|
---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000285/LER-1999-002, :on 980910,inadvertent Ventilation Isolation Actuation Signal Occurred While Maint Was Being Performed. Caused by Switch Failure.Key Switch for RM-062 Has Been Replaced.With1999-07-0808 July 1999
- on 980910,inadvertent Ventilation Isolation Actuation Signal Occurred While Maint Was Being Performed. Caused by Switch Failure.Key Switch for RM-062 Has Been Replaced.With
05000285/LER-1999-001, :on 990203,shutdown TS Entry Occurred Due to AFW Pump Inoperability.Caused by Inadequate Procedure. Procedure IC-ST-IA-3009 Was Corrected to Properly Perform Surveillance Test.With1999-03-0505 March 1999
- on 990203,shutdown TS Entry Occurred Due to AFW Pump Inoperability.Caused by Inadequate Procedure. Procedure IC-ST-IA-3009 Was Corrected to Properly Perform Surveillance Test.With
05000285/LER-1998-006, :on 980521,outside Design Basis for LOCA with Plant Shutdown Noted.Caused by Lack of Defined Design Basis for Operability Requirements.Procedures & USAR Will Be Updated to Include Operability Requirements.With1999-01-28028 January 1999
- on 980521,outside Design Basis for LOCA with Plant Shutdown Noted.Caused by Lack of Defined Design Basis for Operability Requirements.Procedures & USAR Will Be Updated to Include Operability Requirements.With
05000285/LER-1998-015, :on 981202,questioned Whether Shift Technical Advisor Position Required to Be Respirator Qualified.Caused by Inadequate Program Design/Description for Establishing. Qualifications Will Be Reviewed.With1999-01-0404 January 1999
- on 981202,questioned Whether Shift Technical Advisor Position Required to Be Respirator Qualified.Caused by Inadequate Program Design/Description for Establishing. Qualifications Will Be Reviewed.With
05000285/LER-1998-016, :on 981204,determined That as Found Configuration of Relays & Covers Did Not Meet Seismic Qualifications for Relays.Cause Cannot Be Determined.Relay Covers Have Been re-installed.With1999-01-0404 January 1999
- on 981204,determined That as Found Configuration of Relays & Covers Did Not Meet Seismic Qualifications for Relays.Cause Cannot Be Determined.Relay Covers Have Been re-installed.With
05000285/LER-1998-014, :on 981021,emergency Temporary Mod Placed Plant in Unanalyzed Condition Re Ventilation Duct.Caused by Inadequate Procedural Control of Emergency Temporary Mod. Plant Procedures Will Be Revised.With1998-11-20020 November 1998
- on 981021,emergency Temporary Mod Placed Plant in Unanalyzed Condition Re Ventilation Duct.Caused by Inadequate Procedural Control of Emergency Temporary Mod. Plant Procedures Will Be Revised.With
05000285/LER-1998-012, :on 980828,inappropriate Approval of Change to H Generation Design Basis Wwas Noted.Caused by Failure to Assess Impact of Proposed USAR Changes.Reviewed & Updated Design Analysis as Needed.With1998-11-10010 November 1998
- on 980828,inappropriate Approval of Change to H Generation Design Basis Wwas Noted.Caused by Failure to Assess Impact of Proposed USAR Changes.Reviewed & Updated Design Analysis as Needed.With
05000285/LER-1998-013, :on 980924,CR Radiological Dose Consequences Was Noted Outside of Design Basis.Cause Not Stated.Upgraded Radiological Consequences Program & Calculations.With1998-10-26026 October 1998
- on 980924,CR Radiological Dose Consequences Was Noted Outside of Design Basis.Cause Not Stated.Upgraded Radiological Consequences Program & Calculations.With
05000285/LER-1998-009, :on 980722,waste Disposal Sys CIV Was Noted Outside Design Basis.Caused by Over Reliance on Contractor Design & Review of Mods.Mods Were Completed to Correct Problem.With1998-09-30030 September 1998
- on 980722,waste Disposal Sys CIV Was Noted Outside Design Basis.Caused by Over Reliance on Contractor Design & Review of Mods.Mods Were Completed to Correct Problem.With
05000285/LER-1998-011, :on 980825,violation of TS on Engineered Safety Sys Equipment Operability Occurred.Caused by Lack of Understanding of All Starting Air Circuit Details.Replaced Caution Tags on DG & Control Panels.With1998-09-24024 September 1998
- on 980825,violation of TS on Engineered Safety Sys Equipment Operability Occurred.Caused by Lack of Understanding of All Starting Air Circuit Details.Replaced Caution Tags on DG & Control Panels.With
05000285/LER-1998-010, :on 930208,violation of TS Re Better Axial Shape Selection Sys Was Noted.Caused by Inoperability of Core Monitoring Program.Alternate Methods Will Be Evaluated. with1998-09-17017 September 1998
- on 930208,violation of TS Re Better Axial Shape Selection Sys Was Noted.Caused by Inoperability of Core Monitoring Program.Alternate Methods Will Be Evaluated. with
05000285/LER-1998-008, :on 980528,noted That Plant Had Operated Outside of Design Basis of AFW Sys Due to Overpressurization of AFW Piping.Caused by Misadjustment of Governor.Installed Mod to Sense Overpressure Condition1998-06-29029 June 1998
- on 980528,noted That Plant Had Operated Outside of Design Basis of AFW Sys Due to Overpressurization of AFW Piping.Caused by Misadjustment of Governor.Installed Mod to Sense Overpressure Condition
05000285/LER-1998-007, :on 980522,TS Violation of ISI Reporting Requirements,Was Noted.Caused by Interpretation of Requirements of 10CFR50.55a(g)(5)(iv) Which Differs from Nrc.Listing of Exams Given to NRC1998-06-22022 June 1998
- on 980522,TS Violation of ISI Reporting Requirements,Was Noted.Caused by Interpretation of Requirements of 10CFR50.55a(g)(5)(iv) Which Differs from Nrc.Listing of Exams Given to NRC
05000285/LER-1998-005, :on 980520,161 Kv Transmission Line Circuit Breakers Tripped.Caused by Inappropriate Actuation of Deluge Sys for Transformer T1A-3.Transformer T1A-3 Was Checked to Ensure No Damage to Transformer Occurred1998-06-19019 June 1998
- on 980520,161 Kv Transmission Line Circuit Breakers Tripped.Caused by Inappropriate Actuation of Deluge Sys for Transformer T1A-3.Transformer T1A-3 Was Checked to Ensure No Damage to Transformer Occurred
05000285/LER-1998-004, :on 980423,determined That Indication in Fort Calhoun Station SG Tube Had Been Identified During 1996 Exams,But Had Been Inadvertently Left in Svc.Caused by Personnel Error.Procedures Revised1998-05-22022 May 1998
- on 980423,determined That Indication in Fort Calhoun Station SG Tube Had Been Identified During 1996 Exams,But Had Been Inadvertently Left in Svc.Caused by Personnel Error.Procedures Revised
05000285/LER-1998-003, :on 980407,violation of TS for Control of High Radiation Area Was Noted.Caused by Inadequate Communication of Mgt Expectations.Expectations of Radiation Area Controls Will Be Given to All Radiation Workers1998-05-0707 May 1998
