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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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On January 25, 1988, a locked but improperly latched door to the waste disposal filtering room (a Very High Radiation Area) was discovered by the licensee at 1620 (CST). The plant was in Mode 1, at approximately 100 percent power at the time of i
the event.
Radicactive waste technicians entered the waste disposal filtering room, Poom 11, at 1400 (CST) to check for the presence of expended filters.
The spent filters j
were then transferred to another room to be prepared for off-site shipping.
It is i
believed that no unauthorized personnel entered Room 11 prior to the licensee discovering the locked but unlatched door approximately 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> after the room was accessed.
It was further concluded that the door was not properly secured upon completion of the aforementioned work in Room 11 at 1420 (CST).
To prevent future occurrences, changes have been made to the Radiation Protection Manual requiring the shift health physics technician to perform a documented security check ensuring doors to very high radiation areas are properly locked.
Dual verification is required to ensure the door is properly secured after entries.
Padlocks have been added to doors which presently allow entrance into a very high radiation areas.
New latch bolt monitors will be added to the doors to these areas outside containment by September 1, 1988 with alarm annunciation at the security panel available upon completion of modifications to the security computer on December 31, 1988.
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s-Fort Calhoun Station, Unit No, 1 olsloIeIo 121815 81 8 01011 0 10 0l2 0Fl 013 On January 25, 1988, a locked but improperly latched door to the waste disposal filtering room (a Very High Radiation Area) was discovered by the licensee at 1620 (CST).
The plant was in Mode 1, at approximately 100 percent power at the time of the event.
Technical Specification 5.11.2 requires that radiation areas in which the intensity of radiation is greater than 1000 mrem /hr (a very high radiation area) shall meet all requirements of a radiation area as described in Technical Specification 5.11.1.
In addition, locked doors shall be provided to prevent unauthorized entry into these areas and the key maintained under the administrative control of the Shift Supcrvisor on duty and/or the Plant llealth Physicist where lockable enclosures exist.
Radioactive waste technicians entered the waste disposal filter room, Room 11, at 1400 (CST) to check for the presence of expended filters.
Upon finding spent filters, a radiological survey was performed using a teletector from the door entrance.
Radioactive waste technicians at Fort Calhoun meet ANSI 18.1 qualifications for health physics technicians. Upon completing the radiation survey, the technicians exited the room and allowed the door to close.
Assisting Radioactive Waste Technicians then donned face masks and removed the spent filters from Room 11 through an alternate door which connects to Room 11A, the Waste Disposal Deminerializer Room.
The spent filters were bagged and placed in Room llA.
The alternate door used to transfer the spent filters to Room 11A was then properly locked and all radioactive waste personnel left the area at 1420 (CST).
Radioactive waste technicians returned to the area at 1500 (CST) after preparing Room 67, the Hot Shop, for transfer of the spent filters from Rcom llA. After the filter transfer was completed, Room 67 was secured.
A visual inspection by two Radioactive waste technicians was made as they passed Room 11 and the door appeared tc be secured.
At 1620 (CST), a station operator while performing his first round routine checks found the uniatched door.
Immediate notification was made to the Shift Supervisor.
Mmediate actions were taken by the Supervisor of Chemical and Radiation Protection and the Plant Health Physicist directing the shift health physics technician to physically verify all doors to very high radiation areas outside containment were properly secured.
Red H.P. padlocks utilized at Fort Calhoun for which the Plant Health Physicist and the Shift supervisor on duty have complete accountability of the keys, were installed on the Room 11 and several other doors that allow entry into very high radiation areas.
Further investigation revealed the door had been checked locked and secure by the shift health physics technician at 0800 (CST) the same day.
No keys to open the Room 11 door had been signed out prior to the door being opened at 1400 (CST).
When the door was opened at 1400 (CST) the key was required to gain entrance into the room.
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General Employee Training instructs individuals that continuous H.P. coverage is required upon entering a very high radiation area and to obey all signs posted. Based on OPPD's review of this incident, it is believed that no one entered this room during the time period the door was not properly secured.
To prevent future c.ccurrences, changes have been made to the Radiation Protection Manual requiring the shift health physics technician to perform a documented physical check every four hours to ensure all doors to very hich radiation areas are properly locked. After any entry into a very high radiation area has been completed, a qualified health physics technician will check the very high radiation area door and ensure that it is closed, latched, locked and performing its intended barrier function.
