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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] |
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Omaha Public Power District 444 South 16th Street Mall Omaha, Nebraska 68102-2247 402/636-2000 l
February 8, 1991 LIC-91-0008L V. S. Nuclear Regulatory Commission Attn Document Control Desk Mail Station P1-137 Washing'.an, DC 20555 Reference: Docket No. 50-285 Gentlemen:
Subject:
Licensee Event Report 91-01 for the Fort Calhoun Station l
Please find attached Licensee Event Report 91-01 dated February 8, 1991. This I
report is being submitted pursuant to 10 CFR 50.73(a)(2)(i)(B).
If you should have any questions, please contact me.
Sincerely, i
A&. $. $s&r W. G. Gates Division Manager l_
Nuclear Operations WGG/djm Attachent c:
.R. D. Martin, NRC Regional Administrator W. C. Walker, NRC Project Manager R. P. Mullikin, NRC Senior Resident Inspector INP0 Records Center l
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3 504 0 IC 08 MANActutNT AND Dd004T.W ASMINGTON. 0c gesca ed.CILITV NAMG HI DoCEtT seVMet A GI PAGE i3i Fort Calhoun Station Unit No. 1 o i s I o I o l 0 l218 15 1 lod 014 flTLS les Containment Tendon' Surveillance Determined Not In Accordance With Tech. Specifications tytNT DAf t til LER hvMSIRtel ASPORY DAf t til DTH8 R 7 ACILIIlt$ INVOLytO ($l MONTw OAy Vlam vtAR 88,0M ',
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- - On January 9, 1991, with the reactor-in Mode 1 at approximately 26% power, it was determined that prior to the performance of the containment tendon surveillances c
l in~1981 and 1985, the test procedures were changed to reflect the guidance of L
Revision 3 to Regulatory Guide 1.35. Tecanical Specification 3.5(7)a, which j
restrictive relative to detensioning of tendons.
By using guidance not reflected incorporates the guidance in Revision 1 af Regulatory Guide 1.35, is more-l in the Technical Specifications, both these tests failed to completely detension all the required tendons.
This violation of the Technical Specification is reportablepursuantto10CFR50.73(a)(2)(i)(B).
l The root cause for this event was inadequate administrative control of the tendon I,
surveillance program, with inappropriate actions by personnel as a contributing factor.
Corrective actions include: enhancement of station en implementation of a Containment Testing Program Plan;gineering support, including improvements in the safety evaluation process for procedure changes; and submittal of a proposed license amendment to incorporate appropriate Regulatory Guide 1.35, Revision 3 guidance into the Technical Specifications.
l NRC Form 354 L6491
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Fort Calhoun Station Unit No. 1 o ls jo lo lo l2 l 8l5 9l1 0l0 l 1 0p 0l2 0F 0$
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t The containment structure at Fort Calhoun Station Unit No. 1 is a ' reinforced concrete pressure vessel that includes ungrouted prestressing tendons in the domed roof and the walls.
These tendons are stressed to keep the containment concrete internalforces(i.e.,anincreaseincontainmentpressure)gnitudesuchthattheintroduced b in compression. The compressive. forces are of sufficient ma basis accident will be offset by the containment prestressing. This will result in an essentially stress-free containment building during the event.
Tnere are 210 dome tendons and 616 helical wall tendons in the containment structure. The idome tendons are divided into three layers that are mutually inclined at 120 degrees. The wall tendons consist of four layers arranged in a 45 degree helical-3attern-in two directions,--i.e., two right-handed helical and two left-handed 1elical layers.
Each orientation is considered to be a group.
NuclearRegulatoryCommission(NRC)RegulatoryGuide1.35,"InserviceInspection of Ungrouted Tendons =in Prestressed Concrete Containments, Revision 1", dated June
.1974, specified that a tendon liftoff test should include an unloading cycle going
'down-to essentially complete detensioning of the tendon to identify broken or.
damaged wires or strands.
It also stated that for. containments that differ from the typical, the model program. described should serve as a basis for a com) arable inservice inspection program.
The Fort Calhoun containment differs from tie
, typical model.due to the use of the helical wall tendons.
