Similar Documents at Salem |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000272/LER-1999-006-02, :on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With1999-08-26026 August 1999
- on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With
05000311/LER-1999-008, :on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With1999-07-28028 July 1999
- on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With
05000311/LER-1999-007, :on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With1999-07-0606 July 1999
- on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With
05000272/LER-1999-005-02, :on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With1999-07-0202 July 1999
- on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With
05000311/LER-1999-002, :on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With1999-07-0101 July 1999
- on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With
05000311/LER-1999-006, :on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With1999-07-0101 July 1999
- on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With
05000272/LER-1999-004-02, :on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With1999-06-17017 June 1999
- on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With
05000272/LER-1999-003-02, :on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With1999-06-0909 June 1999
- on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With
05000311/LER-1999-005-01, :on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With1999-06-0202 June 1999
- on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With
05000272/LER-1999-002-02, :on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With1999-05-12012 May 1999
- on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With
05000311/LER-1999-004-01, :on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With1999-05-10010 May 1999
- on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With
05000311/LER-1999-003-01, :on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With1999-05-0404 May 1999
- on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With
05000311/LER-1999-002-01, :on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With1999-05-0303 May 1999
- on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With
05000311/LER-1999-001-03, :on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With1999-04-23023 April 1999
- on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With
05000272/LER-1999-001-01, :on 990228,reactor Scram Resulted in Turbine Trip.Caused by Personnel Error.Revised Lesson Plans to Explicitly Demonstrate Manner in Which Valve Functions. with1999-03-29029 March 1999
- on 990228,reactor Scram Resulted in Turbine Trip.Caused by Personnel Error.Revised Lesson Plans to Explicitly Demonstrate Manner in Which Valve Functions. with
05000272/LER-1999-001-02, :on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with1999-03-29029 March 1999
- on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with
05000311/LER-1998-015-01, :on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With1999-02-16016 February 1999
- on 981208,inadvertent Discharge Through RHR Relief Valve During Startup Was Noted.Caused by Operator Performing Too Many Tasks Simultaneously.Appropriate Actions Have Been Taken IAW Policies & Procedures.With
05000311/LER-1998-007, :on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With1999-01-28028 January 1999
- on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Caused by Transgranular Stress Corrosion Cracking.Replaced Affected Tubing.With
05000311/LER-1998-016, :on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With1999-01-18018 January 1999
- on 981219,ECCS Leakage Was Outside of Design Value.Caused by Leakage Past Seat of 21RH34 Manual Drain. Valve 21RH34 Was Reseated.With
05000272/LER-1997-001, :on 970215,failure to Perform TS Surveillance of Component Cooling Water Sys Check Valves Occurred.Caused by Inadequate Communication Between EOP Group & IST Reviewers.Procedure Revised.With1998-12-24024 December 1998
- on 970215,failure to Perform TS Surveillance of Component Cooling Water Sys Check Valves Occurred.Caused by Inadequate Communication Between EOP Group & IST Reviewers.Procedure Revised.With
05000272/LER-1996-013, :on 960711,concluded That Current Gain & Bias Settings Had Rendered Overtemperature Delta Temp Protection Channels Inoperable.Caused by Scaling Error.Licensee Will Revise Scaling Calculations.With1998-11-0303 November 1998
- on 960711,concluded That Current Gain & Bias Settings Had Rendered Overtemperature Delta Temp Protection Channels Inoperable.Caused by Scaling Error.Licensee Will Revise Scaling Calculations.With
05000311/LER-1997-004, :on 970408,failure to Comply with TS Action Statement,Dg Start & Inadequate Surveillance Testing,Was Noted.Caused by Inadequate Tracking of Inoperable Equipment. Discussed Event & Lessons Learned.With1998-10-30030 October 1998
- on 970408,failure to Comply with TS Action Statement,Dg Start & Inadequate Surveillance Testing,Was Noted.Caused by Inadequate Tracking of Inoperable Equipment. Discussed Event & Lessons Learned.With
05000272/LER-1998-014-01, :on 980725,noted Improper Calibr of Liquid Radwaste Effluent Line Radiation Monitor.Caused by Inattention to Detail by Maint Personnel.Channel Calibr Was Successfully Performed on 1R18 on 980821.With1998-10-21021 October 1998
- on 980725,noted Improper Calibr of Liquid Radwaste Effluent Line Radiation Monitor.Caused by Inattention to Detail by Maint Personnel.Channel Calibr Was Successfully Performed on 1R18 on 980821.With
05000311/LER-1998-014, :on 980918,discovered That Fire Barrier Matl for HVAC Ducts Does Not Meet Required Level of Fire Resistance.Cause Indeterminate.Established Appropriate Compensatory Actions for Fire Barriers.With1998-10-0101 October 1998
- on 980918,discovered That Fire Barrier Matl for HVAC Ducts Does Not Meet Required Level of Fire Resistance.Cause Indeterminate.Established Appropriate Compensatory Actions for Fire Barriers.With
05000311/LER-1998-012, :on 980725,noted That Afs Was Operated with Less than Required Number of Operable AFW Pumps.Caused by Improper Procedure Implementation.Runout Protection Pressure Device for 22 AFW Pumps Was Returned to Svc.With1998-09-28028 September 1998
- on 980725,noted That Afs Was Operated with Less than Required Number of Operable AFW Pumps.Caused by Improper Procedure Implementation.Runout Protection Pressure Device for 22 AFW Pumps Was Returned to Svc.With
05000311/LER-1998-013-01, :on 980820,noted Surveillance of Containment Penetration Overcurrent Protection Devices Missed.Caused by Human Error.Satisfactorily Tested Apprpriate Breakers & Disciplined Involved Personnel.With1998-09-21021 September 1998
- on 980820,noted Surveillance of Containment Penetration Overcurrent Protection Devices Missed.Caused by Human Error.Satisfactorily Tested Apprpriate Breakers & Disciplined Involved Personnel.With
05000311/LER-1996-006-01, :on 960717,determined That non-radioactive Liquid Basin Radwaste Monitor Inoperable During Low Head Conditions.Caused by Inadequate Design Change Package.Design Change 1EC3663-01 Has Been Installed.With1998-09-16016 September 1998
- on 960717,determined That non-radioactive Liquid Basin Radwaste Monitor Inoperable During Low Head Conditions.Caused by Inadequate Design Change Package.Design Change 1EC3663-01 Has Been Installed.With
