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e Attachment to AECM-86/015?
U 8. NUCLE %4 REGULATORY COamsameON NRC Form 333 N'
APrROVED oms eso.3100-0104 LICENSEE EVENT REPORT (LER) i ACILITV Naast til DOCERT NueAS$lt (2)
Pass m Grand Gulf Nuclear Station - Unit 1 0 l5 l 0 l0 l 0 l4 l 116 1 lOFl 0 l 3 TITLE del Nonroutine Surveillance Retest Performed Late SVENT DATE (El Lim NUMetR 163 REPORT DATE 171 OTHER PACILITIES 68eV0LVt0 tel ia6 na MONTM DAY YEAR F ACsLITV N AMee DOCuLET NutsetRIS)
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On April 16, 1985, during the closecut review of a maintenance work order, a maintenance planner identified a failure to perform a nonroutine surveillance retest for a motor operated isolation valve's thermal overload bypass circuitry.
The thermal overload relay for the motor operator of a drywell chemical waste sump discharge isolation valve was replaced on April 9, 1986.
The thermal l
overload protection for the valve motor is required to be continuously bypassed, i
Technical Specification 4.8.4.2.1.c requires this condition to be verified following maintenance on the motor starter.
Due to a procedural error this requirement was not included in the work package retest requirements.
The surveillance retest was performed on April 16, 1986 and verified the thermal i
overload protection to be continuously bypassed.
The Test and Retest Control procedure will be revised and the importance of proper and complete reviews of surveillance retest requirements was emphasized to maintenance planners.
8605210484 860516 PDR ADOCK 0500 6
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J10AECM86051502 - 3 2*0," "*
Attachment to AECM-86/0152 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION A-ovio owe aeo sino-cio.
EXPIRES 8/3195 FACILITV 8eAa84 til DOChET NUtdBER (21 ggg gygiggg ggg pagg g33 "QOP
'*X*,.O vsaa Grand Gulf Nuclear Station - Unit 1 ol5lololo]4l1]6 816 0 l1 l 4 0l0 0l2 OF 0 l3 A.
REPORTABLE OCCURRENCE On April 16, 1986, during the closecut review of a maintenance work order (MW0), a maintenance planner identified a failure to perform a nonroutine Technical Specification surveillance requirement for a motor operated valve's thermal overload bypass circuitry. This report is submitted pursuant to 10CFR50.73(a)(2)(i)(B).
B.
INITIAL CONDITIONS The plant was operating in mode 1 at approximately 65 percent power.
C.
DESCRIPTION OF OCCURRENCE Certain motor operated valves have thermal overload protection which is either continuously bypassed and placed in force only when the valve motors are undergoing testing or normally in force during plant operation and bypassed under accident conditions. Technical Specification 4.8.4.2.1.c requires verification that the thermal overload protection is continuously bypassed or bypassed under accident conditions, as applicable, following maintenance on motor starters.
The thermal overload relay for the motor operator of valve P45-F096, a Drywell Chemical Waste Sump Discharge Isolation Valve, was replaced on April 9, 1986 while the plant was in Cold Shutdown. The valve's thermal overload protection is required to be continuously bypassed.
Plant restart commenced on April 11, 1986. On April 16, 1986, during the closecut review of the work package a maintenance planner noted that the surveillance required by Technical Specification 4.8.4.2.1.c had not been included in the MWO retest requirements.
Operations declared the bypass circuitry inoperable and entered a Limiting Condition for Operation (LC0) at 0900 on April 16, 1986. The surveillance was then performed which verified that the thermal overload protection was bypassed.
The LC0 was cleared at 1330 on April 16, 1986.
The event actually occurred on April 11, 1986 when the isolation valve was first required to be operable following the work, but was not discovered until April 16, 1986 as a result of the final reviews of the completed work package.
J10AECM86051502 - 4 g....
Attachment to AECM-86/0152 asac Form ameA y a touCLEAR meoutaTomV C0ammessoas LICENSEE EVENT REPORT (LER) TEXT CONTINUATION A,*aovio oms a o neo-oio.
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APPARENT CAUSE TheTestandRetestdontrolprocedure,01-S-07-2,providesatableof special retest requirements identified in the Technical Specifications.
The table included the requirements of Technical Specification 4.8.4.2.1.C for "specified motor operated valves".
