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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000266/LER-1999-007, :on 990831,cable Tray Fire Stops Do Not Meet App R Exemption Requirements Occurred.Caused by Improper Installation of Approved Plant Mod.New Mod Has Been Initiated to Provide Three H Rated Fire Barrier1999-09-30030 September 1999
- on 990831,cable Tray Fire Stops Do Not Meet App R Exemption Requirements Occurred.Caused by Improper Installation of Approved Plant Mod.New Mod Has Been Initiated to Provide Three H Rated Fire Barrier
05000266/LER-1999-004, :on 990420,fuel Oil Transfer Pump Cable in AFW Pump Room Was Noted Outside App R Design Basis.Caused by Error in Design of New Fuel Oil Transfer Sys.Condition Rept CR 99-1140 Was Initiated1999-09-0202 September 1999
- on 990420,fuel Oil Transfer Pump Cable in AFW Pump Room Was Noted Outside App R Design Basis.Caused by Error in Design of New Fuel Oil Transfer Sys.Condition Rept CR 99-1140 Was Initiated
05000301/LER-1999-003-01, :on 990505,licensee Personnel Discovered That Refueling Interval Surveillance of Emergency Lighting Required by TS 15.4.6.A.3 Was Not Conducted.Cause Unknown. Task Sheet call-ups for Both Procedures Have Been Created1999-05-28028 May 1999
- on 990505,licensee Personnel Discovered That Refueling Interval Surveillance of Emergency Lighting Required by TS 15.4.6.A.3 Was Not Conducted.Cause Unknown. Task Sheet call-ups for Both Procedures Have Been Created
05000266/LER-1999-004, :on 990420,discovered That Fuel Oil Transfer Pump Cable in AFW Pump Room Outside App R Design Basis. Caused by Cable Routing Discrepancy.Fire Rounds Increased & Procedures Being Developed to Facilitate Using G-05 EDG1999-05-20020 May 1999
- on 990420,discovered That Fuel Oil Transfer Pump Cable in AFW Pump Room Outside App R Design Basis. Caused by Cable Routing Discrepancy.Fire Rounds Increased & Procedures Being Developed to Facilitate Using G-05 EDG
05000266/LER-1999-003, :on 990406,TS SR for ECCS & Containment Spray Was Not Fully Implemented.Caused by Conservative Interpretation of Valve Impact.Revised Procedures.With1999-05-0606 May 1999
- on 990406,TS SR for ECCS & Containment Spray Was Not Fully Implemented.Caused by Conservative Interpretation of Valve Impact.Revised Procedures.With
05000301/LER-1999-002-01, :on 990323,discovered That Red Channel of SG Pressure Indication Passes Through Fire Zone.Caused by 1983 Modification Oversight.Twice Per Shift Fire Round Has Been Established for Fire Zone Pending Cable Routing Correction1999-04-16016 April 1999
- on 990323,discovered That Red Channel of SG Pressure Indication Passes Through Fire Zone.Caused by 1983 Modification Oversight.Twice Per Shift Fire Round Has Been Established for Fire Zone Pending Cable Routing Correction
05000301/LER-1999-001-01, :on 990211,EDG Output Breaker Failed to Remain Closed During Surveillance Testing.Caused by Breaker Control Switch Failing to React Quickly.Modified Closing Circuit for EDG Output1999-03-10010 March 1999
- on 990211,EDG Output Breaker Failed to Remain Closed During Surveillance Testing.Caused by Breaker Control Switch Failing to React Quickly.Modified Closing Circuit for EDG Output
05000266/LER-1998-015, :on 980420,containment Fan Cooler Test Results Were Noted Outside Acceptance Criteria.Cause Is Under Evaluation.Pressure Washing of Air Side of Cooling Coils for All Four Unit 1 CFCs Has Been Completed1998-07-17017 July 1998
- on 980420,containment Fan Cooler Test Results Were Noted Outside Acceptance Criteria.Cause Is Under Evaluation.Pressure Washing of Air Side of Cooling Coils for All Four Unit 1 CFCs Has Been Completed
05000266/LER-1998-019, :on 980615,discovered That Containment Hydrogen Monitors Lacked Environmentally Qualified Coating on Terminal Strips.Caused by Terminal Strips Being Disturbed W/O Subsequent Reapplication of Coating.Replaced Coating1998-07-14014 July 1998
- on 980615,discovered That Containment Hydrogen Monitors Lacked Environmentally Qualified Coating on Terminal Strips.Caused by Terminal Strips Being Disturbed W/O Subsequent Reapplication of Coating.Replaced Coating
05000266/LER-1998-018, :on 980528,missed Surveillances for App J Testing of Containment Electrical Penetrations Occurred. Caused by Valve Discovered on Electrical Penetrations Inside Containment.Electrical Penetration Vent Valves Modified1998-06-29029 June 1998
- on 980528,missed Surveillances for App J Testing of Containment Electrical Penetrations Occurred. Caused by Valve Discovered on Electrical Penetrations Inside Containment.Electrical Penetration Vent Valves Modified
05000301/LER-1998-004-01, :on 980424,operations W/Reactor Core Power Level Was in Excess of 1518.5 Mwt.Caused by Failure to Return FT-466V Input Parameter to Off Scan.Input FT-446V Was Removed from on Scan at Approx 14521998-05-26026 May 1998
- on 980424,operations W/Reactor Core Power Level Was in Excess of 1518.5 Mwt.Caused by Failure to Return FT-466V Input Parameter to Off Scan.Input FT-446V Was Removed from on Scan at Approx 1452
05000301/LER-1998-003-01, :on 980408,ASME Section XI Pressure Test Program Surveillance Was Missed.Caused by Failure to Consult Latest Rev of Increased Frequency Surveillance List. Condition Rept Will Be Written to Document Requirement1998-05-0808 May 1998
- on 980408,ASME Section XI Pressure Test Program Surveillance Was Missed.Caused by Failure to Consult Latest Rev of Increased Frequency Surveillance List. Condition Rept Will Be Written to Document Requirement
05000266/LER-1998-011, :on 980214,missed TS Surveillance of Radiation Monitor Prior to Discharge Occurred.Caused by Failure to Adhere to Procedures Based on Failure to Recognize.Thorough Root Cause Evaluation Performed1998-04-22022 April 1998
- on 980214,missed TS Surveillance of Radiation Monitor Prior to Discharge Occurred.Caused by Failure to Adhere to Procedures Based on Failure to Recognize.Thorough Root Cause Evaluation Performed