Entry into a very high radiation area, with the exception of emergency operator entry, requires continuous coverage by a qualified health physics technician. The second individual may or may not cro.ss the Very High Radiation Area boundary, consistent with the ALARA program, but must maintain communication while ;ne or both remain in the area.
One of the individuals accompanying the health physics technician into the very high radiation area wil.1 also check the very high radiation area door and ensure that it is closed, latched, locked and performing its intended barrier function.
Hasps or equivalent equipment and red H.P. padlocks have been at' ached to present doors which allow entrance into a very high radiation area.
New signs will be posted that "H.P. Technician Must Be Present for Entry," 'Two Persor.ael Required for Entry," and "FC-647 Form Must Be Completed Upon Exit' on doors of i
this nature.
A modification to inttail new latch bolt monitors on entrance dours to very high radiation areas outside.of containment will be completed no later than September 1, 1988. The latch bolt monitor will serve as supervisory circuitry and will provide positive indication of the latching of doors to very high
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radiation areas.
This capability will be available by December 31, 1988 upon completion of modifications to the security comnuter. Until the new bolt latch monitors are installed, both the hetith physics technician and the second individual will verify the locked status of the door to a Very High Radiation Area on a Very High Radiation Area Verification Check Form, FC-647.
These changes are in addition to the corrective actions previously provided in LER 87-026.
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i
Omaha Public Power District 1623 Harney Omaha, Nebraska 68102 402/536 4000 February 22, 1988 LIC-88-0Cl U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Reference: Docket No. 50-285 Gentlemen:
SUBJECT:
Licensee Event Report for the Fort Calhoun Station Please find attached Licensee Event Report 88-001 dated February 22, 1988.
This report is being submitted per requirements of 10 CFR 50.73.
Sincerely, A
R. L. Andrews Divisien Manager Nuclear Production RLA/me Attachment c:
R. D. Hartin, NRC Regional Administrator A. Bournia, NRC Project Manager P. H. Harrell, NRC Senior Resident Inspector INP0 Records Center American Nuclear Insurers 45$124 r mploymeN w ith (Qual Opportumty Male Female
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05000285/LER-1988-001, :on 880125,discovered Locked But Improperly Latched Door to Waste Disposal Filtering Room (Very High Radiation Area).Caused by Inadequate Security Check.Changes Made to Radiation Protection Manual |
- on 880125,discovered Locked But Improperly Latched Door to Waste Disposal Filtering Room (Very High Radiation Area).Caused by Inadequate Security Check.Changes Made to Radiation Protection Manual
| | 05000285/LER-1988-002, :on 880125,high Pressure Safety Injection Isolation Valve Declared Inoperable.Caused by Failure to Meet Design Criteria for Operability.Temporary Mechanical Jumper Installed to Bypass Air Intensifier |
- on 880125,high Pressure Safety Injection Isolation Valve Declared Inoperable.Caused by Failure to Meet Design Criteria for Operability.Temporary Mechanical Jumper Installed to Bypass Air Intensifier
| | 05000285/LER-1988-003, :on 880205,key Control to Very High Radiation Areas Inadequate.Cause Not Stated.Red Health Physics Padlocks Added to Doors Barring Access to Very High Radiation Areas |
- on 880205,key Control to Very High Radiation Areas Inadequate.Cause Not Stated.Red Health Physics Padlocks Added to Doors Barring Access to Very High Radiation Areas
| | 05000285/LER-1988-004, :on 880311,determined That Instrument Air Valve PCV-1849 Did Not Meet Containment Isolation Criteria Specified in Updated Sar.Cause Not Stated.Procedure Changes Made to Reflect Need to Close Valve |