To determine which motor operated valves are applicable to this requirement, the planner must review either the Technical Specifications or the surveillance procedure which is used to perform the test. The planner reviewed the only surveillance procedure referenced in the Test and Retest Control procedure for implementing the requirement. However, this surveillance procedure, 06-EL-1R65-Q-1001, was only for the valves with thermal overload protection normally in force. The correct procedure, 06-EL-1R65-R-0001, for continuously bypassed overload protection was not referenced by the Test and Retest Control procedure. Because valve P45-F096 was not listed in 06-EL-IR65-Q-1001, the planner concluded that the requirement was not applicable.
E.
SUPPLEMENTAL CORRECTIVE ACTION Procedure 01-S-07-2 will be revised to reference the surveillance procedure used to verify that thermal overload protection is continuously bypassed. The importance of proper and complete reviews of surveillance retest requirements for MW0's was emphasized to maintenance planners.
F.
SAFETY ASSESSMENT
The thermal overload bypass was in effect when its operability was required. The redundant isolation valve was also operable. The isolation function of the valve was not degraded by the missed surveillance.
1 J10AECM86051502 - 5 g,,o..
f MISSISSIPPI POWER & LIGHT COMPANY Helping Build Mississippi RetiltMddB P. O. B O X 16 4 0. J A C K S O N. MIS SIS SIP PI 39215-1G40 May 16, 1986 O. D. KINGSLEY, J R.
VICE PREllDENT NUCLEAR OPER ATIONS Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Gentlemen:
SUBJEC':
Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 File: 0260/L-835.0 Nonroutine Surveillanca Retest Performed Late LER 86-014-00 AECM-86/0152 Attached is Licensee Event Report (LER) 86-014-00 which is a final report.
Yours ly, ODX:lm Attachment cc:
Mr. T. H. Cloninger (w/a)
Mr. R. B. McGehee (w/a)
Mr. N. S. Reynolds (w/a)
Mr. H. L. Thomas (w/o)
Mr. R. C. Butcher (w/a)
Mr. James M. Taylor, Director (w/a)
Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Dr. J. Nelson Grace, Regional Administrator (w/a)
U. S. Nuclear Regulatory Commission Region II 101 Marietta St., N. W., Suite 2900 Atlanta, Georgia 30323 Y
9 g
J10AECM86051502 - 1 Member Middle South Utilities System
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| 05000416/LER-1986-001, :on 860101,reactor Scrammed on Low Reactor Water Level.Caused by Operator Error & Stuck Recorder Pen on Water Level Recorder.Memo Issued & Recorder Reworked |
- on 860101,reactor Scrammed on Low Reactor Water Level.Caused by Operator Error & Stuck Recorder Pen on Water Level Recorder.Memo Issued & Recorder Reworked
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1986-004, :on 860212,reactor Scrammed During Shutdown for Excessive Reactor Coolant Leakage.Caused by Deterioration of Seal on Reactor Recirculation Pump B.Seal Replaced |
- on 860212,reactor Scrammed During Shutdown for Excessive Reactor Coolant Leakage.Caused by Deterioration of Seal on Reactor Recirculation Pump B.Seal Replaced
| 10 CFR 50.73(a)(2)(1) | | 05000416/LER-1986-005, :on 860215,heater for Filter Train B Found to Dissipate Approx 44.9 Kw,Violating Tech Spec Min Requirement of 45 Kw.Caused by Failure to Submit Tech Spec Change When Design Change Implemented.Tech Specs Revised |
- on 860215,heater for Filter Train B Found to Dissipate Approx 44.9 Kw,Violating Tech Spec Min Requirement of 45 Kw.Caused by Failure to Submit Tech Spec Change When Design Change Implemented.Tech Specs Revised
| 10 CFR 50.73(a)(2)(1) | | 05000416/LER-1986-006, :on 850207,RCIC Turbine Steam Supply Inboard Isolation Valve Isolated on False RHR Equipment Area High Ambient Temp Signal.Caused by Faulty Thermocouple Shield Wiring.Wiring Repaired |
- on 850207,RCIC Turbine Steam Supply Inboard Isolation Valve Isolated on False RHR Equipment Area High Ambient Temp Signal.Caused by Faulty Thermocouple Shield Wiring.Wiring Repaired
| | | 05000416/LER-1986-007, :on 860220,RHR Pump B & Standby Svc Water Pump B Automatically Started Due to Technician Connecting Test Switch to Wrong Terminal.Caused by Inadequate Verification by Contractor.Contract Terminated |