InAugust1974,OmahaPublicPowerDistrict(0 PPD)submittedaFacilityLicense i
Change to the NRC to in' corporate the guidance provided.by Regulatory Guide 1.35, Revision 1, into the Fort Calhoun Technical Specifications.
In August 1975, the requirement for comp btely detensioning each selected tendon was incorporated into the Technical Specifications by License Amendment No. 6.
The 1976 tendon testing.
was completed to this specification.
Technical Specification 3.5(7)a requires that periodic inspections be performed on three dome-tendons, one from each layer, and on three wall tendons of each orientation.
The surveillance requirements for each tendon selected include taking of lift-off readings,. complete.detensioning, and examination for broken l
wires and for any evidence of damage or deterioration of anchor hardware.
.-Additionally, the Specification requires the removal of one wire from each of three-helical tendons and one from.a dome tendon for inspection and testing. This is accomplished after fully detensioning the selected tendons. Following the
- - surveillance, each detensioned tendon-is fully retensioned to at least the average wire stress indicated by the last liftoff reading for that tendon.
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.a - unc w, am,mn In April 1979, the NRC issued for comment Revision 3 of Regulatory Guide 1.35.
This revision proposed the requirement to detension all sample tendons be relaxed to detensin just one tendon per group. The value and im)act section noted that detensioning all the surveillance tendons to look for broien wires "is quite marginal and the cost is high." Revision 3 of Regulatory Guide 1.35 was approved and issued in July 1990.
1 On January 9, 1991, with the reactor in Mode 1 at approximately 26% power, a nonconformance in the tendon surveillance testing program was identified by the Special Services Engineer in charge of the Containment Tendon Testing Program.
It was found that prior to the performance of the tendon surveillance in 1981, the
_ test procedure was changed to reflect the guidance of the proposed Revision 3 of Regulatory Guide 1.35 without having an approved corresponding change incorporated into Technical Specification 3.5(7). The 1985 test was also performed usir.g the guidance in Regulatory Guide 1.35, Revision 3.
By using guidance not reflected in the Technical Specifications, both these tests failed to completely (detension all therequiredtendonsasrequiredbyTechnicalSpecification3.5(7)ai).
This violation of the Technical Specification is reportable pursuant to 10 CFR 50.73(a)(2)(1)(B).
An operability evaluation was subsequently aerformed by Station Engineering. This I
evaluation confirmed that, although the Tec1nical S)ecification requirement to detension all selected tendons was not fulfilled, tie operability of the tendons and the containment structure was not compromised.
Investigation revealed that the engineers assigned to coordinate the 1981 and 1985 surveillances apparently did not realize that Fort Calhoun Station was committed to Revision 1 of Regulatory Guido 1.35 by License Amendment No. 6.
A procedure change to the surveillance test prior to the performance of the 1981 test revised the test to ref'a t the guidance in Revision 3 of the Regulatory Guide.
Prior to the performance of the 1985 test another 3rocedure change was made to incorporate l
the guidance of a vendor procedure into t1e test procedure.
The vendor procedure stated that it satisfied the requirements of Revision 3 of Regulatory Guide 1.35.
Both these procedures changes were approved by the Plant Review Committee.
The root cause for this event was inadequate administrative control of the tendon surveillanco program, with inappropriate actions by personnel as a contributing factor.
Inexperienced engineers were assigned to coordinate the tendon surveillance tests in 1981 and 1985, and they initiated did not fully comply with the Technical Specifications. procedure changes which There was poor turnover of information between the test engineers.
Inadequate review by management, including the Plant Review Committee, allowed approval of changes to the test procedures such that the tests did not meet all the requirements of the Technical Specifications.
1 306A (6491 I
Pones 3BSA U.S. NUCLSA2 kt1ULATGV COteMISSON 1018'E5 4/30/92 LICENSEE EVENT REPORT (LER).
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The results of the tendon testing indicate that the containment prestressing system is not degraded by the failure to detension all the surveillance tendons in the 1981 and 1985 surveillance tests.
Detensioning of tendons is not required to to inspect for degraded wires or anchor hardware.