- on 980407,violation of TS for Control of High Radiation Area Was Noted.Caused by Inadequate Communication of Mgt Expectations.Expectations of Radiation Area Controls Will Be Given to All Radiation Workers
05000285/LER-1998-002, :on 980226,TS Violation Was Noted Due to Exceeding Qualified Life for Plant Components.Caused by Lack of Depth Analysis When Original Calculation Was Performed. a Panel Was Repaired & Returned to Service1998-03-27027 March 1998
- on 980226,TS Violation Was Noted Due to Exceeding Qualified Life for Plant Components.Caused by Lack of Depth Analysis When Original Calculation Was Performed. a Panel Was Repaired & Returned to Service
05000285/LER-1997-017, :on 971107,low Pressure Safety Injection in Unanalyzed Condition Occurred,Due to Potential for Voiding. OPPD Has Administrative Controls in Place to Monitor & Prevent Conditions Necessary for Voiding1998-03-20020 March 1998
- on 971107,low Pressure Safety Injection in Unanalyzed Condition Occurred,Due to Potential for Voiding. OPPD Has Administrative Controls in Place to Monitor & Prevent Conditions Necessary for Voiding
05000285/LER-1998-001, :on 980202,TS Violation Occurred Due to Inadequate Inservice Testing.Caused by Lack of Attention to Detail When FCS ISI Program Plan for 3rd ten-year Interval Was Put Together in 1992.Changes Will Be Made1998-03-0303 March 1998
- on 980202,TS Violation Occurred Due to Inadequate Inservice Testing.Caused by Lack of Attention to Detail When FCS ISI Program Plan for 3rd ten-year Interval Was Put Together in 1992.Changes Will Be Made
05000285/LER-1997-017, :on 971107,LPSI Was in Unanalyzed Condition Due to Potential for Voiding.Caused by Architects Failure to Consider Water Hammer in Designs.Administrative Controls Placed to Monitor & Prevent Conditions1997-12-0808 December 1997
- on 971107,LPSI Was in Unanalyzed Condition Due to Potential for Voiding.Caused by Architects Failure to Consider Water Hammer in Designs.Administrative Controls Placed to Monitor & Prevent Conditions
05000285/LER-1997-016, :on 971029,nuclear Fuel Was Potentially Outside of Mfgs Fuel Design Criteria.Caused by Fuel Clad Gap Reopening.Gap Reopening May Be Predicted for Fcs,Based on Bounding Analysis1997-11-26026 November 1997
- on 971029,nuclear Fuel Was Potentially Outside of Mfgs Fuel Design Criteria.Caused by Fuel Clad Gap Reopening.Gap Reopening May Be Predicted for Fcs,Based on Bounding Analysis
05000285/LER-1997-015, :on 971017,unanalyzed Condition for Station Batteries Was Noted.Caused by Lack of Detailed Plant Design to Provide Supporting Info Re Requirement.Issued Operations Memo1997-11-17017 November 1997
- on 971017,unanalyzed Condition for Station Batteries Was Noted.Caused by Lack of Detailed Plant Design to Provide Supporting Info Re Requirement.Issued Operations Memo
05000285/LER-1997-014, :on 970831,perimeter Microwave Intrusion Alarm on Zone 2 Received in Security Alarm Stations.Caused by Lack of Attention to Detail on Behalf of CAS & SAS Operators. Alarm Station Operators Involved Retrained1997-09-26026 September 1997
- on 970831,perimeter Microwave Intrusion Alarm on Zone 2 Received in Security Alarm Stations.Caused by Lack of Attention to Detail on Behalf of CAS & SAS Operators. Alarm Station Operators Involved Retrained
05000285/LER-1997-013, :on 970826,TS 2.0.1, Motherhood Was Entered Into General Shutdown Voluntarily.Caused by Failed Switch. Replaced & Tested Inverter Switch & Returned Plant to Full Power1997-09-25025 September 1997
- on 970826,TS 2.0.1, Motherhood Was Entered Into General Shutdown Voluntarily.Caused by Failed Switch. Replaced & Tested Inverter Switch & Returned Plant to Full Power
05000285/LER-1997-012, :on 970821,inadvertent Isolation of All Containment Spray Was Discovered.Caused by Operator Error. Operator,Shift Supervisors,Licensed Senior Operators & Licensed Operators Were Disciplined1997-09-22022 September 1997
- on 970821,inadvertent Isolation of All Containment Spray Was Discovered.Caused by Operator Error. Operator,Shift Supervisors,Licensed Senior Operators & Licensed Operators Were Disciplined
05000285/LER-1997-011-01, :on 970819,violation of Tech Specs Due to Inoperability of Radiation Monitor Occurred.Caused by Lack of Depth in Evaluation/Review by Station Personnel. Procedures Will Be Revised1997-09-19019 September 1997
- on 970819,violation of Tech Specs Due to Inoperability of Radiation Monitor Occurred.Caused by Lack of Depth in Evaluation/Review by Station Personnel. Procedures Will Be Revised
05000285/LER-1997-010, :on 970731,violation of TS Occurred While Moving Spent Fuel in Spent Fuel Pool.Caused by Inadequate Design of CEA Locking Clip.Moved Affected Assembly to Region I of Spent Fuel Pool1997-09-0202 September 1997
- on 970731,violation of TS Occurred While Moving Spent Fuel in Spent Fuel Pool.Caused by Inadequate Design of CEA Locking Clip.Moved Affected Assembly to Region I of Spent Fuel Pool
05000285/LER-1997-004, :on 970505,DG Was Outside Design Basis Due to Violation of App R.Mod Was Completed on 970507 to Provide Ability to Isolate CR Located Tachometer from DG-2 Speed Sensing Circuit Prior to Reaching 300 Degrees1997-08-13013 August 1997
- on 970505,DG Was Outside Design Basis Due to Violation of App R.Mod Was Completed on 970507 to Provide Ability to Isolate CR Located Tachometer from DG-2 Speed Sensing Circuit Prior to Reaching 300 Degrees
05000285/LER-1997-008, :on 970616,improper Shift Staffing Due to Inadequate Control of Respirator Spectacle Kits Occurred. Caused by Program for Obtaining Corrective Lenses Inadequate to Ensure Compliance w/10CFR.Manual Revised1997-07-16016 July 1997
- on 970616,improper Shift Staffing Due to Inadequate Control of Respirator Spectacle Kits Occurred. Caused by Program for Obtaining Corrective Lenses Inadequate to Ensure Compliance w/10CFR.Manual Revised
05000285/LER-1997-009, :on 970619,potential Loss of Remote Shutdown Capability Occurred Due to Fire Induced Damage.Caused by Inadequate Design Basis Documentation.Operations Memo Provided Evacuation Criteria1997-07-12012 July 1997
- on 970619,potential Loss of Remote Shutdown Capability Occurred Due to Fire Induced Damage.Caused by Inadequate Design Basis Documentation.Operations Memo Provided Evacuation Criteria
05000285/LER-1997-006, :on 970606,discovered Loss of All Fire Suppression Due to Inoperability of Fire Pumps.Caused by Atypical Set of Operating Circumstances.Procedures Are Being Modified to Prevent Recurrence of Event1997-07-0707 July 1997
- on 970606,discovered Loss of All Fire Suppression Due to Inoperability of Fire Pumps.Caused by Atypical Set of Operating Circumstances.Procedures Are Being Modified to Prevent Recurrence of Event
