ML18041A190: Difference between revisions
From kanterella
Jump to navigation
Jump to search
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
| Line 2: | Line 2: | ||
| number = ML18041A190 | | number = ML18041A190 | ||
| issue date = 04/24/1989 | | issue date = 04/24/1989 | ||
| title = Special Rept:On 890414, | | title = Special Rept:On 890414,triaxial Time History Accelerometer Horizontal Trigger Circuits Identified As Inoperable. Caused by Incorrect Calibr Procedure.Surveillance Procedure Immediately Revised to Reflect Correct Setpoint Values | ||
| author name = NOONAN T P | | author name = NOONAN T P | ||
| author affiliation = DUQUESNE LIGHT CO. | | author affiliation = DUQUESNE LIGHT CO. | ||
Revision as of 17:17, 26 February 2018
| ML18041A190 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/24/1989 |
| From: | NOONAN T P DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ND3MNO:1867, NUDOCS 8904280274 | |
| Download: ML18041A190 (8) | |
Similar Documents at Beaver Valley | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20042E6431990-04-18018 April 1990
[Table view]Special Rept:On 900305,east Cable Vault Exhaust Damper VS-D-180 Failed to Close During Trip Testing of Fire Dampers Under Air Flow Conditions.Caused by Inadequate Spring Closure Mechanism.Springs Replaced W/Helical Coil Springs ML19324C2941989-11-0808 November 1989 Special Rept:On 891026,inservice Insp of Tubing in Steam Generators Completed.Degradation Mechanisms of Steam Generator Tubing Falls In,Cold Leg Support Plate Thinning & Hot Leg Support Plate Damage ML18041A1901989-04-24024 April 1989 Special Rept:On 890414,triaxial Time History Accelerometer Horizontal Trigger Circuits Identified as Inoperable. Caused by Incorrect Calibr Procedure.Surveillance Procedure Immediately Revised to Reflect Correct Setpoint Values ML20042B4491982-03-15015 March 1982 ROs 82-007/01P & 82-008/01P:during Update of Analysis Required by IE Bulletin 79-14,overstress Condition Found on a Steam Generator Steamline.Condition Analyzed in FSAR & Addressed Through Emergency Procedures ML20004F7401981-06-0808 June 1981 RO 81-047/01P:on 810606,during Normal Plant Tour,Primary Auxiliary Bldg Operator Found High Head Safety Injection Pump Emergency Cooling Water Supply Valve Unlocked & Closed. New Chain & Lock Installed ML20004C4811981-05-29029 May 1981 Ro:On 810527-29,during Routine Review of Surveillance Records,Discovered That Sample of Gaseous Waste Discharge Path Not Taken on 810528 as Required When Radiation Monitor Was Out of Svc.Required Samples Taken on 810527-29 ML20049A5871981-05-0404 May 1981 RO 81-32/01P:on 810502,feedwater Vibrations on a Steam Generator Feed Line Damaged Snubbers,Shims & Shim Retainer of Vertical Energy Constraint.Cause Under Investigation. Steam Release Calculations Will Be Refined ML19350C7411981-03-26026 March 1981 RO 81-029:on 810312,discrepancy Noted Between Plant Mod Manual & Tech Specs During Review of Inservice Insp Requirements for Mods Recently Completed on 0.75 & 1-inch Branch Connection on RCS & Safety Injection Sys ML19345B8001980-11-24024 November 1980 RO 80-086/01P:on 801121,Tech Specs 6.9.1.8.i Analysis of Structures Has Less Conservatism than Originally Calculated. Overstress Condition Exists on Seal Injection Header from Discharge of High Head Safety Injection Pumps ML20049A3351980-11-17017 November 1980 RO 80-078/01P:on 801114 It Was Discovered That Code Safety Valves Challenged W/Water Loop Seal on Inlets Would Result in Overstress of Pressurizer Safety & Power Operated Relief Valve Piping.Drainage of Seals Would Prevent Condition ML19347B6731980-10-0808 October 1980 RO:80-075/01P:on 801008,analysis Revealed Overstress Condition Existed at Pipe Support H-43 on Reactor Coolant Fill Header from High Head Charging Pumps.Cause Not Determined.Mod Will Be Completed Prior to Plant Startup ML19338E8441980-09-29029 September 1980 RO 80-071/01P:on 