- on 860220,RHR Pump B & Standby Svc Water Pump B Automatically Started Due to Technician Connecting Test Switch to Wrong Terminal.Caused by Inadequate Verification by Contractor.Contract Terminated
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1986-008, :on 860224,discovered That Surveillance Procedures Did Not Adequately Test for Complete Response Time of end-of-cycle Recirculation Pump Trip Sys.Caused by Unclear Tech Spec Note.Tech Spec to Be Changed |
- on 860224,discovered That Surveillance Procedures Did Not Adequately Test for Complete Response Time of end-of-cycle Recirculation Pump Trip Sys.Caused by Unclear Tech Spec Note.Tech Spec to Be Changed
| | | 05000416/LER-1986-009, :on 860319,supply Air Flow to Automatic Depressurization Sys Air Receivers Determined to Be Excessive.Caused by Sys Operating Pressure of 185 Psig Exceeding Design Valve Seat Leak Tightness |
- on 860319,supply Air Flow to Automatic Depressurization Sys Air Receivers Determined to Be Excessive.Caused by Sys Operating Pressure of 185 Psig Exceeding Design Valve Seat Leak Tightness
| 10 CFR 50.73(a)(2)(1) | | 05000416/LER-1986-010, :on 860403,field Engineer Inadvertently Bumped Power Switch to Distribution Panel 1484 to Off Position, Causing Primary & Secondary Containment Isolations.Engineer Counseled |
- on 860403,field Engineer Inadvertently Bumped Power Switch to Distribution Panel 1484 to Off Position, Causing Primary & Secondary Containment Isolations.Engineer Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1986-011, :on 860407,safety Relief Valve Inadvertently Lifted & Could Not Be Verified to Close within 2-minute Limiting Condition for Operation Time Limit.Unit Shut Down. on 860408,automatic Reactor Scram Actuated |
- on 860407,safety Relief Valve Inadvertently Lifted & Could Not Be Verified to Close within 2-minute Limiting Condition for Operation Time Limit.Unit Shut Down. on 860408,automatic Reactor Scram Actuated
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(1) | | 05000416/LER-1986-012, :on 860410,while in Cold Shutdown,Containment Isolation Valve El2-F008 Closed.Caused by Failed Coil in Logic Relay.Relay Replaced |
- on 860410,while in Cold Shutdown,Containment Isolation Valve El2-F008 Closed.Caused by Failed Coil in Logic Relay.Relay Replaced
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1986-014, :on 860411,failure to Perform Nonroutine Surveillance Retest for motor-operated Isolation Valve Thermal Overload Bypass Circuitry Identified.Caused by Procedural Error.Procedure Will Be Revised |
- on 860411,failure to Perform Nonroutine Surveillance Retest for motor-operated Isolation Valve Thermal Overload Bypass Circuitry Identified.Caused by Procedural Error.Procedure Will Be Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000416/LER-1986-015, :on 860303,matl Nonconformance Rept Issued for Four Nonseismically Qualified Agastat Model 7014 Relays in Control Room Emergency Filtration Sys.Condition Existed Since 820816.Qualified Relays Installed |
- on 860303,matl Nonconformance Rept Issued for Four Nonseismically Qualified Agastat Model 7014 Relays in Control Room Emergency Filtration Sys.Condition Existed Since 820816.Qualified Relays Installed
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | | 05000416/LER-1986-016, :on 860417,error Discovered in Procedure That Caused Missed Isolation Time Measurement for Containment power-operated Isolation Valve on MSIV Leakage Control Sys. Caused by Requirement Inadvertently Deleted |
- on 860417,error Discovered in Procedure That Caused Missed Isolation Time Measurement for Containment power-operated Isolation Valve on MSIV Leakage Control Sys. Caused by Requirement Inadvertently Deleted
| | | 05000416/LER-1986-017, :on 860430,wrong Fuse Pulled During Attempt to Deactivate Containment Isolation Valve Causing Actuation of Combustible Gas Control Subsystem A.Fuse Reinserted & Sys Returned to Standby.Operator Disciplined |