05000285/LER-1997-005, :on 970530,improper Entry Into High Radiation Area Occurred.Caused by Lack of self-checking & Inattention to Detail.Discussed Event W/Plant Staff & Counseled Individual Involved1997-06-27027 June 1997
- on 970530,improper Entry Into High Radiation Area Occurred.Caused by Lack of self-checking & Inattention to Detail.Discussed Event W/Plant Staff & Counseled Individual Involved
05000285/LER-1997-002, :on 970414,charging Pump CH-1B Declared Inoperable.Caused by Ineffective Communication Re Amend 125 to TS 2.15.Implemented Improved Procedures Re Submittal of License Amend Requests1997-05-14014 May 1997
- on 970414,charging Pump CH-1B Declared Inoperable.Caused by Ineffective Communication Re Amend 125 to TS 2.15.Implemented Improved Procedures Re Submittal of License Amend Requests
05000285/LER-1997-001, :on 970122,main Steam Outside of Design Basis Occurred Due to an Error in Safety Valve Analysis.Guidance Has Been Provided to Operating Staff to Ensure That Design Basis Maintained1997-02-21021 February 1997
- on 970122,main Steam Outside of Design Basis Occurred Due to an Error in Safety Valve Analysis.Guidance Has Been Provided to Operating Staff to Ensure That Design Basis Maintained
05000285/LER-1996-015, :on 961028,improper Fuel Loading Next to Inoperable Wide Range Nuclear Instrument Occurred.Caused by Inadequate procedures.OP-11 Will Be Revised Before 1998 Refueling Outage to Require Reloading1997-01-21021 January 1997
- on 961028,improper Fuel Loading Next to Inoperable Wide Range Nuclear Instrument Occurred.Caused by Inadequate procedures.OP-11 Will Be Revised Before 1998 Refueling Outage to Require Reloading
05000285/LER-1996-016, :on 961220,inadequate Procedural Guidance for Resetting an Engineering Safety Feature Identified.Caused by Lack of Depth in Evaluation.Memorandum Was Issued to Notify Operators of Issue1997-01-21021 January 1997
- on 961220,inadequate Procedural Guidance for Resetting an Engineering Safety Feature Identified.Caused by Lack of Depth in Evaluation.Memorandum Was Issued to Notify Operators of Issue
05000285/LER-1996-014, :on 961117,reactor Cooldown in Excess of Limits Occurred Due to Starting Reactor Coolant pumps.OP-2A & OI-RC-9 Will Be Revised1996-12-17017 December 1996
- on 961117,reactor Cooldown in Excess of Limits Occurred Due to Starting Reactor Coolant pumps.OP-2A & OI-RC-9 Will Be Revised
05000285/LER-1996-013, :on 961116,util Failed to Satisfy Surveillance Requirement for Containment Penetration M-80.Caused by Lack of Complete & Thorough Ca.Review of All Similarly Configured Penetrations Was Conducted1996-12-13013 December 1996
- on 961116,util Failed to Satisfy Surveillance Requirement for Containment Penetration M-80.Caused by Lack of Complete & Thorough Ca.Review of All Similarly Configured Penetrations Was Conducted
05000285/LER-1996-012, :on 961111,potential for Vaporizing Cooling Water in Containment Fan Cooling Units Occurred.Caused by Loop Coincident with Loca.Analyses Have Been Performed1996-12-11011 December 1996
- on 961111,potential for Vaporizing Cooling Water in Containment Fan Cooling Units Occurred.Caused by Loop Coincident with Loca.Analyses Have Been Performed
05000285/LER-1996-011, :on 961030,containment Closure Breached While Moving Fuel.Caused by Failure to Maintain Valves & Follow & Enforce SO-G-20A Requirements.Rev of Policies & Procedures Re Control & Maint of Containment Closure1996-11-27027 November 1996
- on 961030,containment Closure Breached While Moving Fuel.Caused by Failure to Maintain Valves & Follow & Enforce SO-G-20A Requirements.Rev of Policies & Procedures Re Control & Maint of Containment Closure
05000285/LER-1996-009, :on 961017,pressurizer Safety Valves as Found Lift Appeared to Be Outside Acceptance Criteria.Caused by Valve Bonnet Upper Temp Limits Not Specified in Test Procedure.Test Procedure Will Be Revised1996-11-18018 November 1996
- on 961017,pressurizer Safety Valves as Found Lift Appeared to Be Outside Acceptance Criteria.Caused by Valve Bonnet Upper Temp Limits Not Specified in Test Procedure.Test Procedure Will Be Revised
05000285/LER-1996-010, :on 961018,loss of Containment Closure Noted Due to Maint Activity During Refueling.Station Procedures Including OI-CO-4,will Be Reviewed & Revised as Necessary to Ensure Adequate Controls Exist1996-11-18018 November 1996
- on 961018,loss of Containment Closure Noted Due to Maint Activity During Refueling.Station Procedures Including OI-CO-4,will Be Reviewed & Revised as Necessary to Ensure Adequate Controls Exist
05000285/LER-1996-008, :on 961011,ventilation Isolation Actuation Signal Occurred.Due to High Containment Activity.Plant Procedures Will Be Reviewed & Revised1996-11-12012 November 1996
- on 961011,ventilation Isolation Actuation Signal Occurred.Due to High Containment Activity.Plant Procedures Will Be Reviewed & Revised
05000282/LER-1996-018, :on 961010,surveillance of Low Pressure Start of Component Cooling Pumps Was Missed Due to Inadequate Procedure.Procedures Will Be Revised by 970215 to Test Low Pressure auto-start of Component Cooling Pumps1996-11-12012 November 1996
- on 961010,surveillance of Low Pressure Start of Component Cooling Pumps Was Missed Due to Inadequate Procedure.Procedures Will Be Revised by 970215 to Test Low Pressure auto-start of Component Cooling Pumps
05000285/LER-1996-007, :on 961005,unplanned Reactor Protection Sys Actuation Occurred During Plant Cooldown.Caused by Failure to Complete Step in OP-3A as Required.Procedure Revised.W/1996-11-0404 November 1996
- on 961005,unplanned Reactor Protection Sys Actuation Occurred During Plant Cooldown.Caused by Failure to Complete Step in OP-3A as Required.Procedure Revised.W/
05000285/LER-1996-006, :on 951218,all Charging Pumps Disabled.Caused by Inadequate Administrative Control.Guidance Insuring Consistent Interpretation of Affected TSs Issued.Process for Issuing TS Interpretations Revised1996-10-0909 October 1996
- on 951218,all Charging Pumps Disabled.Caused by Inadequate Administrative Control.Guidance Insuring Consistent Interpretation of Affected TSs Issued.Process for Issuing TS Interpretations Revised
05000285/LER-1996-004, :on 960315,discovered Adequate Shutdown Margin Was Not Maintained.Caused by Inadequate Technical Review by Plant Personnel Involved in Reviewing Procedure Change. Appropriate Personnel Trained on Incident1996-06-0303 June 1996
- on 960315,discovered Adequate Shutdown Margin Was Not Maintained.Caused by Inadequate Technical Review by Plant Personnel Involved in Reviewing Procedure Change. Appropriate Personnel Trained on Incident
05000285/LER-1996-002, :on 960329,reactor Manually Tripped Due to Partial Loss of Vacuum in Main Condenser.Condenser Isolated, Plant Shutdown & Leaking Condenser Tube Plugged.Pm Order WP-006820 Will Be Revised1996-04-29029 April 1996
