ML20064H896
From kanterella
| ML20064H896 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 12/19/1978 |
| From: | Tollison A CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML20064H894 | List: |
| References | |
| LER-78-091-03L, LER-78-91-3L, NUDOCS 7812270292 | |
| Download: ML20064H896 (2) | |
Similar Documents at Brunswick | |
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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEAR05000324/LER-1992-001, Supplemental LER 92-001-01:on 920202,unit Scrammed During Main Turbine Control Valve Testing.Caused by Excessive Cycling of Turbine Control Valves.Hydraulic Accumulators a & B Disassembled1993-09-0202 September 1993
[Table view]Supplemental LER 92-001-01:on 920202,unit Scrammed During Main Turbine Control Valve Testing.Caused by Excessive Cycling of Turbine Control Valves.Hydraulic Accumulators a & B Disassembled 05000324/LER-1993-0081993-08-13013 August 1993 LER 93-008-00:on 930714,core Rated Thermal Power Exceeded Allowable Amount Due to Feedwater Flow Inaccuracy.Cause Believed to Be Due to Erosion/Corrosion of FW Flow Elements. FW Instrumentation recalibr.W/930812 Ltr 05000324/LER-1992-0101993-08-12012 August 1993 LER 92-010-01:on 921207,penetration Leakage Exceeded TS Allowable Limit Due to actuator-to-valve Alignment & disk-to-seat Alignment Problems.Line Bored Valve to Achieve concentricity.W/930812 Ltr 05000324/LER-1991-0191993-08-12012 August 1993 LER 91-019-01:on 911112,LLRT Failure of Two MSL Inboard & Outboard Isolation Valves Resulted in Condition Outside Design Basis.Root Cause Analysis in Process.Msls C & D Inboard & Outboard MSIVs Repairs complete.W/930812 Ltr 05000324/LER-1993-0031993-05-10010 May 1993 LER 93-003-00:on 930408,identified That Drywell Spray Outboard Isolation Valve Installed in Reverse Direction. Caused by Design & Installation Error.Appropriate Documents Will Be revised.W/930507 Ltr 05000324/LER-1988-0011990-08-0101 August 1990 LER 88-001-07:on 880102,manual Reactor Scram Occurred Due to Decreasing Main Condenser Vacuum.Reactor Power at 55% & Vacuum Decreased to 22 Inches Mercury.Caused by Leaks on Main Turbine Piping.Piping repaired.W/900801 Ltr 05000324/LER-1983-019, Updated LER 83-019/01T-2:on 830210,instrument Air Tubing to Safety Relief Valve/Automatic Depressurization Sys Valve Accumulator Inadequately Supported.Caused by Rerouted Tubing.Supports Installed1984-07-12012 July 1984 Updated LER 83-019/01T-2:on 830210,instrument Air Tubing to Safety Relief Valve/Automatic Depressurization Sys Valve Accumulator Inadequately Supported.Caused by Rerouted Tubing.Supports Installed 05000325/LER-1982-108, Updated LER 82-108/03L-1:on 821010 & 14,while Performing Automatic Depressurization Sys Valve Operability Test,Valves 1-B21-F013J & 1-B21-F013D & E Failed to Reclose.Caused by Faulty Spring.Valves Replaced1984-05-18018 May 1984 Updated LER 82-108/03L-1:on 821010 & 14,while Performing Automatic Depressurization Sys Valve Operability Test,Valves 1-B21-F013J & 1-B21-F013D & E Failed to Reclose.Caused by Faulty Spring.Valves Replaced 05000325/LER-1982-122, Supplemental LER 82-122/03L-1:on 821030 & 1104,reactor Recirculation Pump 1A Tripped.On 821101 & 04,reactor Recirculation Pump 1B Tripped.Caused by Spurious Action of ATWS Instrument B21-PS-N045C1984-04-0909 April 1984 Supplemental LER 82-122/03L-1:on 821030 & 1104,reactor Recirculation Pump 1A Tripped.On 821101 & 04,reactor Recirculation Pump 1B Tripped.Caused by Spurious Action of ATWS Instrument B21-PS-N045C 