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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000278/LER-1993-0061993-09-0303 September 1993 LER 93-006-00:on 930814,LPCI Sys Became Inoperable When Triple Low Water Level Signal Simulated on Unit 2.RWL Instrumentation LT-72B Valved Out of Svc & Equalized Allowing Indicated Water Level to increase.W/930903 Ltr 05000278/LER-1993-0051993-09-0303 September 1993 LER 93-005-00:on 930809,HPCI Sys Declared Inoperable Due to Defective Flow Controller.Flow Controller Removed,All Potentiometers & Boards Cleaned,Flow Controller Reinstalled & Necessary Testing & Tuning performed.W/930903 Ltr 05000278/LER-1993-0041993-08-30030 August 1993 LER 93-004-00:on 930730,simulated Low Steam Flow Signal to Recombiner Initiated Isolation Signal to Off Gas Recombiner, Causing Main Condenser Vacuum to Begin Decreasing.Special Procedure SP-1438 revised.W/930830 Ltr 05000277/LER-1990-0141990-07-19019 July 1990 LER 90-014-00:on 900620,RWCU Isolation Occurred During Pressurization of Sys Following Isolation Valve Maint.Caused by Design Weakness.Design of Instrumentation Reviewed & Procedural Controls enhanced.W/900719 Ltr 05000278/LER-1990-0071990-07-18018 July 1990 LER 90-007-00:on 900620,RWCU Isolated While Pressurizing Sys Following Isolation Valve Insp.Caused by Design Weakness. Design of Instrumentation Reviewed & Procedural Controls enhanced.W/900719 Ltr 05000277/LER-1990-0131990-06-27027 June 1990 LER 90-013-00:on 900530,failure to Perform Tech Spec Surveillance Tests Since 891130 Discovered.Caused by Incorrect Std Practice.Tests Revised to Clarify Testing Requirements of Tech Spec 4.14.C.1.c.W/900627 Ltr 05000277/LER-1989-007, Corrected LER 89-007-00:on 890411,green Discoloration Discovered in Grease on Stabs of Control Fuses in Switchgear.Root Cause of Event Under Investigation.Stabs Lubricated W/Different Type of Approved Grease1989-05-0909 May 1989 Corrected LER 89-007-00:on 890411,green Discoloration Discovered in Grease on Stabs of Control Fuses in Switchgear.Root Cause of Event Under Investigation.Stabs Lubricated W/Different Type of Approved Grease 05000277/LER-1989-006, Corrected LER 89-006-00:on 890209 & 25,determined That Tubing to Containment Isolation Valve Installed W/Inadequate Support & Containment Atmosphere Control & Dilution Sys Not Per Applicable Installation Criteria.Controls Estab1989-05-0909 May 1989 Corrected LER 89-006-00:on 890209 & 25,determined That Tubing to Containment Isolation Valve Installed W/Inadequate Support & Containment Atmosphere Control & Dilution Sys Not Per Applicable Installation Criteria.Controls Established 05000277/LER-1987-016, Corrected LER 87-016-00:on 870820,isolations Occurred When Four of Eight 4 Kv Emergency Transformers Momentarily de-energized.Caused by Inadequate Concern for Potential Electrical Hazard by Maint Craft Supervision1987-09-28028 September 1987 Corrected LER 87-016-00:on 870820,isolations Occurred When Four of Eight 4 Kv Emergency Transformers Momentarily de-energized.Caused by Inadequate Concern for Potential Electrical Hazard by Maint Craft Supervision 05000000/LER-1986-022, Partially Deleted LER 86-022-02:on 861018,potential Undetected Access Into Vital Area Discovered.Caused by Use of Incorrect Procedure.Card Reader Replaced & Tested to Ensure Proper Operation1987-02-20020 February 1987 Partially Deleted LER 86-022-02:on 861018,potential Undetected Access Into Vital Area Discovered.Caused by Use of Incorrect Procedure.Card Reader Replaced & Tested to Ensure Proper Operation 