- on 880311,determined That Instrument Air Valve PCV-1849 Did Not Meet Containment Isolation Criteria Specified in Updated Sar.Cause Not Stated.Procedure Changes Made to Reflect Need to Close Valve
| | 05000285/LER-1988-005, :on 880309,discovered Condition in Which Specific LOCA Could Incapacitate Instrumentation Feeding Protective Function,Resulting in Loss of Pressurizer Pressure Transmitters Following Spray Break |
- on 880309,discovered Condition in Which Specific LOCA Could Incapacitate Instrumentation Feeding Protective Function,Resulting in Loss of Pressurizer Pressure Transmitters Following Spray Break
| | 05000285/LER-1988-005-01, :on 880612,reactor Trip Occurred on Generated lo-lo Steam Generator Level Received from Steam Generator 32.Caused by Failure of Smoothing Orifice Relief Device in Westinghouse Main Turbine.Orifice Repaired |
- on 880612,reactor Trip Occurred on Generated lo-lo Steam Generator Level Received from Steam Generator 32.Caused by Failure of Smoothing Orifice Relief Device in Westinghouse Main Turbine.Orifice Repaired
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000285/LER-1988-006, :on 880315,discovered That Surveillance Test ST-DC-1 F.1, Station Batteries Not Completed During Jan 1988.Caused by Faulty Test Program Design.Test Will Be Manually Scheduled for Same Date Each Month |
- on 880315,discovered That Surveillance Test ST-DC-1 F.1, Station Batteries Not Completed During Jan 1988.Caused by Faulty Test Program Design.Test Will Be Manually Scheduled for Same Date Each Month
| | 05000285/LER-1988-007, :on 880323,Emergency Diesel Generator D-2 Tripped Resulting in Autostart of Emergency Diesel Generator D-1.Caused by Operator Error.Usar Section 6 Revised |
- on 880323,Emergency Diesel Generator D-2 Tripped Resulting in Autostart of Emergency Diesel Generator D-1.Caused by Operator Error.Usar Section 6 Revised
| | 05000285/LER-1988-008, :on 870503,12 Spray Heads on Containment Spray Sys Not Inspected Per Surveillance Test ST-NZ-1 within Required Time Interval.Effect of Potentially Disabled Heads on Containment Spray Headers Will Be Evaluated |
- on 870503,12 Spray Heads on Containment Spray Sys Not Inspected Per Surveillance Test ST-NZ-1 within Required Time Interval.Effect of Potentially Disabled Heads on Containment Spray Headers Will Be Evaluated
| | 05000285/LER-1988-009, :on 880406,investigation Concluded Identifying Concerns Re Capability of Listed Valves to Perform Design Function During Dba.Efforts Made to Find Alternative Method of Performing Affected Valve Functions |
- on 880406,investigation Concluded Identifying Concerns Re Capability of Listed Valves to Perform Design Function During Dba.Efforts Made to Find Alternative Method of Performing Affected Valve Functions
| | 05000285/LER-1988-010, :on 880415,inoperable Check Valves on Safety Injection & Refueling Water Tank Bubblers Discovered.Caused by Inability of Valves to Hold back-pressure as Designed. Check Valves Replaced & New Valves Tested |
- on 880415,inoperable Check Valves on Safety Injection & Refueling Water Tank Bubblers Discovered.Caused by Inability of Valves to Hold back-pressure as Designed. Check Valves Replaced & New Valves Tested
| | 05000285/LER-1988-011, :on 880327,containment Integrity Lost Because Swagelok Cap on PC-743 Test Tee Removed for Leak Rate Testing Not Reinstalled Until Discovered on 880419.Caused by Inadequate Procedure.Procedure Upgraded |
- on 880327,containment Integrity Lost Because Swagelok Cap on PC-743 Test Tee Removed for Leak Rate Testing Not Reinstalled Until Discovered on 880419.Caused by Inadequate Procedure.Procedure Upgraded
| | 05000285/LER-1988-012, :on 880428,discovered That Special Rept on Fire Barrier Inoperability Not Submitted,Per Tech Spec 5.9.3. Caused by Maint Order Not Properly Tracked & Inadequate Procedure Controls.Procedures Changed |
- on 880428,discovered That Special Rept on Fire Barrier Inoperability Not Submitted,Per Tech Spec 5.9.3. Caused by Maint Order Not Properly Tracked & Inadequate Procedure Controls.Procedures Changed