05000325/LER-1981-053, Updated LER 81-053/03L-1:on 810922,during Reactor Startup, Reactor Recirculation Pump 1B Tripped.Caused by Spurious Trip Signal from ATWS Low Water Level Instrument B21-LTM- NO24B-2.Instrument replaced.W/840329 Ltr1984-03-29029 March 1984 Updated LER 81-053/03L-1:on 810922,during Reactor Startup, Reactor Recirculation Pump 1B Tripped.Caused by Spurious Trip Signal from ATWS Low Water Level Instrument B21-LTM- NO24B-2.Instrument replaced.W/840329 Ltr 05000325/LER-1981-055, Updated LER 81-055/03L-1:on 820622,drywell Equipment Drain Flow Integrator 1-G16-FQ-K603 Continuously Indicated Dwed Sump Flow W/No Pumps Running.Caused by Water Being Introduced Into Pneumatic calibrator.W/840328 Ltr1984-03-28028 March 1984 Updated LER 81-055/03L-1:on 820622,drywell Equipment Drain Flow Integrator 1-G16-FQ-K603 Continuously Indicated Dwed Sump Flow W/No Pumps Running.Caused by Water Being Introduced Into Pneumatic calibrator.W/840328 Ltr 05000325/LER-1983-063, Updated LER 83-063/03L-1:on 831203,reactor Water Cleanup Sys (Rwcs) Differential Flow Indicator 1-G31-R615 Showed Erroneous Indication.On 831207,spurious Rwcs Alarm Annunciated.Caused by Air in Sensing lines.W/840222 Ltr1984-02-22022 February 1984 Updated LER 83-063/03L-1:on 831203,reactor Water Cleanup Sys (Rwcs) Differential Flow Indicator 1-G31-R615 Showed Erroneous Indication.On 831207,spurious Rwcs Alarm Annunciated.Caused by Air in Sensing lines.W/840222 Ltr 05000325/LER-1983-057, Updated LER 83-057/03L-1:on 831119,during Unit Power Performance,Temp Recorder TR-1258 Printed Erratically.Caused by Dirty Electrical Contacts in Control Board Timing Relay. Contacts Cleaned & Returned to svc.W/840222 Ltr1984-02-22022 February 1984 Updated LER 83-057/03L-1:on 831119,during Unit Power Performance,Temp Recorder TR-1258 Printed Erratically.Caused by Dirty Electrical Contacts in Control Board Timing Relay. Contacts Cleaned & Returned to svc.W/840222 Ltr 05000324/LER-1983-097, Updated LER 83-097/01T-1:on 831212,during Testing,Per IE Bulletin 83-02,crack Indications Discovered in 19 of 131 Welds in Reactor Recirculation & Reactor Water Cleanup Sys. Caused by Stress Corrosion Cracking1984-01-24024 January 1984 Updated LER 83-097/01T-1:on 831212,during Testing,Per IE Bulletin 83-02,crack Indications Discovered in 19 of 131 Welds in Reactor Recirculation & Reactor Water Cleanup Sys. Caused by Stress Corrosion Cracking 05000325/LER-1983-045, Updated LER 83-045/03L-2:on 830919 & 24,inboard PCIV Steam Supply Valve ES1-F007 to RCIC Sys Would Not Completely Reopen.Caused by Loose Limitorque Motor Operator Spring Pack1984-01-24024 January 1984 Updated LER 83-045/03L-2:on 830919 & 24,inboard PCIV Steam Supply Valve ES1-F007 to RCIC Sys Would Not Completely Reopen.Caused by Loose Limitorque Motor Operator Spring Pack 05000324/LER-1982-024, Updated LER 82-024/01T-1:on 820205,determined That Control Bldg Emergency Ventilation Sys Trains Will Not Isolate Upon Receipt of Chlorine Isolation Signal If Control Switch in on Position Due to Design Deficiency1983-11-14014 November 1983 Updated LER 82-024/01T-1:on 820205,determined That Control Bldg Emergency Ventilation Sys Trains Will Not Isolate Upon Receipt of Chlorine Isolation Signal If Control Switch in on Position Due to Design Deficiency 05000324/LER-1983-083, Updated LER 83-083/01T-1:on 830905,supply Valve 2-FP-V39 to Deluge Sys of Both Standby Gas Treatment Sys Discovered Shut.Caused by Operator Error.Valves Tagged for Identification.Auxiliary Operator Disciplined1983-09-23023 