05000000/LER-1986-030, Partially Deleted LER 86-030-00:on 861211,unauthorized Opening Into Protected Area Discovered.Caused by Area Not Properly Identified as Area for Security Concern.Signs Posted1986-12-16016 December 1986 Partially Deleted LER 86-030-00:on 861211,unauthorized Opening Into Protected Area Discovered.Caused by Area Not Properly Identified as Area for Security Concern.Signs Posted 05000000/LER-1986-026, Partially Deleted LER 86-026-00:on 861124,vital Area Door Discovered W/O Alarm Capability.Caused by Personnel Error. Secutiry Officer in Question Terminated & Function of Administrative Sergeant Reviewed1986-12-0101 December 1986 Partially Deleted LER 86-026-00:on 861124,vital Area Door Discovered W/O Alarm Capability.Caused by Personnel Error. Secutiry Officer in Question Terminated & Function of Administrative Sergeant Reviewed 05000000/LER-1986-023, Partially Deleted LER 86-023-01:on 861023,unauthorized Access Into Vital Area Door Discovered.Caused by Card Reader Malfunction.Malfunctioning Card Reader Replaced.Cause Still Under Investigation1986-11-21021 November 1986 Partially Deleted LER 86-023-01:on 861023,unauthorized Access Into Vital Area Door Discovered.Caused by Card Reader Malfunction.Malfunctioning Card Reader Replaced.Cause Still Under Investigation 05000000/LER-1986-024, Partially Deleted LER 86-024-00:on 861113,attempted Introduction of Unauthorized Weapon Into Protected Area Discovered.Caused by Personnel Attempt to Enter Plant W/ Concealed Gun.Personnel Denied Facility Access1986-11-18018 November 1986 Partially Deleted LER 86-024-00:on 861113,attempted Introduction of Unauthorized Weapon Into Protected Area Discovered.Caused by Personnel Attempt to Enter Plant W/ Concealed Gun.Personnel Denied Facility Access 05000000/LER-1986-052, Partially Withheld LER 86-052-01:on 860926,security Data Mgt Sys Computer Terminals Became Inoperable (Ref 10CFR73.21). Caused by Overload of Alarms & Sys Instability.Sys Restored by Placing Sys Multiplexers Online1986-11-13013 November 1986 Partially Withheld LER 86-052-01:on 860926,security Data Mgt Sys Computer Terminals Became Inoperable (Ref 10CFR73.21). Caused by Overload of Alarms & Sys Instability.Sys Restored by Placing Sys Multiplexers Online 05000000/LER-1986-007, Partially Deleted LER 86-007-01:on 860218,loss of Alarm Surveillance Occurred.Caused by Water Leaking Into Cable Due to Heavy Rain.Cable Dried,Leak Repaired & Design Corrected1986-10-0606 October 1986 Partially Deleted LER 86-007-01:on 860218,loss of Alarm Surveillance Occurred.Caused by Water Leaking Into Cable Due to Heavy Rain.Cable Dried,Leak Repaired & Design Corrected 05000000/LER-1986-021, Partially Deleted LER 86-021-00:on 860911,vital Area Doors Failed to Alarm When Tested During Surveillance.Caused by Failure to Report Door Transactions to Host Computer.Central Procesing Unit Board Replaced1986-09-15015 September 1986 Partially Deleted LER 86-021-00:on 860911,vital Area Doors Failed to Alarm When Tested During Surveillance.Caused by Failure to Report Door Transactions to Host Computer.Central Procesing Unit Board Replaced 05000000/LER-1986-020, Partially Deleted LER 86-020-00:on 860812,security Sys Experienced Loss of Power.Caused Withheld.Numerous Failures Experienced Until Machine a Designated as Prime.Procedures to Reboot Computers Revised1986-08-15015 August 1986 Partially Deleted LER 86-020-00:on 860812,security Sys Experienced Loss of Power.Caused Withheld.Numerous Failures Experienced Until Machine a Designated as Prime.Procedures to Reboot Computers