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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000285/LER-1999-002, :on 980910,inadvertent Ventilation Isolation Actuation Signal Occurred While Maint Was Being Performed. Caused by Switch Failure.Key Switch for RM-062 Has Been Replaced.With1999-07-0808 July 1999
- on 980910,inadvertent Ventilation Isolation Actuation Signal Occurred While Maint Was Being Performed. Caused by Switch Failure.Key Switch for RM-062 Has Been Replaced.With
05000285/LER-1999-001, :on 990203,shutdown TS Entry Occurred Due to AFW Pump Inoperability.Caused by Inadequate Procedure. Procedure IC-ST-IA-3009 Was Corrected to Properly Perform Surveillance Test.With1999-03-0505 March 1999
- on 990203,shutdown TS Entry Occurred Due to AFW Pump Inoperability.Caused by Inadequate Procedure. Procedure IC-ST-IA-3009 Was Corrected to Properly Perform Surveillance Test.With
05000285/LER-1998-006, :on 980521,outside Design Basis for LOCA with Plant Shutdown Noted.Caused by Lack of Defined Design Basis for Operability Requirements.Procedures & USAR Will Be Updated to Include Operability Requirements.With1999-01-28028 January 1999
- on 980521,outside Design Basis for LOCA with Plant Shutdown Noted.Caused by Lack of Defined Design Basis for Operability Requirements.Procedures & USAR Will Be Updated to Include Operability Requirements.With
05000285/LER-1998-015, :on 981202,questioned Whether Shift Technical Advisor Position Required to Be Respirator Qualified.Caused by Inadequate Program Design/Description for Establishing. Qualifications Will Be Reviewed.With1999-01-0404 January 1999
- on 981202,questioned Whether Shift Technical Advisor Position Required to Be Respirator Qualified.Caused by Inadequate Program Design/Description for Establishing. Qualifications Will Be Reviewed.With
05000285/LER-1998-016, :on 981204,determined That as Found Configuration of Relays & Covers Did Not Meet Seismic Qualifications for Relays.Cause Cannot Be Determined.Relay Covers Have Been re-installed.With1999-01-0404 January 1999
- on 981204,determined That as Found Configuration of Relays & Covers Did Not Meet Seismic Qualifications for Relays.Cause Cannot Be Determined.Relay Covers Have Been re-installed.With
05000285/LER-1998-014, :on 981021,emergency Temporary Mod Placed Plant in Unanalyzed Condition Re Ventilation Duct.Caused by Inadequate Procedural Control of Emergency Temporary Mod. Plant Procedures Will Be Revised.With1998-11-20020 November 1998
- on 981021,emergency Temporary Mod Placed Plant in Unanalyzed Condition Re Ventilation Duct.Caused by Inadequate Procedural Control of Emergency Temporary Mod. Plant Procedures Will Be Revised.With
05000285/LER-1998-012, :on 980828,inappropriate Approval of Change to H Generation Design Basis Wwas Noted.Caused by Failure to Assess Impact of Proposed USAR Changes.Reviewed & Updated Design Analysis as Needed.With1998-11-10010 November 1998
- on 980828,inappropriate Approval of Change to H Generation Design Basis Wwas Noted.Caused by Failure to Assess Impact of Proposed USAR Changes.Reviewed & Updated Design Analysis as Needed.With
05000285/LER-1998-013, :on 980924,CR Radiological Dose Consequences Was Noted Outside of Design Basis.Cause Not Stated.Upgraded Radiological Consequences Program & Calculations.With1998-10-26026 October 1998
- on 980924,CR Radiological Dose Consequences Was Noted Outside of Design Basis.Cause Not Stated.Upgraded Radiological Consequences Program & Calculations.With
05000285/LER-1998-009, :on 980722,waste Disposal Sys CIV Was Noted Outside Design Basis.Caused by Over Reliance on Contractor Design & Review of Mods.Mods Were Completed to Correct Problem.With1998-09-30030 September 1998
- on 980722,waste Disposal Sys CIV Was Noted Outside Design Basis.Caused by Over Reliance on Contractor Design & Review of Mods.Mods Were Completed to Correct Problem.With
05000285/LER-1998-011, :on 980825,violation of TS on Engineered Safety Sys Equipment Operability Occurred.Caused by Lack of Understanding of All Starting Air Circuit Details.Replaced Caution Tags on DG & Control Panels.With1998-09-24024 September 1998
- on 980825,violation of TS on Engineered Safety Sys Equipment Operability Occurred.Caused by Lack of Understanding of All Starting Air Circuit Details.Replaced Caution Tags on DG & Control Panels.With
05000285/LER-1998-010, :on 930208,violation of TS Re Better Axial Shape Selection Sys Was Noted.Caused by Inoperability of Core Monitoring Program.Alternate Methods Will Be Evaluated. with1998-09-17017 September 1998
- on 930208,violation of TS Re Better Axial Shape Selection Sys Was Noted.Caused by Inoperability of Core Monitoring Program.Alternate Methods Will Be Evaluated. with
05000285/LER-1998-008, :on 980528,noted That Plant Had Operated Outside of Design Basis of AFW Sys Due to Overpressurization of AFW Piping.Caused by Misadjustment of Governor.Installed Mod to Sense Overpressure Condition1998-06-29029 June 1998
- on 980528,noted That Plant Had Operated Outside of Design Basis of AFW Sys Due to Overpressurization of AFW Piping.Caused by Misadjustment of Governor.Installed Mod to Sense Overpressure Condition
05000285/LER-1998-007, :on 980522,TS Violation of ISI Reporting Requirements,Was Noted.Caused by Interpretation of Requirements of 10CFR50.55a(g)(5)(iv) Which Differs from Nrc.Listing of Exams Given to NRC1998-06-22022 June 1998
- on 980522,TS Violation of ISI Reporting Requirements,Was Noted.Caused by Interpretation of Requirements of 10CFR50.55a(g)(5)(iv) Which Differs from Nrc.Listing of Exams Given to NRC
05000285/LER-1998-005, :on 980520,161 Kv Transmission Line Circuit Breakers Tripped.Caused by Inappropriate Actuation of Deluge Sys for Transformer T1A-3.Transformer T1A-3 Was Checked to Ensure No Damage to Transformer Occurred1998-06-19019 June 1998
