LER-1980-023, /03L-0:on 800517,radioactive Matl in Form of Bagged Contaminated Waste & Poly Wrapped Scrap Lumber Was Taken to Site Dump.Caused by Apparent Communication Problem Between Health Physics Personnel & Bldg Servicemen |
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avsNT QEScAIPitCN ANO *RC8 A3L1 CONSECusNCIS h g IAt 1645 on 18 May 1980 it was discovered that on 17 May 1980 radioactive materia 1l g,in the form of bagged' contaminated waste and poly wrapped scrap lumber was taken t,c g [the site dump.
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SUPPLEMENTARY INFORMATION R: port No.:
50-302/80-023/03L-0 Fecility:
Crystal River Unit #3 Roport Date:
6 June 1980-Occurrence Date:
17 May 1980 Idantification of Occurrence:
Removal of radioactive material from the established radiation contro area to the site dump.
Reportable udner 10 CFR 20.405.
' Conditions Prior to Occurrence:
Mode 6 refueling.
Description of Occurrence:
Radioactive material in the form of bagged contaminated waste and poly wrapped scrap lumber was inadvertently taken to the site dump.
Two off-duty Building Servicemen removed a portion of the scrap wood for personal use at home. After unloading the scrap lumber, the radioactive material t'ag was discovered.
The Chemistry and Radiation
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Protection Department was then notified of the condition.
Health Phy-sies personnel were deployed to the Building Serviceman'a home as wel as the site dump, for the purpose of radioactive material retrieval a;.
survey of the affected areas. All of the radioactive material was re-trieved intact. Of ten (10) yellow bags retrieved, only one indicate, readings greater than background, (4.0 mr/hr).
Of all the scrap lumber retrieved, only one board indicated smearable contamination.
(Approximately 800 dpm). Survey results of all affected areas were de-termined to be within acceptable limits.
Designation of apparent Cause:
The apparent cause of this event is attributed to communication prob-lems between Health Physics personnel and Building Servicemen which occurred while performing a sort of trash to be disposed.
Analysis of Occurrence:
All contaminated waste was recovered and returned to the plant site for proper disposal.
As a result, there was no affect upon the plant or general public.
Corrsctive Action:
Building Service and Health Physics personnel have been reinstruct ed and procedural changes to RP-101, RP217, and RP-220, which include a requirement for Health Physics surveys of all vehicles leaving tie protected area, have been implemented to prevent recurrence.
Failure Data:
This is the first occurrence of this type reported.
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| 05000302/LER-1980-001-01, /01T-0:on 800107,in Mode 1,determinted That Plant Was Taken Into Operational Mode While in Action Statement of Limiting Condition for Operation.Caused by Personnel Error.Revision to Tech Specs Has Been Submitted | /01T-0:on 800107,in Mode 1,determinted That Plant Was Taken Into Operational Mode While in Action Statement of Limiting Condition for Operation.Caused by Personnel Error.Revision to Tech Specs Has Been Submitted | | | 05000302/LER-1980-001, Forwards LER 80-001/01T-0 | Forwards LER 80-001/01T-0 | | | 05000302/LER-1980-002-03, /03L-0:on 800105,following Normal Reactor Shutdown,Chem/Rod Sampling Revealed Reactor Coolant Dose Equivalent I-131 Exceeded Tech Spec Limit.Caused by Leaking Fuel Pins & Anticipated