- on 960329,reactor Manually Tripped Due to Partial Loss of Vacuum in Main Condenser.Condenser Isolated, Plant Shutdown & Leaking Condenser Tube Plugged.Pm Order WP-006820 Will Be Revised
05000285/LER-1996-001, :on 960318,containment Ventilation Isolation Signal Occurred Due to High Activity During Purge.Revised Applicable Procedures1996-04-17017 April 1996
- on 960318,containment Ventilation Isolation Signal Occurred Due to High Activity During Purge.Revised Applicable Procedures
05000285/LER-1995-007, :on 951108,potential Tripping of 480 Volt Circuit Breakers W/Digital Reip Units Identified.Caused by Circuit Breaker Component Not Operating as Specified.Issued SA for Operability1996-03-0404 March 1996
- on 951108,potential Tripping of 480 Volt Circuit Breakers W/Digital Reip Units Identified.Caused by Circuit Breaker Component Not Operating as Specified.Issued SA for Operability
1999-07-08
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217B5401999-10-0606 October 1999 Safety Evaluation Supporting Amend 193 to License DPR-40 ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data LIC-99-0096, Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Fcs,Unit 1.With ML20211J9321999-09-0202 September 1999 Safety Evaluation Concluding That Licensee Proposed Alternatives Provide Acceptable Level of Quality & Safety. Proposed Alternatives Authorized for Remainder of Third ten- Yr ISI Interval for Fort Calhoun Station,Unit 1 LIC-99-0084, Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Fort Calhoun Station.With ML20216E6431999-08-26026 August 1999 Rev 19 to TDB-VI, COLR for FCS Unit 1 ML20210R1961999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Fcs,Unit 1 ML20210G2181999-07-27027 July 1999 Safety Evaluation Supporting Amend 192 to License DPR-40 ML20210D9951999-07-22022 July 1999 Safety Evaluation Supporting Amend 191 to License DPR-40 ML20216E6361999-07-21021 July 1999 Rev 18 to TDB-VI, COLR for FCS Unit 1 05000285/LER-1999-002, :on 980910,inadvertent Ventilation Isolation Actuation Signal Occurred While Maint Was Being Performed. Caused by Switch Failure.Key Switch for RM-062 Has Been Replaced.With1999-07-0808 July 1999
- on 980910,inadvertent Ventilation Isolation Actuation Signal Occurred While Maint Was Being Performed. Caused by Switch Failure.Key Switch for RM-062 Has Been Replaced.With
ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20210R2081999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Fcs,Unit 1 LIC-99-0065, Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Fort Calhoun Station,Unit 1.With ML20210P5461999-06-0808 June 1999 Rev 0,Vols 1-5 of Fort Calhoun Station 1999 Emergency Preparedness Exercise Manual, to Be Conducted on 990810. Pages 2-20 & 2-40 in Vol 2 & Page 4-1 in Vol 4 of Incoming Submittal Not Included ML20195B4581999-05-31031 May 1999 Rev 3 to CE NPSD-683, Development of RCS Pressure & Temp Limits Rept for Removal of P-T Limits & LTOP Requirements from Ts LIC-99-0053, Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 11999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Fort Calhoun Station,Unit 1 ML20207H7401999-05-31031 May 1999 Performance Indicators Rept for May 1999 ML20195B4521999-05-17017 May 1999 Technical Data Book TDB-IX, RCS Pressure - Temp Limits Rept (Ptlr) ML20206L4241999-05-10010 May 1999 Safety Evaluation Supporting Corrective Actions to Ensure That Valves Are Capable of Performing Intended Safety Functions & OPPD Adequately Addressed Requested Actions Discussed in GL 95-07 ML20206M2601999-05-0606 May 1999 SER Concluding That Licensee IPEEE Complete Re Info Requested by Suppl 4 to GL 88-20 & IPEEE Results Reasonable Given FCS Design,Operation & History ML20195E8621999-04-30030 April 1999 Performance Indicators, for Apr 1999 LIC-99-0047, Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Fort Calhoun Station Unit 1.With ML20205Q5831999-04-15015 April 1999 Safety Evaluation Supporting Amend 190 to License DPR-40 ML20210J4331999-03-31031 March 1999 Changes,Tests, & Experiments Carried Out Without Prior Commission Approval for Period 981101-990331.With USAR Changes Other than Those Resulting from 10CFR50.59 LIC-99-0034, Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With1999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Fcs,Unit 1.With ML20206G2641999-03-31031 March 1999 Performance Indicators Rept for Mar 1999 05000285/LER-1999-001, :on 990203,shutdown TS Entry Occurred Due to AFW Pump Inoperability.Caused by Inadequate Procedure. Procedure IC-ST-IA-3009 Was Corrected to Properly Perform Surveillance Test.With1999-03-0505 March 1999
- on 990203,shutdown TS Entry Occurred Due to AFW Pump Inoperability.Caused by Inadequate Procedure. Procedure IC-ST-IA-3009 Was Corrected to Properly Perform Surveillance Test.With
ML20205J8181999-02-28028 February 1999 Performance Indicators, for Feb 1999 LIC-99-0025, Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With1999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Fort Calhoun Station,Unit 1.With ML20207F3291999-01-31031 January 1999 FCS Performance Indicators for Jan 1999 05000285/LER-1998-006, :on 980521,outside Design Basis for LOCA with Plant Shutdown Noted.Caused by Lack of Defined Design Basis for Operability Requirements.Procedures & USAR Will Be Updated to Include Operability Requirements.With1999-01-28028 January 1999
- on 980521,outside Design Basis for LOCA with Plant Shutdown Noted.Caused by Lack of Defined Design Basis for Operability Requirements.Procedures & USAR Will Be Updated to Include Operability Requirements.With
05000285/LER-1998-016, :on 981204,determined That as Found Configuration of Relays & Covers Did Not Meet Seismic Qualifications for Relays.Cause Cannot Be Determined.Relay Covers Have Been re-installed.With1999-01-0404 January 1999
- on 981204,determined That as Found Configuration of Relays & Covers Did Not Meet Seismic Qualifications for Relays.Cause Cannot Be Determined.Relay Covers Have Been re-installed.With
05000285/LER-1998-015, :on 981202,questioned Whether Shift Technical Advisor Position Required to Be Respirator Qualified.Caused by Inadequate Program Design/Description for Establishing. Qualifications Will Be Reviewed.With1999-01-0404 January 1999
- on 981202,questioned Whether Shift Technical Advisor Position Required to Be Respirator Qualified.Caused by Inadequate Program Design/Description for Establishing. Qualifications Will Be Reviewed.With
