Caused by Instrument Drift.Instrument Recalibr & Returned to Svc | | | 05000333/LER-1981-014, Forwards LER 81-014/03L-0 | Forwards LER 81-014/03L-0 | | | 05000333/LER-1981-014-03, /03L-0:on 810129,instrument Functional Surveillance Test of LPCI Cross Connect Valve Alarm Not Performed Per Tech Specs.Caused by Lack of Surveillance Test Procedure Due to Personnel Error.Test F-ST-2T Written | /03L-0:on 810129,instrument Functional Surveillance Test of LPCI Cross Connect Valve Alarm Not Performed Per Tech Specs.Caused by Lack of Surveillance Test Procedure Due to Personnel Error.Test F-ST-2T Written | | | 05000333/LER-1981-015-03, /03L-0:on 810129,primary Containment Isolation Valve 10-MOV-39B Motor Contactor Tripped Due to Water Entering Motor Control Ctr from Electrical Conduit Outside Bldg.Caused by Const Deficiency.Motor Contactor Dried Out | /03L-0:on 810129,primary Containment Isolation Valve 10-MOV-39B Motor Contactor Tripped Due to Water Entering Motor Control Ctr from Electrical Conduit Outside Bldg.Caused by Const Deficiency.Motor Contactor Dried Out | | | 05000333/LER-1981-015, Forwards LER 81-015/03L-0 | Forwards LER 81-015/03L-0 | | | 05000333/LER-1981-016, Forwards LER 81-016/03L-0 | Forwards LER 81-016/03L-0 | | | 05000333/LER-1981-016-03, /03L-0:on 810203,reactor Core Isolation Cooling Made Inoperable to Repair Thermocouple Connection in Subsys. Caused by Thermocouple Failure Due to Normal Wear & Tear. Connection Repaired | /03L-0:on 810203,reactor Core Isolation Cooling Made Inoperable to Repair Thermocouple Connection in Subsys. Caused by Thermocouple Failure Due to Normal Wear & Tear. Connection Repaired | | | 05000333/LER-1981-017-03, /03L-0:on 810207,average Power Range Monitors a & E Downscale Trips Found Set at Less than 2.5/125,in Violation of Tech Spec 3.1-1.Possibly Caused by Instrument Drift.Downscale Trips Adjusted | /03L-0:on 810207,average Power Range Monitors a & E Downscale Trips Found Set at Less than 2.5/125,in Violation of Tech Spec 3.1-1.Possibly Caused by Instrument Drift.Downscale Trips Adjusted | | | 05000333/LER-1981-017, Forwards LER 81-017/03L-0 | Forwards LER 81-017/03L-0 | | | 05000333/LER-1981-018-03, /03L-0:on 810209,steam Line High Flow Switches 02-DPIS-116A & 116B Were Found Outside Tech Spec.Probably Caused by Instrument Drift.Switches Calibr | /03L-0:on 810209,steam Line High Flow Switches 02-DPIS-116A & 116B Were Found Outside Tech Spec.Probably Caused by Instrument Drift.Switches Calibr | | | 05000333/LER-1981-018, Forwards LER 81-018/03L-0 | Forwards LER 81-018/03L-0 | | | 05000333/LER-1981-019, Forwards LER 81-019/03L-0 | Forwards LER 81-019/03L-0 | | | 05000333/LER-1981-019-03, /03L-0:on 810210,during Normal Operation,Reactor Water Conductivity Exceeded Tech Spec 3.6.C.4 Limits.Caused by Addition of Caustic to Condensate Storage Tanks Due to Personnel Error.Two Condensate Storage Tanks Cleaned | /03L-0:on 810210,during Normal Operation,Reactor Water Conductivity Exceeded Tech Spec 3.6.C.4 Limits.Caused by Addition of Caustic to Condensate Storage Tanks Due to Personnel Error.Two Condensate Storage Tanks Cleaned | | | 05000333/LER-1981-020-03, /03L-0:on 810213,during Normal Operation,Hpci Controller