- on 860430,wrong Fuse Pulled During Attempt to Deactivate Containment Isolation Valve Causing Actuation of Combustible Gas Control Subsystem A.Fuse Reinserted & Sys Returned to Standby.Operator Disciplined
| | | 05000416/LER-1986-018, :on 860513,grab Samples Not Collected During Limiting Condition for Operation Due to Inoperability of Hydrogen Monitors.Caused by Failure of Supervisor to Verify Termination of Condition |
- on 860513,grab Samples Not Collected During Limiting Condition for Operation Due to Inoperability of Hydrogen Monitors.Caused by Failure of Supervisor to Verify Termination of Condition
| | | 05000416/LER-1986-019, :on 860522,PVC Drain Pipes from Computer Room Air Conditioners Improperly Routed Through Penetrations. Initially Identified During 841215 Insp.Caused by Personnel Error.Fire Watch Instituted.Design Changed |
- on 860522,PVC Drain Pipes from Computer Room Air Conditioners Improperly Routed Through Penetrations. Initially Identified During 841215 Insp.Caused by Personnel Error.Fire Watch Instituted.Design Changed
| | | 05000416/LER-1986-020, :on 860603,discovered That Nonqualified Relay Could Cause Loss of Standby Gas Treatment Sys Safety Function During Accidents.Caused by Approved Design.Circuit Design Will Be Modified to Bypass Fan Contact |
- on 860603,discovered That Nonqualified Relay Could Cause Loss of Standby Gas Treatment Sys Safety Function During Accidents.Caused by Approved Design.Circuit Design Will Be Modified to Bypass Fan Contact
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000416/LER-1986-021, :on 860607,unplanned RCIC Sys Isolation Occurred Due to False High Steam Flow Trip Signal.Caused by Faulty Calibr Unit Power Supply.Unit Replaced.Isolation Valve Reopened & Trip Channel Restored to Svc |
- on 860607,unplanned RCIC Sys Isolation Occurred Due to False High Steam Flow Trip Signal.Caused by Faulty Calibr Unit Power Supply.Unit Replaced.Isolation Valve Reopened & Trip Channel Restored to Svc
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1986-022, :on 860619,discovered That Instrument Channel Which Provides Automatic Depressurization Sys Actuation Permissive Signal Not Tested During Mar 1986.Caused by Personnel Error.Package Checks Improved |
- on 860619,discovered That Instrument Channel Which Provides Automatic Depressurization Sys Actuation Permissive Signal Not Tested During Mar 1986.Caused by Personnel Error.Package Checks Improved
| | | 05000416/LER-1986-023, :on 860619,discovered Potentially Generic Deficiency Re Inoperability of HPCS Diesel Generator During Automatic Unexcited Idle Run.Caused by Circuit Design Problem.Sys Operating Instruction Revised |
- on 860619,discovered Potentially Generic Deficiency Re Inoperability of HPCS Diesel Generator During Automatic Unexcited Idle Run.Caused by Circuit Design Problem.Sys Operating Instruction Revised
| | | 05000416/LER-1986-024, :on 860711,operations Personnel Discovered That Monthly Functional Test of Drywell Personnel Air Lock Outer Door Inflatable Seal Pressure Instrumentation Not Performed by 860706 |
- on 860711,operations Personnel Discovered That Monthly Functional Test of Drywell Personnel Air Lock Outer Door Inflatable Seal Pressure Instrumentation Not Performed by 860706
| | | 05000416/LER-1986-025, :on 860725,breaker Inadvertently Bumped Open While Performing Mod Work Activities Resulting in Loss of Power in Certain Div 1 Isolation Valves.Caused by Personnel Error.Procedures Revised |
- on 860725,breaker Inadvertently Bumped Open While Performing Mod Work Activities Resulting in Loss of Power in Certain Div 1 Isolation Valves.Caused by Personnel Error.Procedures Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1986-027, :During NRC 860611-15 Insp,Hourly Fire Watches Found to Exceed Tech Spec 1 H Frequency.Caused by Administrative Deficiencies.Fire Watch Personnel Received Verbal & Written Instructions |
- During NRC 860611-15 Insp,Hourly Fire Watches Found to Exceed Tech Spec 1 H Frequency.Caused by Administrative Deficiencies.Fire Watch Personnel Received Verbal & Written Instructions