800926,during Surveillance Test to Verify Equipment Operating Times,Control Room Isolation Times Determined Not in Accordance W/Tech Specs.Caused by Tech Spec Error in Specified Response Time ML19338F1291980-09-29029 September 1980 RO 80-071/01P-0:on 800925,during Surveillance Test to Verify Equipment Operating Times,Control Room Isolation Times Determined Contrary to Tech Spec.Caused by Tech Spec Error in Required Time Determination ML19338F0261980-09-26026 September 1980 Ro:On 800925,diesel-driven Fire Pump Auto Started.Caused by Hole in Section of Pipe from Back Hoe Operator Digging Up Portion of Fire Main Yard Loop.Leak Isolated & Backup Water Made Available.Pipe Section Repaired ML19347A8531980-09-23023 September 1980 RO 80-070/01P:on 800922,born Dilution Discovered During RCS Initial Fill & Vent,Causing Unplanned Reactivity Insertion to Exceed Tech Specs Limits.Caused by Procedural Deficiency.Boric Acid Blender Total Flow Setpoint Changed ML19347B1011980-09-22022 September 1980 RO 80-069/01P-0:on 800920,motor Driven Fire Pump Began Smoking & Leaking Oil After Surveillance Test.Investigation Showed Cooling Water Lost from Upper Bearing Cooler.Cause Undetermined.Temporary back-up Pumps Available ML19338D1191980-09-15015 September 1980 Ro:Evaluation & Analysis Required by IE Bulletin 79-14 Revealed Piping & Supports Have Less Conservatism During Seismic Events.Mods Will Be Made Prior to Startup ML19344F5341980-09-0808 September 1980 Ro:Evaluation & Reanalysis Required by IE Bulletin 79-14 Revealed That Certain Piping & Supports Have Less Conservatism than Assumed for Safety Analysis.Cause Unstated.Pipe Support Will Be Added Prior to Startup ML19330B4241980-07-28028 July 1980 RO 80-052/01P:on 800726,diesel Fire Pump auto-started Below Rated RPM & Pressure.No Specific Cause Found.Fuel Oil Filter Changed & Pump Tested Successfully ML19318D0731980-06-30030 June 1980 RO 80-044/01T:design for Steam Generator Snubber Embedment Found Not to Reflect as-constructed Condition, Resulting in Nonconservative Loads for Anchors.Caused by Assumption That Load Was Applied to Normal Surface ML19318B3361980-06-20020 June 1980 RO 80-037/01T:during Review of Radiographs of Reactor Containment Liner Seam Welds,Portion of One Weld Is Code Rejectable.Authenticity of Other Seam Weld Radiographs Questionable.Investigation Continuing ML19323H6721980-06-0909 June 1980 Ro:On 800529,meteorological Instrumentatiion Computer Channels Found Not Responding Properly to Automatic Calibr Signals.Caused by Output Resistors Not Being Removed During 800515 Move.Resistors Removed & Sys Calibr Verified ML19323F1501980-05-21021 May 1980 RO 80-031/01T:on 800521,while Energizing RHR motor-operated Isolation Valves,Suction Valve Closed.Caused by False High Pressure Signal Input Due to de-energized Instrument Loop. RHR Pump Shut Down.Sys Isolated for Repairs ML19323F1541980-05-20020 May 1980 RO-80-030/01T:on 800519,during Test of Diesel Driven Fire Pump High Temp Alarm Occured.Cause Unknown.Temporary Fire Pump Hooked Up.Investigation Underway ML19309E7821980-04-16016 April 1980 RO 80-025/01T:during Tank Mod Project,Field Engineers Reported That Weld on 12-inch Nozzle Penetrations to Refueling Water Storage Tank Does Not Conform W/Manufacturer Design.Addl Penetrations Are Being Checked ML19323A0961980-04-11011 April 1980 RO 80-023/01T:during Operational Mode 5,w/steam Generators & RCS Level at mid-span in Loops,Complete Loss of RHR Flow Occurred While Plant Operators Were Increasing Heat Exchanger Flow.Procedure Rewritten ML19305D2851980-04-0808 April 1980 RO 80-22/01T:on 800407,during Operational Mode 5,complete Loss of RHR Flow Occurred During Attempt to Increase Flow. Operating Procedure Changed to Require Venting RHR During Flow Increase ML19309D7511980-04-0303 April 1980 Ro:On 800225,two Frequencies on Peak Shock Annunciator Sys Actuated Visual Alarms.Cause Unknown.Problem w/70% (OBE) Visual