05000301/LER-1998-002-01, :on 980313,discovered Serious Degradation of Reactor Coolant Cooling Water Return Line Check Valve.Caused by Service Related Wear.Valve Was Opened,Repaired & Returned to Service1998-04-13013 April 1998
- on 980313,discovered Serious Degradation of Reactor Coolant Cooling Water Return Line Check Valve.Caused by Service Related Wear.Valve Was Opened,Repaired & Returned to Service
05000266/LER-1998-010, :on 980213,inadequate TSs Surveillance of Containment Spray Logic Was Noted.Caused by Failure to Adequately Verify Bistable Trip Switch Position After Placement Into Normal Position1998-03-16016 March 1998
- on 980213,inadequate TSs Surveillance of Containment Spray Logic Was Noted.Caused by Failure to Adequately Verify Bistable Trip Switch Position After Placement Into Normal Position
05000266/LER-1997-043, :on 971115,inadequate TS Surveillance of RT Sys Interlocks Was Noted.Caused by Failure to Adequately Test RT Interlock Permissive Circuitry.Required Surveillance Testing of Permissive Circuitry Was Completed on 971121 & 9711251998-03-16016 March 1998
- on 971115,inadequate TS Surveillance of RT Sys Interlocks Was Noted.Caused by Failure to Adequately Test RT Interlock Permissive Circuitry.Required Surveillance Testing of Permissive Circuitry Was Completed on 971121 & 971125
05000266/LER-1998-008, :on 980203,EDG Air Start Motor Solenoid Valves W/Spring Not in Accordance W/Design Occurred.Caused by Use of 275 Psig Solenoid Valve Which Does Not Meet Minimum DC Voltage Available.Solenoid Valves Modified1998-03-0505 March 1998
- on 980203,EDG Air Start Motor Solenoid Valves W/Spring Not in Accordance W/Design Occurred.Caused by Use of 275 Psig Solenoid Valve Which Does Not Meet Minimum DC Voltage Available.Solenoid Valves Modified
05000266/LER-1998-009, :on 980203,inadequate TS Surveillance of under- Voltage Relay Contacts in Safeguards Sequence Circuitry,Was Determined.Caused by Failure to Adequately Test Relay Circuitry.Required Surveillance Testing Completed1998-03-0404 March 1998
- on 980203,inadequate TS Surveillance of under- Voltage Relay Contacts in Safeguards Sequence Circuitry,Was Determined.Caused by Failure to Adequately Test Relay Circuitry.Required Surveillance Testing Completed
05000301/LER-1998-001-01, :on 980202,SG Vent Mispositioned During Plant Heatup Were Noted.Caused by Inadequate Procedure Coordination.Subject Vent Valve Was Closed Approx 0928 on 9802021998-03-0404 March 1998
- on 980202,SG Vent Mispositioned During Plant Heatup Were Noted.Caused by Inadequate Procedure Coordination.Subject Vent Valve Was Closed Approx 0928 on 980202
05000266/LER-1998-001, :on 980102,missed Surveillances Required by Section XI Pressure Tp Constituted Condition Prohibited by Ts.Caused by Inadequate Procedural Control.Procedure Changes Completed to Set Test Frequency Requirements1998-02-0202 February 1998
- on 980102,missed Surveillances Required by Section XI Pressure Tp Constituted Condition Prohibited by Ts.Caused by Inadequate Procedural Control.Procedure Changes Completed to Set Test Frequency Requirements
05000266/LER-1997-043, :on 971115,inadequate TS Surveillance of RTS Interlocks Was Discovered.Caused by Failure to Adequately Test Reactor Trip Interlock Permissive Circuitry.Required Surveillance Testing of Permissive Circuitry Was Completed1997-12-15015 December 1997
- on 971115,inadequate TS Surveillance of RTS Interlocks Was Discovered.Caused by Failure to Adequately Test Reactor Trip Interlock Permissive Circuitry.Required Surveillance Testing of Permissive Circuitry Was Completed
05000266/LER-1997-040, :on 971017,discovered That Potential Existed for Unit 1 Lines to Fail,Due to Thermal Stresses Induced During Full Loss of Cooling to Reactor Coolant Pump Seals. Formal Code Compliance Analysis Initiated1997-11-17017 November 1997
- on 971017,discovered That Potential Existed for Unit 1 Lines to Fail,Due to Thermal Stresses Induced During Full Loss of Cooling to Reactor Coolant Pump Seals. Formal Code Compliance Analysis Initiated
05000266/LER-1997-039-01, :on 970615,RHR Loop Inoperable.Caused by Removal of CCW Pump from Svc.Ccw Pump Restored1997-11-0505 November 1997
- on 970615,RHR Loop Inoperable.Caused by Removal of CCW Pump from Svc.Ccw Pump Restored
05000266/LER-1996-016, :on 961030,discovered as-found Lift Pressure for Unit 2 Pressurizer Safety Valve 2RC-434 Exceeded Max Lift Pressure Allowed by ASME Code.Caused by Use of Ambient Temp in Test Lab.Set Valve at More Appropriate Ambient Temp1997-10-24024 October 1997
- on 961030,discovered as-found Lift Pressure for Unit 2 Pressurizer Safety Valve 2RC-434 Exceeded Max Lift Pressure Allowed by ASME Code.Caused by Use of Ambient Temp in Test Lab.Set Valve at More Appropriate Ambient Temp
05000266/LER-1997-038, :on 970926,determined That Inoperability of Standby Emergency Power Placed Unit 2 in 7-day Lco.Caused by Failure That Occurred When EDG G-03 Was Shutdown.Repaired Governor & Returned EDG G-03 to Service1997-10-24024 October 1997
- on 970926,determined That Inoperability of Standby Emergency Power Placed Unit 2 in 7-day Lco.Caused by Failure That Occurred When EDG G-03 Was Shutdown.Repaired Governor & Returned EDG G-03 to Service
05000266/LER-1997-020, :on 970414,discovered Conditions Outside of 10CFR50,App R,Safe Shutdown Analysis.Caused by Inadequate Documentation of Implementation of Existing App R,Safe Shutdown Analysis.Supplemented Compensatory Measures1997-10-14014 October 1997
- on 970414,discovered Conditions Outside of 10CFR50,App R,Safe Shutdown Analysis.Caused by Inadequate Documentation of Implementation of Existing App R,Safe Shutdown Analysis.Supplemented Compensatory Measures
05000266/LER-1997-036, :on 970826,potential Common Mode Failure in DC Power Supply Which Could Disable AFW Sys Was Noted.Caused by Inadequate Design & Design Review.Plant Mods Were Performed to Eliminate Potential Common Mode Failure1997-09-25025 September 1997
- on 970826,potential Common Mode Failure in DC Power Supply Which Could Disable AFW Sys Was Noted.Caused by Inadequate Design & Design Review.Plant Mods Were Performed to Eliminate Potential Common Mode Failure
