ML19308A437
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| ML19308A437 | |
| Person / Time | |
|---|---|
| Site: | Peach Bottom  |
| Issue date: | 10/04/1979 |
| From: | Ullrich W PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| To: | |
| References | |
| NUDOCS 7910150483 | |
| Download: ML19308A437 (2) | |
Similar Documents at Peach Bottom | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20045B2381993-06-0909 June 1993
[Table view]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 Category:LER) MONTHYEARML20045B2381993-06-0909 June 1993
[Table view]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 Category:TEXT-SAFETY REPORT MONTHYEARML20217K9931999-10-14014 October 1999
[Table view]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 |
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