Since this examination was adequately performed during the performance of the liftoff portion of the surveillance and no problems were found, the operability of the containment prestressing system was never compromised. The surveillance methods used met the guidelines of Regulatory Guide 1.35, Revision 3 which has been approved by the NRC.
It is concluded that there is no safety significance associated with this event.
The following corrective actions have been completed:
(1)
Anoperabilityevaluation(PED-SSE-91-0032, Revision 1 dated January 16, 1991) and root cause analysis were performed by the Special Services Engineer in charge of the Containment Tendon Testing Program.
(2)
The OPPD program for generation and review of nuclear safety evaluations associated with procedure changes has been improved in recent years. This will assure compliance with regulatory guidance.
(3)
Station engineering support has been enhanced with additional personnel and administrative controls. A Programs Development Project was initiated to establish program plans which insure quality, regulatory compliance, and continuity for infrequent tests such as tendon surveillance. The Technical-Specification noncompliance noted in this report was identified during the preparation of the Containment Tendon Testing program plan by the Program-Engineer.
l l
The following corrective actions will be completed:
e (1)
A Facility License Change will be submitted to incorporate ap3ropriate guidance provided by Regulatory Guide 1.35, Revision 3 into t1e Technical
' Specifications. This change will be submitted by June 30, 1991.
(2)
The Containment Testing Program Plan and Basis Document will be completed and issued prior to performance of the next scheduled tendon surveillance.
Therehavebeen-4additionalLER's(87-10,87-37,88-08,and89-02)dealingwith surveillance tests-that did not meet the r"uirements of the Technical Specifications.
. Nac P.r= sesA quei
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05000285/LER-1991-001, :on 910109,determined That Containment Tendon Surveillances Performed in 1981 & 1985 Did Not Reflect Guidance in Tech Specs.Caused by Inadequate Administrative Controls.Testing Program Plan Implemented |
- on 910109,determined That Containment Tendon Surveillances Performed in 1981 & 1985 Did Not Reflect Guidance in Tech Specs.Caused by Inadequate Administrative Controls.Testing Program Plan Implemented
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1) | 05000285/LER-1991-002, :on 901209,ventilation Isolation Actuation Signal Generated by High Alarm on Process Radiation Monitor RM-062.Caused by Accumulation of Noncondensible Gases in Sample Piping.Valve Packing Leak Repaired |
- on 901209,ventilation Isolation Actuation Signal Generated by High Alarm on Process Radiation Monitor RM-062.Caused by Accumulation of Noncondensible Gases in Sample Piping.Valve Packing Leak Repaired
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000285/LER-1991-003, Informs of Extension of Completion Date for Changing Abnormal Operating Procedures & Emergency Operating Procedures to Resolve Containment Penetration M-3 Potential Leak Path Issue,Per 910306 LER 91-003 | Informs of Extension of Completion Date for Changing Abnormal Operating Procedures & Emergency Operating Procedures to Resolve Containment Penetration M-3 Potential Leak Path Issue,Per 910306 LER 91-003 | | 05000285/LER-1991-004, :on 910212,offsite Power Low Signal Outside Design Basis.Caused by Inadequate Mod Design at Time of Performance of Original Degraded Voltage Analysis. Engineering Analysis EA-FC-91-017 Performed |
- on 910212,offsite Power Low Signal Outside Design Basis.Caused by Inadequate Mod Design at Time of Performance of Original Degraded Voltage Analysis. Engineering Analysis EA-FC-91-017 Performed
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000285/LER-1991-005, :on 910228,steam Generator Pressure Indicator B/PIC-905 Declared Inoperable Due Reading Approx 56 Psig Lower than Normal.Caused by Misinterpretation of Affected Ts.Formal Interpretation Will Be Written |
