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Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20045B2381993-06-0909 June 1993 Special Rept:On 930523,EDG E-2 Declared Inoperable When Engine Lubricating Oil Temp Alarm Annunicated on Low Temp Condition.Caused by Circulating Pump Trip on Thermal Overload.Thermal Overload Assembly Reinstalled ML20044C4091993-03-17017 March 1993 Special Rept:On 930302,motor Driven Fire Pump Administratively Declared Inoperable Due to Lack of Water Leakage Through Pump Packing.Backup Water Supply Established to Satisfy Requirements Specified in TS 3.14.A.3.a ML20029A1281991-01-28028 January 1991 Special Rept:On 910107,diesel Driven Fire Pump Out of Svc in Excess of 7 Days.Three Control Relays Burned Out Due to Failure of Voltage Regulator for diesel-mounted Generator. Generator Rebuilt & Reinstalled.Relays & Regulator Replaced ML20043G1171990-06-0606 June 1990 Special Rept:On 900501,diesel Driven Fire Pump Out of Svc for More than 7 Days During Performance of Annual Insp.Pump Returned to Svc on 900508 ML20006F3861990-02-16016 February 1990 Ro:On 900103,common Plant Standby Gas Treatment Sys Train a Fire Protection Deluge Sys Declared Inoperable for More than 14 Days.Caused by Replacement of Filter W/Threaded Pipe Plug.Fire Watch Patrol Established & Nozzle Replaced ML20024D2331983-07-0505 July 1983 Followup Ro:Response Spectrum Analyzer Experienced Intermittent Operability Problems.Caused by Voltage Spikes in Dc Current Due to Induced Noise on Dc Signal Lines of Seismic Instrumentation.Fuses Removed ML20028G1991983-02-0101 February 1983 RO 3-83-6/IP:on 830131,test Valve Between Penetration Boundary,Inboard & Outboard Containment Isolation Valve Exceeded Tech Spec Leak Rate.Caused by Improper Seating of Manual Valve.Penetration Isolated ML20028G1961983-01-28028 January 1983 RO 3-83-2/IP:on 830126,containment Isolation Valve MO-5244, Associated W/Hpci Turbine Exhaust Line Vacuum Breaker,Failed to Fully Close During Local Leak Rate Testing.Caused by Solidified Lubricant in Valve Operator ML20028G2071983-01-20020 January 1983 RO 2-83-2/1P:on 830120,during Surveillance of Control Room,Indicating Lights for RCIC Inboard Steam Supply Isolation Valve Found Not Lit,Due to Open Feed Breaker Valve.Caused by Personnel Error.Feed Breaker Closed ML20028C5011983-01-0505 January 1983 RO 2-83-1/1P:on 830104,electrical Control Switch Failed During Environ Qualification Testing.Caused by Embrittlement of Nylon Cam Surface Matl Due to Radiation.Control Switch Contacts Jumpered & Leads Lifted ML20052F9001982-04-16016 April 1982 RO 2-82-10/01P:on 820413,w/Unit 2 Shutdown for Refueling/ Maint Outage & Unit 3 at Full Power,Possible Overexposure Identified on Eberline TLD for Month of Mar 1982.Cause Under Investigation ML20052F8791982-03-29029 March 1982 RO 2-82-08/01P:on 820328,w/Unit 2 Shutdown for Refueling/ Maint Outage & Unit 3 at Full Power,Diesel Fuel Oil Storage Tank Inventory Less than 104,000 Gallons.Caused by Unusual Usage of Fuel Oil by Auxiliary Boilers ML20041B0451982-02-10010 February 1982 RP 2-81-40/IT:on 810923, Survivability of Rockbestos Type RSS-6-104 & Rss-6-110 Coaxial Cable at Elevated Ambient Temps Not Proven.Caused by Apparent Design Deficiency.Cable to Be Replaced During Mar 1982 Refueling Outage ML20049A6051981-06-12012 June 1981 RO 2-81-34/1P:on 810612,during Safe Shutdown Analysis,Four Cables Were Found Improperly Routed & Improperly Designated as Nonsafeguard.Caused by Improper Designation of Three Cables Associated W/Power Supply to Room Cooler Fans ML19326E2421980-07-22022 July 1980 RO 2-80-12/1P:on 800721,while Testing Unit 2 During Refueling Outage,Scram Backup Valves in Air Supply to Control Rod Drive Scram Valves Failed.Caused by