| 10 CFR 50.73(a)(2)(B) | | 05000416/LER-1986-028, :on 860825,reactor Automatically Scrammed in Response to Inadvertent Fast Closure of Turbine Control Valves.Caused by Actuation of Main Generator Load Reject Circuitry Due to Personnel Error |
- on 860825,reactor Automatically Scrammed in Response to Inadvertent Fast Closure of Turbine Control Valves.Caused by Actuation of Main Generator Load Reject Circuitry Due to Personnel Error
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1986-029, :on 860826,discovered Incorrect Flow Measuring Device Coefficient Used in Establishing Coolant Flow to ESF Electrical Switchgear Room Coolers Resulting in Low Flows. Caused by Ae Design Error.Pipes Flushed |
- on 860826,discovered Incorrect Flow Measuring Device Coefficient Used in Establishing Coolant Flow to ESF Electrical Switchgear Room Coolers Resulting in Low Flows. Caused by Ae Design Error.Pipes Flushed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000416/LER-1986-029-04, Forwards Corrected LER 86-029-04,reflecting Omitted Rept Date from Page 1 & Incorporating Final Safety Assessments Re Reevaluations of Impact of Increased post-accident Auxiliary Bldg Corridor Temps on Reportability Determin | Forwards Corrected LER 86-029-04,reflecting Omitted Rept Date from Page 1 & Incorporating Final Safety Assessments Re Reevaluations of Impact of Increased post-accident Auxiliary Bldg Corridor Temps on Reportability Determinations | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000416/LER-1986-030, :on 860826 & 0902,certain Control Room Boundary Penetrations Breached in Excess of License Condition.Caused by Personnel Error.Tracking Method & Procedures Revised. Responsible Engineer Reinstructed |
- on 860826 & 0902,certain Control Room Boundary Penetrations Breached in Excess of License Condition.Caused by Personnel Error.Tracking Method & Procedures Revised. Responsible Engineer Reinstructed
| | | 05000416/LER-1986-031, :on 860901,prior to Changing from Startup to Run,Aprm Flow Channels Not Checked as Required by Startup Integrated Operating Instruction.Caused by Technician Error in Interpreting Procedure.Procedure Revised |
- on 860901,prior to Changing from Startup to Run,Aprm Flow Channels Not Checked as Required by Startup Integrated Operating Instruction.Caused by Technician Error in Interpreting Procedure.Procedure Revised
| 10 CFR 50.73(a)(2)(1) | | 05000416/LER-1986-032, :on 860916,17 & 1015,inadvertent Secondary Containment Isolations & ESF Sys Actuations Experienced Due to Outage Work Activities.Special Review Team Established to Examine Electrical tag-outs |
- on 860916,17 & 1015,inadvertent Secondary Containment Isolations & ESF Sys Actuations Experienced Due to Outage Work Activities.Special Review Team Established to Examine Electrical tag-outs
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1986-033, :on 860923,primary Containment Cooling Sys Isolated Due to High Radiation Trip Signal from Containment Drywell Ventilation Exhaust Radiation Monitors.Containment Ventilation Sys Will Remain Isolated |
- on 860923,primary Containment Cooling Sys Isolated Due to High Radiation Trip Signal from Containment Drywell Ventilation Exhaust Radiation Monitors.Containment Ventilation Sys Will Remain Isolated
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1986-034, :on 861014,isolation Valve on Common Suction Pipe for RHR Shutdown Cooling Loops a & B Isolated as Result of Contact Between Conduit & Rectifier Fin.Caused by Unprotected Fins.Edgeguards Installed on Fins |
- on 861014,isolation Valve on Common Suction Pipe for RHR Shutdown Cooling Loops a & B Isolated as Result of Contact Between Conduit & Rectifier Fin.Caused by Unprotected Fins.Edgeguards Installed on Fins
| | | 05000416/LER-1986-035, :on 861021,effluent Releases Continued for More than Tech Spec Limit of 30 Days.Caused by Failure to Adequately Track Expiration of Limiting Condition for Operation.Rept Form Revised |
- on 861021,effluent Releases Continued for More than Tech Spec Limit of 30 Days.Caused by Failure to Adequately Track Expiration of Limiting Condition for Operation.Rept Form Revised