Alarms May Have Been Caused by Reed Switches or Alarm Circuitry.Investigation Is Continuing ML19305A9711980-03-12012 March 1980 RO 80-12/01T:on 800312,during Operations Audit,Tech Spec Surveillance 4.3.3.5 Found to Be Violated.Required Channel Check Not Performed Since Jul 1976.Requirement Deleted Due to Meter Reading of Zero During Normal Operation ML19344D3071980-03-0505 March 1980 Ro:On 800226,fire Pump Removed from Svc Due to Suspicion of Water in Pump Oil.Cause Unstated.Oil Cooler Checked & Hydroed Satisfactorily.Motor Bearing Will Be Replaced & Returned to Svc ML19296D1651980-02-25025 February 1980 RO 80-08/01T:on 800225,during Cable Tray & Conduit as-built Configuration Review,Preliminary Framing Beam Analysis Indicated Potential Floor Beam Overstress.Caused by Conduit & Tray Support Horizontal Acceleration ML19305A7641980-02-22022 February 1980 RO 80-7/01P:on 800221,condition Found Resulting in No Supplementary Leak Collection & Release Flow Through Main Filter Banks During Fuel Movement.Caused by Procedure Inadequacy.Procedures Revised ML19257C6371980-01-24024 January 1980 RO-80-3/01P:on 800124,analysis Showed That,During Postulated Seismic Event,Pipe Support H-95 on Component Cooling Water Sys Line CC-323 Would Receive Overstress.Support H-95 Will Be Altered to 3-way Restraint ML19291C2671980-01-17017 January 1980 LER 80-02/01T:on 800117,while in Operational Mode 5,received Indication of Low Residual Heat Removal Sys Flow When Low Flow Alarm Was Annunciated & Low Pump Amps Noted.Caused by Steam Generator Burp.Air Eductor Installed ML19291C2571980-01-11011 January 1980 Suppl to 790718 RO Re Fire Main Sys Rupture.Problem at Facility Not Considered Generic.Piping Was Probably Struck Sharp Blow During Const or Installation of Nearby Conduit Which Contributed to Failure ML19210E4051979-11-28028 November 1979 RO 79-46/01P:on 791127 Flowpath to Charging Pumps Closed Due to Planned Removal of Emergency Diesel Generator.High Head Injection Would Have Not Been Available If Needed.Error Corrected When Valve Opened to Increase Flow Path to Pumps ML19254F9231979-11-13013 November 1979 LER 79-47/01P:on 791110,review of Plant Operator Logs & History of Containment Vacuum Pumps Suggested Air Leak Into Containment.Caused by Particulate Monitor Leak.Leak Repaired.Monitor Returned to Svc ML19210C1141979-11-0505 November 1979 RO 79-49/01P:on 791105,during Routine Review of Operations, Samples of Containment Atmosphere Gaseous Monitor Could Not Be Taken.Activity Levels Could Still Be Monitored.Addl Info in Followup Rept ML19256A1471978-10-27027 October 1978 RO 78-053/01P:on 781026 During Review of Stresscalculations for Safety Injection Piping Inside Containment,Errors in Piping Stress Analysis Were Discovered.Caused by Error in Hand Calculating Method 1990-04-18 Category:LER) MONTHYEARML20042E6431990-04-18018 April 1990
[Table view]Special Rept:On 900305,east Cable Vault Exhaust Damper VS-D-180 Failed to Close During Trip Testing of Fire Dampers Under Air Flow Conditions.Caused by Inadequate Spring Closure Mechanism.Springs Replaced W/Helical Coil Springs ML19324C2941989-11-0808 November 1989 Special Rept:On 891026,inservice Insp of Tubing in Steam Generators Completed.Degradation Mechanisms of Steam Generator Tubing Falls In,Cold Leg Support Plate Thinning & Hot Leg Support Plate Damage ML18041A1901989-04-24024 April 1989 Special Rept:On 890414,triaxial Time History Accelerometer Horizontal Trigger Circuits Identified as Inoperable. Caused by Incorrect Calibr Procedure.Surveillance Procedure Immediately Revised to Reflect Correct Setpoint Values ML20042B4491982-03-15015 March 1982 ROs 82-007/01P & 82-008/01P:during Update of Analysis Required by IE Bulletin 79-14,overstress Condition Found on a Steam Generator Steamline.Condition Analyzed in FSAR & Addressed Through Emergency Procedures ML20004F7401981-06-0808 June 1981 RO 81-047/01P:on 810606,during Normal Plant