ML20203B0991998-12-31031 December 1998 Performance Indicators for Dec 1998 ML20198S3771998-12-31031 December 1998 Safety Evaluation Supporting Amend 189 to License DPR-40 LIC-99-0026, 1998 Omaha Public Power District Annual Rept. with1998-12-31031 December 1998 1998 Omaha Public Power District Annual Rept. with ML20198S4831998-12-31031 December 1998 Safety Evaluation Supporting Amend 188 to License DPR-40 LIC-99-0003, Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With1998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Fort Calhoun Station.With ML20196G2251998-12-18018 December 1998 Rev 2 to EA-FC-90-082, Potential Over-Pressurization of Containment Penetration Piping Following Main Steam Line Break in Containment LIC-98-0172, Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With1998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Fort Calhoun Station,Unit 1.With ML20198M3141998-11-30030 November 1998 Performance Indicators Rept for Nov 1998 LIC-98-0160, Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated1998-11-25025 November 1998 Special Rept:On 981113,MSL RM RM-064 Was Declared Inoperable Due to Leakage Past Isolation Valve HCV-922.Troubleshooting Has Indicated That Leakage Has Stopped & Cause of Leak Continues to Be Investigated 05000285/LER-1998-014, :on 981021,emergency Temporary Mod Placed Plant in Unanalyzed Condition Re Ventilation Duct.Caused by Inadequate Procedural Control of Emergency Temporary Mod. Plant Procedures Will Be Revised.With1998-11-20020 November 1998
- on 981021,emergency Temporary Mod Placed Plant in Unanalyzed Condition Re Ventilation Duct.Caused by Inadequate Procedural Control of Emergency Temporary Mod. Plant Procedures Will Be Revised.With
ML20203B0721998-11-16016 November 1998 Rev 6 to HI-92828, Licensing Rept for Spent Fuel Storage Capacity Expansion 05000285/LER-1998-012, :on 980828,inappropriate Approval of Change to H Generation Design Basis Wwas Noted.Caused by Failure to Assess Impact of Proposed USAR Changes.Reviewed & Updated Design Analysis as Needed.With1998-11-10010 November 1998
- on 980828,inappropriate Approval of Change to H Generation Design Basis Wwas Noted.Caused by Failure to Assess Impact of Proposed USAR Changes.Reviewed & Updated Design Analysis as Needed.With
LIC-98-0154, Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With1998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Fort Calhoun Station,Unit 1.With ML20196G2441998-10-31031 October 1998 Changes,Tests & Experiments Carried Out Without Prior Commission Approval. with USAR Changes Other than Those Resulting from 10CFR50.59 ML20196E4981998-10-31031 October 1998 Performance Indicators Rept for Oct 1998 05000285/LER-1998-013, :on 980924,CR Radiological Dose Consequences Was Noted Outside of Design Basis.Cause Not Stated.Upgraded Radiological Consequences Program & Calculations.With1998-10-26026 October 1998
- on 980924,CR Radiological Dose Consequences Was Noted Outside of Design Basis.Cause Not Stated.Upgraded Radiological Consequences Program & Calculations.With
1999-09-30
[Table view] |
text
e 4
..I i L'[.
h$
v; [bk M n h, a.
...o Omaha Public Power District 444 South 16th Street kli!!
Omaha. Netaraka 68102 2247 402/630 2000 february 20, 1992 LIC-92-051L U. S. Nuc1 car Regulatory Commission Attn Document Control Desk Mail Station PI-137 dashington, DC 20555 Reference: Docket No. 50-285 Gentlemen:
Subject:
1.icensee Cvent Report 92-001 for the fort Calhoun Station Please find attached Licensee Event Report 92-001 dated February 20, 1992.
This re) ort is being submitted pursuant to 10 CfR 50./3(a)(2)(1)(B).
If you should iave any questions, please contact me.
Sincerely,
& ),2 5 %
W. G. Gates Division Manager Nuclear Operations l
WGG/dle Attachment 1
c:
R. D. Martin, NRC Regional Administrator D. L. Wigginton, NRC Senior Project Manager R. P. Mullikin, NRC Senior Resident inspector INPO Records Center i
l)4 O
em o
gggm_
m,m 240059
" * * " * " " " ^ " " " " " '
Ammon w. c.mm.
en m an UCENSEE EVENT REPORT (LER) hhb[h'h5Th,$5 I
N%3?boC&"hw@
&"u'aMt%'&FJoE.MiJ(d%EN A
Mne Eirm== m nuaart summi n
==
Fort Calhoun Station Unit No. 1 ofslofolof21815 ilOF 013 i
ma i
Unmonitored Release on loss of 13.8 kV System son mis a umanean m
= = m ri m onen mmm..-o a lA%dfH DAY Yt.AM VIAR Mu A
'EMTH
, DAY YEAN N,
01 81 01 01 01 l l l
0l 1 2l 1 92 9l 2 0l 0l 1 0l 0 0l 2 2l 0 9l 2 ol si ol ol ol I l
- " ' " " * " " ' " ' " * ' ' ' ' " ' ' " * " " " ' ' " ' " ' " * * ~ " ' ' * ' ' ' ' ' ' * "
1 '* 's"o' "= M 8" M po sam eonWAM ta tim M
0l 8 2
=* *"* *n
~
I
=wm naamm anwmm otp g g g g g,,
na nammm X wnmu wnam 94 nunmu unwen wnem
. r> em.uw unem m nr.m usewoowtwrronweimna NAuti tu a tuced NUMin H l
4,u ua Keith A. Voss,-Shift Technical Advisor 41012 51 3131-l 61.91311 oninete tw un mwe cowoesa rawne onwamp w me suew na CAUDE SYSTfM COMPONT.NT "yNg k%$I CAUDE SYSTCM COMPONLNi fI f O 1 A
I I I I I I -l l
I I I I I 1 I
l l l l l l l
l l l l l l f
su,unsurat =w me unas ne um nav vsAn DATE (
i l Y. n -. c-rro =~mw nam W
l l
I amermne.,,,.m - s. -.va w.-.em
% m On January 21, 1992, at 1258 hours0.0146 days <br />0.349 hours <br />0.00208 weeks <br />4.78669e-4 months <br />, Fort Calhoun Station Unit No. I was operating at 82 percent power, coasting down in preparation for a refueling outage, when Control Room personnel received alarms that indicated a loss of the 13.8 kV electrical system.
Immediate action was taken to determine the status of the Laboratory and Radioactive Waste Processing-Building (LRWPB) Exhaust Stack gas, iodine, and parti:ulate radiation monitors (RM-041/042/043) and the associated sample pump. During the five minutes that the sample pump was deenergized due to the loss of power, the exhaust fans ware still in operation resulting in an unmonitored release. This is in violation of Technical Specification 2.9 and is being reportedpursuanttotherequirementsof10CFR50.73(a)(2)(1)(B).
The cause of this event is the inadequate design of the RM-041/042/043 sample pump motor control and supervisory circuitry for a loss of power.
Since there were no radioactive releases from the LRWPD stack during the time that the sample pump was deenergized, this event has minimal nuclear safety significance.
However, normal ventilation releases were restarted when the 13.8 kV electrical system was rc. stored.
The cause of this momentary loss of the 13.8 kV electrical system is undetermined.
Corrective actions included immediately restarting the sample pump. A temporary modification was-also installed to change the sample pump start switch to allow the sample pump to restart l
automatically upon restoration of power after a loss of power.
The long term corrective l
actions include evaluating the current design configuration of the exhaust fan control circuits and an Engineering Change Notice 91-524 to provide Control Room indication if the sample pump experiences a loss of power or a loss of flow.