Revised 05000000/LER-1986-004, Partially Deleted LER 86-004-01:on 860204,loss of Dynamic Reporting of Alarm Surveillance Occurred.Cause Withheld. Computer Svcs Personnel Will Continue to Monitor Sys for Indicators of Cause1986-06-11011 June 1986 Partially Deleted LER 86-004-01:on 860204,loss of Dynamic Reporting of Alarm Surveillance Occurred.Cause Withheld. Computer Svcs Personnel Will Continue to Monitor Sys for Indicators of Cause 05000000/LER-1986-016, Partially Deleted LER 86-016-00:on 860501,vital Area Door Discovered W/O Alarm Capabilities.Caused by Access Control Security Officer Asleep at Post.Determination to Suspend or Discontinue Employment Being Made1986-05-0606 May 1986 Partially Deleted LER 86-016-00:on 860501,vital Area Door Discovered W/O Alarm Capabilities.Caused by Access Control Security Officer Asleep at Post.Determination to Suspend or Discontinue Employment Being Made 05000000/LER-1986-015, Partially Deleted LER 86-015-00:on 860428,stationary Side of Door Failed to Alarm When Tested.Cause Withheld.Alarm Repaired1986-05-0202 May 1986 Partially Deleted LER 86-015-00:on 860428,stationary Side of Door Failed to Alarm When Tested.Cause Withheld.Alarm Repaired 05000000/LER-1986-014, Partially Deleted LER 86-014-00:on 860421,bomb Threat Received by Security Officer in Security Assembly Room. Cause Not Applicable.Actions Taken to Minimize Station Threat & Investigation Underway1986-04-25025 April 1986 Partially Deleted LER 86-014-00:on 860421,bomb Threat Received by Security Officer in Security Assembly Room. Cause Not Applicable.Actions Taken to Minimize Station Threat & Investigation Underway ML20203L0281986-04-25025 April 1986 Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points 05000000/LER-1986-013, Partially Deleted LER 86-013-00:on 860414,vital Area Door W/O Alarm Capability Discovered.Caused by Personnel Error. Personnel Removed from Shift & Vital Area Checked for Unauthorized Personnel W/None Being Found1986-04-18018 April 1986 Partially Deleted LER 86-013-00:on 860414,vital Area Door W/O Alarm Capability Discovered.Caused by Personnel Error. Personnel Removed from Shift & Vital Area Checked for Unauthorized Personnel W/None Being Found 05000000/LER-1986-012, Partially Deleted LER 86-012-00:on 860412,breach Discovered in Protected Area Barrier.Caused by Personnel Error. Personnel Counseled1986-04-17017 April 1986 Partially Deleted LER 86-012-00:on 860412,breach Discovered in Protected Area Barrier.Caused by Personnel Error. Personnel Counseled 05000000/LER-1986-011, Partially Deleted LER 86-011-00:on 860410,vital Area Intrusion Alarm Failure Occurred.Cause of Event Deleted. Alarm & Door Tested Satisfactorily1986-04-15015 April 1986 Partially Deleted LER 86-011-00:on 860410,vital Area Intrusion Alarm Failure Occurred.Cause of Event Deleted. Alarm & Door Tested Satisfactorily 05000000/LER-1986-003, Partially Deleted LER 86-003-00:on 860125,loss of Dynamic Reporting of Vital Area Door Activity Occurred.Caused by Equipment Malfunction.Corrective Action Withheld1986-01-29029 January 1986 Partially Deleted LER 86-003-00:on 860125,loss of Dynamic Reporting of Vital Area Door Activity Occurred.Caused by Equipment Malfunction.Corrective Action Withheld 05000000/LER-1986-002, Partially Deleted LER 86-002-00:on 860117,loss of Alarm Surveillance on Doors Occurred.Caused by Erroneously Listing Officer as Being Posted on Door 398.Processing of Rev to Physical Security Plan Initiated1986-01-23023 January 1986 Partially Deleted LER 86-002-00:on 860117,loss of Alarm