Design Error.Manual Venting Provided ML19330B8651980-07-17017 July 1980 RO 3-80-16/1P:on 800717,pipe Support Snubber 3-10-GB-S44 Exceeded Operability Criteria.Caused by Differences Between as-built Condition & Seismic Analysis Input Info.Hydraulic Snubber to Be Replaced W/Mechanical Snubber ML19320D4721980-07-15015 July 1980 RO-2-80-11/1P:on 800714,diesel Generator Cardox Sys Vapor Pilot Valve Was Found Closed.Caused by Failure to Properly Clear Safety Permit on 800730.Vapor Pilot Valve Locked Open ML19318D2251980-06-30030 June 1980 Ro:On 800329,RHR Motor Failed.Caused by Failure of Lower Guide Bearing.Instructions Issued to Operate RHR Sys at Full Flow Conditions.Fans on Motor Shaft Ends Being Replaced. Failed Motor Replaced W/New Motor ML19310A3201980-06-0404 June 1980 RO 2-80-10/1P:on 800330-0407 & 17-22,radioactive Water Was Released to Circulating Water Sys.Caused by Flooding of Normal Condenser Steam Space Permitting Radioactive Water to Leak Through Defective Condenser Tube to Water Sys ML19309H1051980-05-0202 May 1980 RO 2-80-9/1P:on 800502,during Shutdown & Movement of Fuel within Spent Fuel Pool,Secondary Containment Integrity Was Not Maintained.Caused by Removal of Steam & Feedwater Boot Seals.Boots Will Be Replaced & Procedures Will Be Revised ML19323C9981980-05-0101 May 1980 RO 2-80-8/1T:on 800417,preliminary Calculations Associated W/High Energy Line Breaks Revealed That Guillotine Failure of HPCI Steam Supply Would Result in Peak Pressure & Failure of Reinforced Concrete Block Wall.Mods Are Underway ML19323A6911980-04-28028 April 1980 RO 2-80-8-1P:updates Info Re Pressure Profile within Unit 3 Valve Following Guillotine Failure of HPCI Steam Supply Piping.Analysis Indicates Higher Peak Pressure than Originally Reported.Caused by Engineering Error ML19323A6901980-04-18018 April 1980 RO 2-80-8/1P:on 800417,development of Environ Spectrums Associated W/High Energy Line Breaks Indicated Guillotine Failure of Steam Supply Piping to HPCI Turbine.Caused by Engineering Deficiency ML19305A7661980-02-22022 February 1980 RO 3-80-7/1P:on 800221,seismic Nitrogen Supply to Five Containment Ventilation Valves Found Valved Out of Svc. Caused by Possible Lack of Info During 800205 Inerting Operation & 800220 Blocking Error During Mod Work ML19322B9381979-12-10010 December 1979 RO-2-79-53/1P:on 791207,recirculation Sys Sample Line Outer Valves Isolation Function Inoperable.Caused by Improper Testing of Installed Jumper.Jumper Removed,Valves Tested for Manual & Automatic Isolation & Found Operable ML19275B6471979-12-0606 December 1979 RO-2-79-52/1P:on 791127,seismic Capabilities of Concrete Block Walls on Elevation 135 Ft Reanalyzed as Less than Required Safety Factor.Caused by Engineering Design Deficiency.Mod of Wall Support Will Raise Safety Factor ML19268C4211979-12-0606 December 1979 Update to RO 2-79-52/1P:on 791205,discovered Low Safety Factor for Concrete Expansion Bolts.Engineering Analysis Indicates Stress in Concrete Block Wall Outer Fibers Will Not Exceed Design Allowable Values for DBE ML19322B9061979-12-0404 December 1979 RO-3-79-39/1P,update:on 791130,eight Seismic Supports Inside Containment & Supporting Control Rod Drive Piping Line Found Not to Be Seismically Qualified.Caused by Design Deficiency. Mods Will Be Completed During Outage Beginning 791207 ML19322B9051979-11-21021 November 1979 RO-3-79-38/1P:on 791121,review of 791117 Surveillance Test Revealed That Two MSIVs in Steamline a Closed in Shorter Times than Specified in Tech Specs.Caused by Possible Temp Effects on Hydraulic Fluid Viscosity ML19312B7581979-11-0202 November 1979 RO-2-79-49:on 791005,insp Program in Accordance W/Ie Bulletin 79-02 Revealed Design Deficiency in Four Seismic Supports Associated w/1-inch