| | 05000285/LER-1988-013, :on 880509,Channel C Reactor Coolant Low Flow Trip Setpoint Found to Be Out of Tolerance Low.Caused by Failed Power Supply to Trip Unit.Supply Replaced,Unit Returned to Operability & Memo Issued |
- on 880509,Channel C Reactor Coolant Low Flow Trip Setpoint Found to Be Out of Tolerance Low.Caused by Failed Power Supply to Trip Unit.Supply Replaced,Unit Returned to Operability & Memo Issued
| | 05000285/LER-1988-014, :on 880518,emergency Diesel Generator D-2 Tripped Resulting in auto-start of Emergency Diesel Generator D-1.Caused by Failure of Fuse.Fuse Replaced |
- on 880518,emergency Diesel Generator D-2 Tripped Resulting in auto-start of Emergency Diesel Generator D-1.Caused by Failure of Fuse.Fuse Replaced
| | 05000285/LER-1988-015, :on 880621,redundant Component Cooling Water Pump AC-3A Inadvertently Started During Breaker Testing. Pump Shut Down & Control Switch Placed in pull-to-lock Position to Prevent Restarting |
- on 880621,redundant Component Cooling Water Pump AC-3A Inadvertently Started During Breaker Testing. Pump Shut Down & Control Switch Placed in pull-to-lock Position to Prevent Restarting
| | 05000285/LER-1988-016, :on 880629,discrepancies Identified in Cycle 11 Setpoint Analysis Affecting Tech Specs Figures 1-3 & 2-6. Caused by Misunderstanding W/Staff.Operations Memo Issued & Proposed Changes to Tech Specs Prepared |
- on 880629,discrepancies Identified in Cycle 11 Setpoint Analysis Affecting Tech Specs Figures 1-3 & 2-6. Caused by Misunderstanding W/Staff.Operations Memo Issued & Proposed Changes to Tech Specs Prepared
| | 05000285/LER-1988-017, :on 880708,discovered That Special Rept on Fire Barrier Inoperability,Required by Tech Spec 5.9.3,not Submitted.Caused by Lack of Procedural Responsibilities & Controls for Fire Protection |
- on 880708,discovered That Special Rept on Fire Barrier Inoperability,Required by Tech Spec 5.9.3,not Submitted.Caused by Lack of Procedural Responsibilities & Controls for Fire Protection
| | 05000285/LER-1988-018, :on 880704,failure to Conduct Surveillance Test within Prescribed Interval Occurred.Test Performed on 880711.Cause to Be Investigated.Procedure Will Be Revised |
- on 880704,failure to Conduct Surveillance Test within Prescribed Interval Occurred.Test Performed on 880711.Cause to Be Investigated.Procedure Will Be Revised
| | 05000285/LER-1988-019, :on 880816,analysis of Design Basis of Diesel Generator Revealed Circuitry Could Not Be Isolated.Power Breaker to Damper Circuitry Opened & Emergency Control Room Evacuation Procedure Changed |
- on 880816,analysis of Design Basis of Diesel Generator Revealed Circuitry Could Not Be Isolated.Power Breaker to Damper Circuitry Opened & Emergency Control Room Evacuation Procedure Changed
| | 05000285/LER-1988-020, :on 880903,diesel Oil Storage Tank 7 Day Run Capacity Requirement Exceeded.Review of Design Basis Determined Amount of Diesel Fuel Required.Revised Emergency Planning Procedure to Provide Guidance |
- on 880903,diesel Oil Storage Tank 7 Day Run Capacity Requirement Exceeded.Review of Design Basis Determined Amount of Diesel Fuel Required.Revised Emergency Planning Procedure to Provide Guidance
| | 05000285/LER-1988-021, :on 880902,determined That Control Room Panels W/O Smoke Detectors.Maint Order 88393 Issued to Install Smoke Detectors in Panels |
- on 880902,determined That Control Room Panels W/O Smoke Detectors.Maint Order 88393 Issued to Install Smoke Detectors in Panels
| | 05000285/LER-1988-022, :on 880909,discovered That Special Rept Re Removal of Electric Latching Mechanism for Fire Door Not Issued.Caused by Inadequate Tracking of Maint Orders. Personnel Training Implemented |
- on 880909,discovered That Special Rept Re Removal of Electric Latching Mechanism for Fire Door Not Issued.Caused by Inadequate Tracking of Maint Orders. Personnel Training Implemented
| | 05000285/LER-1988-023, :on 880928,3 of 10 MSIVs Failed to Lift in Violation of Tech Spec Operability Requirements.Valves Shipped to Independent Testing Lab for Testing & Possible Refurbishment |