Surveillance on Doors Occurred.Caused by Erroneously Listing Officer as Being Posted on Door 398.Processing of Rev to Physical Security Plan Initiated 05000000/LER-1986-001, Partially Deleted LER 86-001-00:on 860105,loss of Dynamic Reporting of Vital Door Activity Occurred.Cause & Corrective Action Completely Deleted1986-01-10010 January 1986 Partially Deleted LER 86-001-00:on 860105,loss of Dynamic Reporting of Vital Door Activity Occurred.Cause & Corrective Action Completely Deleted 05000277/LER-1984-008, Revised LER 84-008-01:on 840427,standby Gas Treatment Sys Solenoid Valve SV-00009 Failed to Operate Properly, Preventing Fan a Inlet & Outlet Dampers from Opening.Cause of Solenoid Failure Under Investigation1984-07-24024 July 1984 Revised LER 84-008-01:on 840427,standby Gas Treatment Sys Solenoid Valve SV-00009 Failed to Operate Properly, Preventing Fan a Inlet & Outlet Dampers from Opening.Cause of Solenoid Failure Under Investigation 05000278/LER-1984-001, Revised LER 84-001-02:on 840106,turbine Exhaust Rupture Diaphragm Alarm Annunicated Following Startup of HPCI Turbine.Caused by Rupture of Inner Rupture Disc.Inner Rupture Disc Replaced1984-06-0101 June 1984 Revised LER 84-001-02:on 840106,turbine Exhaust Rupture Diaphragm Alarm Annunicated Following Startup of HPCI Turbine.Caused by Rupture of Inner Rupture Disc.Inner Rupture Disc Replaced 05000277/LER-1984-003, Revised LER 84-003-01:on 840131,heatup Rate Exceeded Tech Spec Limits.Caused by Personnel Error.Operator Disciplined. Memo Issued to All Licensed Operators Re Tech Spec Rate1984-05-0303 May 1984 Revised LER 84-003-01:on 840131,heatup Rate Exceeded Tech Spec Limits.Caused by Personnel Error.Operator Disciplined. Memo Issued to All Licensed Operators Re Tech Spec Rate 05000278/LER-1983-018, Updated LER 83-018/03X-1:on 831117,control Rods 34-35 & 34-7 34-27 Exceeded Allowable Scram Insertion Time of 7 S.Caused by Failure of Scram Solenoid Valve in Both Hydraulic Control Units.Solenoids Replaced1984-02-10010 February 1984 Updated LER 83-018/03X-1:on 831117,control Rods 34-35 & 34-7 34-27 Exceeded Allowable Scram Insertion Time of 7 S.Caused by Failure of Scram Solenoid Valve in Both Hydraulic Control Units.Solenoids replaced.W/840210 Ltr 05000278/LER-1983-008, Followup LER 83-008/01X-1:on 830214,during Refueling Outage, Surveillance Testing Indicated Combined Leakage for Listed Valves Exceeded Limits or Failed to Meet Requirements.Caused by Seat Surface Degradation1983-09-13013 September 1983 Followup LER 83-008/01X-1:on 830214,during Refueling Outage, Surveillance Testing Indicated Combined Leakage for Listed Valves Exceeded Limits or Failed to Meet Requirements.Caused by Seat Surface Degradation 05000278/LER-1982-022, Revised LER 82-022/01X-1:on 821025-1102,RHR HX 3D Leaked Slightly Radioactive Water Into Intake Structure.Caused by Expansion Bellows Leak Between Inner Floating Head & Drain. HX Repaired1983-01-11011 January 1983 Revised LER 82-022/01X-1:on 821025-1102,RHR HX 3D Leaked Slightly Radioactive Water Into Intake Structure.Caused by Expansion Bellows Leak Between Inner Floating Head & Drain. HX Repaired 05000277/LER-1982-030, Telecopy Message of LER 82-030/01P:on 820917,contaminated Water Released from Recombiner Bldg Into Storm Drain Sys. Caused by Spurious Actuation of Fire Protection Sprinkler Sys in B Filter Train of Exhaust Ventilation Sys1982-09-21021 September 1982 Telecopy Message of LER 82-030/01P:on 820917,contaminated Water Released from Recombiner Bldg Into Storm Drain Sys. Caused by Spurious Actuation of