Indicated Possible Controller Failure.Sys Declared Inoperable.Caused by Failure of Two Transistors in Amplifier.Controller Replaced & Returned to Svc | /03L-0:on 810213,during Normal Operation,Hpci Controller Indicated Possible Controller Failure.Sys Declared Inoperable.Caused by Failure of Two Transistors in Amplifier.Controller Replaced & Returned to Svc | | | 05000333/LER-1981-020, Forwards LER 81-020/03L-0 | Forwards LER 81-020/03L-0 | | | 05000333/LER-1981-021-03, /03L-0:on 810219,core Spray Pipe Break Switch 14-DPIS-43A Found Set Above Tech Spec Limit.Caused by Instrument Drift.Surveillance Increased to Daily,Guide Valve Changed to More Conservative Set Point & Training Conducted | /03L-0:on 810219,core Spray Pipe Break Switch 14-DPIS-43A Found Set Above Tech Spec Limit.Caused by Instrument Drift.Surveillance Increased to Daily,Guide Valve Changed to More Conservative Set Point & Training Conducted | | | 05000333/LER-1981-021, Forwards LER 81-021/03L-0 | Forwards LER 81-021/03L-0 | | | 05000333/LER-1981-022, Forwards LER 81-022/03L-0 | Forwards LER 81-022/03L-0 | | | 05000333/LER-1981-022-03, /03L-0:on 810220,review Revealed Torus Water Level Recorders Had Not Been Included in Calibr Program Per 800123 Tech Specs Change.Caused by Personnel Error.Recorders Checked & Calibr Will Be Performed Once Each Six Months | /03L-0:on 810220,review Revealed Torus Water Level Recorders Had Not Been Included in Calibr Program Per 800123 Tech Specs Change.Caused by Personnel Error.Recorders Checked & Calibr Will Be Performed Once Each Six Months | | | 05000333/LER-1981-023, Forwards LER 81-023/03L-0 | Forwards LER 81-023/03L-0 | | | 05000333/LER-1981-023-03, /03L-0:on 810225,reactor Water Level Instrument 02-3-LIS-101C Found Set Below Allowable Limits & on 810302 Instrument Found Above Allowable Limits.Cause for Both Failures Believed to Be Broken Switch Lock.Lock Repaired | /03L-0:on 810225,reactor Water Level Instrument 02-3-LIS-101C Found Set Below Allowable Limits & on 810302 Instrument Found Above Allowable Limits.Cause for Both Failures Believed to Be Broken Switch Lock.Lock Repaired | | | 05000333/LER-1981-024-03, /03L-0:on 810323,drywell Equipment Drain Sump Pump B Lost Suction & Could Not Effect Sump Pump Out.Cause Unknown.Amend to Tech Spec Submitted | /03L-0:on 810323,drywell Equipment Drain Sump Pump B Lost Suction & Could Not Effect Sump Pump Out.Cause Unknown.Amend to Tech Spec Submitted | | | 05000333/LER-1981-024, Forwards LER 81-024/03L-0 | Forwards LER 81-024/03L-0 | | | 05000333/LER-1981-025-03, /03L-0:on 810323,while Conducting Surveillance During Normal Operation,Reactor Water Level Switch Found Set Contrary to Tech Specs.Caused Attributed to Instrument Drift.Switch Adjusted & Weekly Surveillance Performed | /03L-0:on 810323,while Conducting Surveillance During Normal Operation,Reactor Water Level Switch Found Set Contrary to Tech Specs.Caused Attributed to Instrument Drift.Switch Adjusted & Weekly Surveillance Performed | | | 05000333/LER-1981-025, Forwards LER 81-025/03L-0 | Forwards LER 81-025/03L-0 | | | 05000333/LER-1981-026, Forwards LER 81-026/03L-0 | Forwards LER 81-026/03L-0 | |
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