NPL-97-0565, LER 97-S02-00:on 970815,perimeter Zones,Doors & Cameras Were Lost.Caused by Inadequate Compensatory Measures Taken for Failed Multiplexer.Repaired Mux for e-field Zone 81997-09-15015 September 1997 LER 97-S02-00:on 970815,perimeter Zones,Doors & Cameras Were Lost.Caused by Inadequate Compensatory Measures Taken for Failed Multiplexer.Repaired Mux for e-field Zone 8 05000301/LER-1997-004-01, :on 970729,declared RHR Loop Inoperable Due to CCW Leak.Caused by Failure of RHR Heat Exchanger CCW Piping. Repaired Piping & Declared RHR Loop Operable1997-08-28028 August 1997
- on 970729,declared RHR Loop Inoperable Due to CCW Leak.Caused by Failure of RHR Heat Exchanger CCW Piping. Repaired Piping & Declared RHR Loop Operable
05000301/LER-1997-005-01, :on 970806,RHR Pump Was Declared Inoperable Due to Abnormal Seal Leakage from Loop a RHR 2P-10A.Repaired RHR Pump1997-08-28028 August 1997
- on 970806,RHR Pump Was Declared Inoperable Due to Abnormal Seal Leakage from Loop a RHR 2P-10A.Repaired RHR Pump
05000266/LER-1997-027, :on 970521,non-environmentally Qualified Matl Existed in Containment Hatch Applications.Caused by Inadequate Design Review.Mods Will Be Performed to Remove Existing Teflon Material1997-06-19019 June 1997
- on 970521,non-environmentally Qualified Matl Existed in Containment Hatch Applications.Caused by Inadequate Design Review.Mods Will Be Performed to Remove Existing Teflon Material
05000266/LER-1997-025, :on 970520,pressurizer Level Was Controlled Higher than Assumed in Accident Analysis.Caused by Inappropriately Changing Procedures W/O Adequate Consideration.Listed Affected Procedures Will Be Revised1997-06-19019 June 1997
- on 970520,pressurizer Level Was Controlled Higher than Assumed in Accident Analysis.Caused by Inappropriately Changing Procedures W/O Adequate Consideration.Listed Affected Procedures Will Be Revised
05000266/LER-1997-023, :on 970508,discovered Noncompliant Emergency Lighting for Postulated App R Fires.Caused by Alternative Provisions Made in Original Safe Shutdown Analysis.Emergency Lights Will Be Installed1997-06-0505 June 1997
- on 970508,discovered Noncompliant Emergency Lighting for Postulated App R Fires.Caused by Alternative Provisions Made in Original Safe Shutdown Analysis.Emergency Lights Will Be Installed
05000266/LER-1997-024, :on 970501,determined Post Accident Sampling Sys Degradation.Caused by Inadequate Design Review.Will Upgrade Containment Atmosphere Sample Sys & Will Perform Mod to Reduce Dose within GDC 19 Dose Limits1997-06-0505 June 1997
- on 970501,determined Post Accident Sampling Sys Degradation.Caused by Inadequate Design Review.Will Upgrade Containment Atmosphere Sample Sys & Will Perform Mod to Reduce Dose within GDC 19 Dose Limits
05000266/LER-1997-021, :on 970430,determined That Spent Fuel Pool Cooling Sys Was Not in Accordance W/Plant Design Basis.Cause Indeterminate.Closed & re-tagged Valves SF-27 & SF-28 & Investigated Basis for Fsar,App a1997-05-30030 May 1997
- on 970430,determined That Spent Fuel Pool Cooling Sys Was Not in Accordance W/Plant Design Basis.Cause Indeterminate.Closed & re-tagged Valves SF-27 & SF-28 & Investigated Basis for Fsar,App a
05000266/LER-1997-020, :on 970414,conditions Outside 10CFR50 App R Safe Shutdown Analysis,Discovered.Caused by Inaccurate Interpretation.Compensatory Measures Originally Implemented as Deemed Necessary & Will Be Supplemented1997-05-14014 May 1997
- on 970414,conditions Outside 10CFR50 App R Safe Shutdown Analysis,Discovered.Caused by Inaccurate Interpretation.Compensatory Measures Originally Implemented as Deemed Necessary & Will Be Supplemented
05000301/LER-1997-002-01, :on 970415,potential Reactor Coolant Sys Branch Connection Stresses Beyond Design Basis,Indicated.Caused by Mod Initiated to Remove RTD Bypass Line Isolation Valves. Stress Analysis Conducted on RTD Bypass Piping1997-05-14014 May 1997
- on 970415,potential Reactor Coolant Sys Branch Connection Stresses Beyond Design Basis,Indicated.Caused by Mod Initiated to Remove RTD Bypass Line Isolation Valves. Stress Analysis Conducted on RTD Bypass Piping
05000266/LER-1997-016, :on 970325,SG Level Logic Was Not Tested IAW Ts.Caused by Nonconservative Interpretation of Tss.Ts Amends Proposed to Provide Consistency Between Test Requirements & LCO Associated W/Sg Tests1997-04-24024 April 1997
- on 970325,SG Level Logic Was Not Tested IAW Ts.Caused by Nonconservative Interpretation of Tss.Ts Amends Proposed to Provide Consistency Between Test Requirements & LCO Associated W/Sg Tests
05000266/LER-1997-015, :on 970324,control Room Ventilation Sys Declared Inoperable Due to Failures of Backdraft Damper & Vent Duct Access Door.Backdraft Damper,Replaced1997-04-23023 April 1997
- on 970324,control Room Ventilation Sys Declared Inoperable Due to Failures of Backdraft Damper & Vent Duct Access Door.Backdraft Damper,Replaced
05000266/LER-1997-014, :on 970321,auxiliary Feedwater Sys Inoperability Due to Loss of Instrument Air.Design Mods Initiated,Providing Pneumatic Supply to Control Valves1997-04-18018 April 1997
- on 970321,auxiliary Feedwater Sys Inoperability Due to Loss of Instrument Air.Design Mods Initiated,Providing Pneumatic Supply to Control Valves
05000266/LER-1997-011, :on 970305,containment Fan Cooler Accident Fans Were Not Tested in Accordance with Tss.Caused by non-conservative Interpretation of Literal Requirements of Tss.Unit 1 & 2 Accident Fans Were Tested1997-04-0303 April 1997
- on 970305,containment Fan Cooler Accident Fans Were Not Tested in Accordance with Tss.Caused by non-conservative Interpretation of Literal Requirements of Tss.Unit 1 & 2 Accident Fans Were Tested
05000266/LER-1997-012, :on 970304,diesel-drive Fire Pump Day Tank Not Sampled IAW TSs.Non-conservative Interpretation of TS Led to Failure.Day Tank T-30 Sample Was Drawn & Analyzed W/Satisfactory Results1997-04-0202 April 1997
- on 970304,diesel-drive Fire Pump Day Tank Not Sampled IAW TSs.Non-conservative Interpretation of TS Led to Failure.Day Tank T-30 Sample Was Drawn & Analyzed W/Satisfactory Results