September 1983 Updated LER 83-083/01T-1:on 830905,supply Valve 2-FP-V39 to Deluge Sys of Both Standby Gas Treatment Sys Discovered Shut.Caused by Operator Error.Valves Tagged for Identification.Auxiliary Operator Disciplined 05000325/LER-1983-034, Updated LER 83-034/01T-1:on 830811,following Extended Maint & Refueling Outage,Instrument Isolation Valves to 1CAC-PDS-4222 & 4223 Discovered Closed.Caused by Cancelation of Equipment Clearance.Valves Reopened1983-09-12012 September 1983 Updated LER 83-034/01T-1:on 830811,following Extended Maint & Refueling Outage,Instrument Isolation Valves to 1CAC-PDS-4222 & 4223 Discovered Closed.Caused by Cancelation of Equipment Clearance.Valves Reopened 05000325/LER-1983-017, Updated LER 83-017/03L-1:on 830326-28 & 0402,listed Control Rods Had No Indications for Identified Positions.Caused by Loose Prototypic Inlet Piping Connectors Due to Undervessel Work.Connectors Will Be Properly Fastened1983-07-19019 July 1983 Updated LER 83-017/03L-1:on 830326-28 & 0402,listed Control Rods Had No Indications for Identified Positions.Caused by Loose Prototypic Inlet Piping Connectors Due to Undervessel Work.Connectors Will Be Properly Fastened 05000324/LER-1982-131, Supplemental LER 82-131/03L-1:on 821206,one-half Automatic Reactor Scram Signal Received Due to Instrument Downscale Signal from Main Steam Line Radiation Monitor D, 2-D12-RM-K603D.Caused by Disconnection of Instrument Cable1983-03-11011 March 1983 Supplemental LER 82-131/03L-1:on 821206,one-half Automatic Reactor Scram Signal Received Due to Instrument Downscale Signal from Main Steam Line Radiation Monitor D, 2-D12-RM-K603D.Caused by Disconnection of Instrument Cable 05000324/LER-1981-090, Updated LER 81-090/03L-3:on 810817 & 23,suppression Chamber Water Level Indicator 2-CAC-LI-2601-3 Indicated Lower Level & on 810820,indicated Higher Level than Other Indicator.Caused by Changes in Trickle Flow to Wet Ref Leg1983-01-28028 January 1983 Updated LER 81-090/03L-3:on 810817 & 23,suppression Chamber Water Level Indicator 2-CAC-LI-2601-3 Indicated Lower Level & on 810820,indicated Higher Level than Other Indicator.Caused by Changes in Trickle Flow to Wet Ref Leg 05000325/LER-1982-127, Updated LER 82-127/01T-1:on 821103,quick Start Testing of Diesel Generators 2,3 & 4 Not Performed for 12 H Period Per Tech Spec.Caused by Failure to Enter Requirement Into Daily Surveillance Rept on 821102.Testing Performed1982-12-23023 December 1982 Updated LER 82-127/01T-1:on 821103,quick Start Testing of Diesel Generators 2,3 & 4 Not Performed for 12 H Period Per Tech Spec.Caused by Failure to Enter Requirement Into Daily Surveillance Rept on 821102.Testing Performed 05000325/LER-1982-135, Supplemental LER 82-135/03L-1:on 821019,1.5-inch Discrepancy Noted Between Narrow & Wide Range Instruments.Caused by Inoperable RTGB Level Instruments.Plant Mod Package Developed to Increase Accuracy1982-12-23023 December 1982 Supplemental LER 82-135/03L-1:on 821019,1.5-inch Discrepancy Noted Between Narrow & Wide Range Instruments.Caused by Inoperable RTGB Level Instruments.Plant Mod Package Developed to Increase Accuracy 05000325/LER-1982-024, Supplemental LER 82-024/03L-2:on 820214,during Periodic Test,Discovered That Open Position Indication for Drywell to Suppression Vacuum Breaker X18H Could Not Be Achieved.Caused by Failure of Vacuum Breaker to Fully Stroke Open1982-10-13013 October 1982 Supplemental LER 82-024/03L-2:on 820214,during Periodic Test,Discovered That Open Position Indication for Drywell to