Fire Protection Sprinkler Sys in B Filter Train of Exhaust Ventilation Sys 05000278/LER-1982-0111982-07-13013 July 1982 LER 82-011/03L-0:on 820620,fuse on Positive Leg to Transmitter Circuit Board Blew Causing Downscale Failure of Drywell 0-70 Psig Pressure Recorder.Caused by Intentional Ground Installed on Positive of Transmitter.Fuse Replaced 05000277/LER-1982-0161982-07-13013 July 1982 LER 82-016/01P:on 820709,equalizing Valve on Main Steam Line a High Flow Transmitter (Dpis 116B) Found Open.Cause Under Investigation.Valving of Instrument Performance Verified 05000278/LER-1982-0101982-07-13013 July 1982 LER 82-010/03L-0:on 820618,downscale Failure of Drywell 0-70 Psig Pressure Recorder Occurred.Caused by Blown 0.3 Ampere Fuse Installed on Positive Side of Power Supply to Transmitter Circuit Board.Fuse Replaced 05000277/LER-1982-0131982-07-0808 July 1982 LER 82-013/03L-0:on 820608,while Filling Diesel Generator Carbon Dioxide Fire Suppression Sys Storage Tank,Tank Pressure Dropped Below Tech Spec Limit.Caused by Venting Tank Vapor Space to Atmosphere Instead of Delivery Truck 05000277/LER-1982-0151982-07-0606 July 1982 LER 82-015/1P:on 820703,main Steam Line Flow Transmitter D & 1 of 4 Main Steam Line High Flow Transmitters Found W/Open Equalizing Valves.Cause Under Investigation.Valving of Instruments Verified 05000278/LER-1982-0091982-06-28028 June 1982 LER 82-009/03L-0:on 820530,operator Lost Valve Indication Position on HPCI Sys.Caused by Blown Fuse in Instrument Panel Due to Shortened Solenoid Coil in Turbine Exhaust Drain Valve.Fuse Replaced & Valves Stroked 05000278/LER-1982-0071982-06-21021 June 1982 LER 82-007/03L-0:on 820519,during Operability Testing,Hpci Steam Inlet valve,MO-14,blew Fuses When Stroked & Turbine Stop valve,HO-5513,failed to Close in Response to Remote Trip Signal.Steam Inlet Valve Repacked & Switch Replaced 05000278/LER-1982-0051982-06-14014 June 1982 LER 82-005/03L-0:on 820514,during Normal Operation,Reactor Operator Heard Relay in Primary Containment Isolation Sys Energize.Caused by Defective Component in Rosemount Model 510DU Slave Trip Unit.Instrument Replaced 05000277/LER-1982-0121982-06-11011 June 1982 LER 82-012/03L-0:on 820517,pressure Drop Across Combined HEPA Filters & Charcoal Absorber Banks in Control Room Emergency Ventilation Sys Exceeded Tech Spec Limits.Caused by Pin on Connecting Linkage of Damper OBV-30 Falling Out 05000277/LER-1982-010, Sanitized Version of LER 82-010/01X-0:on 820413,Eberline Instrument Corp Reported 9.175 Rem Exposure to TLD Badge. Caused by Deliberate Tampering W/Badge Found Near Radiation Source.Individual Denied Access to Site1982-05-13013 May 1982 Sanitized Version of LER 82-010/01X-0:on 820413,Eberline Instrument Corp Reported 9.175 Rem Exposure to TLD Badge. Caused by Deliberate Tampering W/Badge Found Near Radiation Source.Individual Denied Access to Site 05000277/LER-1982-008, Revised LER 82-008/01X-1:on 820328,auxiliary Boiler Operated on Diesel Fuel 2 Instead of Fuel Oil 6,decreasing Diesel Fuel Inventory Below Tech Spec Limit of 104,000 Gallons. Caused by Failure to Monitor Fuel Tank Inventory1982-04-15015 April 1982 Revised LER 82-008/01X-1:on 820328,auxiliary Boiler Operated on Diesel Fuel 2 Instead of Fuel Oil 6,decreasing Diesel Fuel Inventory Below Tech Spec Limit of 104,000 Gallons. Caused by Failure to Monitor Fuel Tank Inventory 05000277/LER-1982-0061982-04-12012 April 1982 LER 82-006/03L-0:on 820313,during Surveillance Testing of Fire Protection Sys,Diesel Fire Pump Tripped Off on Overspeed Condition.Caused by Defective Overspeed Control Switch.Defective Switch Replaced ML20064J1791978-12-20020 December 1978 /03L-0 on 781127:D Reactor Bldg Area Exhaust Radiat Monitor Indicated Downscale & Was Determined to Be Inoperable.Caused by Defective Zener Diode in Amplifier of GE sensor-converter Unit,Model 194X927011 ML20062E8681978-12-0606 December 1978 /03L-0 on 781117:output Demand Signal from RCIC Flow Controller (Inst HCS213-115) Read Down Scale.Caused by Open Circuit in Controller Demand Current Loop 1993-09-03