- on 910228,steam Generator Pressure Indicator B/PIC-905 Declared Inoperable Due Reading Approx 56 Psig Lower than Normal.Caused by Misinterpretation of Affected Ts.Formal Interpretation Will Be Written
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000285/LER-1991-006, :on 910305,fire Detection Zone 6 Alarmed in Control Room & Could Not Be Reset.Caused by Inadequate Administrative Control to Assure Mod to XL-3 Panel Properly Reflected in Procedures.Personnel Trained |
- on 910305,fire Detection Zone 6 Alarmed in Control Room & Could Not Be Reset.Caused by Inadequate Administrative Control to Assure Mod to XL-3 Panel Properly Reflected in Procedures.Personnel Trained
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000285/LER-1991-007, :on 910320,480 Volt Circuit Breaker Coordination Outside Design Basis.Caused by Deficiencies in Original Sys Design.Breaker/Fuse Coordination Study to Be Completed & Problems Will Be Corrected |
- on 910320,480 Volt Circuit Breaker Coordination Outside Design Basis.Caused by Deficiencies in Original Sys Design.Breaker/Fuse Coordination Study to Be Completed & Problems Will Be Corrected
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000285/LER-1991-008, Revises Completion Dates for Corrective Actions to Address LER 91-08 Re Inappropriate Surveillance Requirements for RPS Level I Bistables & LER 91-11 Re Pressurizer Pressure Low Signal Setpoints to 921120 & 1231,respectively | Revises Completion Dates for Corrective Actions to Address LER 91-08 Re Inappropriate Surveillance Requirements for RPS Level I Bistables & LER 91-11 Re Pressurizer Pressure Low Signal Setpoints to 921120 & 1231,respectively | | 05000285/LER-1991-009, Corrected Ltr Forwarding LER 91-009-00.Memo Stationery Inadvertently Used Instead of Letterhead Stationery for Cover Ltr | Corrected Ltr Forwarding LER 91-009-00.Memo Stationery Inadvertently Used Instead of Letterhead Stationery for Cover Ltr | 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) | 05000285/LER-1991-010, :on 910517,determined That Auxiliary Steam Piping in Upper Electrical Penetration Room 27 Outside Design Basis.Caused by Lack of Attention to Detail During Initial Drawing Review.Fire Dampers Closed |
- on 910517,determined That Auxiliary Steam Piping in Upper Electrical Penetration Room 27 Outside Design Basis.Caused by Lack of Attention to Detail During Initial Drawing Review.Fire Dampers Closed
| | 05000285/LER-1991-011, :on 910606,mgt Determined Potential Existed for Pressurizer Pressure Instrument Loops to Be Calibrated in Manner Resulting in Inability to Trip Pressurizer Pressure Low Signal within Limits |
- on 910606,mgt Determined Potential Existed for Pressurizer Pressure Instrument Loops to Be Calibrated in Manner Resulting in Inability to Trip Pressurizer Pressure Low Signal within Limits
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000285/LER-1991-012, :on 910620,emergency Diesel Generator Auto Start Occurred Due to Loss of Transformer.Caused by Personnel Error.Relays Labelled for Proper Identification |
- on 910620,emergency Diesel Generator Auto Start Occurred Due to Loss of Transformer.Caused by Personnel Error.Relays Labelled for Proper Identification
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2) | 05000285/LER-1991-013, :on 910626,diesel Generator DG-2 Autostarted During Performance of Surveillance Test,Resulting in Tripping & Locking Out Breaker 1AD1.Caused by Human Error. Event Discussed W/Licensed Operator |
- on 910626,diesel Generator DG-2 Autostarted During Performance of Surveillance Test,Resulting in Tripping & Locking Out Breaker 1AD1.Caused by Human Error. Event Discussed W/Licensed Operator
| 10 CFR 50.73(a)(2) | 05000285/LER-1991-014, :on 910629,radiation Monitor RM-054A Discovered Out of Svc.Caused by Personnel Error.Test OP-ST-SHIFT-0001 Revised to Include check-off When All Radiation Monitors Calibrated |
- on 910629,radiation Monitor RM-054A Discovered Out of Svc.Caused by Personnel Error.Test OP-ST-SHIFT-0001 Revised to Include check-off When All Radiation Monitors Calibrated