Tour,Primary Auxiliary Bldg Operator Found High Head Safety Injection Pump Emergency Cooling Water Supply Valve Unlocked & Closed. New Chain & Lock Installed ML20004C4811981-05-29029 May 1981 Ro:On 810527-29,during Routine Review of Surveillance Records,Discovered That Sample of Gaseous Waste Discharge Path Not Taken on 810528 as Required When Radiation Monitor Was Out of Svc.Required Samples Taken on 810527-29 ML20049A5871981-05-0404 May 1981 RO 81-32/01P:on 810502,feedwater Vibrations on a Steam Generator Feed Line Damaged Snubbers,Shims & Shim Retainer of Vertical Energy Constraint.Cause Under Investigation. Steam Release Calculations Will Be Refined ML19350C7411981-03-26026 March 1981 RO 81-029:on 810312,discrepancy Noted Between Plant Mod Manual & Tech Specs During Review of Inservice Insp Requirements for Mods Recently Completed on 0.75 & 1-inch Branch Connection on RCS & Safety Injection Sys ML19345B8001980-11-24024 November 1980 RO 80-086/01P:on 801121,Tech Specs 6.9.1.8.i Analysis of Structures Has Less Conservatism than Originally Calculated. Overstress Condition Exists on Seal Injection Header from Discharge of High Head Safety Injection Pumps ML20049A3351980-11-17017 November 1980 RO 80-078/01P:on 801114 It Was Discovered That Code Safety Valves Challenged W/Water Loop Seal on Inlets Would Result in Overstress of Pressurizer Safety & Power Operated Relief Valve Piping.Drainage of Seals Would Prevent Condition ML19347B6731980-10-0808 October 1980 RO:80-075/01P:on 801008,analysis Revealed Overstress Condition Existed at Pipe Support H-43 on Reactor Coolant Fill Header from High Head Charging Pumps.Cause Not Determined.Mod Will Be Completed Prior to Plant Startup ML19338E8441980-09-29029 September 1980 RO 80-071/01P:on 800926,during Surveillance Test to Verify Equipment Operating Times,Control Room Isolation Times Determined Not in Accordance W/Tech Specs.Caused by Tech Spec Error in Specified Response Time ML19338F1291980-09-29029 September 1980 RO 80-071/01P-0:on 800925,during Surveillance Test to Verify Equipment Operating Times,Control Room Isolation Times Determined Contrary to Tech Spec.Caused by Tech Spec Error in Required Time Determination ML19338F0261980-09-26026 September 1980 Ro:On 800925,diesel-driven Fire Pump Auto Started.Caused by Hole in Section of Pipe from Back Hoe Operator Digging Up Portion of Fire Main Yard Loop.Leak Isolated & Backup Water Made Available.Pipe Section Repaired ML19347A8531980-09-23023 September 1980 RO 80-070/01P:on 800922,born Dilution Discovered During RCS Initial Fill & Vent,Causing Unplanned Reactivity Insertion to Exceed Tech Specs Limits.Caused by Procedural Deficiency.Boric Acid Blender Total Flow Setpoint Changed ML19347B1011980-09-22022 September 1980 RO 80-069/01P-0:on 800920,motor Driven Fire Pump Began Smoking & Leaking Oil After Surveillance Test.Investigation Showed Cooling Water Lost from Upper Bearing Cooler.Cause Undetermined.Temporary back-up Pumps Available ML19338D1191980-09-15015 September 1980 Ro:Evaluation & Analysis Required by IE Bulletin 79-14 Revealed Piping & Supports Have Less Conservatism During Seismic Events.Mods Will Be Made Prior to Startup ML19344F5341980-09-0808 September 1980 Ro:Evaluation & Reanalysis Required by IE Bulletin 79-14 Revealed That Certain Piping & Supports Have Less Conservatism than Assumed for Safety Analysis.Cause Unstated.Pipe Support Will Be Added Prior to Startup ML19330B4241980-07-28028 July 1980 RO 80-052/01P:on 800726,diesel Fire Pump auto-started Below Rated RPM & Pressure.No Specific Cause Found.Fuel Oil Filter Changed & Pump Tested Successfully ML19318D0731980-06-30030 June 1980 RO 80-044/01T:design for Steam Generator Snubber Embedment Found Not to Reflect as-constructed Condition, Resulting in Nonconservative Loads for Anchors.Caused by Assumption That Load Was Applied to Normal Surface ML19318B3361980-06-20020 June 1980 RO 80-037/01T:during