05000266/LER-1997-010, :on 970219,svc Water & Component Cooling Water TS Action Requirements Were Not Met.Caused Because Licensee Did Not Comply W/Cold Shutdown Requirements of TS 15.3.3.C.2 & 15.3.3.D.2.Evaluations Were Performed1997-03-21021 March 1997
- on 970219,svc Water & Component Cooling Water TS Action Requirements Were Not Met.Caused Because Licensee Did Not Comply W/Cold Shutdown Requirements of TS 15.3.3.C.2 & 15.3.3.D.2.Evaluations Were Performed
05000266/LER-1997-009, :on 970214,potential for Safety Injection Failure During Filling of Safety Injection Accumulator Discovered.Caused by Situation Not Adequately Covered by Procedures.Procedure OI-100 Revised1997-03-17017 March 1997
- on 970214,potential for Safety Injection Failure During Filling of Safety Injection Accumulator Discovered.Caused by Situation Not Adequately Covered by Procedures.Procedure OI-100 Revised
NPL-97-0061, LER 97-S01-00:on 970204,compensatory Measures for Microwave Zones Had Not Been Implemented.Caused by Mgt Oversight of CAS & SAS Activities Was Inadequated.Addl Mgt Oversight of CAS & SAS Operations Has Been Implemented1997-03-0404 March 1997 LER 97-S01-00:on 970204,compensatory Measures for Microwave Zones Had Not Been Implemented.Caused by Mgt Oversight of CAS & SAS Activities Was Inadequated.Addl Mgt Oversight of CAS & SAS Operations Has Been Implemented 05000266/LER-1997-008, :on 970131,non-seismic Ductwork Located Above safety-related Equipment in Containment Occurred.Caused by Incomplete Seismic Evaluation.Mods Will Be Completed During Current Unit 2 Refueling Outage1997-03-0303 March 1997
- on 970131,non-seismic Ductwork Located Above safety-related Equipment in Containment Occurred.Caused by Incomplete Seismic Evaluation.Mods Will Be Completed During Current Unit 2 Refueling Outage
05000266/LER-1997-007, :on 970124,determined That Potential Existed for EDG Overload Condition.Caused by Failure to Recognize This Condition When Plants Initially Licensed W/Two Edgs. Implemented Procedure Changes1997-02-21021 February 1997
- on 970124,determined That Potential Existed for EDG Overload Condition.Caused by Failure to Recognize This Condition When Plants Initially Licensed W/Two Edgs. Implemented Procedure Changes
05000266/LER-1997-006, :on 970120,refueling Cavity Drain Failed During Loca.Caused by Inadequate Evaluation of Original Design.Design of Refueling Cavity Drains Was Revised with Respect Capability to Withstand an Earthquake1997-02-19019 February 1997
- on 970120,refueling Cavity Drain Failed During Loca.Caused by Inadequate Evaluation of Original Design.Design of Refueling Cavity Drains Was Revised with Respect Capability to Withstand an Earthquake
05000266/LER-1997-005, :on 970116,1SI-852A Was Not Tested IAW Inservice Test Program Required by Tss.Caused Because Condition Revealed That Valve 1SI-852A Had Not Been Completely Tested.Tests Will Be Reviewed1997-02-14014 February 1997
- on 970116,1SI-852A Was Not Tested IAW Inservice Test Program Required by Tss.Caused Because Condition Revealed That Valve 1SI-852A Had Not Been Completely Tested.Tests Will Be Reviewed
05000266/LER-1997-004, :on 970113,potential for Particular Common Mode Failure That Could Affect Opposite Trains of Unit 2 Safeguards Equipment Was Noted.Caused by Lack of Physical Separation.Replaced Subject Circuit Breakers1997-02-12012 February 1997
- on 970113,potential for Particular Common Mode Failure That Could Affect Opposite Trains of Unit 2 Safeguards Equipment Was Noted.Caused by Lack of Physical Separation.Replaced Subject Circuit Breakers
1999-09-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARNPL-99-0569, Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with 05000266/LER-1999-007, :on 990831,cable Tray Fire Stops Do Not Meet App R Exemption Requirements Occurred.Caused by Improper Installation of Approved Plant Mod.New Mod Has Been Initiated to Provide Three H Rated Fire Barrier1999-09-30030 September 1999
- on 990831,cable Tray Fire Stops Do Not Meet App R Exemption Requirements Occurred.Caused by Improper Installation of Approved Plant Mod.New Mod Has Been Initiated to Provide Three H Rated Fire Barrier
ML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 05000266/LER-1999-004, :on 990420,fuel Oil Transfer Pump Cable in AFW Pump Room Was Noted Outside App R Design Basis.Caused by Error in Design of New Fuel Oil Transfer Sys.Condition Rept CR 99-1140 Was Initiated1999-09-0202 September 1999
- on 990420,fuel Oil Transfer Pump Cable in AFW Pump Room Was Noted Outside App R Design Basis.Caused by Error in Design of New Fuel Oil Transfer Sys.Condition Rept CR 99-1140 Was Initiated
NPL-99-0051, Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with ML20211A7641999-08-11011 August 1999 Safety Evaluation Supporting Amends 190 & 195 to Licenses DPR-24 & DPR-27,respectively NPL-99-0449, Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with ML20209D2691999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbnps,Units 1 & 2 ML20196J4251999-06-30030 June 1999 Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 ML20196F3341999-06-22022 June 1999 Safety Evaluation for Implementation of 422V+ Fuel Assemblies at Pbnp Units 1 & 2 ML20195F9781999-06-10010 June 1999 Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1 NPL-99-0328, Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with ML20209D2751999-05-31031 May 1999 Revised MORs for May 1999 for Pbnps,Units 1 & 2 05000301/LER-1999-003-01, :on 990505,licensee Personnel Discovered That Refueling Interval Surveillance of Emergency Lighting Required by TS 15.4.6.A.3 Was Not Conducted.Cause Unknown. Task Sheet call-ups for Both Procedures Have Been Created1999-05-28028 May 1999
- on 990505,licensee Personnel Discovered That Refueling Interval Surveillance of Emergency Lighting Required by TS 15.4.6.A.3 Was Not Conducted.Cause Unknown. Task Sheet call-ups for Both Procedures Have Been Created