05000272/LER-1998-013, :on 980806,operation with TS Required Equipment OOS Was Noted.Caused by Human Error.Reviewed Processes & Practices Re Safety Sys Status Control,Procedure Rev & Extra Training.With1998-09-0808 September 1998
- on 980806,operation with TS Required Equipment OOS Was Noted.Caused by Human Error.Reviewed Processes & Practices Re Safety Sys Status Control,Procedure Rev & Extra Training.With
05000311/LER-1998-007-01, :on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Cause of Event Has Not Yet Been Determined.Assembled Root Cause Team & Replaced Affected Tubing1998-08-27027 August 1998
- on 980730,reactor Coolant Instrument Line through-wall Leak Was Noted.Cause of Event Has Not Yet Been Determined.Assembled Root Cause Team & Replaced Affected Tubing
05000311/LER-1998-011-01, :on 980803,ESFA During a 4KV Automatic Transfer Test Was Noted.Caused by Premature Release of Control Console Pushbutton Due to Inadequate Procedural Step.Revised Procedure1998-08-27027 August 1998
- on 980803,ESFA During a 4KV Automatic Transfer Test Was Noted.Caused by Premature Release of Control Console Pushbutton Due to Inadequate Procedural Step.Revised Procedure
05000311/LER-1998-012-01, :on 980725,discovered That Plant Had Operated in Modes 1 & 2 w/twenty-two AFW Pumps Inoperable.Caused by Failure to Restore Pump Runout Protection Pressure Device to Svc.Returned Subject Device to Svc1998-08-24024 August 1998
- on 980725,discovered That Plant Had Operated in Modes 1 & 2 w/twenty-two AFW Pumps Inoperable.Caused by Failure to Restore Pump Runout Protection Pressure Device to Svc.Returned Subject Device to Svc
05000311/LER-1998-009-01, :on 980810,failure to Post Continuous Firewatch as Required by Fire Protection Plan Noted.Caused by Failure to Recognize Concurrent Conditions.Continuous Firewatch Was Posted Immediately & Repaired Smoke Detectors1998-08-24024 August 1998
- on 980810,failure to Post Continuous Firewatch as Required by Fire Protection Plan Noted.Caused by Failure to Recognize Concurrent Conditions.Continuous Firewatch Was Posted Immediately & Repaired Smoke Detectors
05000311/LER-1998-010-01, :on 980714,determined That Leakage from Boron Injection Tank Exceeded Max Allowable ECCS Leakage from Sources Outside Containment.Caused by Leaking 2SJ404 Manual Sample valve.2SJ404 Valve Repaired1998-08-13013 August 1998
- on 980714,determined That Leakage from Boron Injection Tank Exceeded Max Allowable ECCS Leakage from Sources Outside Containment.Caused by Leaking 2SJ404 Manual Sample valve.2SJ404 Valve Repaired
05000272/LER-1998-012, :on 980715,potential to Exceed Rating of Piping Due to Isolation of Overpressure Protection Line Was Noted. Caused by Inadequate Procedural Guidance.Appropriate Operations Dept Procedures Have Been Revised1998-08-13013 August 1998
- on 980715,potential to Exceed Rating of Piping Due to Isolation of Overpressure Protection Line Was Noted. Caused by Inadequate Procedural Guidance.Appropriate Operations Dept Procedures Have Been Revised
05000311/LER-1998-003-02, :on 980122,inappropriate Plugging of Tubes R9C60 & R10C60 in Salem Unit 2 Sg,Was Performed.Caused by Failure of Qualification,Verification & Validation Process. Tubes Reviewed to Verify No Others Inappropriately Plugged1998-06-29029 June 1998
- on 980122,inappropriate Plugging of Tubes R9C60 & R10C60 in Salem Unit 2 Sg,Was Performed.Caused by Failure of Qualification,Verification & Validation Process. Tubes Reviewed to Verify No Others Inappropriately Plugged
05000272/LER-1998-011, :on 980505,improper Isolation of Single Cell Battery Charger from 125 Vdc Battery Was Noted.Caused by Inadequate 10CFR50.59 Applicability Review.Placed Procedure SC.MD-CM.ZZ-0024(Q) on Administrative Hold1998-06-0404 June 1998
- on 980505,improper Isolation of Single Cell Battery Charger from 125 Vdc Battery Was Noted.Caused by Inadequate 10CFR50.59 Applicability Review.Placed Procedure SC.MD-CM.ZZ-0024(Q) on Administrative Hold
05000272/LER-1998-010, :on 931019,reactor Pressure Vessel Insp Plugs Were Out of Configuration,Was Noted.Caused by Personnel Error.Proper Configuration Was Restored Shortly After Discovery Prior to Entering Mode 21998-06-0101 June 1998
- on 931019,reactor Pressure Vessel Insp Plugs Were Out of Configuration,Was Noted.Caused by Personnel Error.Proper Configuration Was Restored Shortly After Discovery Prior to Entering Mode 2
05000311/LER-1998-006, :on 980227,determined Incorrect Scaling Error of First Stage Pressure Transmitter Existed.Caused by Human Error.Revised Setpoint Calculation SC-MS002-01 & Revised Associated Instrument Calibr Database Info1998-05-29029 May 1998
- on 980227,determined Incorrect Scaling Error of First Stage Pressure Transmitter Existed.Caused by Human Error.Revised Setpoint Calculation SC-MS002-01 & Revised Associated Instrument Calibr Database Info
05000311/LER-1998-008-01, :on 970814,failure to Test 21 & 22 AF 40 Valves in Closed Direction as Required by TS 4.0.5 Was Noted.Caused by Inadequate Design Mod Process.Motor Driven 21/22 AF 40 Valves Were Tested IAW Revised Procedure1998-05-18018 May 1998
- on 970814,failure to Test 21 & 22 AF 40 Valves in Closed Direction as Required by TS 4.0.5 Was Noted.Caused by Inadequate Design Mod Process.Motor Driven 21/22 AF 40 Valves Were Tested IAW Revised Procedure
05000272/LER-1998-009, :on 980405,epoxy Missing from Terminals of H Analyzer Was Noted.Caused by Inadequate Development of Procedure.H Analyzers Were Repaired & Review of Other Safety Related Equipment in Containment Was Performed1998-05-0101 May 1998
- on 980405,epoxy Missing from Terminals of H Analyzer Was Noted.Caused by Inadequate Development of Procedure.H Analyzers Were Repaired & Review of Other Safety Related Equipment in Containment Was Performed
05000272/LER-1998-008, :on 980323,inadequate Testing of Salem Unit 1 Containment Air Locks Resulted in Entering TS 3.0.3.Caused by less-than-adequate Work Practices During Replacement of Equalizing Valve.Salem Unit 2 Airlocks Were Inspected1998-04-20020 April 1998
- on 980323,inadequate Testing of Salem Unit 1 Containment Air Locks Resulted in Entering TS 3.0.3.Caused by less-than-adequate Work Practices During Replacement of Equalizing Valve.Salem Unit 2 Airlocks Were Inspected
05000272/LER-1998-004, Corrected LER 98-004-00:on 980302,failure to Comply W/Tss 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Have Been Taken to Correctly Document Safety Factors.Corrects Prior Similar Occurrences1998-04-0101 April 1998 Corrected LER 98-004-00:on 980302,failure to Comply W/Tss 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Have Been Taken to Correctly Document Safety Factors.Corrects Prior Similar Occurrences 05000272/LER-1998-004-01, :on 980302,failure to Perform TS 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Were Taken to Correctly Document Safety Factors1998-04-0101 April 1998
- on 980302,failure to Perform TS 4.11.1.1.2 & 3.3.3.8 Was Noted.Caused by Organizational Deficiency.Steps Were Taken to Correctly Document Safety Factors
05000311/LER-1998-006-01, :on 980227,incorrect Scaling of First Stage Turbine Impulse Pressure Transmitters Noted.Cause Indeterminate.Implemented Procedure Changes & re-scaled Affected Turbine Impulse Pressure Transmitters1998-03-30030 March 1998
- on 980227,incorrect Scaling of First Stage Turbine Impulse Pressure Transmitters Noted.Cause Indeterminate.Implemented Procedure Changes & re-scaled Affected Turbine Impulse Pressure Transmitters