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K9931999-10-14014 October 1999 Safety Evaluation Supporting Amend 234 to License DPR-56 ML20217B4331999-10-0505 October 1999 Safety Evaluation Supporting Amend 233 to License DPR-56 ML20217G3541999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbaps,Units 2 & 3. with ML20216H7091999-09-24024 September 1999 Safety Evaluation Supporting Amends 229 & 232 to Licenses DPR-44 & DPR-56,respectively ML20212D1281999-09-17017 September 1999 Safety Evaluation Supporting Proposed Alternatives CRR-03, 05,08,09,10 & 11 ML20212A5871999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Peach Bottom,Units 2 & 3.With ML20211D5501999-08-23023 August 1999 Safety Evaluation Supporting Amends 228 & 231 to Licenses DPR-44 & DPR-56,respectively ML20212H6311999-08-19019 August 1999 Rev 2 to PECO-COLR-P2C13, COLR for Pbaps,Unit 2,Reload 12 Cycle 13 ML20210N7641999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for PBAPS Units 2 & 3. with ML20209H1121999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbaps,Units 2 & 3. with ML20195H8841999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbaps,Units 2 & 3. with ML20206N1661999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pbaps,Units 2 & 3. with ML20206A2921999-04-20020 April 1999 Safety Evaluation Concluding That Proposed Changes to EALs for PBAPS Are Consistent with Guidance in NUMARC/NESP-007 & Identified Deviations Meet Requirements of 10CFR50.47(b)(4) & App E to 10CFR50 ML20205K7411999-04-0707 April 1999 Safety Evaluation Supporting Amends 227 & 230 to Licenses DPR-44 & DPR-56,respectively ML20205P5851999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Peach Bottom Units 2 & 3.With ML20207G9971999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Peach Bottom Units 2 & 3.With ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20206R2571998-11-17017 November 1998 PBAPS Graded Exercise Scenario Manual (Sections 1.0 - 5.0) Emergency Preparedness 981117 Scenario P84 ML20198C6751998-11-0505 November 1998 Rev 3 to COLR for PBAPS Unit 3,Reload 11,Cycle 12 ML20195E5341998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Pbaps,Units 2 & 3. with ML20155C6071998-10-26026 October 1998 Safety Evaluation Supporting Amend 226 to License DPR-44 ML20155C1681998-10-22022 October 1998 Safety Evaluation Accepting Proposed Alternative Plan for Exam of Reactor Pressure Vessel Shell Longitudinal Welds ML20155H7721998-10-12012 October 1998 Rev 1 to COLR for Peach Bottom Atomic Power Station Unit 2, Reload 12,Cycle 13 ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 to Licenses DPR-44 & DPR-56,respectively ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively ML20154G6821998-10-0101 October 1998 SER Related to Request for Relief 01A-VRR-1 Re Inservice Testing of Automatic Depressurization Sys Safety Relief Valves at Peach Bottom Atomic Power Station,Units 2 & 3 ML20154H5541998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Pbaps,Units 2 & 3. with ML20153B9651998-09-14014 September 