- on 880928,3 of 10 MSIVs Failed to Lift in Violation of Tech Spec Operability Requirements.Valves Shipped to Independent Testing Lab for Testing & Possible Refurbishment
| | 05000285/LER-1988-024, :on 881003,emergency Diesel Generator Automatically Started Due to Apparent Momentary Low Voltage Condition on 4160 Volt Bus.Cause Inconclusive.Circulating Water Pump Restarted & Shutdown |
- on 881003,emergency Diesel Generator Automatically Started Due to Apparent Momentary Low Voltage Condition on 4160 Volt Bus.Cause Inconclusive.Circulating Water Pump Restarted & Shutdown
| | 05000285/LER-1988-026, :on 881014,emergency Diesel Generator 2 Automatically Started to Idle Speed.Caused by Personnel Error Compounded by Procedure Inadequacy.Relay Work Scheduled During Bus or Equipment Outages |
- on 881014,emergency Diesel Generator 2 Automatically Started to Idle Speed.Caused by Personnel Error Compounded by Procedure Inadequacy.Relay Work Scheduled During Bus or Equipment Outages
| | 05000285/LER-1988-027, :on 881020,steamfitter Disabled by Heat Exhaustion After Exiting Steam Generator.Caused by Contamination of Protective Clothing.First Aid Provided & Victim Taken to Hosp for Medical Treatment |
- on 881020,steamfitter Disabled by Heat Exhaustion After Exiting Steam Generator.Caused by Contamination of Protective Clothing.First Aid Provided & Victim Taken to Hosp for Medical Treatment
| | 05000285/LER-1988-028, :on 881020,failure of YCV-1045A Instrument Air Check Valve.Caused by a Metal Particle Lodged in Valve Seat.Air Check Valve Bench Tested & Successfully Passed |
- on 881020,failure of YCV-1045A Instrument Air Check Valve.Caused by a Metal Particle Lodged in Valve Seat.Air Check Valve Bench Tested & Successfully Passed
| | 05000285/LER-1988-030, :on 880929,two Hourly Fire Door Patrols Not Performed.Caused by Security Personnel Being Reassigned to Area Considered to Be of Greater Priority.Security Bulletin Issued & Procedure Revised |
- on 880929,two Hourly Fire Door Patrols Not Performed.Caused by Security Personnel Being Reassigned to Area Considered to Be of Greater Priority.Security Bulletin Issued & Procedure Revised
| | 05000285/LER-1988-031, :on 881029,bus-tie Breaker (BT-1B4C) Tripped Open & de-energized 480 Volt Buses 1B3C & 1B3C-4C.Caused by Excessive Loading of Buses 1B3C & 1B3C-4C.Procedure Change to OI-EE-2B Made to Caution Operators |
- on 881029,bus-tie Breaker (BT-1B4C) Tripped Open & de-energized 480 Volt Buses 1B3C & 1B3C-4C.Caused by Excessive Loading of Buses 1B3C & 1B3C-4C.Procedure Change to OI-EE-2B Made to Caution Operators
| | 05000285/LER-1988-032, :on 881101,safety Injection/Containment Spray Recirculation Piping Design Deficiency Noted.Caused by Design Deficiency in Recirculation Header.Miniflow Test of Safety Injection Pumps Performed |
- on 881101,safety Injection/Containment Spray Recirculation Piping Design Deficiency Noted.Caused by Design Deficiency in Recirculation Header.Miniflow Test of Safety Injection Pumps Performed
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | 05000285/LER-1988-037, :on 881214,one of Two Supply Headers Supplying Fire Suppression Headers in Auxiliary Bldg Isolated.Caused by Lack of Procedural Guidance & Inadequate Procedural Controls.Standing Order G-58 Will Be Revised |
- on 881214,one of Two Supply Headers Supplying Fire Suppression Headers in Auxiliary Bldg Isolated.Caused by Lack of Procedural Guidance & Inadequate Procedural Controls.Standing Order G-58 Will Be Revised
| 10 CFR 50.73(a)(2)(1) | 05000285/LER-1988-038, :on 881231,ESF Actuation Occurred W/Technician Working on Mod to Pressurizer Level Instrumentation Behind Control Panels CB-1/2/3.Affected Sys Returned to Svc & Containment Purge Restarted |
- on 881231,ESF Actuation Occurred W/Technician Working on Mod to Pressurizer Level Instrumentation Behind Control Panels CB-1/2/3.Affected Sys Returned to Svc & Containment Purge Restarted
| 10 CFR 50.73(a)(2)(iv), System Actuation |
|