- on 980520,161 Kv Transmission Line Circuit Breakers Tripped.Caused by Inappropriate Actuation of Deluge Sys for Transformer T1A-3.Transformer T1A-3 Was Checked to Ensure No Damage to Transformer Occurred
05000285/LER-1998-004, :on 980423,determined That Indication in Fort Calhoun Station SG Tube Had Been Identified During 1996 Exams,But Had Been Inadvertently Left in Svc.Caused by Personnel Error.Procedures Revised1998-05-22022 May 1998
- on 980423,determined That Indication in Fort Calhoun Station SG Tube Had Been Identified During 1996 Exams,But Had Been Inadvertently Left in Svc.Caused by Personnel Error.Procedures Revised
05000285/LER-1998-003, :on 980407,violation of TS for Control of High Radiation Area Was Noted.Caused by Inadequate Communication of Mgt Expectations.Expectations of Radiation Area Controls Will Be Given to All Radiation Workers1998-05-0707 May 1998
- on 980407,violation of TS for Control of High Radiation Area Was Noted.Caused by Inadequate Communication of Mgt Expectations.Expectations of Radiation Area Controls Will Be Given to All Radiation Workers
05000285/LER-1998-002, :on 980226,TS Violation Was Noted Due to Exceeding Qualified Life for Plant Components.Caused by Lack of Depth Analysis When Original Calculation Was Performed. a Panel Was Repaired & Returned to Service1998-03-27027 March 1998
- on 980226,TS Violation Was Noted Due to Exceeding Qualified Life for Plant Components.Caused by Lack of Depth Analysis When Original Calculation Was Performed. a Panel Was Repaired & Returned to Service
05000285/LER-1997-017, :on 971107,low Pressure Safety Injection in Unanalyzed Condition Occurred,Due to Potential for Voiding. OPPD Has Administrative Controls in Place to Monitor & Prevent Conditions Necessary for Voiding1998-03-20020 March 1998
- on 971107,low Pressure Safety Injection in Unanalyzed Condition Occurred,Due to Potential for Voiding. OPPD Has Administrative Controls in Place to Monitor & Prevent Conditions Necessary for Voiding
05000285/LER-1998-001, :on 980202,TS Violation Occurred Due to Inadequate Inservice Testing.Caused by Lack of Attention to Detail When FCS ISI Program Plan for 3rd ten-year Interval Was Put Together in 1992.Changes Will Be Made1998-03-0303 March 1998
- on 980202,TS Violation Occurred Due to Inadequate Inservice Testing.Caused by Lack of Attention to Detail When FCS ISI Program Plan for 3rd ten-year Interval Was Put Together in 1992.Changes Will Be Made
05000285/LER-1997-017, :on 971107,LPSI Was in Unanalyzed Condition Due to Potential for Voiding.Caused by Architects Failure to Consider Water Hammer in Designs.Administrative Controls Placed to Monitor & Prevent Conditions1997-12-0808 December 1997
- on 971107,LPSI Was in Unanalyzed Condition Due to Potential for Voiding.Caused by Architects Failure to Consider Water Hammer in Designs.Administrative Controls Placed to Monitor & Prevent Conditions
05000285/LER-1997-016, :on 971029,nuclear Fuel Was Potentially Outside of Mfgs Fuel Design Criteria.Caused by Fuel Clad Gap Reopening.Gap Reopening May Be Predicted for Fcs,Based on Bounding Analysis1997-11-26026 November 1997
- on 971029,nuclear Fuel Was Potentially Outside of Mfgs Fuel Design Criteria.Caused by Fuel Clad Gap Reopening.Gap Reopening May Be Predicted for Fcs,Based on Bounding Analysis
05000285/LER-1997-015, :on 971017,unanalyzed Condition for Station Batteries Was Noted.Caused by Lack of Detailed Plant Design to Provide Supporting Info Re Requirement.Issued Operations Memo1997-11-17017 November 1997
- on 971017,unanalyzed Condition for Station Batteries Was Noted.Caused by Lack of Detailed Plant Design to Provide Supporting Info Re Requirement.Issued Operations Memo
05000285/LER-1997-014, :on 970831,perimeter Microwave Intrusion Alarm on Zone 2 Received in Security Alarm Stations.Caused by Lack of Attention to Detail on Behalf of CAS & SAS Operators. Alarm Station Operators Involved Retrained1997-09-26026 September 1997
- on 970831,perimeter Microwave Intrusion Alarm on Zone 2 Received in Security Alarm Stations.Caused by Lack of Attention to Detail on Behalf of CAS & SAS Operators. Alarm Station Operators Involved Retrained
05000285/LER-1997-013, :on 970826,TS 2.0.1, Motherhood Was Entered Into General Shutdown Voluntarily.Caused by Failed Switch. Replaced & Tested Inverter Switch & Returned Plant to Full Power1997-09-25025 September 1997
- on 970826,TS 2.0.1, Motherhood Was Entered Into General Shutdown Voluntarily.Caused by Failed Switch. Replaced & Tested Inverter Switch & Returned Plant to Full Power
05000285/LER-1997-012, :on 970821,inadvertent Isolation of All Containment Spray Was Discovered.Caused by Operator Error. Operator,Shift Supervisors,Licensed Senior Operators & Licensed Operators Were Disciplined1997-09-22022 September 1997
- on 970821,inadvertent Isolation of All Containment Spray Was Discovered.Caused by Operator Error. Operator,Shift Supervisors,Licensed Senior Operators & Licensed Operators Were Disciplined
05000285/LER-1997-011-01, :on 970819,violation of Tech Specs Due to Inoperability of Radiation Monitor Occurred.Caused by Lack of Depth in Evaluation/Review by Station Personnel. Procedures Will Be Revised1997-09-19019 September 1997
- on 970819,violation of Tech Specs Due to Inoperability of Radiation Monitor Occurred.Caused by Lack of Depth in Evaluation/Review by Station Personnel. Procedures Will Be Revised
05000285/LER-1997-010, :on 970731,violation of TS Occurred While Moving Spent Fuel in Spent Fuel Pool.Caused by Inadequate Design of CEA Locking Clip.Moved Affected Assembly to Region I of Spent Fuel Pool1997-09-0202 September 1997
- on 970731,violation of TS Occurred While Moving Spent Fuel in Spent Fuel Pool.Caused by Inadequate Design of CEA Locking Clip.Moved Affected Assembly to Region I of Spent Fuel Pool