Control Rod Drive Piping. Bechtel Corp Redesigning Supports within Acceptable Limits ML19260A2541979-10-19019 October 1979 RO-3-79-29/1P:on 791019,piping Sys Insp & Measurement Program Indicated Damaged Sway Strut on Reactor Feed Pump C Discharge Line.Cause Under Investigation.New Sway Strut Ordered ML19276H6491979-10-19019 October 1979 RO 3-79-29/1P:on 791019,response to IE Bulletin 79-14 Revealed Damaged Sway Strut on C Reactor Feed Pump Discharge Line.Cause Under Investigation.New Sway Strut Will Arrive 791023 ML19322A3801979-10-0505 October 1979 RO-3-79-32/1P:on 791005,insp Performed Re IE Bulletin 79-02 Revealed Failure of Supports in Emergency Svc Water Return Line.Caused by Improper Installation of Anchor Bolts.Plate Washers Will Be Installed Over Bolts ML19308A4371979-10-0404 October 1979 RO-3-79-31/1P:on 791003,insp Performed in Response to IE Bulletin 79-02 Revealed Failure in Support in Loop Core B Spray Min Flow Line.Caused by Improper Installation of Anchor Bolts.Bolts Replaced ML19318A6481979-10-0303 October 1979 RO 3-79-30/1P:on 791002,seismic Anchor Insp Program Identified Failure in Support Associated W/Loop B Core Spray Discharge Line.Caused by Improper Installation of Anchor Bolt.Replacement of Two Failed Bolts Is in Progress ML19209B4321979-09-0707 September 1979 RO 2-79-43/1P:on 790906,in Response to IE Bulletin 79-07, Failure in One Support Associated W/High Pressure Svc Water Sys Piping in RHR Room 2A Identified.Larger Anchor Bolts Will Replace 7/8 Inch Bolts W/Installation of Plate Washers ML19209B4291979-09-0505 September 1979 RO 3-79-26/1P:on 790904,failure of Pipe Support Anchor on HPCI Pump Discharge Piping Noted.Undetermined Factor Caused Overstress Resulting in Failure.Vendor Presently Conducting Tests to Determine Optimum Method of Repair ML19259D1111979-08-22022 August 1979 RO 2-79-40/1P on 790821:while Cardox Sys Was Disabled, Continuous Fire Watch Not Maintained in Diesel Generator Bldg.Caused by Failure to Follow Procedure Designating Duties of Fire Watch.Personnel Reinstructed ML19270H4311979-07-25025 July 1979 RO 3-79-23/1P on 790724:anchor Support on Emergency Svc Water Piping in RHR Room Failed.Apparently Caused by Improper Installation.Anchors & Bolts Replaced & Satisfactorily Tested ML19259C5361979-05-17017 May 1979 RO 2-79-24/10:control Rod Driveline Return Line Outside Containment Support.Seismic Support Calculations in Response Ot IE Bulletin 79-04 Indicate Support for Piping Unsatisfactory ML19282B9531979-02-20020 February 1979 RO 2-79-8/10 on 790219:steady State Power Level Exceeded License Limit of 3293 Mw.Caused by Erroneous Feedwater Flow Input to Computer Causing Reactor Heat Balance to Indicate Less than Actual Power Level 1993-06-09
[Table view] Category:LER)
MONTHYEARML20045B2381993-06-0909 June 1993 Special Rept:On 930523,EDG E-2 Declared Inoperable When Engine Lubricating Oil Temp Alarm Annunicated on Low Temp Condition.Caused by Circulating Pump Trip on Thermal Overload.Thermal Overload Assembly Reinstalled ML20044C4091993-03-17017 March 1993 Special Rept:On 930302,motor Driven Fire Pump Administratively Declared Inoperable Due to Lack of Water Leakage Through Pump Packing.Backup Water Supply Established to Satisfy Requirements Specified in TS 3.14.A.3.a ML20029A1281991-01-28028 January 1991 Special Rept:On 910107,diesel Driven Fire Pump Out of Svc in Excess of 7 Days.Three Control Relays Burned Out Due to Failure of Voltage Regulator for diesel-mounted Generator. Generator Rebuilt & Reinstalled.Relays & Regulator Replaced ML20043G1171990-06-0606 June 1990 Special Rept:On 900501,diesel Driven Fire Pump Out of Svc for More than 7 Days During Performance of Annual Insp.Pump Returned to Svc on 900508 ML20006F3861990-02-16016 