05000266/LER-1999-004, :on 990420,discovered That Fuel Oil Transfer Pump Cable in AFW Pump Room Outside App R Design Basis. Caused by Cable Routing Discrepancy.Fire Rounds Increased & Procedures Being Developed to Facilitate Using G-05 EDG1999-05-20020 May 1999
- on 990420,discovered That Fuel Oil Transfer Pump Cable in AFW Pump Room Outside App R Design Basis. Caused by Cable Routing Discrepancy.Fire Rounds Increased & Procedures Being Developed to Facilitate Using G-05 EDG
05000266/LER-1999-003, :on 990406,TS SR for ECCS & Containment Spray Was Not Fully Implemented.Caused by Conservative Interpretation of Valve Impact.Revised Procedures.With1999-05-0606 May 1999
- on 990406,TS SR for ECCS & Containment Spray Was Not Fully Implemented.Caused by Conservative Interpretation of Valve Impact.Revised Procedures.With
ML20196F3521999-04-30030 April 1999 Non-proprietary WCAP-14788, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt - NSSS Power) NPL-99-0273, Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With ML20206A5031999-04-23023 April 1999 Safety Evaluation Supporting Amends 189 & 194 to Licenses DPR-24 & DPR-27,respectively 05000301/LER-1999-002-01, :on 990323,discovered That Red Channel of SG Pressure Indication Passes Through Fire Zone.Caused by 1983 Modification Oversight.Twice Per Shift Fire Round Has Been Established for Fire Zone Pending Cable Routing Correction1999-04-16016 April 1999
- on 990323,discovered That Red Channel of SG Pressure Indication Passes Through Fire Zone.Caused by 1983 Modification Oversight.Twice Per Shift Fire Round Has Been Established for Fire Zone Pending Cable Routing Correction
NPL-99-0193, Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with 05000301/LER-1999-001-01, :on 990211,EDG Output Breaker Failed to Remain Closed During Surveillance Testing.Caused by Breaker Control Switch Failing to React Quickly.Modified Closing Circuit for EDG Output1999-03-10010 March 1999
- on 990211,EDG Output Breaker Failed to Remain Closed During Surveillance Testing.Caused by Breaker Control Switch Failing to React Quickly.Modified Closing Circuit for EDG Output
ML20207K2751999-03-0202 March 1999 Safety Evaluation Supporting Amends 188 & 193 to Licenses DPR-24 & DPR-27,respectively ML20207L3471999-03-0202 March 1999 Safety Evaluation Supporting Amends 187 & 192 to Licenses DPR-24 & DPR-27,respectively ML20207D5691999-03-0101 March 1999 Safety Evaluation Supporting Amends 186 & 191 to Licenses DPR-24 & DPR-27,respectively NPL-99-0134, Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with ML20207D6751999-02-22022 February 1999 Assessment of Design Info on Piping Restraints for Point Beach Nuclear Plant,Units 1 & 2.Staff Concludes That Licensee Unable to Retrieve Original Analyses That May Have Been Performed to Justify Removal of Shim Collars ML20206R9001999-01-13013 January 1999 SER Accepting Nuclear Quality Assurance Program Changes for Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0091, 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with1998-12-31031 December 1998 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with NPL-99-0008, Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with ML20198C7671998-12-10010 December 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME BPV Code,1986 Edition,Section XI Requirement IWA-2232, to Use Performance Demonstration Initiative Program During RPV Third 10-yr ISI for Plant,Unit 2 NPL-98-1006, Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20195J5101998-11-16016 November 1998 Proposed Revs to Section 1.3 of FSAR for Pbnp QA Program ML20198J5941998-11-0303 November 1998 1998 Graded Exercise,Conducted on 981103 NPL-98-0948, Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With NPL-98-0880, Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored1998-10-21021 October 1998 Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored ML20154M9121998-10-14014 October 1998 Unit 1 Refueling 24 Repair/Replacement Summary Rept for Form NIS-2 ML20154L6751998-10-14014 October 1998 Unit 1 Refueling 24 ISI Summary Rept for Form NIS-1 NPL-98-0826, Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20151W3851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbnp Units 1 & 2 NPL-98-0653, Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4471998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 2 ML20151W4541998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 1 ML20236U7201998-07-21021 July 1998 Safety Evaluation Supporting Amend 190 to License DPR-27 05000266/LER-1998-015, :on 980420,containment Fan Cooler Test Results Were Noted Outside Acceptance Criteria.Cause Is Under Evaluation.Pressure Washing of Air Side of Cooling Coils for All Four Unit 1 CFCs Has Been Completed1998-07-17017 July 1998
- on 980420,containment Fan Cooler Test Results Were Noted Outside Acceptance Criteria.Cause Is Under Evaluation.Pressure Washing of Air Side of Cooling Coils for All Four Unit 1 CFCs Has Been Completed
ML20236T1761998-07-17017 July 1998 Safety Evaluation Supporting Amends 185 & 189 to Licenses DPR-24 & DPR-27,respectively 05000266/LER-1998-019, :on 980615,discovered That Containment Hydrogen Monitors Lacked Environmentally Qualified Coating on Terminal Strips.Caused by Terminal Strips Being Disturbed W/O Subsequent Reapplication of Coating.Replaced Coating1998-07-14014 July 1998
- on 980615,discovered That Containment Hydrogen Monitors Lacked Environmentally Qualified Coating on Terminal Strips.Caused by Terminal Strips Being Disturbed W/O Subsequent Reapplication of Coating.Replaced Coating
ML20236S0161998-07-13013 July 1998 Safety Evaluation Supporting Amends 184 & 188 to Licenses DPR-24 & DPR-27,respectively ML20236Q3161998-07-10010 July 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements PTP-3-01 & PTP-3-02 ML20236L6061998-07-0808 July 1998 Safety Evaluation Granting Request for Relief RR-2-23,from Performing ASME Code,Section XI Volumetric Coverage Requirements for SG nozzle-to-safe End Welds & Associated Safe end-to-pipe Welds During Third 10-yr ISI Interval 1999-09-30
[Table view] |
text
a s
Wisconsin Electnc v
' POWER COMPANY -
Point Beoch Nucbar Plant (920) 755-2321.