Suppression Vacuum Breaker X18H Could Not Be Achieved.Caused by Failure of Vacuum Breaker to Fully Stroke Open ML20054L9761982-06-29029 June 1982 LER82-054/03L-0:on 820607,reactor Core Isolation Cooling Sys Turbine Automatically Started on Reactor Low Level,But Tripped Due to Closure of Control Valve 1-E51-V9.Caused by Lack of Turbine Speed Demand Signal Due to Governor Failure 05000325/LER-1982-0531982-06-29029 June 1982 LER 82-053/03L-0:on 820604,during startup,09 Position Found Superimposed on 00 RTGB Position Indication for Fully Inserted Control Rod 10-07.Caused by Defective Rod Position Reed Switch.Investigation Scheduled for 1982 Outage 05000325/LER-1981-092, Updated LER 81-092/01T-2:on 811226,action Statement 3.3.2b Not Entered When B21-LT-N017D-1 Instrument Failed Upscale. Caused by Failure of Operations Personnel to Recognize & Perform Required Action1982-06-21021 June 1982 Updated LER 81-092/01T-2:on 811226,action Statement 3.3.2b Not Entered When B21-LT-N017D-1 Instrument Failed Upscale. Caused by Failure of Operations Personnel to Recognize & Perform Required Action 05000325/LER-1981-093, Updated LER 81-093/01T-2:on 811226,reactor Protection Sys Vessel Low Level Trip instrument,1-B21-LT-NO17D-1,was Indicating Upscale.Caused by Personnel Failure to Recognize & Perform Tech Specs.Personnel Counseled1982-06-18018 June 1982 Updated LER 81-093/01T-2:on 811226,reactor Protection Sys Vessel Low Level Trip instrument,1-B21-LT-NO17D-1,was Indicating Upscale.Caused by Personnel Failure to Recognize & Perform Tech Specs.Personnel Counseled 05000325/LER-1982-038, Updated LER 82-038/03L-1:on 820419.Reactor Scrammed When Electrical Bus 1A-1 Dc de-energized.Caused by Operator Error in Opening 125-volt Dc Battery Charger Output Breaker for Battery 1A-1.Breaker Closed & Power Restored to Bus1982-06-0404 June 1982 Updated LER 82-038/03L-1:on 820419.Reactor Scrammed When Electrical Bus 1A-1 Dc de-energized.Caused by Operator Error in Opening 125-volt Dc Battery Charger Output Breaker for Battery 1A-1.Breaker Closed & Power Restored to Bus ML20062G3081978-12-21021 December 1978 /03L-0 on 781122:HPCI & RCIC Component Tests Were Overlooked Because Rescheduling Technique Provided No Clear Indication of Test Due Dates.Responsible Technician Reinstructed & Admin Operating Instruction AOI-5 Rev ML20064H8961978-12-19019 December 1978 /03L-0 on 781120:Senior Control Operator Did Not Have Completed Hatch Leak Rate Test Before Beginning Reactor Startup Due to Misunderstanding.Test completed.GP-1 Revised to Require Leak Test Verification by Control Operators ML20064H6181978-12-14014 December 1978 /03L-0 on 781114:torus Level of the HPCI Turbine Control Sys Was Slightly Above the Allowed 27 Inches.Proper Torus Level Restored to Normal.Torus Level Indicator Will Be More Clearly Marked ML20064H5971978-12-14014 December 1978 /03L-0 on 781114:Fire Hoses of Radwaste Bldg 3 Elevation Fire Stations Were Found Missing Due to Use by Personnel for Routine Radwaste Washdown.New Firehoses Installed & Mod Re Alternate Water Supply Is in Progress ML20064H5891978-12-14014 December 1978 /03L-0 on 781114:during Periodic Test 9.3.a the HPCI Egr Actuator Failed to Oper Properly Due to Water in Hydraulic Fluid Corroding Egr Actuator.Steam Leaking Past Seat of Valve HPCI E41-F001 Allowed Water Into Fluid ML20062F6781978-12-13013 December 1978 /03L-0 on 781112:reactor Steam Dome High Pressure Switch B32-PS-N018B Did Not Reset & Would Not Allow RHR Valve E11-F008 to Open for Shutdown Cooling at Reactor Pressure