=.
Thr,,,- m
i seu uuuuM eueWi-,4
~
(
UCENSEE EVENT REPORT (LER)
TEXT CONTINUATlON UE E'E'EE E'E M On M M fJIM F " M'iU M n'nua&MMMbhN 10N,lcPha 5 M Lt Of MAW MtNT MD EUL* JET. WMA WEKf fem (1)
LKXDIT DdJWEHR M L1R NVWinM M fMEM l
q WM Mm Fort Calhoun Station Unit No. 1 olslololol21815 91 2 0l0l1 0l0 012 G
Ol 3 sur m.u m.<
.a w wer.~ w en The Chemistry and Radiation Protection (CARP) Building and the Radioactive Waste Duilding (RWB) are two new structures built as part of Fort Calhoun Station (FCS) improvements.
Their ventilation systems use a common exhaust stack that is independently operateu from the rest of the plant and is equipped with its own radiation monitors designated as the Laboratory and Radioactive Waste Processing Building (LRWPB) Exhaust Stack gas, iodine and particulate monitors.
The CARP and RWB are powered from an offsite 13.8 kV electrical system.
TechnicalSpecification2.9.1(2)hstates,inpart,thatduringreleasesfromthe Laboratory and Radioactive Waste processing Building (LRWPB) Exhaust Stack the gas, iodine, and particulate monitors shall be monitoring the LRWPB Exhaust Stack.
The s)ecification allows the particulate and the iodine monitors to be inoperable provided t1at samples are continuously collected.
The radiation monitors that accomplish this are RM'041,RM-042,andRM-043(Particulate, lodine,andNobleGas,respectively.)
RM-041/042/043 nonitor a continuous sample stream from the LRWPB exhaust stack.
The sample is drawn from the LRWPB exhaust duct through the sample pipe, analyzed at the detector, and returned to the exhaust duct. The sample is representative of the flow going up the stack and is drawn by a sample pump.
The sample pump control circuitry is designed to deenergize and remain deenergized if control power is lost and requires operator action to restart.
The control circuits for the ventilation units in the LRWPB are designed to shutdown with the loss of power and restart automatically when the power returns.
There currently is not an interlock in place to ensure that the sample pump is running prior to the start / restart of the building's exhaust fans.
On January 21, 1992 at 1258 hours0.0146 days <br />0.349 hours <br />0.00208 weeks <br />4.78669e-4 months <br />, Fort Calhoun Station was o)erating at 82 percent power, coasting doe in preparction for a refueling outage, wten Control Room personnel received alarms that inditated a loss of the 13.8 kV electrical system.
Initially it was thought that the 13.8 kV feed was cut during work which was in progress in the switchyard.
However, post-event review indicated that there were no problems in the switchyard and that the 13.8 kV electrical system experienced only a momentary loss. The cause uf this momentary loss of the 13.8 kV electrical system is undetermined.
The Control Room also notified the auxiliary building operator to immediately start the sample pum of power. p for RM-041/042/043.The pump was restarted within five minutes of this loss The exhaust fans restarted immediately upon restoration of power, but the sample pump was not running. Operation of the exhaust fans while the sample pump is not running was determined to be an unmonitored release in violation of Technical Specification 2.9.
Technical Specification 2.9.1(2)h(i) allows the particulate and iodine monitors to be ino>erable provided that samples are continuously collected.
These samples are required to ae representative of the average quantities and concentrations of radioactive materials in particulate form released in the gaseous effluents, and the sam)le should be collected in proportion to the design flow rate of the effluent stream. Wit 1out the sample pump drawing the proper sample flow through the radiation monitors, a representative sample was not analyzed and subsequently the Technical Specification requirement was not met.
Therefore, this report is being submitted pursuant to the requirements of 10 CFR 50.73(a)(2)(i)(B).
IsFQ form 306A (t> dy
een o cue wo, otap4 g
UCENSEE EVENT REPORT (LER)
MYiUO&&.MJM'";t}'N hM EENEM'3 TEXT CONTINUATION 4
' 's uni 2 MW'M WO M M."% dd M M2Y v um m,mu uan. mmkam
- u m.nvsw a (y rnni Wasan m un W nawn M PAu m
$T'h*'
NM vt A8i fort Calhoun Station Unit No. 1 olelololel21815 91 2 01011 0l0 Ol3 M 01 3 sw w..mw.e,a
.wac tm m n The root cause of this event was the inadequate design of the RM-041/042/043 sample pump motor control and supervisory circuitry.
There are no control circuit interlocks or permissives between the RM-041/042/043 sample pump (which requires operator action to powerreturns)powerreturns)andtheLRWPBexhaustfans(whichtutomaticallyrestartwhen restart after There were no inappropriate personnel actions for this event.
The operators, both licensed and non-licensed, were aware of the required actions that had to be performed for this type of event.
The auxiliary building operator had the sample pump started within five minutes of the 13.8 kV electrical system being restored.
The control room operators immediately notified the equipment operators and personnel working in the switchyard to start looking for equipment that was de-energized or power cables that had problems.
This event did not involve a reactor trip.
All equipment (the ventilation units, radiation monitors, and sample pump) functioned as designed.
This event has minimal nuclear safety significance.
There was no chemistry sampling being performed while the sample pump was off and there were no radioactive releases in progress through the LRWPB stack during this time.
The only release that occurred during this event were normal ventilation releases that restarted when the 13.8 kV electrical system was restored.
The radiation monitors were also available, but did not have adequate sample flow.
Therefore, the monitors were not able to get a representative sample of the release until the semple pump was restarted.
The short term corrective actions included:
- 1) immediately restarting the sample pump and, 2) changing out the switch on the sample ) ump so that the pump will automatically restart when power is returned to the pump. Tlis switch change-out was incorporated by installing Temporary Modification 92-04 on January 25,1992(MWO920291).
The long term corrective actions for this event are as follows:
1.
Engineering Change Notice (ECN)91-524 was initiated on December 17, 1991.
This ECN will provide the Control Room with an annuncictor on the Radiation Monitor panel, in'the event of a flow fault or loss or power on the RM-041/042/043 sample pump. This change will be installed under MWO 920496.
The expected installation date is March 20, 1992.
2.
CAR 92-002 was initiated to evaluate the present design configurations of the RM-041/042/043 sample pump control circuit and the exhaust fans that discharge through the LRWPB stack.
This evaluation will be completed by December 31, 1992.
LER 91-028 was submitted concerning an unmonitored release through the LRWPB stack.