05000272/LER-1998-006, :on 980221,ESF Actuation of 11 & 12 Auxiliary Feedwater Pumps Occurred.Caused by Human Error.Operators Promptly Established Feedwater to All SG & Restored Proper Water Levels1998-03-20020 March 1998
- on 980221,ESF Actuation of 11 & 12 Auxiliary Feedwater Pumps Occurred.Caused by Human Error.Operators Promptly Established Feedwater to All SG & Restored Proper Water Levels
05000272/LER-1998-005-01, :on 980219,inoperability of Twelve EDG Fuel Oil Transfer Pump (FOTP) Noted.Caused by Installation of Incorrect Control Switch.Installed Correct off-auto-manual Switch & Verified Operability of Twelve FOTP1998-03-20020 March 1998
- on 980219,inoperability of Twelve EDG Fuel Oil Transfer Pump (FOTP) Noted.Caused by Installation of Incorrect Control Switch.Installed Correct off-auto-manual Switch & Verified Operability of Twelve FOTP
05000272/LER-1998-005, Corrected LER 98-005-00:on 980219,inoperability of 12 Fuel Oil Transfer Pump (Fotp),Noted.Caused by Installation of Incorrect Control Switch.Field Insp Performed to Verify Configuration of Switches for 11,21 & 22 FOTPs1998-03-20020 March 1998 Corrected LER 98-005-00:on 980219,inoperability of 12 Fuel Oil Transfer Pump (Fotp),Noted.Caused by Installation of Incorrect Control Switch.Field Insp Performed to Verify Configuration of Switches for 11,21 & 22 FOTPs 05000272/LER-1998-007, :on 980218,failure to Establish Containment Integrity (Closure) Prior to Fuel Movement Was Noted.Caused by Failure to Identify & Include Condensate Pot Vent in Appropriate Valve Lineup.Valves Identified1998-03-20020 March 1998
- on 980218,failure to Establish Containment Integrity (Closure) Prior to Fuel Movement Was Noted.Caused by Failure to Identify & Include Condensate Pot Vent in Appropriate Valve Lineup.Valves Identified
05000272/LER-1998-002, :on 971217,auxiliary Building Ventilation (Abv) Excess Flow Damper Was Found Wired Open W/Spring Removed. Caused by Personnel Error.Repaired 1ABS8 Damper & Inspected Other Abv Excess Flow Dampers in Abv Sys1998-03-20020 March 1998
- on 971217,auxiliary Building Ventilation (Abv) Excess Flow Damper Was Found Wired Open W/Spring Removed. Caused by Personnel Error.Repaired 1ABS8 Damper & Inspected Other Abv Excess Flow Dampers in Abv Sys
05000272/LER-1998-003, :on 980216,inadequate Surveillance Testing of FW Isolation & P-10 SR Block Was Noted.Caused by Inadequate Development of Original Surveillance Tps for Ssps Logic Testing.Revised Ssps Logic Functional Tps1998-03-16016 March 1998
- on 980216,inadequate Surveillance Testing of FW Isolation & P-10 SR Block Was Noted.Caused by Inadequate Development of Original Surveillance Tps for Ssps Logic Testing.Revised Ssps Logic Functional Tps
1999-08-26
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARLR-N99-0448, Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 1.With LR-N99-0449, Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Salem,Unit 2.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20212B7221999-09-14014 September 1999 Safety Evaluation Supporting Amends 224 & 205 to Licenses DPR-70 & DPR-75,respectively LR-N99-0415, Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 9909131999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 1.With 990913 LR-N99-0416, Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Salem,Unit 2.With 05000272/LER-1999-006-02, :on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With1999-08-26026 August 1999
- on 990729,determined That SG Blowdown RMs Setpoint Was non-conservative.Caused by Inadequate ACs for Incorporating Original Plant Licensing Data Into Plant Procedures.Blowdown Will Be Restricted.With
ML18107A5201999-08-12012 August 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO 9) Second Interval,Second Period, First Outage (96RF) LR-N99-0380, Monthly Operating Rept for July 1999 for Salem,Unit 2.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 2.With LR-N99-0379, Monthly Operating Rept for July 1999 for Salem,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Salem,Unit 1.With 05000311/LER-1999-008, :on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With1999-07-28028 July 1999
- on 990714,determined That Limit Switch Cables Were Subject to Multiple Hot Shorts in Same Fire Area.Caused by Inadequate Original Post Fire Safe Shutdown Analysis.All Limit Switch Cables for MOVs Were Reviewed.With
ML20210B7371999-07-21021 July 1999 Safety Evaluation Supporting Amends 223 & 204 to Licenses DPR-70 & DPR-75,respectively ML18107A4411999-07-0909 July 1999 SER Denying Licensee 980730 & 990222 Requests to Revise TS 3/4.7.6, Control Room Emergency Air Conditioning Sys, & Associated Bases to Change Acceptable Criteria for Control Room Emergency Air Conditioning System 05000311/LER-1999-007, :on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With1999-07-0606 July 1999
- on 990605,surveillance for Quadrant Power Tilt Ratio (QPTR) Was Missed.Caused by Human Error.Qptr Calculation Was Performed & Personnel Involved Have Been Held Accountable IAW Pse&G Policies.With
05000272/LER-1999-005-02, :on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With1999-07-0202 July 1999
- on 990605,11 Containment Declared Inoperable. Caused by Valves 11SW72 & 11SW223 Both Leaking.Procedure S1.OP-ST.SW-0010(Q) Was Enhanced to Provide Specific Instructions to Ensure Proper Sequencing.With
05000311/LER-1999-006, :on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With1999-07-0101 July 1999
- on 990501,determined That There Was No Flow in One of Four Injection Legs.Caused by Sticking of Valve in Safety Injection Discharge Line to 21 Cold Leg.Valve Was Cut Out of Sys & Replaced.With
05000311/LER-1999-002, :on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With1999-07-0101 July 1999
- on 990405,determined That 2SA118 Failed as Found Leakrate Test.Caused by Foreign Matl Found in 2SA118 valve.2SA118 Valve Was Cycled Several Times & Seat Area Was Air Blown in Order to Displace Foreign Matl.With
ML18107A5211999-07-0101 July 1999 Rev 0 to Sgs Unit 2 ISI RFO Exam Results (S2RFO 10) Second Interval,Second Period,Second Outage (99RF) LR-N99-0324, Monthly Operating Rept for June 1999 for Salem,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 1.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept LR-N99-0325, Monthly Operating Rept for June 1999 for Salem,Unit 2.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Salem,Unit 2.With ML18107A3931999-06-23023 June 1999 Safety Evaluation Supporting Licensee Response to GL 95-07 ML18107A4161999-06-23023 June 1999 Safety Evaluation Accepting Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions 05000272/LER-1999-004-02, :on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With1999-06-17017 June 1999
- on 990520,reactor Tripped from 100% Power,Due to Negative Flux Trip Signal from Nuclear Instrumentation. Cause Has Not Been Determined.Discoloration Was Identified on One of Penetrations.With
ML18107A3751999-06-15015 June 1999 Safety Evaluation Accepting Licensee Request for Approval of Proposed Changes to Nuclear Business Unit EP for Hope Creek & Salem Generating Stations,Iaw 10CFR50.54(q) 05000272/LER-1999-003-02, :on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With1999-06-0909 June 1999
- on 990513,unplanned Entry Into TS 3.0.3 Was Made.Caused by Human error.Re-positioned Creacs Supply Fan Selector Switches & Revised Procedures S1 & S2.OP-ST.SSP-0001(Q).With
05000311/LER-1999-005-01, :on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With1999-06-0202 June 1999