of 102psig.Caused by Sticking micro-switch ML20062F6681978-12-13013 December 1978 /03L-0 on 781117:while Reactor Was in Hot Shutdown Torus Level Increased .2 Above Tech Specs.Caused by Demineralized make-up Water Leakage Through Valves from RHR Keep-fill System Causing Torus Level to Rise ML20064G9301978-12-11011 December 1978 /03L-0 on 781109:Reactor Vessel Chemistry Exceeded Tech Spec Limits for Conductivity & Concentration Due to Presence of Organic Compounds in Condensate Sys.Organic Filtration & High Concentration of Ion Resin Cleanup Begun ML20062E4381978-11-30030 November 1978 /03L-0 on 781101:rod Block Monitor(Rbm) Channel a Was Found Out of Calibr During Testing Due to Setpoint Drift.Calibr Frequency Will Be Increased from Once to Twice Per Year ML20064E8001978-11-15015 November 1978 /03L-0 on 781017:reactor Bldg Radiat Exhaust Monitor D12-RM-N010B Failed Safe Causing Reactor Bldg Vent to Isolate,Due to Defective Transistor 2N1711 on 24V Pwr Supply ML20064E4581978-11-14014 November 1978 /01T-0 on 781101:util Was Informed by NRR of Nonconformance w/10CFR50 Append a Gen Design Criteria 54 & 56.Two Reactor bldg-to-torus Vacuum Breaker Lines Have Never Had Design Review by Nrc.Tech Spec Change Effective 781108 ML20064E3371978-11-0909 November 1978 /03L-0 on 781014:RCIC Turbine Was Tripped on Manual Overspeed for Training Purposes & Turbine control- Stop Valve E51-V8 Would Not Reset.Caused by Improperly Worn Adjusted Reset Lever ML20064E2921978-11-0909 November 1978 /03L-0 on 781011:torus Level Dropped Below Tech Spec Minimum While Water from Torus Was Being Pumped,Via Rgr to Radwaste in Efforts to Reduce Torus Water Level. Caused by Operator Being Distracted ML20064E3541978-11-0707 November 1978 /03L-0 on 781006:condensate Storage Tank Level Switch E41-LS-N003 Found Out of Calibration During Periodic Condensate Storage Tank Low Level Channel.Caused by Instru Drift ML20064E3491978-11-0606 November 1978 /03L-0 on 781105:Control Oper Received Control Rod Drift Alarm for Rod 10-31.When Rod Position Display Was Selected,A False 3 Was Superimposed on Actual Rod Position Due to Aground on the Rpls Probe ML20064D8211978-11-0202 November 1978 /03L-0 on 781004:pressure Switch E11-PS-NO16B Failed During Periods Plci Pump Discharges ADS Permissive Test,Due to Corrosion Buildup on Plunger of Switch ML20064C0151978-10-10010 October 1978 /03L-0 on 780911:during Monthly 1 Diesel Generator Load Test,It Was Found That 1 Cylinder Was Not Firing,Due to Faulty Fuel Pump ML20064C0011978-10-0909 October 1978 /03L-0 on 780911:Snubber SW-142SS164 Found Inoperable During Periodic Test.Caused by Seal Degradation & Resulting Loss of Fluid ML20147C9141978-10-0404 October 1978 /03L-0 on 780904:RCIC Isolation Channel a Tripped Momentarily,Causing RCIC Sys to Be Inoper,Due to Defective RX-2 Relay ML20062A0691978-10-0303 October 1978 /03L-0 on 780904:rod Block Monitor B Inoperative Trip Came on & Stayed on for 1/4 of the Control Rod Selection Matrix.Caused by Failed Integrated Circuit in Rod Block Monitor self-test Circuitry ML20064B7231978-10-0303 October 1978 /03L-0 on 780905:during Periodic Test,Radiat Monitor D12-RM-NO10B HI-HI Trip Point Drifted to Higher than Permitted Level.Monitor Recalibrated.Drift Appears to Be Isolated Incident;No Further Action Taken 1993-09-02 Category:TEXT-SAFETY REPORT MONTHYEARML20217N3271999-10-21021 October 1999