05000285/LER-1997-004, :on 970505,DG Was Outside Design Basis Due to Violation of App R.Mod Was Completed on 970507 to Provide Ability to Isolate CR Located Tachometer from DG-2 Speed Sensing Circuit Prior to Reaching 300 Degrees1997-08-13013 August 1997
- on 970505,DG Was Outside Design Basis Due to Violation of App R.Mod Was Completed on 970507 to Provide Ability to Isolate CR Located Tachometer from DG-2 Speed Sensing Circuit Prior to Reaching 300 Degrees
05000285/LER-1997-008, :on 970616,improper Shift Staffing Due to Inadequate Control of Respirator Spectacle Kits Occurred. Caused by Program for Obtaining Corrective Lenses Inadequate to Ensure Compliance w/10CFR.Manual Revised1997-07-16016 July 1997
- on 970616,improper Shift Staffing Due to Inadequate Control of Respirator Spectacle Kits Occurred. Caused by Program for Obtaining Corrective Lenses Inadequate to Ensure Compliance w/10CFR.Manual Revised
05000285/LER-1997-009, :on 970619,potential Loss of Remote Shutdown Capability Occurred Due to Fire Induced Damage.Caused by Inadequate Design Basis Documentation.Operations Memo Provided Evacuation Criteria1997-07-12012 July 1997
- on 970619,potential Loss of Remote Shutdown Capability Occurred Due to Fire Induced Damage.Caused by Inadequate Design Basis Documentation.Operations Memo Provided Evacuation Criteria
05000285/LER-1997-006, :on 970606,discovered Loss of All Fire Suppression Due to Inoperability of Fire Pumps.Caused by Atypical Set of Operating Circumstances.Procedures Are Being Modified to Prevent Recurrence of Event1997-07-0707 July 1997
- on 970606,discovered Loss of All Fire Suppression Due to Inoperability of Fire Pumps.Caused by Atypical Set of Operating Circumstances.Procedures Are Being Modified to Prevent Recurrence of Event
05000285/LER-1997-005, :on 970530,improper Entry Into High Radiation Area Occurred.Caused by Lack of self-checking & Inattention to Detail.Discussed Event W/Plant Staff & Counseled Individual Involved1997-06-27027 June 1997
- on 970530,improper Entry Into High Radiation Area Occurred.Caused by Lack of self-checking & Inattention to Detail.Discussed Event W/Plant Staff & Counseled Individual Involved
05000285/LER-1997-002, :on 970414,charging Pump CH-1B Declared Inoperable.Caused by Ineffective Communication Re Amend 125 to TS 2.15.Implemented Improved Procedures Re Submittal of License Amend Requests1997-05-14014 May 1997
- on 970414,charging Pump CH-1B Declared Inoperable.Caused by Ineffective Communication Re Amend 125 to TS 2.15.Implemented Improved Procedures Re Submittal of License Amend Requests
05000285/LER-1997-001, :on 970122,main Steam Outside of Design Basis Occurred Due to an Error in Safety Valve Analysis.Guidance Has Been Provided to Operating Staff to Ensure That Design Basis Maintained1997-02-21021 February 1997
- on 970122,main Steam Outside of Design Basis Occurred Due to an Error in Safety Valve Analysis.Guidance Has Been Provided to Operating Staff to Ensure That Design Basis Maintained
05000285/LER-1996-015, :on 961028,improper Fuel Loading Next to Inoperable Wide Range Nuclear Instrument Occurred.Caused by Inadequate procedures.OP-11 Will Be Revised Before 1998 Refueling Outage to Require Reloading1997-01-21021 January 1997
- on 961028,improper Fuel Loading Next to Inoperable Wide Range Nuclear Instrument Occurred.Caused by Inadequate procedures.OP-11 Will Be Revised Before 1998 Refueling Outage to Require Reloading
05000285/LER-1996-016, :on 961220,inadequate Procedural Guidance for Resetting an Engineering Safety Feature Identified.Caused by Lack of Depth in Evaluation.Memorandum Was Issued to Notify Operators of Issue1997-01-21021 January 1997
- on 961220,inadequate Procedural Guidance for Resetting an Engineering Safety Feature Identified.Caused by Lack of Depth in Evaluation.Memorandum Was Issued to Notify Operators of Issue
05000285/LER-1996-014, :on 961117,reactor Cooldown in Excess of Limits Occurred Due to Starting Reactor Coolant pumps.OP-2A & OI-RC-9 Will Be Revised1996-12-17017 December 1996
- on 961117,reactor Cooldown in Excess of Limits Occurred Due to Starting Reactor Coolant pumps.OP-2A & OI-RC-9 Will Be Revised
05000285/LER-1996-013, :on 961116,util Failed to Satisfy Surveillance Requirement for Containment Penetration M-80.Caused by Lack of Complete & Thorough Ca.Review of All Similarly Configured Penetrations Was Conducted1996-12-13013 December 1996
- on 961116,util Failed to Satisfy Surveillance Requirement for Containment Penetration M-80.Caused by Lack of Complete & Thorough Ca.Review of All Similarly Configured Penetrations Was Conducted
05000285/LER-1996-012, :on 961111,potential for Vaporizing Cooling Water in Containment Fan Cooling Units Occurred.Caused by Loop Coincident with Loca.Analyses Have Been Performed1996-12-11011 December 1996
- on 961111,potential for Vaporizing Cooling Water in Containment Fan Cooling Units Occurred.Caused by Loop Coincident with Loca.Analyses Have Been Performed
05000285/LER-1996-011, :on 961030,containment Closure Breached While Moving Fuel.Caused by Failure to Maintain Valves & Follow & Enforce SO-G-20A Requirements.Rev of Policies & Procedures Re Control & Maint of Containment Closure1996-11-27027 November 1996
- on 961030,containment Closure Breached While Moving Fuel.Caused by Failure to Maintain Valves & Follow & Enforce SO-G-20A Requirements.Rev of Policies & Procedures Re Control & Maint of Containment Closure
05000285/LER-1996-009, :on 961017,pressurizer Safety Valves as Found Lift Appeared to Be Outside Acceptance Criteria.Caused by Valve Bonnet Upper Temp Limits Not Specified in Test Procedure.Test Procedure Will Be Revised1996-11-18018 November 1996