Review of Radiographs of Reactor Containment Liner Seam Welds,Portion of One Weld Is Code Rejectable.Authenticity of Other Seam Weld Radiographs Questionable.Investigation Continuing ML19323H6721980-06-0909 June 1980 Ro:On 800529,meteorological Instrumentatiion Computer Channels Found Not Responding Properly to Automatic Calibr Signals.Caused by Output Resistors Not Being Removed During 800515 Move.Resistors Removed & Sys Calibr Verified ML19323F1501980-05-21021 May 1980 RO 80-031/01T:on 800521,while Energizing RHR motor-operated Isolation Valves,Suction Valve Closed.Caused by False High Pressure Signal Input Due to de-energized Instrument Loop. RHR Pump Shut Down.Sys Isolated for Repairs ML19323F1541980-05-20020 May 1980 RO-80-030/01T:on 800519,during Test of Diesel Driven Fire Pump High Temp Alarm Occured.Cause Unknown.Temporary Fire Pump Hooked Up.Investigation Underway ML19309E7821980-04-16016 April 1980 RO 80-025/01T:during Tank Mod Project,Field Engineers Reported That Weld on 12-inch Nozzle Penetrations to Refueling Water Storage Tank Does Not Conform W/Manufacturer Design.Addl Penetrations Are Being Checked ML19323A0961980-04-11011 April 1980 RO 80-023/01T:during Operational Mode 5,w/steam Generators & RCS Level at mid-span in Loops,Complete Loss of RHR Flow Occurred While Plant Operators Were Increasing Heat Exchanger Flow.Procedure Rewritten ML19305D2851980-04-0808 April 1980 RO 80-22/01T:on 800407,during Operational Mode 5,complete Loss of RHR Flow Occurred During Attempt to Increase Flow. Operating Procedure Changed to Require Venting RHR During Flow Increase ML19309D7511980-04-0303 April 1980 Ro:On 800225,two Frequencies on Peak Shock Annunciator Sys Actuated Visual Alarms.Cause Unknown.Problem w/70% (OBE) Visual Alarms May Have Been Caused by Reed Switches or Alarm Circuitry.Investigation Is Continuing ML19305A9711980-03-12012 March 1980 RO 80-12/01T:on 800312,during Operations Audit,Tech Spec Surveillance 4.3.3.5 Found to Be Violated.Required Channel Check Not Performed Since Jul 1976.Requirement Deleted Due to Meter Reading of Zero During Normal Operation ML19344D3071980-03-0505 March 1980 Ro:On 800226,fire Pump Removed from Svc Due to Suspicion of Water in Pump Oil.Cause Unstated.Oil Cooler Checked & Hydroed Satisfactorily.Motor Bearing Will Be Replaced & Returned to Svc ML19296D1651980-02-25025 February 1980 RO 80-08/01T:on 800225,during Cable Tray & Conduit as-built Configuration Review,Preliminary Framing Beam Analysis Indicated Potential Floor Beam Overstress.Caused by Conduit & Tray Support Horizontal Acceleration ML19305A7641980-02-22022 February 1980 RO 80-7/01P:on 800221,condition Found Resulting in No Supplementary Leak Collection & Release Flow Through Main Filter Banks During Fuel Movement.Caused by Procedure Inadequacy.Procedures Revised ML19257C6371980-01-24024 January 1980 RO-80-3/01P:on 800124,analysis Showed That,During Postulated Seismic Event,Pipe Support H-95 on Component Cooling Water Sys Line CC-323 Would Receive Overstress.Support H-95 Will Be Altered to 3-way Restraint ML19291C2671980-01-17017 January 1980 LER 80-02/01T:on 800117,while in Operational Mode 5,received Indication of Low Residual Heat Removal Sys Flow When Low Flow Alarm Was Annunciated & Low Pump Amps Noted.Caused by Steam Generator Burp.Air Eductor Installed ML19291C2571980-01-11011 January 1980 Suppl to 790718 RO Re Fire Main Sys Rupture.Problem at Facility Not Considered Generic.Piping Was Probably Struck Sharp Blow During Const or Installation of Nearby Conduit Which Contributed to Failure ML19210E4051979-11-28028 November 1979 RO 79-46/01P:on 791127 Flowpath to Charging Pumps Closed Due to Planned Removal of Emergency Diesel Generator.High Head Injection Would Have Not Been Available If Needed.Error Corrected When Valve Opened to Increase Flow Path to Pumps ML19254F9231979-11-13013 November 1979 LER 79-47/01P:on 791110,review of Plant