- on 990504,failure to Meet TS Action Statement Requirements for High Oxygen Concentration in Waste Gas Holdup Sys Occurred.Caused by Inability of Operators. Existing Procedures Will Be Evaluated.With
ML18107A3441999-06-0101 June 1999 Interim Part 21 Rept Re Premature Over Voltage Protection Actuation in Circuit Specific Application in Dc Power Supply.Testing & Evaluation Activities Will Be Completed on 990716 LR-N99-0278, Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 2.With LR-N99-0275, Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Salem Generating Station,Unit 1.With ML18107A3111999-05-21021 May 1999 SER Accepting GL-88-20,suppl 4, IPEEEs for Severe Accident Vulnerabilities, for Plant,Units 1 & 2 05000272/LER-1999-002-02, :on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With1999-05-12012 May 1999
- on 990413,determined That Number 12 Auxiliary Bldg Exhaust Fan Was Rotating Backwards.Caused by mis-wiring of Motor Due to Human Error by Maint technician.Mis-wiring Was Corrected & Fan Was Returned to Svc.With
05000311/LER-1999-004-01, :on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With1999-05-10010 May 1999
- on 990411,automatic Actuation of ESF Occurred During Reactor Vessel Head Removal in Support of Refueling Operations.Caused by High Radiation Condition.Containment Atmosphere Was Monitored.With
05000311/LER-1999-003-01, :on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With1999-05-0404 May 1999
- on 990406,all Salem Unit 2 Chillers Rendered Inoperable.Caused by Human Error.Lessons Learned from Event Were Communicated to All Operators by Including Them in Night Orders.With
ML20206H2631999-05-0404 May 1999 Safety Evaluation Supporting Amend 222 to License DPR-70 05000311/LER-1999-002-01, :on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With1999-05-0303 May 1999
- on 990405,determined That Containment Isolation Valve Failed as Found Leakrate Test.Caused by Foreign Matl Blocking Valves from Closing.Check Valve Mechanically Agitated.With
ML18107A3151999-04-30030 April 1999 Submittal-Only Screening Review of Salem Generating Station Individual Plant Exam for External Events (Seismic Portion), Rev 1 LR-N99-0225, Monthly Operating Rept for Apr 1999 for Salem Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 1.With ML18107A3711999-04-30030 April 1999 Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1 LR-N99-0226, Monthly Operating Rept for Apr 1999 for Salem Unit 2.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Salem Unit 2.With ML20206B4761999-04-26026 April 1999 Safety Evaluation Supporting Amends 220 & 202 to Licenses DPR-70 & DPR-75,respectively 05000311/LER-1999-001-03, :on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With1999-04-23023 April 1999
- on 990330,MSSV Failed Lift Set Test.Caused by Setpoint Variance Which Is Result of Aging.Valves Were Adjusted & Retested to Ensure TS Tolerance.With
ML18107A1791999-04-15015 April 1999 Safety Evaluation Supporting Changes to QA Program in That QA Program Continues to Meet Requirements of App B to 10CFR50 ML18107A2881999-04-0707 April 1999 Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11 ML18107A1601999-04-0707 April 1999 Safety Evaluation Accepting Request for Exemption from Update Requirements of 10CFR50.71(e)(4) ML18106B1461999-04-0101 April 1999 SER Accepting Util Proposed Request to Use 1992 Edition of ASME Boiler & Pressure Vessel Code,Section Xi,Article, IWA-4500,for Potential Repair of Feedwater Nozzles for Salem Nuclear Generating Station,Unit 2 LR-N99-0176, Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 1.With LR-N99-0177, Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Salem,Unit 2.With 05000272/LER-1999-001-02, :on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with1999-03-29029 March 1999
- on 990228,reactor Scram Was Noted as Result of Turbine Trip.Caused by Operator Error.Lesson Plans Revised to Explicitly Demonstrate Manner in Which Valve Functions. with
05000272/LER-1999-001-01, :on 990228,reactor Scram Resulted in Turbine Trip.Caused by Personnel Error.Revised Lesson Plans to Explicitly Demonstrate Manner in Which Valve Functions. with1999-03-29029 March 1999
- on 990228,reactor Scram Resulted in Turbine Trip.Caused by Personnel Error.Revised Lesson Plans to Explicitly Demonstrate Manner in Which Valve Functions. with
1999-09-30
[Table view] |
text
NllC Form311 IM3)
U.I, NUCLEAll llEGULATOllY COflWllllON APl'AOVED OMI NO. 311111-4104 LICENSEE EVENT REPORT (LER)
EXl'IRES: 11/31115 I
DOCKET NUM9Ell (2)
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""""' I'll 0 I 5 I 0 I 0 I 0 I 2 17 I 2 1 I OF 0 I 5 FACILITY NAME 111 Sa1em Generating Station - Unit 1 TITLE l*I T. s. Survei11ance 4.7.11 Ron-Comp1iance - Fire Pampers Rot Survei11ed -
Inad. Admin. Con EVENT DATE (II)
LEA NUMDEll Ill llEl'OAT DATE (7)
OTHEll FACILITIES INVOLVED Ill MONTH QAY YEAR YEAR ]@ SE~~~~i~AL ft =~= MONTH DAY YEAR FACILITY NAMES DOCKET NUMllERISI Sa1em - Unit 2 o 1 s Io I o I o 13 1 111 nlgolg a a ale -ol1IG-olo1lo ol4ala OPlRATING MODE tel THll llEl'OAT II IUIMITTED l'UlllUANT TO THE REQUlllEMENTI OF 10 CFll §: (Ch<<:lt one or man of Ill* followln11J (11)
..,.. ______............ __. 21U02(bl 20.-lcl I0,7311oll2llM I0.*1*1111 ll0.731oll21M LEVEL 731.71lb) 73..71.lcl POWEii I N/A 20.G(1111 Ill) 1101 I
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1111.*Ccll21 "Y llll.73(ol(21(1J llll.73(oll211wH)
I0.7311oll211wlllllAI OTHEll ($/>>c/fymAb,,,.,r l>>low ond In Toxr, NRC Fann 366A) 1111.731(11121(111 I0.731Cell211wfllllll 1111.7:11(81121 (Ill) 1111.731(111211*1 LICENIEE CONTACT FOR THll LEI! (12)
NAME AREA CODE M. J. _Po11ack -
LER Coordinator COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DEICAllED IN THll llEl'OAT (1311 CAUSE SYSTEM COMPONENT I
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I I I MANUFAC-TURER I
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SYSTEM I
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COMPONENT MANUFAC-TUR ER I
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I I I I
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I TELEPHONE NUMBER EXPECTED IUJIPLEMENTAL llEl'ORT EXl'ECTED 1141 MONTH DAY Y~AA SUllMISSION DATE (151 kl NO n YES (If ya, comp-EXPECTED SU6MISSION DATE)
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On September 9, 1988, it was identified, by Site Protection personnel, that "twenty-nine ( 29) Air Balance Model #119 dampers, in several Unit 1 and Unit 2 fire areas, have never been surveilled as required by Technical Specification 4.7.11.
The apparent root cause of this event has been attributed to inadequate administrative control.
The dampers although shown on controlled mechanical arrangement drawings, did not have unique equipment identifier tag numbers.
Consequently, the dampers were not identified on the equipment lists used as a reference to prepare surveillance procedures.
Subsequently, -the damper surveillance requirement was missed.
The surveillance for the subject dampers was completed.
All dampers successfully passed.
The Site Protection staff engineer(s) have been counseled on* the use of AP-6~
"Incident Report/Licensee Event Report Program".
Engineering is reviewing fire protection programmatic requirements to ensure timely dissemination of information to departments which may be affected.
As part of the Fire Protection Improvement -program, a design change will be made to have the appropriate P&ID-schematics identify and number (i.e., component I.D.) the dampers.