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1) | 05000285/LER-1991-015, :on 910710,personnel Declared Radiation Monitor RM-060 Inoperable Due to Flow Totalizer,Located Inside Monitor Cabinet,Not Seismically Mounted.Caused by Inadequacies in Design Process |
- on 910710,personnel Declared Radiation Monitor RM-060 Inoperable Due to Flow Totalizer,Located Inside Monitor Cabinet,Not Seismically Mounted.Caused by Inadequacies in Design Process
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1) | 05000285/LER-1991-016, :on 910711,roll Pin for Diesel Generator Exhaust Damper Linkage Failed.On 910718,crack Discovered in Roll Pin for DG-1 Linkage.On 910802,util Notified That Crack Due to Mfg Defect.Also Reported Per Part 21 |
- on 910711,roll Pin for Diesel Generator Exhaust Damper Linkage Failed.On 910718,crack Discovered in Roll Pin for DG-1 Linkage.On 910802,util Notified That Crack Due to Mfg Defect.Also Reported Per Part 21
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat | 05000285/LER-1991-017, :on 910819,potential for Radiological Release Through Safety Injection Refueling Water Tank Vents Identified as Result of Evaluations Prompted by Similar Industry Events |
- on 910819,potential for Radiological Release Through Safety Injection Refueling Water Tank Vents Identified as Result of Evaluations Prompted by Similar Industry Events
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2) | 05000285/LER-1991-018, :on on 910911,0314,0701,0912 & 900311,side Wall Cracks Discovered in Cells of Station Batteries.Caused by Inadequate Design of Battery Cell Terminal Post Seals. Batteries Replaced |
- on on 910911,0314,0701,0912 & 900311,side Wall Cracks Discovered in Cells of Station Batteries.Caused by Inadequate Design of Battery Cell Terminal Post Seals. Batteries Replaced
| 10 CFR 50.73(a)(2)(ii)(A), Seriously Degraded 10 CFR 50.73(a)(2)(i)(A), Completion of TS Shutdown 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(1) | 05000285/LER-1991-019, :on 910913,approved Procedure Specified Incorrect Position for Valves in Backup Nitorgen Sys.Caused by Inadequate Preparation & Review of 10CFR50.59 SE W/ Procedure Revs.Revised Procedure OI-NG-1 |
- on 910913,approved Procedure Specified Incorrect Position for Valves in Backup Nitorgen Sys.Caused by Inadequate Preparation & Review of 10CFR50.59 SE W/ Procedure Revs.Revised Procedure OI-NG-1
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000285/LER-1991-020, :on 910919,SG Water Containing Approx 2.25 Lbs of Hydrazine Inadvertently Released to Missouri River.Caused by Failure of Procedure OI-FW-6 to Specify Proper Sequence for Performance of Valve Checklist |
- on 910919,SG Water Containing Approx 2.25 Lbs of Hydrazine Inadvertently Released to Missouri River.Caused by Failure of Procedure OI-FW-6 to Specify Proper Sequence for Performance of Valve Checklist
| | 05000285/LER-1991-021, :on 911004,inadvertent Partial Actuation of Containment Isolation Actuation Sys Occurred.Caused by Improper Switch Contact Stackup.Caution Tag Placed on Switch Until Corrective Actions Completed |
- on 911004,inadvertent Partial Actuation of Containment Isolation Actuation Sys Occurred.Caused by Improper Switch Contact Stackup.Caution Tag Placed on Switch Until Corrective Actions Completed
| | 05000285/LER-1991-022, :on on 911009,evaluation Initiated in Response to 910912 Neutron Flux Channel Concerns,Per Rev 2 to Reg Guide 1.97.Caused by Failure to Follow Procedure PED-QP-5. Memo Issued.Also Reported Per Part 21 |
- on on 911009,evaluation Initiated in Response to 910912 Neutron Flux Channel Concerns,Per Rev 2 to Reg Guide 1.97.Caused by Failure to Follow Procedure PED-QP-5. Memo Issued.Also Reported Per Part 21
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | 05000285/LER-1991-023, :on 911022,emergency Response Facilities Computer Sys Taken off-line for Maint Activities & Power Increased to 99.3%.Caused by Failure to Review Appropriate Tech Specs.Precaution Added to Procedure |