6610 Nuclear Rd.. Iwo Rtvers WI 54241 NPL 98-0076 February 2,1998-Document Control Desk U.S. NUCLEAR REGULATORY COMMIS3 ION Mail Station Pl-137 Washington, D. C,20555 Ladies / Gentlemen:
DOCKETS 50-266 AND 50-301 LICENSEE EVENT _REPORTJ8-001-00 MISSED SURVEILLANCES REOUIRED BY TIIE SECTION XI PRESSURE TEST PROGRAM CONSTITUTED AN OPERATION PROHIBITED BY TECHNICAL SPECIFICATIONS.
EDINT BEACil NUCLEAR PLANT. UNITS 1 AND 2 Enclosed is Licensee Event Repcrt 98 001-00 for Point Beach Nuclear Plant, Unit I and Unit 2.
This report is provided in accordance with 10 CFR 50.73(a)(2)(i)(B), an " operation prohibited by the plant's Technical Specifications " This report describes the discovery that five 40 month Section XI pressure tests were not performed within the required time frame.
- Please coraact us ifyou r vire additionalinformatior..
Sincerely,.
h'j
/
ouglas F. Johnson 1
Manager - Regulatory Services & Licensing Enclosure -
cc:
NRC Resident inspector NRC Regional Administrator
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EXPlRES 04/30/80 ESilMATED SURDEN PER RESPOfiSE TO COMPLY WITH p
THIS INFORMATION COLLECTION REQUFSY 50.0 HRS.
LICENSEE EVENT REPORT (LER)
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- INDUSTRY, FORWARD COMMENTS RE GARDINO SURDEN ESilMATE TO THE INFORMATIOP AND (See reverse for required number of RECORDS MANAGEMENT BRANCH (T 6 F33).
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NUCLEAR REOULATORY COMMISSON. WA4mNOTON.
'l DC 20556 0001, AND TO THE PAPERWORK REDUCTION FHOJE CT P ACEfTY NAME (1)
DOCKET NUMSER (2)
PA 3E (3)
Point Beach Nuclear Plant, Unit 1 05000266 1 OF 5 TITLE 141 Missed Surveillances Required by the Section XI Preasure Test Program Constituted an Condition Prohibited by Technical Specifications l
EVEN) DATE (El l
LER NUMC'R ISI REPORT DATE (7)
OTHER F ACElTIES INVOLVI J (8)
SEQUENTIAL F4EVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR YEAP NUMBER NUMBER MONT DAY YEAR Unit 2 05000301 H
I 98 FACILITY NAME DOCKET NUMBER I1 001 00 02 02 93 05000 02 98 I OPERATING THIS REFORT IS SUSMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR E: ICheck one or enorel (til MODE (S)
N l 20 220iini 20.2203.H 2)lvi X
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bo.73<aH2)uo 73.75 20.2203taH2)(io 20.2203taH4) 50.736al12)0vi OTHER 20.2203(aH2Han 60.36tcH1) 60.73(aH2Hv) so.edy in Abeweet blow
- 20. 2203taH2H6vt 50.36(cH2) 50.73(aH2Hvu) er 6n NRC Few. 346A LICENSEE CONTACT FOR THIS LER 112) l N AME TELEPHONE NUMBER (include Area Code) lJcmes E. Knorr Regulation Compliance Manger (414) 221-6863 COMPLETE ONE LINE FOR E ACH COMPONENT FAILURE DESCRISED IN THIS REPORT (13)
CAUSE
SYSTEM COMPONt.N T MANUFAFURER REPOR T ABLE
CAUSE
SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPROS TO NPROS l
SUPPLEMENT AL REPORT EXPECTED 1141 XPECTED YFAR l
YES SUSMISSION ttf yea, cornplete f XPECTED SUBMISSION DATEl.
X NO DATE (18)
ASaf RACT (Lirnet to 1400 spaces. 6 e., approstrnately 15 smgle-spaced typewritten bnes) (IS)
On January 2, 1998, while Point Beach Nuclear Plant (PBNP) Unit 1 was operating at 98 percent power and Unit 2 was in a cold shutdown condition, Wisconsin Electric determined that five pressure tests required by the Gection XI pressure test program that had not been conducted were in fact missed surveillances. The pressure testing was completed on January 3, or prior to returning equipment associated with the tests to operable status.
The cause of the missed surveillances was inadequate procedural control to assure completion in accoraance with the requirements of the Pressure Test Program. Procedure changes will be completed to set test frequency requirements.
NRC FORM 3d6 (4 85) l
NRC FORM M4A U.S. LUCLE AR REGULATORY COMMi&&lON (4 961 LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION F ACRRV NAME (U DOCK!T NUM8f R (21 (f M NUMBER (S)
FAOE (3)
Point Beach Nuclear Plant, Unit 1 05000266 NU M V E 2 OF 5 001 00 98 it K1 Irf mate wece ne requeed, use addotenal casues of NRC f arm 3664) l1h 4
Event Description
^
On September 16, 1996 five ASME Section XI tests wers discovered which were not completed in accordance with the Pressure Test Program.
These were documented on a condition report (CR 96-840) at that time. As a recult of that condition report a corrective action was assigned to perform the tests prior to the end of the interval which ends for Unit 1 on November 30, 2000 and for Unit 2 on September 30, 2002.
On November 4, 1997 an additional condition report (CR 97-3730) was created to occument the operability of the systems associated with the original condition report. On January 2, 1998, while Point Beach Nuclear Plant (PBNP) Unit 1 was operating at 98 percent power and Unit 2 was in a cold shutdown condition, Wisconsin Electric determined that the five pressure tests required by the Section XI pressure test program that had been identified in 1996 were in fact missad surveillances.
The following 40 month pressure tests were not performed within the required frequency and their last completion date prior to January 3, 1998 is listed:
Functional Test of the Gol Emergency Diesel Generator Air Start System (February 7, 1990)
Functional Test of the G02 Emergency Diesel Generator Air Start System (August 17, 1989)
Inservice Test of the Waste Gas System (Deceraber 7, 1991 and September 19, 1991) i Inservice Test of the Unit 1 Boric Acid Tanks and Transfer Piping (April 1, 1987 and April 15, 1987)
Functional Test of the Unit 2 RWST and Associated Piping (September 19, 1989)
The first three of the missed pressure tests were completed on January 3.
The remainder were tested prior to returning equipment associated with the tested systems to operable statua.
Causes
The cause of the missed surveillances was inadequate procedural control to assure completion in accordance with the requirements of the Pressure Test Program.