February 1990 Ro:On 900103,common Plant Standby Gas Treatment Sys Train a Fire Protection Deluge Sys Declared Inoperable for More than 14 Days.Caused by Replacement of Filter W/Threaded Pipe Plug.Fire Watch Patrol Established & Nozzle Replaced ML20024D2331983-07-0505 July 1983 Followup Ro:Response Spectrum Analyzer Experienced Intermittent Operability Problems.Caused by Voltage Spikes in Dc Current Due to Induced Noise on Dc Signal Lines of Seismic Instrumentation.Fuses Removed ML20028G1991983-02-0101 February 1983 RO 3-83-6/IP:on 830131,test Valve Between Penetration Boundary,Inboard & Outboard Containment Isolation Valve Exceeded Tech Spec Leak Rate.Caused by Improper Seating of Manual Valve.Penetration Isolated ML20028G1961983-01-28028 January 1983 RO 3-83-2/IP:on 830126,containment Isolation Valve MO-5244, Associated W/Hpci Turbine Exhaust Line Vacuum Breaker,Failed to Fully Close During Local Leak Rate Testing.Caused by Solidified Lubricant in Valve Operator ML20028G2071983-01-20020 January 1983 RO 2-83-2/1P:on 830120,during Surveillance of Control Room,Indicating Lights for RCIC Inboard Steam Supply Isolation Valve Found Not Lit,Due to Open Feed Breaker Valve.Caused by Personnel Error.Feed Breaker Closed ML20028C5011983-01-0505 January 1983 RO 2-83-1/1P:on 830104,electrical Control Switch Failed During Environ Qualification Testing.Caused by Embrittlement of Nylon Cam Surface Matl Due to Radiation.Control Switch Contacts Jumpered & Leads Lifted ML20052F9001982-04-16016 April 1982 RO 2-82-10/01P:on 820413,w/Unit 2 Shutdown for Refueling/ Maint Outage & Unit 3 at Full Power,Possible Overexposure Identified on Eberline TLD for Month of Mar 1982.Cause Under Investigation ML20052F8791982-03-29029 March 1982 RO 2-82-08/01P:on 820328,w/Unit 2 Shutdown for Refueling/ Maint Outage & Unit 3 at Full Power,Diesel Fuel Oil Storage Tank Inventory Less than 104,000 Gallons.Caused by Unusual Usage of Fuel Oil by Auxiliary Boilers ML20041B0451982-02-10010 February 1982 RP 2-81-40/IT:on 810923, Survivability of Rockbestos Type RSS-6-104 & Rss-6-110 Coaxial Cable at Elevated Ambient Temps Not Proven.Caused by Apparent Design Deficiency.Cable to Be Replaced During Mar 1982 Refueling Outage ML20049A6051981-06-12012 June 1981 RO 2-81-34/1P:on 810612,during Safe Shutdown Analysis,Four Cables Were Found Improperly Routed & Improperly Designated as Nonsafeguard.Caused by Improper Designation of Three Cables Associated W/Power Supply to Room Cooler Fans ML19326E2421980-07-22022 July 1980 RO 2-80-12/1P:on 800721,while Testing Unit 2 During Refueling Outage,Scram Backup Valves in Air Supply to Control Rod Drive Scram Valves Failed.Caused by Design Error.Manual Venting Provided ML19330B8651980-07-17017 July 1980 RO 3-80-16/1P:on 800717,pipe Support Snubber 3-10-GB-S44 Exceeded Operability Criteria.Caused by Differences Between as-built Condition & Seismic Analysis Input Info.Hydraulic Snubber to Be Replaced W/Mechanical Snubber ML19320D4721980-07-15015 July 1980 RO-2-80-11/1P:on 800714,diesel Generator Cardox Sys Vapor Pilot Valve Was Found Closed.Caused by Failure to Properly Clear Safety Permit on 800730.Vapor Pilot Valve Locked Open ML19318D2251980-06-30030 June 1980 Ro:On 800329,RHR Motor Failed.Caused by Failure of Lower Guide Bearing.Instructions Issued to Operate RHR Sys at Full Flow Conditions.Fans on Motor Shaft Ends Being Replaced. Failed Motor Replaced W/New Motor ML19310A3201980-06-0404 June 1980 RO 2-80-10/1P:on 800330-0407 & 17-22,radioactive Water Was Released to Circulating Water Sys.Caused by Flooding of Normal Condenser Steam Space Permitting Radioactive Water to Leak Through Defective Condenser Tube to Water Sys ML19309H1051980-05-0202 May 1980 RO 2-80-9/1P:on 800502,during Shutdown & Movement of Fuel within Spent Fuel Pool,Secondary Containment Integrity Was Not Maintained.Caused by Removal of Steam & Feedwater Boot Seals.Boots Will Be Replaced & Procedures Will Be Revised ML19323C9981980-05-0101 May 1980 RO 2-80-8/1T:on 800417,preliminary Calculations Associated W/High Energy Line Breaks Revealed That Guillotine Failure of HPCI Steam Supply Would Result in Peak Pressure & Failure of Reinforced Concrete Block Wall.Mods Are Underway ML19323A6911980-04-28028 April 1980 RO 2-80-8-1P:updates Info Re Pressure Profile within Unit 3 Valve Following Guillotine Failure of HPCI Steam Supply Piping.Analysis Indicates Higher Peak Pressure than Originally Reported.Caused by Engineering Error ML19323A6901980-04-18018 April 1980 RO 2-80-8/1P:on 800417,development of Environ Spectrums Associated W/High Energy Line Breaks Indicated Guillotine Failure of Steam Supply Piping to HPCI Turbine.Caused by Engineering Deficiency ML19305A7661980-02-22022 February 1980 RO 3-80-7/1P:on 800221,seismic Nitrogen Supply to Five Containment Ventilation Valves Found Valved Out of Svc. Caused by Possible Lack of Info During 800205 Inerting Operation & 800220 Blocking Error During Mod Work ML19322B9381979-12-10010 December 1979 RO-2-79-53/1P:on 791207,recirculation Sys Sample Line Outer Valves Isolation Function Inoperable.Caused by Improper Testing of Installed Jumper.Jumper Removed,Valves Tested for Manual & Automatic Isolation & Found Operable ML19275B6471979-12-0606 December 1979 RO-2-79-52/1P:on 791127,seismic Capabilities of Concrete Block Walls on Elevation 135 Ft Reanalyzed as Less than Required Safety Factor.Caused by Engineering Design Deficiency.Mod of Wall Support Will Raise Safety Factor ML19268C4211979-12-0606 December 1979 Update to RO 2-79-52/1P:on 791205,discovered Low Safety Factor for Concrete Expansion Bolts.Engineering Analysis Indicates Stress in Concrete Block Wall Outer Fibers Will Not Exceed Design Allowable Values for DBE ML19322B9061979-12-0404 December 1979 RO-3-79-39/1P,update:on 791130,eight Seismic Supports Inside Containment & Supporting Control Rod Drive Piping Line Found Not to Be Seismically Qualified.Caused by Design Deficiency. Mods Will Be Completed During Outage Beginning 791207 ML19322B9051979-11-21021 November 1979 RO-3-79-38/1P:on 791121,review of 791117 Surveillance Test Revealed That Two MSIVs in Steamline a Closed in Shorter Times than Specified in Tech Specs.Caused by Possible Temp Effects on Hydraulic Fluid Viscosity ML19312B7581979-11-0202 November 1979 RO-2-79-49:on 791005,insp Program in Accordance W/Ie Bulletin 79-02 Revealed Design Deficiency in Four Seismic Supports Associated w/1-inch Control Rod Drive Piping. Bechtel Corp Redesigning Supports within Acceptable Limits ML19260A2541979-10-19019 October 1979 RO-3-79-29/1P:on 791019,piping Sys Insp & Measurement Program Indicated Damaged Sway Strut on Reactor Feed Pump C Discharge Line.Cause Under Investigation.New Sway Strut Ordered ML19276H6491979-10-19019 October 1979 RO 3-79-29/1P:on 791019,response to IE Bulletin 79-14 Revealed Damaged Sway Strut on C Reactor Feed Pump Discharge Line.Cause Under Investigation.New Sway Strut Will Arrive 791023 ML19322A3801979-10-0505 October 1979 RO-3-79-32/1P:on 791005,insp Performed Re IE Bulletin 79-02 Revealed Failure of Supports in Emergency Svc Water Return Line.Caused by Improper Installation of Anchor Bolts.Plate Washers Will Be Installed Over Bolts ML19308A4371979-10-0404 October 1979 RO-3-79-31/1P:on 791003,insp Performed in Response to IE Bulletin 79-02 Revealed Failure in Support in Loop Core B Spray Min Flow Line.Caused by Improper Installation of Anchor Bolts.Bolts Replaced ML19318A6481979-10-0303 October 1979 RO 3-79-30/1P:on 791002,seismic Anchor