Operator Logs & History of Containment Vacuum Pumps Suggested Air Leak Into Containment.Caused by Particulate Monitor Leak.Leak Repaired.Monitor Returned to Svc ML19210C1141979-11-0505 November 1979 RO 79-49/01P:on 791105,during Routine Review of Operations, Samples of Containment Atmosphere Gaseous Monitor Could Not Be Taken.Activity Levels Could Still Be Monitored.Addl Info in Followup Rept ML19256A1471978-10-27027 October 1978 RO 78-053/01P:on 781026 During Review of Stresscalculations for Safety Injection Piping Inside Containment,Errors in Piping Stress Analysis Were Discovered.Caused by Error in Hand Calculating Method 1990-04-18 Category:TEXT-SAFETY REPORT MONTHYEARL-99-154, Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with1999-09-30030 September 1999
[Table view]Monthly Operating Repts for Sept 199 for Bvps,Units 1 & 2. with L-99-139, LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With1999-09-0202 September 1999 LER 99-S01-00:on 990813,uncompensated Loss of Ability to Detect within Single Intrusion Security Detection Zone Occurred.Caused by Procedure non-compliance.Involved Personnel Received Counseling Re Event.With L-99-140, Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Bvps,Units 1 & 2. with L-99-126, Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for Jul 1999 for Beaver Valley Power Station,Units 1 & 2.With L-99-107, Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bvps,Units 1 & 2. with ML20209D9531999-06-27027 June 1999 Inservice Insp Ninety-Day Rept Bvps,Unit 2 Outage 7,Year 1999 L-99-096, Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for BVPS Units 1 & 2. with L-99-078, Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable1999-05-0303 May 1999 Special Rept:On 990326,seismic Monitoring Instruments Were Declared Inoperable.Caused by Resolution of Potential TS Compliance Issue & Work Scheduling Issue.Instrumentation Was Returned to Svc Following Calibr & Declared Operable L-99-079, Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Beaver Valley Power Station,Units 1 & 2.With ML20205L0401999-04-0909 April 1999 SER Accepting Util Relief Requests for Inservice Insp Second 10-year Interval for Beaver Valley Power Station, Unit 2 L-99-054, Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite1999-04-0505 April 1999 Special Rept:On 990320,meteorological Tower Wind Speed Sensors Were Declared Inoperable.Caused by Calibration Completed by Vendor Did Not Adequately Cover Full Operating Range of Sensors.Removed Sensors & Sent Offsite L-99-058, Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bvps,Units 1 & 2. with ML20196K7981999-03-25025 March 1999 Rev 4 to COLR, for Cycle 8 L-99-038, Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Bvps,Units 1 & 2. with ML20203E1181999-02-10010 February 1999 SER Accepting Proposed Revs to Plant,Units 1 & 2 Quality Assurance Program Description L-99-019, Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced1999-02-0505 February 1999 Special Rept:On 990120,meteorological Tower Wind Speed Sensors Declared Inoperable.Caused by Processor Card for Sensor Locked Up & Needed to Be Reset.Heater That Fit Around Shaft of Sensor Replaced ML20196F7011999-01-31031 January 1999 BVPS Unit 2 Heatup & Cooldown Limit Curves During Normal Operation at 15 EFPY Using Code Case N-626 ML20203D4811999-01-31031 January 1999 Monthly Operating Repts for Jan 1999 for Bvps,Units 1 & 2, in Accordance with NRC GL 97-02.With ML20207E6631999-01-28028 January 1999 Rev 0 to EMECH-0713-1, Operational Assessment of SG Tubing at Beaver Valley Unit 1,Cycle 13 ML20210G7041999-01-22022 January 1999 BVPS Unit 1 Facility Changes,Tests & Experiments for 980123-990122 ML20207E5861998-12-31031 December 1998 Annual Rept 1998 for Toledo Edison ML20207E5601998-12-31031 December 1998 Annual Rept 1998 for Pennpower ML20198B9021998-12-31031 December 1998 BVPS Unit 1 Simulator Four Yr Certification Rept for 1995-1998 