- on 961017,pressurizer Safety Valves as Found Lift Appeared to Be Outside Acceptance Criteria.Caused by Valve Bonnet Upper Temp Limits Not Specified in Test Procedure.Test Procedure Will Be Revised
05000285/LER-1996-010, :on 961018,loss of Containment Closure Noted Due to Maint Activity During Refueling.Station Procedures Including OI-CO-4,will Be Reviewed & Revised as Necessary to Ensure Adequate Controls Exist1996-11-18018 November 1996
- on 961018,loss of Containment Closure Noted Due to Maint Activity During Refueling.Station Procedures Including OI-CO-4,will Be Reviewed & Revised as Necessary to Ensure Adequate Controls Exist
05000285/LER-1996-008, :on 961011,ventilation Isolation Actuation Signal Occurred.Due to High Containment Activity.Plant Procedures Will Be Reviewed & Revised1996-11-12012 November 1996
- on 961011,ventilation Isolation Actuation Signal Occurred.Due to High Containment Activity.Plant Procedures Will Be Reviewed & Revised
05000282/LER-1996-018, :on 961010,surveillance of Low Pressure Start of Component Cooling Pumps Was Missed Due to Inadequate Procedure.Procedures Will Be Revised by 970215 to Test Low Pressure auto-start of Component Cooling Pumps1996-11-12012 November 1996
- on 961010,surveillance of Low Pressure Start of Component Cooling Pumps Was Missed Due to Inadequate Procedure.Procedures Will Be Revised by 970215 to Test Low Pressure auto-start of Component Cooling Pumps
05000285/LER-1996-007, :on 961005,unplanned Reactor Protection Sys Actuation Occurred During Plant Cooldown.Caused by Failure to Complete Step in OP-3A as Required.Procedure Revised.W/1996-11-0404 November 1996
- on 961005,unplanned Reactor Protection Sys Actuation Occurred During Plant Cooldown.Caused by Failure to Complete Step in OP-3A as Required.Procedure Revised.W/
05000285/LER-1996-006, :on 951218,all Charging Pumps Disabled.Caused by Inadequate Administrative Control.Guidance Insuring Consistent Interpretation of Affected TSs Issued.Process for Issuing TS Interpretations Revised1996-10-0909 October 1996
- on 951218,all Charging Pumps Disabled.Caused by Inadequate Administrative Control.Guidance Insuring Consistent Interpretation of Affected TSs Issued.Process for Issuing TS Interpretations Revised
05000285/LER-1996-004, :on 960315,discovered Adequate Shutdown Margin Was Not Maintained.Caused by Inadequate Technical Review by Plant Personnel Involved in Reviewing Procedure Change. Appropriate Personnel Trained on Incident1996-06-0303 June 1996
- on 960315,discovered Adequate Shutdown Margin Was Not Maintained.Caused by Inadequate Technical Review by Plant Personnel Involved in Reviewing Procedure Change. Appropriate Personnel Trained on Incident
05000285/LER-1996-002, :on 960329,reactor Manually Tripped Due to Partial Loss of Vacuum in Main Condenser.Condenser Isolated, Plant Shutdown & Leaking Condenser Tube Plugged.Pm Order WP-006820 Will Be Revised1996-04-29029 April 1996
- on 960329,reactor Manually Tripped Due to Partial Loss of Vacuum in Main Condenser.Condenser Isolated, Plant Shutdown & Leaking Condenser Tube Plugged.Pm Order WP-006820 Will Be Revised
05000285/LER-1996-001, :on 960318,containment Ventilation Isolation Signal Occurred Due to High Activity During Purge.Revised Applicable Procedures1996-04-17017 April 1996
- on 960318,containment Ventilation Isolation Signal Occurred Due to High Activity During Purge.Revised Applicable Procedures
05000285/LER-1995-007, :on 951108,potential Tripping of 480 Volt Circuit Breakers W/Digital Reip Units Identified.Caused by Circuit Breaker Component Not Operating as Specified.Issued SA for Operability1996-03-0404 March 1996
- on 951108,potential Tripping of 480 Volt Circuit Breakers W/Digital Reip Units Identified.Caused by Circuit Breaker Component Not Operating as Specified.Issued SA for Operability
1999-07-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data LIC-99-0096, Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With ML20211J9321999-09-0202 September 1999 Safety Evaluation Concluding That Licensee Proposed Alternatives Provide Acceptable Level of Quality & Safety. Proposed Alternatives Authorized for Remainder of Third ten- Yr ISI Interval for Fort Calhoun Station,Unit 1 LIC-99-0084, Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With ML20216E6431999-08-26026 August 1999 Rev 19 to TDB-VI, COLR for FCS Unit 1 ML20210R1961999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fcs,Unit 1 ML20210G2181999-07-27027 July 1999 Safety Evaluation Supporting Amend 192 to License DPR-40 ML20210D9951999-07-22022 July 1999 Safety Evaluation Supporting Amend 191 to License DPR-40 ML20216E6361999-07-21021 July 1999 Rev 18 to TDB-VI, COLR for FCS Unit 1 05000285/LER-1999-002, :on 980910,inadvertent Ventilation Isolation Actuation Signal Occurred While Maint Was Being Performed. Caused by Switch Failure.Key Switch for RM-062 Has Been Replaced.With1999-07-0808 July 1999
- on 980910,inadvertent Ventilation Isolation Actuation Signal Occurred While Maint Was Being Performed. Caused by Switch Failure.Key Switch for RM-062 Has Been Replaced.With
ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20210R2081999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Fcs,Unit 1 LIC-99-0065, Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With ML20210P5461999-06-0808 June 1999 Rev 0,Vols 1-5 of Fort Calhoun Station 1999 Emergency Preparedness Exercise Manual, to Be Conducted on 990810. Pages 2-20 & 2-40 in Vol 2 & Page 4-1 in Vol 4 of Incoming Submittal Not Included ML20195B4581999-05-31031 May 1999 Rev 3 to CE NPSD-683, Development of RCS Pressure & Temp Limits Rept for Removal of P-T Limits & LTOP Requirements from Ts LIC-99-0053, Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 11999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 1 ML20207H7401999-05-31031 May 1999 Performance Indicators Rept for May 1999 ML20195B4521999-05-17017 May 1999 Technical Data Book TDB-IX, RCS Pressure - Temp Limits Rept (Ptlr) ML20206L4241999-05-10010 May 1999 Safety Evaluation Supporting Corrective Actions to Ensure That Valves Are Capable of Performing Intended Safety Functions & OPPD Adequately Addressed Requested Actions Discussed in GL 95-07 ML20206M2601999-05-0606 May 1999 SER Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & IPEEE Results Reasonable Given FCS Design,Operation & History ML20195E8621999-04-30030 April 1999 Performance Indicators, for Apr 1999 LIC-99-0047, Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With ML20205Q5831999-04-15015 April 1999 Safety Evaluation Supporting Amend 190 to License DPR-40 ML20210J4331999-03-31031 March 1999 Changes,Tests, & Experiments Carried Out Without Prior Commission Approval for Period 981101-990331.With USAR Changes Other than Those Resulting from 10CFR50.59 LIC-99-0034, Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With ML20206G2641999-03-31031 March 1999 Performance Indicators Rept for Mar 1999 05000285/LER-1999-001, :on 990203,shutdown TS Entry Occurred Due to AFW Pump Inoperability.Caused by Inadequate Procedure. Procedure IC-ST-IA-3009 Was Corrected to Properly Perform Surveillance Test.With1999-03-0505 March 1999
- on 990203,shutdown TS Entry Occurred Due to AFW Pump Inoperability.Caused by Inadequate Procedure. Procedure IC-ST-IA-3009 Was Corrected to Properly Perform Surveillance Test.With
ML20205J8181999-02-28028 February 1999 Performance Indicators, for Feb 1999 LIC-99-0025, Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With ML20207F3291999-01-31031 January 1999 FCS Performance Indicators for Jan 1999 05000285/LER-1998-006, :on 980521,outside Design Basis for LOCA with Plant Shutdown Noted.Caused by Lack of Defined Design Basis for Operability Requirements.Procedures & USAR Will Be Updated to Include Operability Requirements.With1999-01-28028 January 1999
- on 980521,outside Design Basis for LOCA with Plant Shutdown Noted.Caused by Lack of Defined Design Basis for Operability Requirements.Procedures & USAR Will Be Updated to Include Operability Requirements.With
05000285/LER-1998-016, :on 981204,determined That as Found Configuration of Relays & Covers Did Not Meet Seismic Qualifications for Relays.Cause Cannot Be Determined.Relay Covers Have Been re-installed.With1999-01-0404 January 1999
- on 981204,determined That as Found Configuration of Relays & Covers Did Not Meet Seismic Qualifications for Relays.Cause Cannot Be Determined.Relay Covers Have Been re-installed.With
05000285/LER-1998-015, :on 981202,questioned Whether Shift Technical Advisor Position Required to Be Respirator Qualified.Caused by Inadequate Program Design/Description for Establishing. Qualifications Will Be Reviewed.With1999-01-0404 January 1999
- on 981202,questioned Whether Shift Technical Advisor Position Required to Be Respirator Qualified.Caused by Inadequate Program Design/Description for Establishing. Qualifications Will Be Reviewed.With
ML20203B0991998-12-31031 December 1998 Performance Indicators for Dec 1998 ML20198S3771998-12-31031 December 1998 Safety Evaluation Supporting Amend 189 to License DPR-40 LIC-99-0026, 1998 Omaha Public Power District Annual Rept. with1998-12-31031 December 1998 1998 Omaha Public Power District Annual Rept. with ML20198S4831998-12-31031 December 1998 Safety Evaluation Supporting Amend 188 to License DPR-40 LIC-99-0003, Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With ML20196G2251998-12-18018 December 1998 Rev 2 to EA-FC-90-082, Potential Over-Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment LIC-98-0172, Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With ML20198M3141998-11-30030 November 1998 Performance Indicators Rept for Nov 1998 LIC-98-0160, Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated1998-11-25025 November 1998 Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated 05000285/LER-1998-014, :on 981021,emergency Temporary Mod Placed Plant in Unanalyzed Condition Re Ventilation Duct.Caused by Inadequate Procedural Control of Emergency Temporary Mod. Plant Procedures Will Be Revised.With1998-11-20020 November 1998
- on 981021,emergency Temporary Mod Placed Plant in Unanalyzed Condition Re Ventilation Duct.Caused by Inadequate Procedural Control of Emergency Temporary Mod. Plant Procedures Will Be Revised.With
ML20203B0721998-11-16016 November 1998 Rev 6 to HI-92828, Licensing Rept for Spent Fuel Storage Capacity Expansion 05000285/LER-1998-012, :on 980828,inappropriate Approval of Change to H Generation Design Basis Wwas Noted.Caused by Failure to Assess Impact of Proposed USAR Changes.Reviewed & Updated Design Analysis as Needed.With1998-11-10010 November 1998
- on 980828,inappropriate Approval of Change to H Generation Design Basis Wwas Noted.Caused by Failure to Assess Impact of Proposed USAR Changes.Reviewed & Updated Design Analysis as Needed.With
LIC-98-0154, Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With ML20196G2441998-10-31031 October 1998 Changes,Tests & Experiments Carried Out Without Prior Commission Approval. with USAR Changes Other than Those Resulting from 10CFR50.59 ML20196E4981998-10-31031 October 1998 Performance Indicators Rept for Oct 1998 05000285/LER-1998-013, :on 980924,CR Radiological Dose Consequences Was Noted Outside of Design Basis.Cause Not Stated.Upgraded Radiological Consequences Program & Calculations.With1998-10-26026 October 1998
- on 980924,CR Radiological Dose Consequences Was Noted Outside of Design Basis.Cause Not Stated.Upgraded Radiological Consequences Program & Calculations.With
1999-09-30
[Table view] |
text
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1.