NiG Fenm 30hA (6 60)
.. ~.. _ -,
|
---|
|
|
|
05000285/LER-1992-001, :on 920121,alarms That Indicated Loss of 13.8 Kv Electric Sys.Caused by Inadequate Design of RM-041/042 & 043 Sample Pump Motor Control.Sample Pump Restarted |
- on 920121,alarms That Indicated Loss of 13.8 Kv Electric Sys.Caused by Inadequate Design of RM-041/042 & 043 Sample Pump Motor Control.Sample Pump Restarted
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1) | 05000285/LER-1992-002, :on 920127,inner Containment Personnel Air Lock Door Failed to Meet Acceptance Criteria of Pal O-ring Seal Surveillance Test.Caused by Condensate Dripping on Inner Door Bracket.Corrosion to Be Removed |
- on 920127,inner Containment Personnel Air Lock Door Failed to Meet Acceptance Criteria of Pal O-ring Seal Surveillance Test.Caused by Condensate Dripping on Inner Door Bracket.Corrosion to Be Removed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1) | 05000285/LER-1992-003, :on 920128,alarm on Fire Alarm Panel AI-54A Actuated as Required by Tech Spec 2.19(1).Caused by Inadequate Personnel Performance Due to Lack of Attention. Compensatory Measures Established |
- on 920128,alarm on Fire Alarm Panel AI-54A Actuated as Required by Tech Spec 2.19(1).Caused by Inadequate Personnel Performance Due to Lack of Attention. Compensatory Measures Established
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | 05000285/LER-1992-004, :on 920201,5 of 10 Main Steam Safety Valve Liftpoints Found Out of Acceptance Criteria.Caused by Use of Overly Restrictive Operability Criteria.Valves Recalibr & Tested Satisfactorily |
- on 920201,5 of 10 Main Steam Safety Valve Liftpoints Found Out of Acceptance Criteria.Caused by Use of Overly Restrictive Operability Criteria.Valves Recalibr & Tested Satisfactorily
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | 05000285/LER-1992-005, :on 920201,zero Power Mode Bypass Switch Placed in Bypass Condition Resulting in Unplanned Reactor Protective Sys Actuation.Caused by Procedural Noncompliance. Standing Order Re Notification Reviewed |
- on 920201,zero Power Mode Bypass Switch Placed in Bypass Condition Resulting in Unplanned Reactor Protective Sys Actuation.Caused by Procedural Noncompliance. Standing Order Re Notification Reviewed
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | 05000285/LER-1992-006, :on 920125,discovered That Alarm Function on Radioactive Waste Bldg Stack Monitors Were Inoperable.Caused by Personnel Error.Training Re self-checking & post-mod Testing Requirements Will Be Performed |
- on 920125,discovered That Alarm Function on Radioactive Waste Bldg Stack Monitors Were Inoperable.Caused by Personnel Error.Training Re self-checking & post-mod Testing Requirements Will Be Performed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1) | 05000285/LER-1992-007, :on 920219,three Ventilation Isolation Valves Closed Unexpectedly.Cause Undetermined.Util Will Provide Training on Event,On Monitoring Alarm Printer & Will Investigate New Training for Operators |
- on 920219,three Ventilation Isolation Valves Closed Unexpectedly.Cause Undetermined.Util Will Provide Training on Event,On Monitoring Alarm Printer & Will Investigate New Training for Operators
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(1) | 05000285/LER-1992-008, :on 920227,relief Valves on SI Sys Piping Had Been Installed W/Relief Setpoints Not within SI Sys Design. Caused by Inconsistencies Between Relief Valve Spec Sheets. Drawings & Design Basis Documents Updated |
- on 920227,relief Valves on SI Sys Piping Had Been Installed W/Relief Setpoints Not within SI Sys Design. Caused by Inconsistencies Between Relief Valve Spec Sheets. Drawings & Design Basis Documents Updated
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000285/LER-1992-009, :on 920302,lockout Relay on Channel B of Emergency Safeguards Ventilation Isolation Actuation Signal Actuated.Caused by Procedural Deficiency.Procedure Re Lockout Relays Revised & Event Discussed |
- on 920302,lockout Relay on Channel B of Emergency Safeguards Ventilation Isolation Actuation Signal Actuated.Caused by Procedural Deficiency.Procedure Re Lockout Relays Revised & Event Discussed
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000285/LER-1992-010, :on 910517,determined That Room 57 Was Outside Design Basis of Plant.Caused by Lack of Attention to Detail. Completed Engineering Analysis to Evaluate Remainder of as Sys |
- on 910517,determined That Room 57 Was Outside Design Basis of Plant.Caused by Lack of Attention to Detail. Completed Engineering Analysis to Evaluate Remainder of as Sys
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) | 05000285/LER-1992-011, :on 920320,determined That Valve Arrangement for Svc Air Sys Containment Penetration M-74 Did Not Meet Isolation Criteria for Exposed Sys.Caused by Failure to Address Revised Fsar.Mod Will Be Performed |
- on 920320,determined That Valve Arrangement for Svc Air Sys Containment Penetration M-74 Did Not Meet Isolation Criteria for Exposed Sys.Caused by Failure to Address Revised Fsar.Mod Will Be Performed
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | 05000285/LER-1992-012, :on 920325,determined That SG Differential Pressure/Asymmetric SG Transient Protection Trip Function Setpoints Higher than Allowed by Ts.Caused by Inadequate Program/Methodology.Procedures Revised |
- on 920325,determined That SG Differential Pressure/Asymmetric SG Transient Protection Trip Function Setpoints Higher than Allowed by Ts.Caused by Inadequate Program/Methodology.Procedures Revised
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) | 05000285/LER-1992-013, :on 920408,actuation of Engineered Safety Feature (ESF) Components Occurred.Caused by Spade Wire Lugs Loosening & Loss of Connection.Maint Procedure Requirements for Terminating Wires Revised |
- on 920408,actuation of Engineered Safety Feature (ESF) Components Occurred.Caused by Spade Wire Lugs Loosening & Loss of Connection.Maint Procedure Requirements for Terminating Wires Revised
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000285/LER-1992-014, :on 920514,steam Leak Identified Coming from Capped Connection on Turbine Trip Switch on Moisture Separator,Resulting in Reactor Trip.Caused by Communication Problems.Training Provided & Order Issued |
- on 920514,steam Leak Identified Coming from Capped Connection on Turbine Trip Switch on Moisture Separator,Resulting in Reactor Trip.Caused by Communication Problems.Training Provided & Order Issued
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000285/LER-1992-015, :on 920412,480-volt Bus Feeder Breaker Tripped, Resulting in Loss of Power to Shutdown Cooling Flow Control Valve Controller.Caused by Failure to Have Policy to Address Event.Policy Developed |
- on 920412,480-volt Bus Feeder Breaker Tripped, Resulting in Loss of Power to Shutdown Cooling Flow Control Valve Controller.Caused by Failure to Have Policy to Address Event.Policy Developed
| 10 CFR 50.73(a)(2)(v)(B), Loss of Safety Function - Remove Residual Heat 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000285/LER-1992-016, Revises Commitment to AEC Safety Guide 1 (Reg Guide 1.1), Contained in Section 6.2 of Updated Sar.Commitment Covers Method of Calculating Available Net Positive Suction Head for Containment Spray Sys Per LER 92-016 | Revises Commitment to AEC Safety Guide 1 (Reg Guide 1.1), Contained in Section 6.2 of Updated Sar.Commitment Covers Method of Calculating Available Net Positive Suction Head for Containment Spray Sys Per LER 92-016 | | 05000285/LER-1992-017, :on 920314,switchgear Revealed Indications of Cracks on Additional Lexan Cam Followers.Caused by Mechanical Stress Cracking of Cam Followers.Switches Have Been Replaced |