NAC Form 311 (Ml) 8810120307" 881004
.8PDR ADOCK 05000272 PNU I
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 LER NUMBER 88-016-00 PAGE 2 of 5
PLANT AND SYSTEM IDENTIFICATION
Westinghouse Pressu~ized Water Reactor Energy Industry Identification System (EIIS) codes are identified in the text as {xx}
IDENTIFICATION OF OCCURRENCE:
Technical Specification Surveillance 4.7.11 Non-compliance; Fire Dampers Not Surveilled Due To Inadequate Design Review Event Date:
9/09/88 Report Date: 10/04/88 This report was initiated by Incident Report Nos.88-379 and 88-380.
CONDITIONS PRIOR TO OCCURRENCE:
N/A DESCRIPTION OF OCCURRENCE:
On September 9, 1988, it was identified, by Site Protection personnel, that twenty-nine (29) Air Balance Model #119 dampers, 1n several Unit 1 and Unit 2 fire areas, have never been surveilled as required by Technical Specification 4.7.11.
Technical Specification 3.. 7.11 states:
"All fire penetrations (including cable penetration barriers, fire doors and fire dampers), in fire zone boundaries, protecting safety related areas shall be functional."
Technical Specification Action Statement 3.7.11.a states:
"With one or more of the above required fire barrier penetrations non-functional, within one hour either establish a continuous fire watch on at least one side of the affected penetration, or
- verify* the OPERABILITY of fire detectors on at least one side of
.the non-functional fire barrier and establish an hourly fire watch patrol.
Restore the non-functional fire barrier penetration(s) to functional status within 7 days or, in lieu of any other report required by Specification 6.9.1, prepare and s_ubmi t a Special Report to the Commission pursuant to Specification 6.9.2 within the next {30) days outlining the action taken, the cause of the 'non-functional penetration and plans and schedule for restoring the fire barrier penetration (s) to functional status."
Technical Specification Surveillance 4.7~11 states:
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1 DOCKET NUMBER 5000272 LER NUMBER 88-016-00 PAGE 3 of 5 DESCRIPTION OF OCCURRENCE:
(cont'd) verified to be functional:
a.
At least once per 18 months by a visual inspection, and b.
Prior to returning a penetration fire barrier to functional status following repairs or maintenance by the performance of a visual inspection of the affected penetration fire barrier(s}."
Note - Unit 1 Technical Specification 3.7.11 differs from Unit 2.
The Unit 1 words "functional" and "non-functional" are replaced by the words "OPERABLE" and "inoperable" respectively.
The fire areas in which the dampers were not surveilled include:
Unit Area Number of Dampers 1
Battery Rooms 8
1 84' El. Switchgear Room 7
1
- 11 Diesel Fuel Oil Storage Tank Room 1
1
- 12 Diesel Fuel Oil Storage Tank Room 1
2 Battery Rooms 9
2 84' El. Switchgear Room 1
.2
- 21 Diesel Fuel Oil Storage Tank Room 1
2
- 22 Diesel Fuel Oil Storage Tank Room 1
APPARENT CAUSE OF OCCURRENCE:
The apparent root cause of this event has been attributed to inadequate administrative control.
The dampers although shown on controlled mechanical arrangement drawings, did not have unique equipment identifier tag numbers.
Consequently, the dampers were not identified on the equipment lists used as a reference to p~epare surveillance'procedures.
Subsequently,:the damper surveillance requirement was missed.
ANALYSIS OF OCCURRENCE:
The fire barrier penetration visual surveillance ensures the functional integrity of barrier penetrations, including dampers, is not violated.
The functional integrity of fire barriers ensures fires will be confined or adequately reta~ded from spreading to adjacent portions of the facility.
- This design feature minimizes the
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION
~~~~~~~---:-~~~~~~~~~--~~~~~~~~~~~~~--~~~~~*---~~~-
Salem Generating Station DOCKET NUMBER LER NUMBER PAGE U-'-=n=i~t-=1'--~~~~~~~~~~~~--=5000272 88-016-00 4 of 5 ANALYSIS OF OCCURRENCE:
(cont'd) possibility of a single fire involving several areas of the facility prior to detection and extinguishment.
The penetration fire barriers are a passive element in the facility fire protection program.
However, because the fire barrier dampers have not been inspected within the 18 month period as per Technical Specification Surveillance 4.7.11 this event is reportable in accordance with Code of Federal Regulations 10CFR 50.73(a) (2) (i) (B).
An hourly fire watch patrol, for the fire barriers containing these dampers, had been previously established due to other fire protection and 10CFR 50, Appendix R concerns.
This fire watch complies with the action required per Technical Specification Action Statement 3.7.11.a.
Investigation of this event revealed that in August 1987, field walkdowns, conducted by engineering, were performed to evaluate fire area boundaries in support of revision to 10CFR 50 Appendix R exemption requests.
One of the results of this walkdown recognized these dampers as being a component of the fire barrier(s).
The scope of the review, however, did not include surveillance compliance thus the deficiency was not identified at that time.
Coincidentally, in the spring of 1988 pr~paration of procedure MlO-SST-031-1, "18 Month Fire Damper Visual Inspection", was initiated to address newly installed dampers.
Other dampers (without a fusible link) have historically been functionally tested.
The Site Protection staff engineer becam~ aware of the subject dampers through detailed review of the mechanical arrangement drawings.
The Site Protection staff engineer, however, did not recognize the_ potential
reportability
In August 1988,,the procedure was approved by the Station Operations Review Committee (SO~C).
At that SORC meeting, it was questioned whether these dampers have been surveilled historically*.
Investigation of the historical records indicated that these dampers have not been surveilled historically.
CORRECTIVE ACTION
The surveillance for the subject dampers was completed.
All dampers successfully passed.
The Site Protection staff engineers have been counseled on the use of AP-6, "Incident Report/Licensee Evept Report.Progra*".
Engineering is reviewing fire protection programmatic requirements to ensure timely dissemination of information to departments which may be affected.
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION Salem Generating Station Unit 1
CORRECTIVE ACTION
(cont'd)
DOCKET NUMBER 5000272 LER NUMBER 88-016-00 PAGE 5 of 5 As part of the Fire Protection Improvement Program, a design change will be made to have the appropriate drawings revised to identify and number (i.e., component I.D.) the dampers.
MJP:pc SORC Mtg.88-082
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General Manager -
Salem Operations
OPS~G Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
Dear Sir:
SALEM GENERATING STATION LICENSE NO. DPR-70 DOCKET NO. 50-272 UNIT NO. 1 LICENSEE EVENT REPORT 88-016-00 October 4, 1988 This Licensee Event Report is being submitted pursuant to the requirements of the Code of Federal Regulations *1ocFR 50.73(a) (2) (i) (B).
This report is required within thirty (30) days of*discovery.