1998 Safety Evaluation Supporting Amend 9 to License DPR-12 ML20151Y2901998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbaps,Units 2 & 3. with ML20238F2661998-08-24024 August 1998 Safety Evaluation Supporting Amend 222 to License DPR-44 ML20237B9531998-08-10010 August 1998 Specification for ISI Program Third Interval,Not Including Class Mc,Primary Containment for Bpaps Units 2 & 3 ML20237A7761998-08-10010 August 1998 SER Accepting Licensee Response to NRC Bulleting 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode ML20237A5351998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Pbaps,Units 2 & 3 ML20236R8281998-07-15015 July 1998 Safety Evaluation Approving Proposed Alternative (one-time Temporary non-Code Repair) Pursuant to 10CFR50.55a(a)(3) (II) ML20236M3471998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbaps,Units 2 & 3 ML20249C4791998-06-0202 June 1998 Rev 6 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20248F4781998-06-0101 June 1998 Corrected Page 1 to SE Supporting Amends 221 & 226 to Licenses DPR-44 & DPR-56,respectively.Original Page 1 of SE Had Three Typos ML20248M3001998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pbaps,Units 2 & 3 ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20247N5351998-05-11011 May 1998 SER Accepting Third 10-year Interval Inservice Program for Pump & Valves for Plant,Units 2 & 3 ML20249C4751998-05-0707 May 1998 Rev 5 to COLR for PBAPS Unit 2 Reload 11,Cycle 12 ML20247G0721998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Pbaps,Units 2 & 3 1999-09-30
[Table view] |
LER-2077-005, Updated LER 77-005/1T:on 770114,failure of High Pressure Svc Water/Emergency Svc Water & Emergency Cooling Water Pumps to Meet FSAR Seismic Requirements Noted.Caused by Change in Calculation Techniques |
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O- O '
j PHILADELPHIA ELECTRIC COMPANY .
, 2301 MARKET ST.* LEET l
PHILADELPHIA. PA.19101 i (215) 84 t-4000 January 28, 1 U7 l .
. ./ .'
Mr. J. P. O'Rel liy l
l Director, Region 1 .
' Office or Inspection and Enforcement #
U. S. Nucicar Regulatory Comnission 631 Park Avenue -
y King of Prussia, PA 19406 -
Daar Mr. O'Reilly: ' ' ~~ y'
SUBJECT:
hortable Occurrence Folicw-up Report-1, Office of Inspection and Enforcement 14, on1977 JanuaryTheWritten following occurren notification was made to Mr. George I. car, Chief, Operating Reactors Branch
- 3, Division of Reactor Licensing and Mr. J. P. O'Reilly, Director, Region 1, Office of Inspection and Enfc,rcement on January 14, 1977. In accordance with Section 6 9.2.a of the Technical Specifications, Appendix A of DPR -
for Unit 2 and OPR-56 for Unit 3, Peach Bottom. Atomic Power Station, the following Event Report.information is being provided to supplement the attached i.icensee
Reference:
,' Docket Nos. 50-277 and 50 278-Technical Specification Reference 6 9 2.a(9)
I Report No.: 2-77-5/1T Report Date: January 28, 1977 l- Occurrence Date: Ja.uary 14, 1977 -
Facility:
Feach Cottom Atomic Power Station
- Units 2 and 3 R.9. 1, Delta, Pennsylvania 17314 l Event
Description:
During the perforr.iance of a sar'ety e val'aation of a proposed
,PIant modification, as .equired by the Peach Bottom Unit.1 2 & 3 qualit assurance progr.w, it we. four.d thac the High Pressure Service Water / y Ernergency Service Vate.-/ Emery ncy Coolir.g ht.sr a umos do not meet FSAR i
seisn.ic c* assification requiruvents. Tr.e. e have beer. no previous occur-tences.
8312130068 771005 l
PDR S ADOCK 05000277
- .' . l
..,o , .
j
1 . ~ / .
l -.'J. P. O 'Rei l ly .