Insp Program Identified Failure in Support Associated W/Loop B Core Spray Discharge Line.Caused by Improper Installation of Anchor Bolt.Replacement of Two Failed Bolts Is in Progress ML19209B4321979-09-0707 September 1979 RO 2-79-43/1P:on 790906,in Response to IE Bulletin 79-07, Failure in One Support Associated W/High Pressure Svc Water Sys Piping in RHR Room 2A Identified.Larger Anchor Bolts Will Replace 7/8 Inch Bolts W/Installation of Plate Washers ML19209B4291979-09-0505 September 1979 RO 3-79-26/1P:on 790904,failure of Pipe Support Anchor on HPCI Pump Discharge Piping Noted.Undetermined Factor Caused Overstress Resulting in Failure.Vendor Presently Conducting Tests to Determine Optimum Method of Repair ML19259D1111979-08-22022 August 1979 RO 2-79-40/1P on 790821:while Cardox Sys Was Disabled, Continuous Fire Watch Not Maintained in Diesel Generator Bldg.Caused by Failure to Follow Procedure Designating Duties of Fire Watch.Personnel Reinstructed ML19270H4311979-07-25025 July 1979 RO 3-79-23/1P on 790724:anchor Support on Emergency Svc Water Piping in RHR Room Failed.Apparently Caused by Improper Installation.Anchors & Bolts Replaced & Satisfactorily Tested ML19259C5361979-05-17017 May 1979 RO 2-79-24/10:control Rod Driveline Return Line Outside Containment Support.Seismic Support Calculations in Response Ot IE Bulletin 79-04 Indicate Support for Piping Unsatisfactory ML19282B9531979-02-20020 February 1979 RO 2-79-8/10 on 790219:steady State Power Level Exceeded License Limit of 3293 Mw.Caused by Erroneous Feedwater Flow Input to Computer Causing Reactor Heat Balance to Indicate Less than Actual Power Level 1993-06-09
[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 ML20199E3471998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Peach Bottom,Units 1 & 2.With ML20205K0381998-12-31031 December 1998 PECO Energy 1998 Annual Rept. with ML20206P1651998-12-31031 December 1998 Fire Protection for Operating Nuclear Power Plants, Section Iii.F, Automatic Fire Detection ML20206D3651998-12-31031 December 1998 1998 PBAPS Annual 10CFR50.59 & Commitment Rev Rept. with ML20206D3591998-12-31031 December 1998 1998 PBAPS Annual 10CFR72.48 Rept. with ML20196G7021998-12-0202 December 1998 SER Authorizing Proposed Alternative to Delay Exam of Reactor Pressure Vessel Shell Circumferential Welds by Two Operating Cycles ML20196E8261998-11-30030 November 1998 Response to NRC RAI Re Reactor Pressure Vessel Structural Integrity at Peach Bottom Units 2 & 3 ML20198B8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Pbaps,Units 2 & 3. with 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 ML20154J2401998-10-0505 October 1998 Safety Evaluation Supporting Amends 224 & 228 to Licenses DPR-44 & DPR-56,respectively ML20154H4771998-10-0505 October 1998 Safety Evaluation Supporting Amends 225 & 229 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 ML20154G6631998-10-0101 October 1998 Safety Evaluation Supporting Amends 223 & 227 to Licenses DPR-44 & DPR-56,respectively 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 ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20248M3001998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Pbaps,Units 2 & 3 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] |
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< f Inspectico and Enforcament Of't.ca i a*ubm. 1 _-
siteclear Regislutary Comission 7 N ewt states .
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l 51mJECT: REPORTABt.E OCCURRENCE l V. T. Il11 rich's etwsversat ten with1940. Mr. firaensman,13.5. Nuc ear .-
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ceference: Oncket No. 5ft.279 T Pe=c81 Mtt w unit '! 6. 9. 2. a (6) .i 1 Tectwsics1 . Spec i fic at irm Reference : .