- on 911022,emergency Response Facilities Computer Sys Taken off-line for Maint Activities & Power Increased to 99.3%.Caused by Failure to Review Appropriate Tech Specs.Precaution Added to Procedure
| 10 CFR 50.73(a)(2)(i) | 05000285/LER-1991-024, :on 911106,ventilation Isolation Actuation Signal Received When Electrician Removed Wrong Fuse Block from Control Panel.Caused by Personnel Error.Standing Order Revised Re Pulling Fuses or Lifting Leads |
- on 911106,ventilation Isolation Actuation Signal Received When Electrician Removed Wrong Fuse Block from Control Panel.Caused by Personnel Error.Standing Order Revised Re Pulling Fuses or Lifting Leads
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000285/LER-1991-025, :on 911114,determined That Upset & Faulted Loadings on Two Safety Injection Sys Pipe Supports Exceeded Design Capacity of Embedded Unistrut.Caused by Design Deficiency.Piping Supports Modified |
- on 911114,determined That Upset & Faulted Loadings on Two Safety Injection Sys Pipe Supports Exceeded Design Capacity of Embedded Unistrut.Caused by Design Deficiency.Piping Supports Modified
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition 10 CFR 50.73(a)(2)(ii)(8) | 05000285/LER-1991-026, :on 911105,discovered That Senior Reactor Operator Did Not Have Current NRC Medical Exam.Caused by Lack of Single Point Control of NRC Medical Exam Program. Personnel Training Info Sys Upgraded |
- on 911105,discovered That Senior Reactor Operator Did Not Have Current NRC Medical Exam.Caused by Lack of Single Point Control of NRC Medical Exam Program. Personnel Training Info Sys Upgraded
| 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 50.73(a)(2) 10 CFR 50.73(a)(2)(i)(3) | 05000285/LER-1991-027, :Between 911016-1118,abnormal Increases Noted in Reactor Coolant Drain Tank Level.Caused by Opening Test Valve WD-1060 During Sampling.Standing Orders Reviewed & Label Developed for Locked Closed Valves |
- Between 911016-1118,abnormal Increases Noted in Reactor Coolant Drain Tank Level.Caused by Opening Test Valve WD-1060 During Sampling.Standing Orders Reviewed & Label Developed for Locked Closed Valves
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1) | 05000285/LER-1991-028, :on 911201,discovered That Sample Pump for Lab & Radwaste Processing Bldg Exhaust Stack Gas & Iodine Monitors Not Running.Caused by Power Excursion Due to Severe Winter Weather.Design Change Under Review |
- on 911201,discovered That Sample Pump for Lab & Radwaste Processing Bldg Exhaust Stack Gas & Iodine Monitors Not Running.Caused by Power Excursion Due to Severe Winter Weather.Design Change Under Review
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1) | 05000285/LER-1991-029, :on 911202,deficiency Discovered in Personnel Air Lock Leak Rate Testing & Procedure.Caused by Past Inadequate Procedure Change Reviews.All Type B Leak Rate Test Procedures Will Be Reviewed |
- on 911202,deficiency Discovered in Personnel Air Lock Leak Rate Testing & Procedure.Caused by Past Inadequate Procedure Change Reviews.All Type B Leak Rate Test Procedures Will Be Reviewed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000285/LER-1991-030, :on 911210,containment Pressure Reduction Not Terminated When Radiation Monitor RM-060 Removed from Svc. Caused by Breakdown in Written & Verbal Communication & Work Practices.Procedures Revised |
- on 911210,containment Pressure Reduction Not Terminated When Radiation Monitor RM-060 Removed from Svc. Caused by Breakdown in Written & Verbal Communication & Work Practices.Procedures Revised
| 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) | 05000285/LER-1991-031, :on 911216,determined That Connections to Personnel Air Lock Bulkheads for Leak Testing Potentially Outside Original Design Requirements.Caused by Lack of Procedures.Danger Tags Hung on Door |
- on 911216,determined That Connections to Personnel Air Lock Bulkheads for Leak Testing Potentially Outside Original Design Requirements.Caused by Lack of Procedures.Danger Tags Hung on Door
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition |
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