LER-1980-051, /01T-0:on 801214,during Troubleshooting Operations While Isolating Leak in Fire Svc sys,FSV-107 Was Shut, Isolating Fire Svc from Aux Bldg Deluge Contrary to Tech Specs.Caused by Failure to Interpret Design Function |
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| 3021980051R01 - NRC Website |
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System, FSV-107.was shut, isolating Fire Service from the Aux. Building Deluge, t
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Sprinkler and Hose Stations contrary to Tech Specs 3.7.11.2 and 3.7.11.4.
The valve had been shut at 2311 on 12/14/0,0 but no backup Fire Suppression System was
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the first event reported contrary to T. S. 3.7.11.4 and the second event reported contrary to T. S. 3.7.11.2.
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SUPPLEMENTARY INFORMATION 4
Report No.:
50-302/80-051/0lT-0 Facility:
Crystal River Unit. #3 Report Date:
26 December 1980 Occurrence Date:
December 14, 1980 l'
Identification of Occurrence:
Failure to have the Deluge and Sprinkler Systems operable i
contrary to Technical Specification 3.7.11.2.
Failure to have Fire Hose Stations operable contrary to Technical Specification 3,7.11.4 Conditions Prior to Occurrence:
Mode 1 power operation (escalation from 75% to 100%).
Description of Occurrence:
1 On December 14, 1980 a leak at the S.W. corner of the berm was reported to the Control Room. At P.311 the senior licensed -
operator sent to investigate the report shut FSV-107, to isolate the leak, but he did'not realize the valve was a yard loop isolation even though the appropriate drawing was consul ted. At 0050 on December 15,1980 a second senior licensed operator reviewed the troubleshooting actions and discovered that the Auxiliary Building Fire Service.had been isolated. An operator was innediately sent to open FSV-107'.
Operability was restored at 0105.
l Designation of Apparent Cause:
The cause of this event is attributed to failure of peIsonnel to accurately interpret drawing FD-302-231 for the function of FSV-107. The cause of the leak was determined to be a partially open hydrant.
Analysis of Occurrence:
No Fire Watch, equivalent capacity fire hose or other backup System of Fire Suppression was available to the affected-portion of the. Auxiliary Building during the event. There l
was no effect upon the health or, safety of the general public.
Corrective Action
l System operability was restored by opening FSV-107. The leak was' resolved by closing the partially open hydrant. The event has been critiqued by the Operational shift involved and lessons Learned training will be provided to all operational shifts by January 15, 1981. (This is the. earliest time possible i
to instruct all personnel, due to shift scheduling) i-Failure Data:
This is the first' occurrence.for FSV-107, the first event re-ported contrary to Technical Specification 3.7.11.4 and the -
I second event reported contrary to Technical-Specification 3.7.11.2.
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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. Caused by Failure of Nni Voltage Buffer Card 4-7-10(4) | /01T-1:on 800226,during Routine Operation,Power Supply Failure Initiated Transient Condition,Resulting in Reactor Trip,Turbine Trip & Engineered Safeguards Actuation. Caused by Failure of Nni Voltage Buffer Card 4-7-10(4) | | | 05000302/LER-1980-010, Forwards LER 80-010/01T-1 | Forwards LER 80-010/01T-1 | | | 05000302/LER-1980-011-04, /04L-0:on 800222,discovered Representative Sample Not Obtained for Feb from Test Well 4,contrary to Tech Spec. Apparently Caused by Intake Canal Mod Const Activity.Tech Spec Change Request Will Be Submitted to Delete Require | /04L-0:on 800222,discovered Representative Sample Not Obtained for Feb from Test Well 4,contrary to Tech Spec. Apparently Caused by Intake Canal Mod Const Activity.Tech Spec Change Request Will Be Submitted to Delete Requirement | | | 05000302/LER-1980-011, Forwards LER 80-011/04L-0 | Forwards LER 80-011/04L-0 | | | 05000302/LER-1980-012, Forwards LER 80-012/04L-0 | Forwards LER 80-012/04L-0 | | | 05000302/LER-1980-012-04, /04L-0:on 800229,discovered That Environ Samples Were Not Taken from Locations at Required Frequencies.Caused by Personnel Error.Incident Occurrence Infrequent Therefore No Corrective Actions Necessary | /04L-0:on 800229,discovered That Environ Samples Were Not Taken from Locations at Required Frequencies.Caused by Personnel Error.Incident Occurrence Infrequent Therefore No Corrective Actions Necessary | | | 05000302/LER-1980-013, Forwards LER 80-013/04L-0 | Forwards LER 80-013/04L-0 | | | 05000302/LER-1980-013-04, /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 | /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 Media Replaced | /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 Media Replaced | | | 05000302/LER-1980-016, Forwards LER 80-016/01T-0 | Forwards LER 80-016/01T-0 | | | 05000302/LER-1980-017-03, /03L-0:on 800405,during Repair of B once-through Steam Generator Feedwater swing-disc Check Valve FWV-46, Discovered Valve Disc Retainer Pin Missing.Caused by Deficiency Occurring During Initial Manufacturer Assembly | /03L-0:on 800405,during Repair of B once-through Steam Generator Feedwater swing-disc Check Valve FWV-46, Discovered Valve Disc Retainer Pin Missing.Caused by Deficiency Occurring During Initial Manufacturer Assembly | | | 05000302/LER-1980-017, Forwards LER 80-017/03L-0 | Forwards LER 80-017/03L-0 | | | 05000302/LER-1980-018-03, /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 | /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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