| 10 CFR 50.73(a)(2)(1) | | 05000416/LER-1986-036, :on 861016,Tech Spec Limiting Condition for Operation Not Met When on 861015,channel Ventilation Exhaust Monitors B & C Removed from Svc by Opening & tagging-out Supply Breakers to Support Mod Work |
- on 861016,Tech Spec Limiting Condition for Operation Not Met When on 861015,channel Ventilation Exhaust Monitors B & C Removed from Svc by Opening & tagging-out Supply Breakers to Support Mod Work
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000416/LER-1986-037, :on 861022,Tech Spec Limiting Conditions for Operation Requirements Not Met When Monthly Functional Surveillance of Containment/Drywell Ventilation Exhaust Radiation Monitors Exceeded Max Frequency |
- on 861022,Tech Spec Limiting Conditions for Operation Requirements Not Met When Monthly Functional Surveillance of Containment/Drywell Ventilation Exhaust Radiation Monitors Exceeded Max Frequency
| 10 CFR 50.73(a)(2)(1) | | 05000416/LER-1986-038, :on 861022,Div I Auxiliary Bldg Isolation Valves Inadvertently Isolated During Test.Caused by Interruption of Circuit During Removal of Jumper. Surveillance Procedures Will Be Revised |
- on 861022,Div I Auxiliary Bldg Isolation Valves Inadvertently Isolated During Test.Caused by Interruption of Circuit During Removal of Jumper. Surveillance Procedures Will Be Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1986-039, :on 861027,discovered That Reactor Coolant Conductivity Samples Taken on 861024,25 & 26 Invalid.Caused by Isolation of RWCU on 861023 During Valve Manipulations. Sample Retaken & Conductivity Found Unchanged |
- on 861027,discovered That Reactor Coolant Conductivity Samples Taken on 861024,25 & 26 Invalid.Caused by Isolation of RWCU on 861023 During Valve Manipulations. Sample Retaken & Conductivity Found Unchanged
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | | 05000416/LER-1986-040, :on 861027,determined That Two Weekly Surveillances of Breaker Alignment Not Performed in Required Tech Spec Time Interval.Caused by Nonlicensed Operator Oversight.Procedures Now Hand Carried |
- on 861027,determined That Two Weekly Surveillances of Breaker Alignment Not Performed in Required Tech Spec Time Interval.Caused by Nonlicensed Operator Oversight.Procedures Now Hand Carried
| 10 CFR 50.73(a)(2)(1) | | 05000416/LER-1986-041, :on 861030,Divs 1 & 2 Auxiliary Bldg Isolation Valve Bypass Switches Found in Bypass Position Following Establishment of Secondary Containment Integrity.Caused by Inadequate Procedure.Procedure to Be Revised |
- on 861030,Divs 1 & 2 Auxiliary Bldg Isolation Valve Bypass Switches Found in Bypass Position Following Establishment of Secondary Containment Integrity.Caused by Inadequate Procedure.Procedure to Be Revised
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000416/LER-1986-042, :on 861105,failure to Revise Daily Operating Log to Incorporate New Channel Check Required by 861013 Amend to Tech Specs Discovered.Caused by Personnel Error. Plant Licensing Activities Procedure Revised |
- on 861105,failure to Revise Daily Operating Log to Incorporate New Channel Check Required by 861013 Amend to Tech Specs Discovered.Caused by Personnel Error. Plant Licensing Activities Procedure Revised
| | | 05000416/LER-1986-043, :on 861106,during Replacement of Agastat Relays,Div 1 Drywell Purge Compressor Inadvertently Started. Caused by Error in Impact Statement of Work Authorization. Control of Work Procedure Revised |
- on 861106,during Replacement of Agastat Relays,Div 1 Drywell Purge Compressor Inadvertently Started. Caused by Error in Impact Statement of Work Authorization. Control of Work Procedure Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000416/LER-1986-044, :on 861118,permanent Electrical Wire Erroneously Removed from Isolation Logic Circuit During Performance of Surveillance.Caused by Procedural Error. Procedure Revised to Delete Incorrect Step |
- on 861118,permanent Electrical Wire Erroneously Removed from Isolation Logic Circuit During Performance of Surveillance.Caused by Procedural Error. Procedure Revised to Delete Incorrect Step
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