Omaha Public Power District P.O. Dox 399 Hwy 75-North cf Ft Calhoun fort Calhoun, NE 680234399 i
402/636-2000 tebruary 8, 1093 LIC-93-0048 l
9, $ W clear Regulatory Commis for, Att Document Control Desk mao Station PI-137 Washington, DC 20555 Reference: Docket No. 50-285 Gentlement
Subject:
Licensee Event Report 93-001 for the Fort Calhoun Station Please find attached Licensee Event Report 93-001 dated February 8, 1993.
This i
report is being submitted pursuant to 10 CFR 50.73(a)(2)(1)(B).
If you should l
have any questions, please contact me.
Sincerely, NU. k W. G. Gates l
Vice President l
l WGG/jrg Attachment c:
J. L. Milhoan, NRC Regional Administrator, Region IV S. D. Bloom, NRC Project Manager R. P. Mullikin, NRC Senior Resident Inspector INP0 Records Center I
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ABSTRACT (umtt to 1400 spaces. I.e., approximately 15 single spaced typewritten lines) (15) on "B" Boric Acid Storage Tank (BAST)pervisor was reviewing maintenance to be performed On January 8, 1993, the Operations Su levelindication(floatswitchLAS-253)withthe Reactor Engineer. A potential 3roblem was discussed regarding the surveillance requirements for a channel checc. On review, it was identified that the BAST level surveillance was not being properly performed in that the existing surveillance test involved comparing two level indications (local and remote) from the same sensor (level bubbler), rather than comparing two independent sensors as required by Technical Specification (TS) 3.1, Table 3-2, Item IS.a.
The root cause of the event was determined to be an inadecuate surveillance test to monitor the BAST levels. A review of plant records showec that the original 1973 surveillance test incorrectly identified the local and remote indications from the level bubblers as meeting the intent of comparing independent indications.
Tem)orary " sight glasses" have been installed to provide independent level indication at eati tank.
Additional actions will include a modification to control room alarm indication for low BAST level to provide individual annunciator windows for float switches t.AS-260 and t.AS-253 for coigarison to level bubbler indications, we tem m paa,
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.mm % en BACKGROUND The Fort Calhoun Station (FCS) Chemical and Volume Control System (CVCS) includes two concentrated Boric Acid Storage Tanks (BASTS)._ The BAST 1cvels are monitored to ensure that a minimum Technical Specification required volume of boric acid is maintained in theavailabletank(s)toachieveacoldshutdownconditionatanytimeduringcorelife.
Permanent level indication on the BASTS is provided by two independent methods. The first is a level bubbler and transmitter that )rovides both a local indication and a remote (control room) level indication for eaci BAST. The local indicator provides a high level alarm in the control room at 94.2% level. The remote indicator provides alarms in the control room for low level at 80.0% level and low low level at 6.0% level.
L1T/LIA-261 provides indication for the "A" BAST and LIT /LIA-254 provides indication-for the "B" BAST.
The second level indication is an independent float switch for cach BAST that is activated at a level of 82.4%. Annunciator A2, Window C-4U in the control room alarms when a coincident low level is indicated by the float switches on both' BASTS. The float-switches for the "A" and "B" BASTS are LAS-260 and LAS-253 respectively.
FCSTechnicalSpecification(TS)3.1, Table 3-2,"MinimumfrequenciesforChecks, Calibrations and Testing:of Engineered Safety Features,-Instrumentation and Controls",
item 15.a. requires a daily check of " Boric Acid Tank Level".
The surveillance method-
- - specified is to " Compare two independent sensors." This check is addressed by FCS SurveillanceTest(ST)OP-ST-SHIFT-0001,"OperationsTechnicalSpecificationRequired Shift Surveillance".
EVENT DESCRIPTION
On January 7, 1993, while operating in Mode 1 at 100% power, the Operations-Supervisor
'was involved in discussions to determine if on-line maintenance could be performed on the "B" BAST level switch (LAS-253), or if the maintenance should be scheduled during an-
.. outage. The maintenance was required in order to correct a " false" low level signal
--being provided by LAS-253 to the coincident alarm circuitry.
The' TS requirements for BAST level indications were reviewed by the-Operations l Supervisor and a Shift Supervisor.
The level indication at that time concisted of one channel, LIT /LIA-254 (local / remote), on_"B" BAST and two channels, LIT /LIA-261 (local / remote)andLAS-260,on"A" BAST.
This was considered an allowable configuration,-however, it was noted that the loss of one level channel on "A" BAST would put the plant in: a 24-hour Limiting Condition for Operation (LC0).
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.ac, we emn On January 8, 1993, the Operations Supervisor reviewed the issue and its implications with the Reactor Engineer.
The Reactor Engineer expressed concern that a problem could exist with the Surveillance Requirements for a channel check.
On review it was identified that the BAST level surveillance specified that LIT-254 be compared to-LIA-254, and that LIT-261 be compared to LIA-261.
The surveillance method specified in TS 3.1, Table 3-2, Item 15.a is to " Compare two independent sensors".
The ST, therefore,didnotcompare"lndependentsensors",butrathercomparedtwodifferent indicators from the same sensor.
On January 9, 1993, administrative controls were established to maintain "A" BAST at a minimum icvel above the alarm setpoint of LAS-260.
This would allow the level surveillance to be performed on "A" by comparing the indication from LIT /LIA-261 to the.
. alarm condition on Window C-4U, which, due to the continuous low level signal from LAS-253, would now annunciate on a low level-signal from LAS-260.
On January 12, 1993 a temporary modification was installed that would allow monitoring ofbothBASTs'levelslocally. This: modification installed a tem orary " sight glass" on each BAST.- The Auxiliary Building Operator began logging the "si ht glass" level indication every two hours in addition to the local level indicat on.