[Table view]Part 21 Rept Re non-linear Oxygen Readings with Two (2) Model 225 CMA-X Containment Monitoring Sys at Bsep.Caused by High Gain Produced by 10K Resistor Across Second Stage Amplifier.Engineering Drawings Will Be Revised BSEP-99-0168, Monthly Operating Repts for Sept 1999 for Bsep,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Bsep,Units 1 & 2. with ML20212D0431999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Brunswick Steam Electric Plant,Units 1 & 2 ML20210P9441999-08-10010 August 1999 Safety Evaluation Accepting Licensee Assessment of Impact on Operation of Plant,Unit 1,with Crack Indications of 2.11, 6.36 & 1.74 Inches in Three Separate Jet Pump Risers ML20210P9181999-08-10010 August 1999 Safety Evaluation Authorizing Request for Reliefs CIP-01,02, 06,07,08,09,10 & 11 (with Certain Exceptions) & 12-18,for Second 10-year ISI Interval.Request CIP-04 & 05 Would Result in hardship,CIP-03 Not Required & CIP-11 Denied in Part ML20210N2341999-08-0505 August 1999 SER Accepting Response to NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issues (USI) A-46 ML20210R1191999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Bsep,Units 1 & 2 ML20210R1311999-06-30030 June 1999 Revised Monthly Operating Rept for June 1999 for Bsep,Unit 2 BSEP-99-0118, Monthly Operating Repts for June 1999 for Bsep,Units 1 & 2. with1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Bsep,Units 1 & 2. with BSEP-99-0095, Monthly Operating Repts for May 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20210M8581999-05-14014 May 1999 B214R1 RPV Hydrotest Bolted Connection Corrective Action Evaluation, Rev 0 ML20211L3711999-05-10010 May 1999 Rev 0 to ESR 98-00333, Unit 2 Invessel Feedwater Sparger Evaluation ML20206G1871999-05-0404 May 1999 Safety Evaluation Approving Third 10-year ISI Program Requests for Relief (RR) RR-08,RR-15 & RR-17 BSEP-99-0075, Monthly Operating Repts for Apr 1999 for Brunswick Steam Electric Plant,Unit 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Brunswick Steam Electric Plant,Unit 1 & 2.With ML20206N1791999-04-23023 April 1999 Rev 0 to 2B21-0554, Brunswick Unit 2,Cycle 14 Colr BSEP-99-0059, Monthly Operating Repts for Mar 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20205F9031999-03-30030 March 1999 Safety Evaluation Supporting Proposed Rev to BSEP RERP to Licenses DPR-62 & DPR-71,respectively ML20206N1831999-02-28028 February 1999 Rev 0 to Suppl Reload Licensing Rept for Bsep,Unit 2 Reload 13 Cycle 14 BSEP-99-0043, Monthly Operating Repts for Feb 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20203D7061999-02-0909 February 1999 SER Accepting Proposed Alternatives Contained in Relief Requests PRR-04,VRR-04,VRR-13,PRR-01,PRR-03,VRR-01.VRR-07, VRR-08 & VRR-09 Denied BSEP-99-0005, Monthly Operating Repts for Dec 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With BSEP-98-0231, Monthly Operating Repts for Nov 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With BSEP-98-0218, Monthly Operating Repts for Oct 1998 for Bsep,Units 1 & 2. with1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Bsep,Units 1 & 2. with BSEP-98-0210, Special Rept:On 980824,temp Element 2-CAC-TE-1258-22 Failed. Cause of Failed Temp Element Cannot Be Conclusively Determined.Temp Element Will Be Replaced & Cable Connections Repaired1998-10-30030 October 1998 Special Rept:On 980824,temp Element 2-CAC-TE-1258-22 Failed. Cause of Failed Temp Element Cannot Be Conclusively Determined.Temp Element Will Be Replaced & Cable Connections Repaired ML20154P8151998-10-16016 October 1998 SER Accepting Revised Safety Analysis of Operational Transient of 920117,for Plant,Unit 1 ML20154P8591998-10-16016 