NRC FOHM 366A (4 95)
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LICENSEE EVENT REPORT (LER)
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Point Beach Nuclear Plant, Unit 1 05000266 NSEIa E a" 3 OF 5
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Corrective Actionst 1.
The Functional Test of the Unit 2 RWST and Associated Piping was completed on November 6, 1997.
2.
An operarility determination addressing the romaining systems was complete.n accord 6nce
.ch the corrective action program and Generic Letter 91-18 on or about Nov6uber 6.,
- 1997, 3.
As discussed above, after determination that the missed tests were in fact missed surveillances, the pressure testing of the following systems wara completed on January 3, 1998:
7 Functional Test of the G01 Emergency Diesel Gcnerator Air Start System Inservice Test of the Waste Gas System Inservice Test of the Unit 1 Boric Acio Tanks and Transfer Piping The last two inspections were not completed within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of determining these tests were required, and appropriate systems were dec1cred inoperable.
No Technical Specification actions r-"ded to be entered.
4.
The Functional Test of the G02 Emergency Diesel Generator Air Start System was completed on January 23, 1998.
5.
The procedures which control the frequency of those tests will be revised to include these pressure tests by June 1, 1998.
i 6.
The following procedures will be reviewed for revision to requ re the 40 month pressure testing to be performed in conjunction with IT-600, IT-17 and IT-1075 as discussed below.
These revisions or new procedures will be implemented by June 1, 1998.
Component and System Description The primary purpose of the G01 and G02 air start systems is to provide a tank with a nominal working pressure of 175 psi to the starting system for the emergency diesel generators.
Each unit has its cwn independent starting system, including two banks of three air storage tanks.
The pressure test for these systems is performed via a Preventive Maintenance / Surveillance Test "ork Order, li l
U.S. P.JCL AR REOUL ATORY commis4 ION NRC f ORM 368A s
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LICENBEE EVENT REPORT (LER)
TEXT CONTINUATION 4
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Point Beach Nuclear Plant, Unit 1 05000265
" YES Uu$$Ii Nu 4 OF 5 00 001 93 i
nx1 af more om os requad, vee eHmonalreques of NRC form 36eN (17) 55 The viste gas system includes the gan decay tank and associated piping.
This test has been performed in the past by a now discontinued procedure.
The pressure test on this system will now be performed once each 40 months in conjunction with IT-600, " Waste Gas System Gaseous Leak Checks ( Annual). "
The Unit 1 boric acid tanks and transfer piping pressure tast was performed by a now discontinued procedure.
The test will. tow be conducted once each 40 months in conjunction with IT-17, Boric Acid Transfer Pumps and Valves (Quarterly)."
The functional tost of the Unit 2 RWST and associated piping was conducted by a now discontinued procedure.
The test will now be conducted in accordance with IT-1075, "40 month Functional Pressure Test of Refueling Water Storage Tank Piping."
Safety Assessment
Each of the systems ic a system required for the safe operation of Point Beach or response to an accident.
The pressure test program is designed to detect any evidence of leakage.
The frequency for each test in this case was 40 months.
The most recent tests showed no evidence of unacceptable Itakage.
Therefore, there was no probability of failure of these systems to perform their safety function during the period of failure to test.
None the less each of these systems would have exhibited some dagradation during their normal Technical Specification surveillances or preventctive maintenance.
No degradation of a type which would have been specifically sought out was discovered during the Technical Specification surveillances or preventative maintenance.
Therefore the haalth and safety of the public or plant personnel was not compromised by these missed surveillances.
System and Component Identifiers The Energy Industry Identification System component function identifier for eacn component / system referred to in this report are as follows:
Component / System Identifier EDG Air Start System TK Waste Gas System TK Transfer Pipe Pipe Acid Tanks TK Refueling Water Storage Tank TK FPC Fori5esA t4-esi
" +
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LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION t
f ACILITV NAtW (1)
DOCEET NUhetER (2)
LER NUMSER 18)
P AGE 133.,
YEAR
&E QUE NTL*
- REVISION PSint Beach Nuclear Plant, Unit 1 05000266 wUweEn wuueER S OF-5 00 98 001 if ni tir more space se reeuemt. use essatenes coone or avec form sesAs s1n similar occurrences:
No recent reportable conditions caused by the miss of surveillances contained in a Section XI program have been found.
NRC FORM 3664 (4 95)
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05000266/LER-1998-001, :on 980102,missed Surveillances Required by Section XI Pressure Tp Constituted Condition Prohibited by Ts.Caused by Inadequate Procedural Control.Procedure Changes Completed to Set Test Frequency Requirements |
- on 980102,missed Surveillances Required by Section XI Pressure Tp Constituted Condition Prohibited by Ts.Caused by Inadequate Procedural Control.Procedure Changes Completed to Set Test Frequency Requirements
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000301/LER-1998-001-01, :on 980202,SG Vent Mispositioned During Plant Heatup Were Noted.Caused by Inadequate Procedure Coordination.Subject Vent Valve Was Closed Approx 0928 on 980202 |
- on 980202,SG Vent Mispositioned During Plant Heatup Were Noted.Caused by Inadequate Procedure Coordination.Subject Vent Valve Was Closed Approx 0928 on 980202
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(iv), System Actuation | 05000301/LER-1998-001, Forwards LER 98-001-00,describing Mispositioning Event Which Resulted in SG Venting Steam Outside Containment During Plant Heatup.Commitments Are Encl in Rept in Italics | Forwards LER 98-001-00,describing Mispositioning Event Which Resulted in SG Venting Steam Outside Containment During Plant Heatup.Commitments Are Encl in Rept in Italics | 10 CFR 50.73(a)(2)(v), Loss of Safety Function | 05000301/LER-1998-002, Forwards LER 98-002-00 Re Serious Degradation of Reactor Coolant Pump Component Cooling Water Return Line Check Valve Which May Prevent Closure | Forwards LER 98-002-00 Re Serious Degradation of Reactor Coolant Pump Component Cooling Water Return Line Check Valve Which May Prevent Closure | | 05000301/LER-1998-002-01, :on 980313,discovered Serious Degradation of Reactor Coolant Cooling Water Return Line Check Valve.Caused by Service Related Wear.Valve Was Opened,Repaired & Returned to Service |