Surveillance Test OP-ST-SHIFT-000h was then revised to address comparing " sight glass" and bubbler readings.
.This event resulted in the identification of a failure to meet the IS 3.1 requirement
.for a daily comparison of independent sensors of boric acid tank level.
This report is beingsubmittedpursuantto10CFR50.73(a)(2)(1)(B).
SAFETY ASSESSM NT The event did not impact nuclear safety. BAST levels are logged every two hours-and-unexplained trends in level would have been identified by'the. operators..
Similar logs have been taken since before 1977.). An increasing level would provide ind cation ofsa.
1 plugged. bubbler or unexplained BAST in-leakage.
Corrective action would.then be taken to identify and correct the problem.. Historically, the LAS float switches are generally =
a highly reliable method for monitoring a minimum tank level. /. condition resulting in an actual low level, below that needed to reach cold shutdown, would-have been identified by the available instrumentation, a
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The root cause of the event has been determined to be an inadequate surveillance test to monitor the BAST levels. A review of plant records showed that the original 1973 surveillance test incorrectly identified the local and remote indications from the level bubblers (originally designated LIA-254 X & Y and LIA-261 X & Y) as meeting the intent of comparing independent indications.
A 3rinciple contributing factor in this event was found to be that incomplete action was tacen in responding to one corrective action identified in LER 91-008. The LER indicated that each surveillance procedure would be reviewed to ensure they met the intent of TS surveillance requirements.
Individuals were assigned-to review each i
surveillance procedure except OP-ST-SHIFT-0001, which, because of its multiple parts, was to be divided among several reviewers. However, due to an administrative oversight, the intended multi-reviewer review of OP-ST-SHIFT-0001 was not assigned, and therefore was not completed.
CORRECTIVE ACTIONS
The following corrective actions-have been or will be completed:
1.
Temporary Modification 93-005 installed a temporary " sight glass" level indication on each BAST, and OP-ST-SHIFT-0001 was revised to address comparing.
t
" sight glass" and bubbler readings, in order to meet TS 3.1, Table 3-2, Item 15.a.
2.
Surveillance Test OP-ST-SHIFT-0001 has been reviewed and determined to adequately meet _the intent of associated TS surveillance requirements.
3.
Modification MR-FC-93-001 has been initiated to split the current single:
annunciator associated with LAS-260 and LAS-253. The modification will provide each BAST with an individual annunciator window.. Necessary procedure changes, including a-change to OP-ST-SHIFT-0001 to specify LAS-260 and LAS-253 as the independent sensors for comparison to LIT /LIA-261 and LIT /LIA-254-respectively, will be completed when the modification is accepted for operation.
This modification will be installed at the first outage of sufficient duration to support the work, but not later than the~1993 Refueling Outage.
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PREVIOUS SIMILAR EVENTS
.LERs91-008, 91-001,89-002, 88-008,87-037 and 87-010 discuss other events involving surveillance tests that did not meet TS surveillance requirements.
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05000285/LER-1993-001, :on 930108,discovered That Bast Level Surveillance Not Performed Properly.Caused by Inadequate Surveillance Test to Monitor Bast Levels.Mod Initiated to Provide Individual Annunciator Windows |
- on 930108,discovered That Bast Level Surveillance Not Performed Properly.Caused by Inadequate Surveillance Test to Monitor Bast Levels.Mod Initiated to Provide Individual Annunciator Windows
| 10 CFR 50.73(a)(2)(1) | 05000285/LER-1993-002, :on 930122,determined That Current SG LP Signal Block Reset Values Greater than Allowed Ts.Caused by Improper Design.Test Procedures Will Be Revised by 930917 to Specify Desired Value for Block Function |
- on 930122,determined That Current SG LP Signal Block Reset Values Greater than Allowed Ts.Caused by Improper Design.Test Procedures Will Be Revised by 930917 to Specify Desired Value for Block Function
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000285/LER-1993-003, :on 930126,discovered That IST Requirement for Raw Water Pump Not Satisfied.Caused by Inadequate Administrative Controls.Station Engineering Instruction on Surveillance Testing Changed |
- on 930126,discovered That IST Requirement for Raw Water Pump Not Satisfied.Caused by Inadequate Administrative Controls.Station Engineering Instruction on Surveillance Testing Changed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) | 05000285/LER-1993-004, :on 930301,confirmed That Channel D Axial Shape Index (Asi) Being Calculated in Reverse Since 921031-930301 Due to Drawing Discrepancies Associated W/Control Channel B. Temporary Mod 92-078 & Standing Order 0-25 Revised |
- on 930301,confirmed That Channel D Axial Shape Index (Asi) Being Calculated in Reverse Since 921031-930301 Due to Drawing Discrepancies Associated W/Control Channel B. Temporary Mod 92-078 & Standing Order 0-25 Revised
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000285/LER-1993-005, :on 930422,determined That Incident Reportable in That SIRWT Recirculation Piping Associated w/MR-FC-83-046 Used Between Dec 1986 & 1992 Refueling Outage in Unacceptable Configuration |
- on 930422,determined That Incident Reportable in That SIRWT Recirculation Piping Associated w/MR-FC-83-046 Used Between Dec 1986 & 1992 Refueling Outage in Unacceptable Configuration
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) | 05000285/LER-1993-006, :on 930118,Halon Fire Suppression Sys for Switchgear Rooms Disabled to Allow Repair/Replacement of Halon Sys Piping.On 930427,individual Responsible for Fire Watch Not Present.Individual Relieved of Responsibilities |
- on 930118,Halon Fire Suppression Sys for Switchgear Rooms Disabled to Allow Repair/Replacement of Halon Sys Piping.On 930427,individual Responsible for Fire Watch Not Present.Individual Relieved of Responsibilities
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000285/LER-1993-007, :on 930430,unplanned Emergency Generator Start & RT Signal Occurred.Caused by Inadequate Attention to Detail,Labeling of Fuse Drawers,Caution Signs & Training. Labeling & Caution Signs Upgraded |