MJP:pc Distribution The Energy People Sincerely yours, ff~
L. K. Miller General Manager-Salem Operations 95-2189 (11 M) 12-84
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05000272/LER-1988-001, :on 880211,improper Anchoring of Three Diesel Generator Day Tanks to Supporting Steel Beam Foundation Identified.Caused by Inadequate Design & Design Review. Tanks Weld Anchored to Steel Beam Foundation |
- on 880211,improper Anchoring of Three Diesel Generator Day Tanks to Supporting Steel Beam Foundation Identified.Caused by Inadequate Design & Design Review. Tanks Weld Anchored to Steel Beam Foundation
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000311/LER-1988-001, :on 880112,chemistry Sample Not Taken on Time, Per Tech Spec Action Statement 3.3.3.8.Caused by Inadequate Administrative Controls.New Form to Help Track Sampling Requirements Issued & Procedures Reviewed |
- on 880112,chemistry Sample Not Taken on Time, Per Tech Spec Action Statement 3.3.3.8.Caused by Inadequate Administrative Controls.New Form to Help Track Sampling Requirements Issued & Procedures Reviewed
| | 05000272/LER-1988-001-02, :on 880211,diesel Generator Day Tanks Found Not Properly Anchored to Supporting Steel Foundation.Cause Not Determined.Tanks Weld Anchored to Wide Flange Steel Beam Foundation on 880212 |
- on 880211,diesel Generator Day Tanks Found Not Properly Anchored to Supporting Steel Foundation.Cause Not Determined.Tanks Weld Anchored to Wide Flange Steel Beam Foundation on 880212
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2) | 05000311/LER-1988-002, :on 880113,during Routine Tour of Svc Water Intake Structure,Operator Observed Excessive Leakage from Pump 22.Caused by Equipment Malfunction.Pump Replaced W/Spare Pump |
- on 880113,during Routine Tour of Svc Water Intake Structure,Operator Observed Excessive Leakage from Pump 22.Caused by Equipment Malfunction.Pump Replaced W/Spare Pump
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000272/LER-1988-002-03, :on 880218,control Room Indication Identified to Register Approx 5 F Above Wide Range RCS Indication. Caused by Mfg Not Identifying Component Design Mod in Specs |
- on 880218,control Room Indication Identified to Register Approx 5 F Above Wide Range RCS Indication. Caused by Mfg Not Identifying Component Design Mod in Specs
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000272/LER-1988-003-02, :on 880224,reactor Trip Occurred on False intermediate-range High Flux Signal.Caused by Personnel Error.Maint Mgt Completed Review of Circumstances Surrounding Event.Individual Counseled |
- on 880224,reactor Trip Occurred on False intermediate-range High Flux Signal.Caused by Personnel Error.Maint Mgt Completed Review of Circumstances Surrounding Event.Individual Counseled
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) | 05000311/LER-1988-003, :on 880208,Tech Spec Table 3.3-12 Action 27 Not Complied With.Caused by Personnel Error Associated W/ Inadequate Communications & Training.Operations Dept Mgt Reviewed Event & Procedures Will Be Modified |
- on 880208,Tech Spec Table 3.3-12 Action 27 Not Complied With.Caused by Personnel Error Associated W/ Inadequate Communications & Training.Operations Dept Mgt Reviewed Event & Procedures Will Be Modified
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000311/LER-1988-004, :on 870312,generator Turbine/Reactor Trip Occurred.Caused by Loss of Generator Excitation Due to Bumped Transfer.Relays Responsible for Subj Occurrence Checked & New Operating Curves Issued |
- on 870312,generator Turbine/Reactor Trip Occurred.Caused by Loss of Generator Excitation Due to Bumped Transfer.Relays Responsible for Subj Occurrence Checked & New Operating Curves Issued
| | 05000272/LER-1988-004-01, :on 880222,change from Mode 3 to Mode 2 Conducted W/Containment Hydrogen Analyzer Technically Inoperable Due to Missed Environ Qualification Surveillance. Caused by Ineffective Administrative Control |
- on 880222,change from Mode 3 to Mode 2 Conducted W/Containment Hydrogen Analyzer Technically Inoperable Due to Missed Environ Qualification Surveillance. Caused by Ineffective Administrative Control
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) | 05000272/LER-1988-005-01, :on 880307,identified Tech Spec Surveillance 4.7.8.1.2.a,sealed Source Leak Check Not Performed within 6 Months from Prior Surveillance.Caused by Inadequate Administrative Controls Associated W/Computer Sys |
- on 880307,identified Tech Spec Surveillance 4.7.8.1.2.a,sealed Source Leak Check Not Performed within 6 Months from Prior Surveillance.Caused by Inadequate Administrative Controls Associated W/Computer Sys
| | 05000272/LER-1988-005, Forwards LER 88-005-00 | Forwards LER 88-005-00 | 10 CFR 50.73(a)(2) | 05000311/LER-1988-005-02, :on 880404,discovered That Hourly Roving Fire Watch Was 23 Minutes Late for 122 Ft Auxiliary Bldg Area. Caused by Personnel Error.Performance of Hourly Fire Watch Surveillances Stressed |
- on 880404,discovered That Hourly Roving Fire Watch Was 23 Minutes Late for 122 Ft Auxiliary Bldg Area. Caused by Personnel Error.Performance of Hourly Fire Watch Surveillances Stressed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000272/LER-1988-006, :on 880318,10CFR50 App R Cable Design Deficiency Identified.Caused by Design Error.Cable Will Be re-routed During Next Refueling Outage.Roving Fire Watch Will Be Continued Until Completion of Repair |
- on 880318,10CFR50 App R Cable Design Deficiency Identified.Caused by Design Error.Cable Will Be re-routed During Next Refueling Outage.Roving Fire Watch Will Be Continued Until Completion of Repair
| 10 CFR 50.73(a)(2)(vi) 10 CFR 50.73(a)(2) | 05000311/LER-1988-006-02, :on 880421,reactor Trip Occurred.Caused by Maint Technician Not Using Proper Procedure When Repairing Leak on Low Pressure Side of Reactor Coolant Loop 23 Flow Channel II Transmitter.Event Reviewed |
- on 880421,reactor Trip Occurred.Caused by Maint Technician Not Using Proper Procedure When Repairing Leak on Low Pressure Side of Reactor Coolant Loop 23 Flow Channel II Transmitter.Event Reviewed
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000272/LER-1988-007, :on 880323,several Fire Dampers Identified as Not Fire Rated & Duct Sections Penetrating Barriers Found W/O Approved Fire Barrier Coating.Caused by Personnel Error in Engineering Review of Procurement Documents |
- on 880323,several Fire Dampers Identified as Not Fire Rated & Duct Sections Penetrating Barriers Found W/O Approved Fire Barrier Coating.Caused by Personnel Error in Engineering Review of Procurement Documents
| | 05000311/LER-1988-007-02, :on 880422,reactor Trip Occurred Due to Turbine Trip as Result of Steam Generator hi-hi Level.Caused by electro-hydraulic Control (EHC) Equipment Problems.Ehc Rate Amplifier Card Replaced & Successfully Tested |
- on 880422,reactor Trip Occurred Due to Turbine Trip as Result of Steam Generator hi-hi Level.Caused by electro-hydraulic Control (EHC) Equipment Problems.Ehc Rate Amplifier Card Replaced & Successfully Tested
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000272/LER-1988-008, :on 880324,0404 & 15,discovered That Hourly Roving Fire Watches Were Late Between 10 & 32 Minutes for Four Areas.Caused by Personnel Error.Time Period Between Roving Fire Watches Reduced |
- on 880324,0404 & 15,discovered That Hourly Roving Fire Watches Were Late Between 10 & 32 Minutes for Four Areas.Caused by Personnel Error.Time Period Between Roving Fire Watches Reduced