- on 920314,switchgear Revealed Indications of Cracks on Additional Lexan Cam Followers.Caused by Mechanical Stress Cracking of Cam Followers.Switches Have Been Replaced
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000285/LER-1992-018, Updates Status of Corrective Actions in LER 92-018 Re Replacement of Carbon Steel Fasteners in Boric Acid Sys. Current Carbon Steel Fasteners Will Perform Satisfactorily Until Scheduled Replacement | Updates Status of Corrective Actions in LER 92-018 Re Replacement of Carbon Steel Fasteners in Boric Acid Sys. Current Carbon Steel Fasteners Will Perform Satisfactorily Until Scheduled Replacement | | 05000285/LER-1992-019, :on 920531,indication Received That CEA 35 Dropped Into Reactor Core Resulting in Plant Shutdown,Due to Clutch Coil Failure.Util Will Verify Whether Resistor Is Installed in Series W/Cea 35 Clutch Coil |
- on 920531,indication Received That CEA 35 Dropped Into Reactor Core Resulting in Plant Shutdown,Due to Clutch Coil Failure.Util Will Verify Whether Resistor Is Installed in Series W/Cea 35 Clutch Coil
| | 05000285/LER-1992-020, :on 920601,determined That Operators Failed to Obtain Appropriate Grab Samples During Radiation Monitor Inoperability.Caused by Procedural Inadequacies.Procedure Upgraded & Personnel Trained Re Monitors |
- on 920601,determined That Operators Failed to Obtain Appropriate Grab Samples During Radiation Monitor Inoperability.Caused by Procedural Inadequacies.Procedure Upgraded & Personnel Trained Re Monitors
| | 05000285/LER-1992-021, :on 920611,failure to Initiate Fire Watch for Inoperable Fire Door Noted.Caused by Ambiguous Instructions Contained in Note.Procedure Revised & Personnel Informed of Requirements for Maintaining Fire Door |
- on 920611,failure to Initiate Fire Watch for Inoperable Fire Door Noted.Caused by Ambiguous Instructions Contained in Note.Procedure Revised & Personnel Informed of Requirements for Maintaining Fire Door
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | 05000285/LER-1992-022, :on 920702,discovered That Cables Supplying Power to Three Heater Drain Pump Motors Were Inadequately Sized.Caused by Error in Original Plant Design.Fire Watch Established & Cables Will Be Upgraded |
- on 920702,discovered That Cables Supplying Power to Three Heater Drain Pump Motors Were Inadequately Sized.Caused by Error in Original Plant Design.Fire Watch Established & Cables Will Be Upgraded
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000285/LER-1992-023, :on 920703,RPS Automatically Tripped & Power Momentarily Lost to Instrument Bus That Supplies Power to Turbine Electrohydraulic Control Sys.Caused by Failure to Isolate Inverters.Mod to Inverters Underway |
- on 920703,RPS Automatically Tripped & Power Momentarily Lost to Instrument Bus That Supplies Power to Turbine Electrohydraulic Control Sys.Caused by Failure to Isolate Inverters.Mod to Inverters Underway
| 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.73(a)(2)(x) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(1) | 05000285/LER-1992-024, :on 920717,identified Potential for Previous TS Violations Involving Lhr Monitoring Requirements.Caused by Lack of Procedure Covering Monitoring of Key Reactor Physics Parameters.Ts Interpretation Will Be Developed |
- on 920717,identified Potential for Previous TS Violations Involving Lhr Monitoring Requirements.Caused by Lack of Procedure Covering Monitoring of Key Reactor Physics Parameters.Ts Interpretation Will Be Developed
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000285/LER-1992-025, :on 920723,EDG DG-2 Started When Operator Inadvertently Pushed Normal Start Button Instead of Alarm Ack Button.Caused by Failure to self-check to Ensure Action correct.Self-checking Reemphasized |
- on 920723,EDG DG-2 Started When Operator Inadvertently Pushed Normal Start Button Instead of Alarm Ack Button.Caused by Failure to self-check to Ensure Action correct.Self-checking Reemphasized
| 10 CFR 50.73(a)(2)(iv), System Actuation | 05000285/LER-1992-027, :on 920817,determined That Open Stop Valve Between Regenerative Heat Exchanger & CH-202 Did Not Conform to Code Requirements.Caused by Inadequate Design Review. Plant Procedures Will Be Reviewed & Revised |
- on 920817,determined That Open Stop Valve Between Regenerative Heat Exchanger & CH-202 Did Not Conform to Code Requirements.Caused by Inadequate Design Review. Plant Procedures Will Be Reviewed & Revised
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000285/LER-1992-028, :on 920822,RPS Automatically Tripped Reactor on Thermal Margin/Low Pressure,Causing Increase in RCS Pressure Caused by Failure of Ac to Dc Power Converter in EHC Panel. Power Source Modified & Pressures Adjusted |
- on 920822,RPS Automatically Tripped Reactor on Thermal Margin/Low Pressure,Causing Increase in RCS Pressure Caused by Failure of Ac to Dc Power Converter in EHC Panel. Power Source Modified & Pressures Adjusted
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(vii), Common Cause Inoperability 10 CFR 50.73(a)(2)(iv), System Actuation 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) | 05000285/LER-1992-029, :on 920416,Radiation Protection Technician Received Unanticipated Intake of Radioactive Matls Due to Deficiencies in Method Used to Change Listed Filters.Maint & Radiation Protection Procedure Revised |
- on 920416,Radiation Protection Technician Received Unanticipated Intake of Radioactive Matls Due to Deficiencies in Method Used to Change Listed Filters.Maint & Radiation Protection Procedure Revised
| 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) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000285/LER-1992-030, :on 921130,fire Barrier Penetration 19-E-30 Breached to Support Maint on Ccw/Raw Water Hx.Between 921201 to 02,no Hourly Fire Watch Established.Caused by Lack of Attention to Detail.Personnel Counseled |
- on 921130,fire Barrier Penetration 19-E-30 Breached to Support Maint on Ccw/Raw Water Hx.Between 921201 to 02,no Hourly Fire Watch Established.Caused by Lack of Attention to Detail.Personnel Counseled
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2) | 05000285/LER-1992-031-01, Forwards LER 92-031-01 Providing Supplemental Info Re Safety Significance Evaluation & Updated Info on Several Corrective Actions | Forwards LER 92-031-01 Providing Supplemental Info Re Safety Significance Evaluation & Updated Info on Several Corrective Actions | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000285/LER-1992-031, :on 921203,steam Leak Developed in Drain Valve in SG Blowdown Processing Sys,Resulting in Automatic Start of Electric Fire Pump FP-1A.Caused by Lack of Sys Control. Equipment Tagging Procedure Revised & Piping Evaluated |
- on 921203,steam Leak Developed in Drain Valve in SG Blowdown Processing Sys,Resulting in Automatic Start of Electric Fire Pump FP-1A.Caused by Lack of Sys Control. Equipment Tagging Procedure Revised & Piping Evaluated
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) | 05000285/LER-1992-032, :on 921217,Door 1011-4 Declared Inoperable as Fire Barrier Because of Inoperable Latch.Caused by Personnel Error.Training Initiated for Licensed Operators & Security Supervisory Personnel |
- on 921217,Door 1011-4 Declared Inoperable as Fire Barrier Because of Inoperable Latch.Caused by Personnel Error.Training Initiated for Licensed Operators & Security Supervisory Personnel
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(1) |
|