M-yort Mo. 3.ag-7/IP 71. 1990 r-Occurrenc, Pete: Fahrtenry : .3 Identifiestien of Occurrence _: {
seismic air supply to five containment ventitation valves volved euc .
af s rvice. E f-Apparent Cause of Occiscrence:
procedurst and operator error.
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Anntrsis of Occurrence: backupp seismically- y threiner a emittne inspection of plant equipent, the I tion he==ver, were j ,
gastified,bott. led nitresen vyp1y to fletve eontaionmt The vaiv-s vesitx =
nd werg,ther=(ove, t
l volv=s was foned te be volved esat of serv e . l 7 y>
heing supplied frw the normel instrinnent air supp y aThe nersel instriunmt sie supp completely operable. j' If a selwte event ocentrednvolved whichcmeld e*7ntted in fat havn permitted t* r, of the '
qaneli f ted. tha five valven i t instrio W . sirlesysteet, kare aft =r so=e time latervat if correctiv, action was i no d ,
egeteine m.t If a ealmete mt had ocetrered, the valves decreased woestd have rwen ne takest. to about
' tite required seated for abowt 24 ho.ses. If the disc s==L pressure 52 psig, en ledicating 1.t she in the control roa=this identi.fr wowtd condition show that.
ance-per-shift pawnet chack by the operator wm:14b t h d prior to less of and the **immic *ir supply would cbe re-este i s e hevw r***elted in leas of conteinment Amrastrity. This e mne* eettid rs occurred and if
cesstata==nt integeity enly if addifica=1 orarster erroadonai i
C4=et. ,
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800227o 6 0 9.
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e
. s Corr-etive Action:
When tb- First se t.m le,lly 'pst: 81flad batt imi backtip sirpply was i den t i ficit ,
nu investination into *.hst enu*e and an inapactiim of all containment vantilstien vnivaa v eta im= diataly initiesta,l. This inspection i<len t t fled ;
the co 'te other battled surpi.le9 which wara vntved out of *ervice. !
Pr-11minnry invetig= tion indientes that thesa bottles Wre l valved ant of re- eice en February 5; 19810 when tha etmeriinment VGntiitttien valves were set up for inerting of the containment prior to reactor startty.
The containnent vantilatien valva eparators and si.r mgply systems are being m lified to qualify the-t for operation ditring salmic avents.
See of the y=Iv-s have bean nimlified and others have not baen nodified.
Those valvas which are nat 'wodified have a nitroen bottia supply to the valve disc sael which is manually actumted following the positioning of tha volve in a closeil pas ttion. In order to opan these uneodt. fled vaivae, an acentar ==ts t VMlve out the str supply to the disc sam t prior to <merattne the valva fram tlie control ruim. It is pos=ibia that3 due to lack of overstor infamestion. in operator vatved out tha bott1=d mir supply en t!m five valves twtiaving they wera me yat not modified.
These five valves, Sewever, bed haen modified. Th9 whift that comoteted the inerting operntion on Fabruary 6. t#80,therefore ,Enited to restare the sai smic air supply bacouse they were not swere it had been valved out-ef service.
The inspection of the Unit 3 centnipaent ventilation valves also identifted a recent blocking nrrer. . At approximataly 2:20 AM on February 20 1980.
ventilation valve A9. 3512 was blocked for modification work. The operator cyplying the permit incorrectly velved ont the disc sesi sit supply to A0 3511 as wel.1 me AO 3512. At the time the inspection was made, the disc *ast prea*'tre on these valves ves 15 psig and 55 psia. Normai semi pr ,asure is.. granter than 75 psig. This crnaditten was immediately corrected. Leak tests performed to detemine the seal citpebility of these valves at the lower disc sealing pressure . indicated leakage we,Il be.Iow the . acceptable Iey,1.
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Tha inspectI'm of all other Wit 2 =nd thsit 3 contaim=ent vent 11= tion volves did not identify any other deficiencies. . The deficiencies discuesed above were imedintely corrected. ,
Tho investientinn of this occurr-nce ir continuing. Preliminary investigation indientes that. a6Litionel corractive action is required ist the area of erriipment identification, edification information transfer ,
a to the operations group, and procedural improvements.
Previous Failures: * ~
Mnne.
Very' tru1( yours, u
/h$
4 T. tilt rich
- Station Superintendent WTil:1hd 8
J 9 49 8
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