| 10 CFR 50.73(a)(2)(i) | 05000311/LER-1988-008-02, :on 880426,discovered That Valve 2FP147 Not Surveilled.Caused by Personnel Error.Procedure Revised to Address Requirement to Surveill the 2FP147 Valve & 2FP148 Check Valve at Same Time |
- on 880426,discovered That Valve 2FP147 Not Surveilled.Caused by Personnel Error.Procedure Revised to Address Requirement to Surveill the 2FP147 Valve & 2FP148 Check Valve at Same Time
| 10 CFR 50.73(a)(2) | 05000272/LER-1988-009, :on 880330,electro-hydraulic (Eh) Pumps 11 & 12 Failed to Automatically Start.Caused by lo-lo Condition in Eh Control Oil Reservoir.Mechanical Level Indicator Replaced W/Dipstick to Provide Local Level Indication |
- on 880330,electro-hydraulic (Eh) Pumps 11 & 12 Failed to Automatically Start.Caused by lo-lo Condition in Eh Control Oil Reservoir.Mechanical Level Indicator Replaced W/Dipstick to Provide Local Level Indication
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000311/LER-1988-009-02, :on 880513,reactor Trip Occurred.Caused by Control Rod 1D3 Drop Resulting in Negative Rate Trip.Testing for Probable Causes of Control Rod Drop Completed |
- on 880513,reactor Trip Occurred.Caused by Control Rod 1D3 Drop Resulting in Negative Rate Trip.Testing for Probable Causes of Control Rod Drop Completed
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000272/LER-1988-010-01, :on 880519,discovered That Diesel Generator Area Cardox Fire Suppression Sys PE Relay May Not Be Class 1E Seismically Qualified.Caused by Inadequate Design. Procedure Mods Made Re Resetting Relay |
- on 880519,discovered That Diesel Generator Area Cardox Fire Suppression Sys PE Relay May Not Be Class 1E Seismically Qualified.Caused by Inadequate Design. Procedure Mods Made Re Resetting Relay
| 10 CFR 50.73(a)(2)(v)(A), Loss of Safety Function - Shutdown the Reactor | 05000311/LER-1988-010-02, :on 880509,identified That for 37 Electrical Circuits Penetrating Containment,Backup Overcurrent Protection Device Would Not Operate.Caused by Inadequate Design Review.Detailed Calculation Prepared |
- on 880509,identified That for 37 Electrical Circuits Penetrating Containment,Backup Overcurrent Protection Device Would Not Operate.Caused by Inadequate Design Review.Detailed Calculation Prepared
| | 05000272/LER-1988-011-02, :on 880517,monthly Tech Spec Surveillance 4.0.5 for Apr Not Performed for Valve 12SW39.Caused by Personnel Error.Programmatic Review Conducted to Determine Progammatic Improvements Needed |
- on 880517,monthly Tech Spec Surveillance 4.0.5 for Apr Not Performed for Valve 12SW39.Caused by Personnel Error.Programmatic Review Conducted to Determine Progammatic Improvements Needed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000311/LER-1988-011-01, :on 880523,Tech Spec Surveillance 4.7.10.1.1.c Late Due to Inadequate Communications Between Nuclear Fire Dept Supervision & Station Mgt.Ltr Issued to Station Supervision Addressing Adequate Communications |
- on 880523,Tech Spec Surveillance 4.7.10.1.1.c Late Due to Inadequate Communications Between Nuclear Fire Dept Supervision & Station Mgt.Ltr Issued to Station Supervision Addressing Adequate Communications
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000272/LER-1988-012-02, :on 880712,Tech Spec 3.7.9 Noncompliance Involving Missing Snubber Downstream from 1SJ13 Valve Occurred.Caused by Inadequate Administrative Control Over Design Change Work.New Snubber Installed |
- on 880712,Tech Spec 3.7.9 Noncompliance Involving Missing Snubber Downstream from 1SJ13 Valve Occurred.Caused by Inadequate Administrative Control Over Design Change Work.New Snubber Installed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000311/LER-1988-012-01, :on 880618,Tech Spec Action 3.5.2 Entered W/ Both Centrifugal Charging Pumps (CCP) Declared Inoperable. Caused by Individaul CCP Equipment Problems.Ccp Breaker Replaced |
- on 880618,Tech Spec Action 3.5.2 Entered W/ Both Centrifugal Charging Pumps (CCP) Declared Inoperable. Caused by Individaul CCP Equipment Problems.Ccp Breaker Replaced
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000311/LER-1988-013-01, :on 880615,control Room Overhead Annunciator, Sec Trouble Alarm,Annunciated & on 880616,Tech Spec 3.3.2.1.b,Action 13 Entered in Support of 2B Sec Chassis Replacement.Caused by Circuit Boards Failure |
- on 880615,control Room Overhead Annunciator, Sec Trouble Alarm,Annunciated & on 880616,Tech Spec 3.3.2.1.b,Action 13 Entered in Support of 2B Sec Chassis Replacement.Caused by Circuit Boards Failure
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000272/LER-1988-013-02, :on 880812,several Penetration Seals Did Not Conform to Correct Color or Cell Structure as Recommended by Silicone Foam Mfg to Provide Necessary Fire Protection. Caused by Inadequate Procedural Guidance |
- on 880812,several Penetration Seals Did Not Conform to Correct Color or Cell Structure as Recommended by Silicone Foam Mfg to Provide Necessary Fire Protection. Caused by Inadequate Procedural Guidance
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000311/LER-1988-014, :on 880622,reactor Trip & Safety Injection Occurred.Caused by Failure of C Vital Instrument Bus Inverter.Inverter Repaired.Design Change Initiated to Delete Reactor Trip Logic & to Replace Inverters |
- on 880622,reactor Trip & Safety Injection Occurred.Caused by Failure of C Vital Instrument Bus Inverter.Inverter Repaired.Design Change Initiated to Delete Reactor Trip Logic & to Replace Inverters
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000272/LER-1988-014-01, :on 880830,QA Review Identified Several Missed Fire Barrier Penetration Surveillances.Caused by Inadequate Administrative Controls.Work Schedule Reviewed Monthly by Site Protection Supervisor |
- on 880830,QA Review Identified Several Missed Fire Barrier Penetration Surveillances.Caused by Inadequate Administrative Controls.Work Schedule Reviewed Monthly by Site Protection Supervisor
| 10 CFR 50.73(a)(2)(i) | 05000272/LER-1988-015-02, :on 880831,reactor/turbine Trip Occurred Due to Low Auto Stop Oil Sys Pressure.Caused by Equipment Problem. Functional Testing of Various Turbine Trip Mechanisms Completed Satisfactorily |
- on 880831,reactor/turbine Trip Occurred Due to Low Auto Stop Oil Sys Pressure.Caused by Equipment Problem. Functional Testing of Various Turbine Trip Mechanisms Completed Satisfactorily
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000311/LER-1988-015-01, :on 880726,component Cooling HX 21 Declared Inoperable Due to Svc Water Leakage from Downstream Piping Resulting in Inoperability of HX 22.Caused by Equipment Problems.Leakage Repaired |
- on 880726,component Cooling HX 21 Declared Inoperable Due to Svc Water Leakage from Downstream Piping Resulting in Inoperability of HX 22.Caused by Equipment Problems.Leakage Repaired
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000311/LER-1988-016-01, :on 880730,reactor Trip Occurred.Caused by Equipment Problems Associated W/Vital Instrument Bus C Inverter.Design Change to Delete Specified Reactor Trip Logic Initiated |
- on 880730,reactor Trip Occurred.Caused by Equipment Problems Associated W/Vital Instrument Bus C Inverter.Design Change to Delete Specified Reactor Trip Logic Initiated
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000272/LER-1988-016-02, :on 880909,twenty-nine Air Balance Model 119 Dampers in Units 1 & 2 Fire Areas Not Surveilled as Required by Tech Spec.Caused by Inadequate Administrative Controls. Engineers Counseled & Requirements Reviewed |