Iodine Transient Following Shutdown | /03L-0:on 800105,following Normal Reactor Shutdown,Chem/Rod Sampling Revealed Reactor Coolant Dose Equivalent I-131 Exceeded Tech Spec Limit.Caused by Leaking Fuel Pins & Anticipated Iodine Transient Following Shutdown | | | 05000302/LER-1980-002, Forwards LER 80-002/03L-0 | Forwards LER 80-002/03L-0 | | | 05000302/LER-1980-003, Forwards LER 80-003/03L-0 | Forwards LER 80-003/03L-0 | | | 05000302/LER-1980-003-03, /03L-0:on 800104,following Pressurizer Degassification Operations,Pressurizer Steam Space Sample Isolation Valve CAV-1 Would Not Close.Cause Unknown.Threads on Valve Stem Assembly Found Stripped.Evaluation Scheduled | /03L-0:on 800104,following Pressurizer Degassification Operations,Pressurizer Steam Space Sample Isolation Valve CAV-1 Would Not Close.Cause Unknown.Threads on Valve Stem Assembly Found Stripped.Evaluation Scheduled | | | 05000302/LER-1980-004, Supplemental Info to LER 80-004/04L-0:during Jan 1980, Analyses of Seawater Samples Collected at Six Sample Stations Not Performed Correctly Due to Equipment Malfunctions.Samples Recollected & Analyzed | Supplemental Info to LER 80-004/04L-0:during Jan 1980, Analyses of Seawater Samples Collected at Six Sample Stations Not Performed Correctly Due to Equipment Malfunctions.Samples Recollected & Analyzed | | | 05000302/LER-1980-005-03, /03L-0:on 800116,during Surveillance Schedule Review,Discovered Incore Neutron Detector Sys Calibr Surveillance SP-140 Not Performed within Required Time Interval.Caused by Misinterpretation of Requirements | /03L-0:on 800116,during Surveillance Schedule Review,Discovered Incore Neutron Detector Sys Calibr Surveillance SP-140 Not Performed within Required Time Interval.Caused by Misinterpretation of Requirements | | | 05000302/LER-1980-005, Forwards LER 80-005/03L-0 | Forwards LER 80-005/03L-0 | | | 05000302/LER-1980-006-03, /03L-0:on 800123,during Routine Surveillance, Reactor Bldg Charcoal Filter Bank Efficiency Was Less than 99%.Caused by Natural End of Life for Filter.Filters Replaced | /03L-0:on 800123,during Routine Surveillance, Reactor Bldg Charcoal Filter Bank Efficiency Was Less than 99%.Caused by Natural End of Life for Filter.Filters Replaced | | | 05000302/LER-1980-006, Forwards LER 80-006/03L-0 | Forwards LER 80-006/03L-0 | | | 05000302/LER-1980-007, Forwards LER 80-007/03L-0 | Forwards LER 80-007/03L-0 | | | 05000302/LER-1980-007-03, /03L-0:on 800130,during Daily Plant Operating Surveillance SP-300,discovered Average Reactor Bldg Temp of 130.5F.Caused by Temp Transmitter CI-563-TT Being Stuck,Due to Operation Outside Design Temp Range | /03L-0:on 800130,during Daily Plant Operating Surveillance SP-300,discovered Average Reactor Bldg Temp of 130.5F.Caused by Temp Transmitter CI-563-TT Being Stuck,Due to Operation Outside Design Temp Range | | | 05000302/LER-1980-008, Forwards LER 80-008/03L-0 | Forwards LER 80-008/03L-0 | | | 05000302/LER-1980-008-03, /03L-0:on 800206,during ECCS Pump Operability Demonstration Surveillance SP-340,decay Heat Pump a Discharge Throttle Valve Would Not Control Flow Automatic Phase.Caused by Loose Wires on auto-manual Selector Switch | /03L-0:on 800206,during ECCS Pump Operability Demonstration Surveillance SP-340,decay Heat Pump a Discharge Throttle Valve Would Not Control Flow Automatic Phase.Caused by Loose Wires on auto-manual Selector Switch | | | 05000302/LER-1980-009, Forwards LER 80-009/03L-0 | Forwards LER 80-009/03L-0 | | | 05000302/LER-1980-009-03, /03L-0:on 