- on 930430,unplanned Emergency Generator Start & RT Signal Occurred.Caused by Inadequate Attention to Detail,Labeling of Fuse Drawers,Caution Signs & Training. Labeling & Caution Signs Upgraded
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) | 05000285/LER-1993-008, :on 930520,determined That TS SR Not Satisfied for Stack Flow Indicator,Per Amend 137 Issued on 910307. Caused by Lack of Attention to Detail.Calibr & Functional Test Procedures Developed |
- on 930520,determined That TS SR Not Satisfied for Stack Flow Indicator,Per Amend 137 Issued on 910307. Caused by Lack of Attention to Detail.Calibr & Functional Test Procedures Developed
| 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000285/LER-1993-009, Retracts LER 93-009 Re Automatic Start of Both Backup Charging Pumps Due to Spurious Signal & Subsequent Automatic Isolation of Letdown.Event Did Not Involve Train Level ESF Actuation & Not Reportable | Retracts LER 93-009 Re Automatic Start of Both Backup Charging Pumps Due to Spurious Signal & Subsequent Automatic Isolation of Letdown.Event Did Not Involve Train Level ESF Actuation & Not Reportable | 10 CFR 50.73(a)(2)(iv), System Actuation | 05000285/LER-1993-010, :on 930611,1 of 14 Halon Cylinders Did Not Meet Min Pressure Acceptance Criteria Listed in Semiannual Switchgear Rooms Surveillance Test.Caused by Failure of Test to Include Necessary Steps.Cylinder Recharged |
- on 930611,1 of 14 Halon Cylinders Did Not Meet Min Pressure Acceptance Criteria Listed in Semiannual Switchgear Rooms Surveillance Test.Caused by Failure of Test to Include Necessary Steps.Cylinder Recharged
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) | 05000285/LER-1993-011, :on 930624,experienced Reactor Trip Due to Loss of Load.Caused by Lack of Proper Job Planning,Lack of Formal Decision Making Process & Incomplete Communications.Training Will Be Provided to Operations Personnel |
- on 930624,experienced Reactor Trip Due to Loss of Load.Caused by Lack of Proper Job Planning,Lack of Formal Decision Making Process & Incomplete Communications.Training Will Be Provided to Operations Personnel
| 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(viii) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | 05000285/LER-1993-012, :on 930923,identified Condition Involving Five MOVs Having Cables That Were Inadequately Sized Due to Lack of Attention to Detail in Design Package Preparation for 1990 Mod.Thermal Overloads Enabled |
- on 930923,identified Condition Involving Five MOVs Having Cables That Were Inadequately Sized Due to Lack of Attention to Detail in Design Package Preparation for 1990 Mod.Thermal Overloads Enabled
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000285/LER-1993-013, :on 931002,discovered That as-found Lift Setting Pressure of Pressurizer Safety Valve (Psv) RC-141 Outside Specified Lift Setting Acceptance Criterion.Caused by Normal Setpoint Drift.Psv RC-141 Adjusted |
- on 931002,discovered That as-found Lift Setting Pressure of Pressurizer Safety Valve (Psv) RC-141 Outside Specified Lift Setting Acceptance Criterion.Caused by Normal Setpoint Drift.Psv RC-141 Adjusted
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(3) | 05000285/LER-1993-014, :on 930926,PORV PCV-102-1 Inadvertently Opened During Test.Caused by Improper Valve Maint During 1984 Mod. C/A:Pcv Refurbished & Tested |
- on 930926,PORV PCV-102-1 Inadvertently Opened During Test.Caused by Improper Valve Maint During 1984 Mod. C/A:Pcv Refurbished & Tested
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(1) | 05000285/LER-1993-015, :on 931109,emergency Boration of RCS Was Initiated Due to Induced Electrical Noise.Performed Maint on WR Nuclear Instrumentation Channels a & D |
- on 931109,emergency Boration of RCS Was Initiated Due to Induced Electrical Noise.Performed Maint on WR Nuclear Instrumentation Channels a & D
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | 05000285/LER-1993-016, :on 931113,CEA Withdrew from Reactor Core & Rod 31 Became Fully Withdrawn.Caused by Lack of Ground Detection Sys for Associated Power Supplies.Ground Detection for CRD Power Supply Installed |
- on 931113,CEA Withdrew from Reactor Core & Rod 31 Became Fully Withdrawn.Caused by Lack of Ground Detection Sys for Associated Power Supplies.Ground Detection for CRD Power Supply Installed
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000285/LER-1993-017, :on 931116,time Delay Relays for Offsite Power Low Signal (Opls) Found Out of Tolerence Due to Inadequate Technical Review of Calibr Procedures for Opls Circuitry. Opls Calibr Procedures Revised |
- on 931116,time Delay Relays for Offsite Power Low Signal (Opls) Found Out of Tolerence Due to Inadequate Technical Review of Calibr Procedures for Opls Circuitry. Opls Calibr Procedures Revised
| 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) 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000285/LER-1993-018, :on 931206,reactor Trip Occurred Due to Turbine Trip on Low Hydraulic Fluid Pressure.Caused by Inadequate Design of ECN 93-162.Configuration of EHC Sys Tubing Corrected |
- on 931206,reactor Trip Occurred Due to Turbine Trip on Low Hydraulic Fluid Pressure.Caused by Inadequate Design of ECN 93-162.Configuration of EHC Sys Tubing Corrected
| 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000285/LER-1993-019, :on 931209,AFW Pumps Rendered Inoperable Due to Inappropriate Testing Lineup.Surveillance Test SE-ST-AFW-3005 Will Be Revised |
- on 931209,AFW Pumps Rendered Inoperable Due to Inappropriate Testing Lineup.Surveillance Test SE-ST-AFW-3005 Will Be Revised
| 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)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(B) | 05000285/LER-1993-020, :on 931229,toxic Gas Monitor (Tgm) Rendered Inoperable When Tgm Ran Out of Chemically Impregnated Paper Tape Due to Failure to Complete Procedural Requirements. Briefings Held W/Operating Crews |
- on 931229,toxic Gas Monitor (Tgm) Rendered Inoperable When Tgm Ran Out of Chemically Impregnated Paper Tape Due to Failure to Complete Procedural Requirements. Briefings Held W/Operating Crews
| 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) |
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