ML20207E5901998-12-31031 December 1998 Dqe 1998 Annual Rept to Shareholders ML20199C9971998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Bvps,Units 1 & 2. with ML20207E5521998-12-31031 December 1998 Annual Rept 1998 for Ohio Edison ML20207E5761998-12-31031 December 1998 Annual Rept 1998 for Illuminating Co ML20204J6751998-12-31031 December 1998 1998 Annual Rept for Dbnps,Unit 1,PNPP,Unit 1 & BVPS Units 1 & 2 ML20199F5341998-12-29029 December 1998 Safety Evaluation Granting Relief Requests 1-TYP-3-B3.140-1, 1-TYP-3-B5.70-1,1-TYP-3-RH-E-1-1,1-TYP-3-B-G-1, 1-TYP-3-APP-I-1,1-TYP-3-UT-1,1-TYP-3-N-509,1-TYP-3-N-521, 1-TYP-3-N-524,1-TYP-3-B3.120-1 & 1-TYP-3-C6.10-1 ML20198K8551998-12-21021 December 1998 SER Granting Relief Request PRR-5 for Third 10-year Inservice Testing for Beaver Valley Power Station,Unit 1 ML20198A1631998-12-0909 December 1998 SER Approving Implementation Program to Resolve USI A-46 at Facility That Has Adequately Addressed Purpose of 10CFR50.54(f) Request L-98-229, Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Bvps,Units 1 & 2. with ML20195J3131998-11-12012 November 1998 Safety Evaluation Granting First & Second 10-yr Interval Inservice Insp Request for Relief L-98-210, Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Bvps,Units 1 & 2. with ML20206G0291998-10-31031 October 1998 BVPS Unit 2 Facility Changes,Tests & Experiments for Period 971101-981031 ML20154R9121998-10-20020 October 1998 Safety Evaluation Accepting Proposed Changes to QA Program Description in Chapter 17.2 of BVPS-2 Ufsar.Proposed Changes Would Modify QA Organization to Allow Warehouse QC Inspectors to Report to Manager of Nuclear Procurement Dept ML20154P7491998-10-19019 October 1998 SE Accepting Second ten-year Interval Inservice Insp Request for Relief RR-1-TYP-2-B5.40-1,Rev 0,for Plant, Unit 1 ML20198F7611998-10-0606 October 1998 Duquesne Light Co,Beaver Valley Power Station 1998 Emergency Preparedness Ingestion Zone Exercise, Conducted on 981006 ML20154C6711998-10-0101 October 1998 Safety Evaluation Concluding That Revised Model Identified in Dl Submittal Was Appropriate for Analysis of Installed Conduit Ampacity Limits.Determined That There Are No Outstanding Safety Concerns with Respect to Ampacity ML20154D5001998-09-30030 September 1998 Special Rept on Overview of BVPS-1 & BVPS-2 TS Compliance Issues & Corrective Action Taken L-98-197, Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Beaver Valley Power Station,Units 1 & 2.With ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods L-98-188, Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure1998-09-21021 September 1998 Special Rept:During 1998,Unit 2 SG Eddy Current exam,26 Tubes Were Improperly Encoded in SG 2RCS-SG21C During Previous Outage.Use of Independent Databases to Track New Indications Being Implemented as Preventive Measure L-98-178, Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Bvps,Units 1 & 2. with ML20155B5871998-08-28028 August 1998 Non-proprietary Rev 1 to 51-5001925-01, Risk Assessment for Installation of Electrosleeves at BVPS & Callaway Plant ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed L-98-168, Monthly Operating Repts for July 1998 for Bvps,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Bvps,Units 1 & 2 L-98-157, Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product1998-07-29029 July 1998 Special Rept:On 980423,inoperability of Seismic Monitoring Instrument Noted.Caused by Obsolescence of Instrument & Inability to Obtain Necessary Spare Parts.Design Change Is Being Pursued to Obtain Replacement Product L-98-139, Monthly Operating Repts for June 1998 for Bvps,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Bvps,Units 1 & 2 L-98-119, Monthly Operating Repts for Bvps,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for Bvps,Units 1 & 2 1999-09-30 |
Retrieved from "https://kanterella.com/w/index.php?title=ML18041A190&oldid=370398"