800209,following Power Reduction & on 800211,during Startup Operations,Rcs Sampling Revealed Dose Equivalent I-131 Exceeded Tech Specs.Caused by Leaking Fuel Pins & Iodine Transient Following RCS Transient | /03L-0:on 800209,following Power Reduction & on 800211,during Startup Operations,Rcs Sampling Revealed Dose Equivalent I-131 Exceeded Tech Specs.Caused by Leaking Fuel Pins & Iodine Transient Following RCS Transient | | | 05000302/LER-1980-010-01, /01T-1:on 800226,during Routine Operation,Power Supply Failure Initiated Transient Condition,Resulting in Reactor Trip,Turbine Trip & Engineered Safeguards Actuation. 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Marshes.Possibly Caused by Natural or Seasonal Variations | /04L-0:on 800304,more than Two Std Deviations Were Discovered Between Preoperational Study & Operational Study in Metabolic Function of Discharge Salt Marshes.Possibly Caused by Natural or Seasonal Variations | | | 05000302/LER-1980-015, Forwards LER 80-015/03L-0 | Forwards LER 80-015/03L-0 | | | 05000302/LER-1980-015-03, /03L-0:on 800306,while Performing Engineered Safeguards Functional Test,Decay Heat Suction Isolation Valve Began to Close Inadvertently.No Apparent Cause for Event.Investigation Underway | /03L-0:on 800306,while Performing Engineered Safeguards Functional Test,Decay Heat Suction Isolation Valve Began to Close Inadvertently.No Apparent Cause for Event.Investigation Underway | | | 05000302/LER-1980-016-01, /01T-0:on 800401,inadvertent Actuation of Fire Svc Deluge Sys Resulted in Damage to Auxiliary Bldg Ventilation Exhaust Filter AHFL-2A.Caused by Personnel Error During Reset of Fire Svc Panel alarm.AHFL-2A 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Concentrations Were 0.24 Ppm & 0.274 Ppm.Caused by Chloride & Fluoride Contamination on Walls & Floors of Fuel Transfer Canal | /03L-0:on 800413,during Chemistry Surveillance, Discovered That RCS Chloride & Fluoride Concentrations Were 0.24 Ppm & 0.274 Ppm.Caused by Chloride & Fluoride Contamination on Walls & Floors of Fuel Transfer Canal | | | 05000302/LER-1980-018, Fowards LER 80-018/03L-0 | Fowards LER 80-018/03L-0 | | | 05000302/LER-1980-019-01, /01T-0:on 800517,crack Indication Discovered During Insp of Fuel Assembly NJ018E Upper End Fitting Holddown Spring.Investigation of Cause Underway.When Determined,Rept W/Corrective Actions Will Be Sent | /01T-0:on 800517,crack Indication Discovered During Insp of Fuel Assembly NJ018E Upper End Fitting Holddown Spring.Investigation of Cause Underway.When Determined,Rept W/Corrective Actions Will Be Sent | | | 05000302/LER-1980-019, Forwards LER 80-019/01T-0 | Forwards LER 80-019/01T-0 | | | 05000302/LER-1980-020-03, /03L-0:on 800501,during Review of Surveillance Procedures,Discovered That Procedure for Weekly Battery Check SP-510 Was Not Performed for Wk of 800406.Caused by Damaged Hydrometer Used to Perform Surveillance | /03L-0:on 800501,during Review of Surveillance Procedures,Discovered That Procedure for Weekly Battery Check SP-510 Was Not Performed for Wk of 800406.Caused by Damaged Hydrometer Used to Perform Surveillance | | | 05000302/LER-1980-020, Forwards LER 80-020/03L-0 | Forwards LER 80-020/03L-0 | | | 05000302/LER-1980-021-03, /03L-0:on 800506,during Insp of Feedwater swing- Disc Check Valve FWV-45,valve Hinge Pin Was Discovered Missing.Caused by Deficiency During Initial Assembly of Valve by Manufacturer.Valve Is Being Repaired | /03L-0:on 800506,during Insp of