- on 880909,twenty-nine Air Balance Model 119 Dampers in Units 1 & 2 Fire Areas Not Surveilled as Required by Tech Spec.Caused by Inadequate Administrative Controls. Engineers Counseled & Requirements Reviewed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000272/LER-1988-017, :880919,steam Flow Channels I & II for Steam Generators 12 & 14 & Channel II for Steam Generator 13 Declared Inoperable Due to Low Reading.Cause Not Determined. Steam Flow Channel Recalibr |
- 880919,steam Flow Channels I & II for Steam Generators 12 & 14 & Channel II for Steam Generator 13 Declared Inoperable Due to Low Reading.Cause Not Determined. Steam Flow Channel Recalibr
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000311/LER-1988-017-01, :on 880831,reactor Trip Occurred After Turbine Trip as Result of Steam Generator hi-hi Level.Caused by Design/Equipment Problem Associated w/23BF19 Valve.Maint Requirements Will Be Modified |
- on 880831,reactor Trip Occurred After Turbine Trip as Result of Steam Generator hi-hi Level.Caused by Design/Equipment Problem Associated w/23BF19 Valve.Maint Requirements Will Be Modified
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000272/LER-1988-017-02, :on 880919,Steam Flow Channels I & II for 12 & 14 Steam Generators Declared Inoperable.Channels Were Reading -5% Low.Investigation of Root Cause Continuing.Steam Flow Channels Recalibr |
- on 880919,Steam Flow Channels I & II for 12 & 14 Steam Generators Declared Inoperable.Channels Were Reading -5% Low.Investigation of Root Cause Continuing.Steam Flow Channels Recalibr
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000311/LER-1988-018-01, :on 880914,discovered That Plant Vent Tritium Grab Samples Not Taken Between 880913-15.Refueling Canal Flooded on 880913 in Support of Refueling Efforts.Caused by Inadequate Administrative Controls |
- on 880914,discovered That Plant Vent Tritium Grab Samples Not Taken Between 880913-15.Refueling Canal Flooded on 880913 in Support of Refueling Efforts.Caused by Inadequate Administrative Controls
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000272/LER-1988-018-02, :on 881001,hourly Roving Fire Watch Patrol for Several Areas Not Completed within 1 H (Between 22 & 82 Minutes Late).Caused by Equipment Problem Associated W/ Security Sys Computer.Fire Watch Posted |
- on 881001,hourly Roving Fire Watch Patrol for Several Areas Not Completed within 1 H (Between 22 & 82 Minutes Late).Caused by Equipment Problem Associated W/ Security Sys Computer.Fire Watch Posted
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000272/LER-1988-018, :on 871209,personnel Determined That Lead/Lag & Derivative Amplifiers in Process & Protection Control Sys Incorrectly Calibr.Caused by Procedural Inadequacy. Procedures Revised |
- on 871209,personnel Determined That Lead/Lag & Derivative Amplifiers in Process & Protection Control Sys Incorrectly Calibr.Caused by Procedural Inadequacy. Procedures Revised
| 10 CFR 50.73(a)(2) | 05000272/LER-1988-019-02, :on 880926,discovered That Hourly Roving Fire Watch Patrol for Several Areas Not Completed within H.Caused by Personnel Error.Corrective Disciplinary Action Taken Against Personnel Involved |
- on 880926,discovered That Hourly Roving Fire Watch Patrol for Several Areas Not Completed within H.Caused by Personnel Error.Corrective Disciplinary Action Taken Against Personnel Involved
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000311/LER-1988-019-01, :on 881005,several Tubes Found Degraded in Steam Generator Tubes 22 & 24.Caused by Steam Generator Design.Emergency License Amend Issued to Modify Steam Generator Tube Sampling Method |
- on 881005,several Tubes Found Degraded in Steam Generator Tubes 22 & 24.Caused by Steam Generator Design.Emergency License Amend Issued to Modify Steam Generator Tube Sampling Method
| | 05000272/LER-1988-020-02, :on 881117,two Trains of Engineering Safety Sys Made Inoperable by Common Mode Following Annunciation of Air Particulate Detector Trouble Alarm.Root Cause Attributed to Partially Clogged Bypass Line |
- on 881117,two Trains of Engineering Safety Sys Made Inoperable by Common Mode Following Annunciation of Air Particulate Detector Trouble Alarm.Root Cause Attributed to Partially Clogged Bypass Line
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000272/LER-1988-020, :on 861108,Tech Spec Surveillance 4.7.7.1.a Not Completed within Specified Time.Caused by Personnel Error.Supervisors Counseled About Failure to Take Necessary Steps to Ensure Performance of Surveillance |
- on 861108,Tech Spec Surveillance 4.7.7.1.a Not Completed within Specified Time.Caused by Personnel Error.Supervisors Counseled About Failure to Take Necessary Steps to Ensure Performance of Surveillance
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000311/LER-1988-020-01, :on 881001,fuel Assembly Insert Changeouts in Fuel Handling Building (Fhb) Conducted W/Fhb Exhaust Fan 21 Inoperable.Caused by Personnel Error.Std Tagout of Fhb Ventilation Sys Will Be Prepared |
- on 881001,fuel Assembly Insert Changeouts in Fuel Handling Building (Fhb) Conducted W/Fhb Exhaust Fan 21 Inoperable.Caused by Personnel Error.Std Tagout of Fhb Ventilation Sys Will Be Prepared
| | 05000311/LER-1988-021-01, :on 881031,hourly Roving Fire Watch Patrol for Several Areas Not Completed within 1h.Caused by Personnel Error.Personnel Given Medical Fitness for Duty Exam & Site Protection Dept Mgt Reviewed Event |
- on 881031,hourly Roving Fire Watch Patrol for Several Areas Not Completed within 1h.Caused by Personnel Error.Personnel Given Medical Fitness for Duty Exam & Site Protection Dept Mgt Reviewed Event
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000311/LER-1988-022-01, :on 881022 & 23,visual Exam of Containment Spray Valves 21 & 22CS6 Revealed Cracks in Valve Casting. Cause Attributed to Transgranular Stress Corrosion Cracking. Valves Temporarily Replaced W/Piping Spools |
- on 881022 & 23,visual Exam of Containment Spray Valves 21 & 22CS6 Revealed Cracks in Valve Casting. Cause Attributed to Transgranular Stress Corrosion Cracking. Valves Temporarily Replaced W/Piping Spools
| | 05000311/LER-1988-023-01, :on 880912,discovered That Several Radiation Monitoring Sys Monitors Were Calibr Low Due to Use of Incorrect Calibr Source Response Info.Caused by Inadequate Administrative Controls.Monitors Calibr |
- on 880912,discovered That Several Radiation Monitoring Sys Monitors Were Calibr Low Due to Use of Incorrect Calibr Source Response Info.Caused by Inadequate Administrative Controls.Monitors Calibr
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation | 05000311/LER-1988-024-01, :on 881128,reactor Tripped Due to Inadequate Procedural Guidance Resulting in Equipment Problem. Positioner 23BF19 Repaired & Valve Successfully Stroke Tested |
- on 881128,reactor Tripped Due to Inadequate Procedural Guidance Resulting in Equipment Problem. Positioner 23BF19 Repaired & Valve Successfully Stroke Tested
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000311/LER-1988-025-01, :on 881201,failure to Perform Item from Tech Spec 4.3.2.1.1 as Required Discovered.Caused by Inadequate Administrative Control.Procedure for Changing Modes from Mode 4 to Mode 3 Revised |
- on 881201,failure to Perform Item from Tech Spec 4.3.2.1.1 as Required Discovered.Caused by Inadequate Administrative Control.Procedure for Changing Modes from Mode 4 to Mode 3 Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications |
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