October 1998 SER Accepting Equivalent Margins Analysis for N-16A/B Instrument Nozzles for Plant,Units 1 & 2 BSEP-98-0202, Monthly Operating Repts for Sept 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20151Y6211998-09-14014 September 1998 BSEP Rept Describing Changes,Tests & Experiments, for Bsep,Units 1 & 2 ML20151Y6371998-09-14014 September 1998 Changes to QA Program, for Bsep,Units 1 & 2 BSEP-98-0185, Monthly Operating Repts for Aug 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With1998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Brunswick Steam Electric Plant,Units 1 & 2.With ML20151T5021998-08-0505 August 1998 Project Implementation Plan, Ngg Yr 2000 Readiness Program, Rev 2 BSEP-98-0164, Monthly Operating Repts for July 1998 for BSEP Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for BSEP Units 1 & 2 ML20236T1961998-07-0101 July 1998 Rev 1 to 2B21-0088, Brunswick Unit 2,Cycle 13 Colr ML20236T1921998-07-0101 July 1998 Rev 1 to 1B21-0537, Brunswick Unit 1,Cycle 12 Colr BSEP-98-0142, Monthly Operating Repts for June 1998 for BSEP Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for BSEP Units 1 & 2 ML20236T1971998-06-30030 June 1998 Rev 2 to 24A5412, Supplemental Reload Licensing Rept for Brunswick Steam Electric Plant Unit 2 Reload 12 Cycle 13 ML20249B9691998-06-11011 June 1998 Rev 1 to VC44.F02, Brunswick Steam Electric Plant,Units 1 & 2,ECCS Suction Strainers Replacement Project,Nrc Bulletin 96-003 Final Rept BSEP-98-0129, Monthly Operating Repts for May 1998 for Bsep,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Bsep,Units 1 & 2 ML20151S9041998-05-31031 May 1998 Revised Pages to Monthly Operating Rept for May 1998 for Brunswick Steam Electric Plant,Unit 1 BSEP-98-0104, Monthly Operating Repts for Apr 1998 for Brunswick Steam Electric Plant,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Brunswick Steam Electric Plant,Units 1 & 2 ML20151S8991998-04-30030 April 1998 Revised Pages to Monthly Operating Rept for Apr 1998 for Brunswick Steam Electric Plant,Unit 1 ML20247N7501998-04-30030 April 1998 Rev 0 to BSEP Unit 1,Cycle 12 Colr ML20247N7721998-04-30030 April 1998 Rev 0 to J1103244SRLR, Supplemental Reload Licensing Rept for BSEP Unit 1,Reload 11,Cycle 12 ML20217K8461998-04-24024 April 1998 Safety Evaluation Approving Proposed Use of Code Case N-535 at Brunswick Unit 1 During Second 10-yr Interval,Pursuant to 10CFR50.55a(a)(3)(i).Authorizes Use of Code Case N-535 Until Code Case Included in Future Rev of RG 1.147 ML20217K3941998-04-24024 April 1998 SER Approving Relief Request for Pump Vibration Monitoring, Brunswick Steam Electric Plant,Units 1 & 2 ML20217E6841998-04-23023 April 1998 Safety Evaluation Accepting Code Case N-547, Alternative Exam Requirements for Pressure Retaining Bolting of CRD Housings ML20217E7471998-04-21021 April 1998 Safety Evaluation Accepting Alternative to Insp of Reactor Pressure Vessel Circumferential Welds ML20217B5241998-04-20020 April 1998 SE Accepting Licensee Request for Approval to Use Alternative Exam Requirement for Brunswick,Unit 1,reactor Vessel Stud & Bushing During Second 10-yr ISI Interval Per 10CFR50.55a(a)(3)(ii) BSEP-98-0080, Monthly Operating Repts for Mar 1998 for Bsep,Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Bsep,Units 1 & 2 ML20216B1041998-03-0404 March 1998 SER Approving Alternative to Insp of Reactor Pressure Vessel Circumferential Welds for Brunswick Steam Electric Plant, Unit 1 1999-09-30 |
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