Feedwater swing- Disc Check Valve FWV-45,valve Hinge Pin Was Discovered Missing.Caused by Deficiency During Initial Assembly of Valve by Manufacturer.Valve Is Being Repaired | | | 05000302/LER-1980-021, Forwards LER 80-021/03L-0 | Forwards LER 80-021/03L-0 | | | 05000302/LER-1980-022, Forwards LER 80-022/04L-0 | Forwards LER 80-022/04L-0 | | | 05000302/LER-1980-022-04, /04L-0:on 800528,samples Not Obtained for Apr from Test Wells 1 & 4 & Ph Results Not Reported for Waste Water Ponds,Test Well 5 & Discharge Canal.Caused by Elimination of Test Well Sites Due to Canal Mod & Loss of Ph Data | /04L-0:on 800528,samples Not Obtained for Apr from Test Wells 1 & 4 & Ph Results Not Reported for Waste Water Ponds,Test Well 5 & Discharge Canal.Caused by Elimination of Test Well Sites Due to Canal Mod & Loss of Ph Data | | | 05000302/LER-1980-023-03, /03L-0:on 800517,radioactive Matl in Form of Bagged Contaminated Waste & Poly Wrapped Scrap Lumber Was Taken to Site Dump.Caused by Apparent Communication Problem Between Health Physics Personnel & Bldg Servicemen | /03L-0:on 800517,radioactive Matl in Form of Bagged Contaminated Waste & Poly Wrapped Scrap Lumber Was Taken to Site Dump.Caused by Apparent Communication Problem Between Health Physics Personnel & Bldg Servicemen | | | 05000302/LER-1980-023, Forwards LER 80-023/03L-0 | Forwards LER 80-023/03L-0 | | | 05000302/LER-1980-024, Forwards LER 80-024/04L-0 | Forwards LER 80-024/04L-0 | | | 05000302/LER-1980-024-04, /04L-0:on 800523,discovered That I-131 Charcoal Cartridge for Wk Ending 800401 Was Inadvertently Discarded. Caused by Personnel Error.Responsible Personnel Were Instructed on Proper Procedures | /04L-0:on 800523,discovered That I-131 Charcoal Cartridge for Wk Ending 800401 Was Inadvertently Discarded. Caused by Personnel Error.Responsible Personnel Were Instructed on Proper Procedures | | | 05000302/LER-1980-025-03, /03L-0:on 800609,while Performing SP-112 Calibr of Reactor Protection Sys,Count Rate Amplifier for Channel a Source Range Neutron Flux Monitor Found out-of-tolerance Caused by Defective Pulse & Output Amplifier Cards | /03L-0:on 800609,while Performing SP-112 Calibr of Reactor Protection Sys,Count Rate Amplifier for Channel a Source Range Neutron Flux Monitor Found out-of-tolerance Caused by Defective Pulse & Output Amplifier Cards | | | 05000302/LER-1980-025, Forwards LER 80-025/03L-0 | Forwards LER 80-025/03L-0 | | | 05000302/LER-1980-026-03, /03L-0:on 800714,while Performing SP-710 Rc Decay Heat Removal & Rc Makeup Sys Chemistry Surveillance Program, Chloride & Fluoride Concentrations Exceeded Limits.Caused by High Temp of Decay Heat Sys & Migration of Elements | /03L-0:on 800714,while Performing SP-710 Rc Decay Heat Removal & Rc Makeup Sys Chemistry Surveillance Program, Chloride & Fluoride Concentrations Exceeded Limits.Caused by High Temp of Decay Heat Sys & Migration of Elements | | | 05000302/LER-1980-026, Forwards LER 80-026/03L-0 | Forwards LER 80-026/03L-0 | | | 05000302/LER-1980-027-01, /01T-0:on 800728,in Mode 5,while Performing OP-401 Core Flooding Sys,Check Valve CFV-79 Failed Allowing About 500 Gallons of Liquid to Enter Nitrogen Sys Via NGV-4. Apparently Caused by CFV-79 Failure & Open NGV-4 | /01T-0:on 800728,in Mode 5,while Performing OP-401 Core Flooding Sys,Check Valve CFV-79 Failed Allowing About 500 Gallons of Liquid to Enter Nitrogen Sys Via NGV-4. Apparently Caused by CFV-79 Failure & Open NGV-4 | |
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