[ Jan~uary 28, 1977 ~o O 2 77-5/ir l
Pago 2 g use
Description:
analysis. The purchase specification for these pumps required a seismic This analysis was made using an equivalent static analysis technique which converts a dynamic loading to a static loading. Results of this analysis January 14, 1972.were received by our Architect Engineer (Bechtcl) on These results show that the pumps were capable of withstanding stresses.
the design scismic events well within quoted allowable The Architect Engineer, however, aware of pending project scismic specification changes relating to calculational techniques deferred his detailed review. In March 1974, the vendor was provided with the Philadelphia Electric Company approved General Project Class I Seismic Requirements Specifica*. ion. The vendor performed a seismic re-analysis using the dynamic analysis technique in accordance with the Specification to verify his equipment capability to withstand the design basis seismic events. The results of his re-analysis were reported to.
our Architect Engincer in November 1974, and indicated that the pumps were not capable of withstanding the design basis seismic events with -
in allowable stresses. The report also contained suggested minor modi =
fications to restore scismic Class I capability.
Philadelphic Electric Company. was advised of this recommended corrective action in Bechtel's letter to Philadelphia Electric dated April 9,1975 (BLP 12313); af ter which Philadelphia Electric authorized the preparation mentation of the engineering work package, including quality docu-requirements.
Because of the language in this letter, our engineers, although approving the work, did not assign a high priority to the in delay modifications.'
corrective action. This was an error, and is responsible:for the'.,.
- essary modification sign-offs were It wassought.
not until late 1976.that.the nee -
assurance phase that the defici' n'cy It was during this quality ,
e of not meeting' the FSAR 'scisniic---
requirements was identified and prompt corrective action was initiated.
Corrective Action:
Equipment procurement is underway. Field work is expected to start on ESV and ECW pumps on January 31, 1977 Work on the HPSW
- punps will start shortly thereaf ter. We plan to complete this work as soon as possibic. Specific modifications and schedules are as ' '
follows:
- l. High Pressure Service Water Pumps: ;
a.. Column flange bolts will be replaced with higher 8
strength material; ,
- b. Bolts, are on order and delivery is expected on "
February 11, 1977. Efforts are being made to , ; ,
expidite delivery, t
4 6
e'
.... f. *
'M . J. P. O'Rei l ly -
January 28, 1977 O O sn 9or
- page 3 l . t
- c. Installation will begin upon receipt of materials and is expected to be complete by April 15, 1977 2 Emergency Service Water Purnps and Ernergency Cooling Water Pumps:
- a. Lateral supports will be added at the top to the bowl assemblics f or these pumps. In addition, the motor hold down bolts for the Emergency Service Water Pumps will be replaced with higher strength material.
- b. Material for lateral supports was roccived on site on January 27, 1977.
l
- c. Installation will start on January 31, 1977 and will be errnpleted March 18, 1977.
With regard to the error in 'our quality review program whidh'"
f ailed to note the importance of this item and resulted in delayed implementation of corrective action, it is not expected that this type..
error will recur. Modifications to the Peach Bottom Plant are under -
strict administrative procedure control. This procedure requires section review of all proposed plant modifications and docurrentation of such review on approved document control forms. In 1975, when the deficiency regarding the seitmic design of the pumps was first brought to the attention of Philadelphia Electric, the use of this procedure was in its inf ancy. Considerable progress has been.mado -in complying %
with it.
Safety Imolications:_,
This occurrence .is believed to have minimal effect on plant safety because of tbc low pr obability of the occurrence of a scismic event of intensity equal to the design basis scismic event, and the short period of time required to impicracnt corrective action. The Operation and Safety Revi-w Conmittee has reviewed this matter and cpproved this course of action.
I i l .Very truly yours, .
i 1 . .
. . hj
, .k. J Cooney Su .intendent Generatlon civision-Nuclear Attechment .
cc Mr. Geo. ge Lc?r, Chicf -
Opera-ing Reactorc Or. nch #.7 .
Divisic.n of Oper st'ng Recctors ,
..e me