- on 980313,discovered Serious Degradation of Reactor Coolant Cooling Water Return Line Check Valve.Caused by Service Related Wear.Valve Was Opened,Repaired & Returned to Service
| 10 CFR 50.73(a)(2)(x) | 05000266/LER-1998-003-01, Forwards LER 98-003-01 Re Discovery That Flow Rates Were Outside Design Basis of Plant.Rept Revises Corrective Action Commitment Re Replacement of SW Piping to Unit 2 Fan Cooler Motor Heat Exchangers | Forwards LER 98-003-01 Re Discovery That Flow Rates Were Outside Design Basis of Plant.Rept Revises Corrective Action Commitment Re Replacement of SW Piping to Unit 2 Fan Cooler Motor Heat Exchangers | 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000301/LER-1998-003-01, :on 980408,ASME Section XI Pressure Test Program Surveillance Was Missed.Caused by Failure to Consult Latest Rev of Increased Frequency Surveillance List. Condition Rept Will Be Written to Document Requirement |
- on 980408,ASME Section XI Pressure Test Program Surveillance Was Missed.Caused by Failure to Consult Latest Rev of Increased Frequency Surveillance List. Condition Rept Will Be Written to Document Requirement
| 10 CFR 50.73(a)(2)(1) | 05000301/LER-1998-003, Forwards LER 98-003-00,describing Discovery That Vent Valve from Reactor Coolant Drain Tank Which Had Been Placed on Increased Frequency Surveillance for Stroke Time Was Not Tested in Time Frame Required.New Commitments in Ital | Forwards LER 98-003-00,describing Discovery That Vent Valve from Reactor Coolant Drain Tank Which Had Been Placed on Increased Frequency Surveillance for Stroke Time Was Not Tested in Time Frame Required.New Commitments in Italics | | 05000301/LER-1998-004, Forwards LER 98-004-00,which Describes Operation of Unit W/Eight Hour Average Reactor Thermal Output in Excess of Licensed Limit.Commitments Made within Ltr Encl | Forwards LER 98-004-00,which Describes Operation of Unit W/Eight Hour Average Reactor Thermal Output in Excess of Licensed Limit.Commitments Made within Ltr Encl | 10 CFR 50.73(a)(2)(i) | 05000301/LER-1998-004-01, :on 980424,operations W/Reactor Core Power Level Was in Excess of 1518.5 Mwt.Caused by Failure to Return FT-466V Input Parameter to Off Scan.Input FT-446V Was Removed from on Scan at Approx 1452 |
- on 980424,operations W/Reactor Core Power Level Was in Excess of 1518.5 Mwt.Caused by Failure to Return FT-466V Input Parameter to Off Scan.Input FT-446V Was Removed from on Scan at Approx 1452
| 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(1) | 05000266/LER-1998-008, :on 980203,EDG Air Start Motor Solenoid Valves W/Spring Not in Accordance W/Design Occurred.Caused by Use of 275 Psig Solenoid Valve Which Does Not Meet Minimum DC Voltage Available.Solenoid Valves Modified |
- on 980203,EDG Air Start Motor Solenoid Valves W/Spring Not in Accordance W/Design Occurred.Caused by Use of 275 Psig Solenoid Valve Which Does Not Meet Minimum DC Voltage Available.Solenoid Valves Modified
| 10 CFR 50.73(a)(2)(ii)(B), Unanalyzed Condition | 05000266/LER-1998-009, :on 980203,inadequate TS Surveillance of under- Voltage Relay Contacts in Safeguards Sequence Circuitry,Was Determined.Caused by Failure to Adequately Test Relay Circuitry.Required Surveillance Testing Completed |
- on 980203,inadequate TS Surveillance of under- Voltage Relay Contacts in Safeguards Sequence Circuitry,Was Determined.Caused by Failure to Adequately Test Relay Circuitry.Required Surveillance Testing Completed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(1) | 05000266/LER-1998-010, :on 980213,inadequate TSs Surveillance of Containment Spray Logic Was Noted.Caused by Failure to Adequately Verify Bistable Trip Switch Position After Placement Into Normal Position |
- on 980213,inadequate TSs Surveillance of Containment Spray Logic Was Noted.Caused by Failure to Adequately Verify Bistable Trip Switch Position After Placement Into Normal Position
| 10 CFR 50.73(a)(2)(1) | 05000266/LER-1998-010-01, Forwards LER 98-010-01,re Containment Spray Channel Functional Testing.Commitments Made within Ltr,Encl | Forwards LER 98-010-01,re Containment Spray Channel Functional Testing.Commitments Made within Ltr,Encl | 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications | 05000266/LER-1998-011, :on 980214,missed TS Surveillance of Radiation Monitor Prior to Discharge Occurred.Caused by Failure to Adhere to Procedures Based on Failure to Recognize.Thorough Root Cause Evaluation Performed |
- on 980214,missed TS Surveillance of Radiation Monitor Prior to Discharge Occurred.Caused by Failure to Adhere to Procedures Based on Failure to Recognize.Thorough Root Cause Evaluation Performed
| 10 CFR 50.73(a)(2)(1) | 05000266/LER-1998-015-01, Forwards LER 98-015-01 Re Containment Fan Cooler Test Results Outside Acceptance Criteria.Addl Info Re Corrective Actions Taken,Provided.No New Commitments,Made | Forwards LER 98-015-01 Re Containment Fan Cooler Test Results Outside Acceptance Criteria.Addl Info Re Corrective Actions Taken,Provided.No New Commitments,Made | 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | 05000266/LER-1998-015, :on 980420,containment Fan Cooler Test Results Were Noted Outside Acceptance Criteria.Cause Is Under Evaluation.Pressure Washing of Air Side of Cooling Coils for All Four Unit 1 CFCs Has Been Completed |
- on 980420,containment Fan Cooler Test Results Were Noted Outside Acceptance Criteria.Cause Is Under Evaluation.Pressure Washing of Air Side of Cooling Coils for All Four Unit 1 CFCs Has Been Completed
| | 05000266/LER-1998-018, :on 980528,missed Surveillances for App J Testing of Containment Electrical Penetrations Occurred. Caused by Valve Discovered on Electrical Penetrations Inside Containment.Electrical Penetration Vent Valves Modified |
- on 980528,missed Surveillances for App J Testing of Containment Electrical Penetrations Occurred. Caused by Valve Discovered on Electrical Penetrations Inside Containment.Electrical Penetration Vent Valves Modified
| 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications 10 CFR 50.73(a)(2)(1) | 05000266/LER-1998-019, :on 980615,discovered That Containment Hydrogen Monitors Lacked Environmentally Qualified Coating on Terminal Strips.Caused by Terminal Strips Being Disturbed W/O Subsequent Reapplication of Coating.Replaced Coating |
- on 980615,discovered That Containment Hydrogen Monitors Lacked Environmentally Qualified Coating on Terminal Strips.Caused by Terminal Strips Being Disturbed W/O Subsequent Reapplication of Coating.Replaced Coating
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