ML20040C622
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| ML20040C622 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 01/13/1982 |
| From: | Dietz C CAROLINA POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8201290092 | |
| Download: ML20040C622 (2) | |
Similar Documents at Brunswick | |
|---|---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO
MONTHYEARML20046D0641993-08-0909 August 1993
[Table view]Special Rept SR 1-93-001:on 930706,fire Protection LCOs A1-93-F0553,A1-93-F0554 & A1-93-F0555 Initiated on Fire Seals R1-2-037,R1-2-038 & R1-2-039,respectively.Caused by Discovery of Improper Sealant.Firewatches Established ML20046B5431993-07-30030 July 1993 Special Rept SR 1-93-010:on 930623,LCO A2-93-F0517 Initiated on Fire Seal DG-2-083.Caused by Welding Lead Routed Through Seal Resulting in Inoperability.Fire Sealed Restored & LCO Cancelled on 930723 ML20045G6281993-07-0808 July 1993 Special Rept:On 930525,fire Protection LCO A1-93-F0456 Initiated When Reactor Bldg Zone 4 Fire Detection Sys Discovered Inoperable.Hourly Fire Watch Established & Compensatory Measures Remain in Effect ML20045F2471993-06-30030 June 1993 Suppl Special Rept 1-93-004,summarizing Results of Investigation & Providing Updated Status W/Regard to Repair of Deluge Valve 20 Due to Failure of Latch Arm Gasket. Temporary Repair Package Issued ML20045B9571993-06-15015 June 1993 Suppl Special Rept 1-93-004 Re 930212 Failure of Latch Arm Gasket on Deluge Valve 20,resulting in Leak in Valve Pit.Due to Repeated Failures of Replacement Gaskets,Valve Will Not Be Repaired & Operable by 930415,as Stated in 930329 Ltr ML19346B5661993-06-10010 June 1993 Special Rept SR 1-93-008:on 930504,LCO A1-93-F0430 Initiated Due to Fire Seal R1-2-081 Being Inoperable Due to Damaged Boot Seal.Applicable Fire Detectors Verified Operable & Hourly Fire Watch Established ML20044C1081993-03-11011 March 1993 Special Rept SR 2-93-0002:on 930209,reactor Bldg Fire Door 206 Declared Inoperable to Allow Equipment Cables & Lighting to Be Run Through Door.Compensatory Measures Remained in Effect Until Door Restored on 930223 ML20028H7211991-01-24024 January 1991 Special Rept 2-SR-91-001 on 910106,monitor High Range Pump Would Not Initiate & Stabilize Flow.Monitor Declared Inoperable & Alternate Sampling Initiated.Job Order Issued on 910108 to Troubleshoot to Locate Failed Components ML20012D5731990-03-19019 March 1990 Special Rept 2-SR-90-002:on 900214,fire Barrier Limiting Condition for Operation (LCO) Initiated for Fire Door 206 to Permit Mac Test Equipment Cords to Be Run Into Area, Exceeding Lco.Functional Status Restored on 900308 ML20012D5681990-03-19019 March 1990 Special Rept 2-SR-90-001:on 900210,limiting Condition for Operation Exceeded When Fire Door 206,located at Penetration Seal R2-2-070,opened to Permit Running Electrical Cords. Fire Watches in Effect Until Door Restored on 900308 ML20005H2491990-01-12012 January 1990 Special Rept 1-SR-89-004:on 891130,limiting Condition for Operation Established for Sprinkler Sys of North & South RHR & HPCI Room.Caused by Need to Resolve Engineering Design Concerns.Resolution Determined ML20005G1461990-01-0404 January 1990 Special Rept 1-SR-90-001:on 900103,technician Opened Cabinet Door to 4,160 Volt Contactor Cabinet for motor-driven Fire Pump,Resulting in Operating Fire Pump Trip.Technician Immediately Closed Cabinet Door.Power Supplies Reenergized ML20005D9541989-12-14014 December 1989 Special Rept 2-SR-89-006:on 891114,reactor Bldg Fire Detection Sys Zone 14 Instrumentation Declared Inoperable Due to Erroneous Fire Alarms.Tech Spec 6.9.2 14-day Time Frame Exceeded.Repairs Expected to Be Completed by 900330 ML19351A5841989-12-12012 December 1989 Special Rept 1-SR-89-003:on 891115,7-day Time Frame of Limiting Condition for Operation for Designated Fire Barrier Exceeded.Door Repaired & Returned to Svc ML19332E6031989-12-0101 December 1989 Special Rept 2-SR-89-005:on 891106 & 08,specified 7-day Time Frame for Fire Barrier Limiting Condition for Operation Exceeded for Fire Doors 112 & 004,respectively.Caused by Doors Not Being Repaired in Required Time ML19324B4211989-10-25025 October 1989 Followup Ro:On 890422,limiting Condition for Operation Initiated Re Two Inoperable Fire Barrier Seals in Common Augmented Offgas Bldg.Caused by Corrosion in Base Metal Hatch.Replacement Parts Obtained to re-establish Operation ML19325C4681989-10-0303 October 1989 Special Rept 2-SR-89-004:on 890922,7-day Time Frame for Limiting Condition of Operation Exceeded.Fire Watches Will Be Maintained Until Door Returned to Svc & Limiting Condition for Operation Canceled ML20023B5141983-04-28028 April 1983 Ro:On 830325,fire Barrier Limiting Condition for Operation Generated to Permit Accessing Fire Door in Augmented Offgas Bldg.Caused by Temporary Routing of Flush Lines for Plant Mod.Mod Work Completed on 830411 ML20023B5801983-04-26026 April 1983 Ro:Review of Fire Protection Sys Documentation Revealed 17 Sys Limiting Conditions for Operation Exceeding Respective Time Frames Not Reported to Nrc.Plant Operations Instructions Revised & Special Training Provided ML20028G6401983-02-10010 February 1983 RO 2-83-16:on 830209,emergency Bus E-2 de-energized to Allow Maint on 4,160-volt Switchgear,Thereby Removing One of Two Power Supplies to Motor Driven Fire Pump.Pump Redundant Battery Source Had Less than Required Voltage ML20027E6581982-11-0404 November 1982 RO 1-82-127:on 821103,required Diesel Generator Quick Starts for Diesel Generators 2,3 & 4 Not Performed within 12-h Requirement.Caused by Personnel Error.Investigation in Progress.Quick Starts Immediately Performed ML20027D2741982-10-22022 October 1982 RO 1-82-112:on 821021,continuous Fire Watch Not Maintained as Required by Tech Spec 3.7.7.2.Caused by Misunderstanding on Part of Fire Watch.Fire Watch Established Until Sys Restored to Svc.Event Remains Under Investigation ML20041A5311982-02-0505 February 1982 Ro:On 820205,chlorine Isolation Sys Would Not Isolate Control Bldg Emergency Ventilation Sys W/Control Switch in on Position.Switch Placed in Preferred Position & Tagged, Pending Review of Sys Logic ML20040E5881982-01-25025 January 1982 RO 1-82-03:on 820118,reactor Recirculation Pump Tripped During Testing of Associated Logic Circuits.Pump Restarted Using Incorrect Procedure.Procedures Will Be Revised to Reflect STS ML20040E6721982-01-25025 January 1982 Ro:During Reactor Startup,Automatic Start & Injection of 1A & 1B Core Spray Sys Occurred While Performing Ground Hunting on Dc Electrical Sys.Caused by Loss of Div 2 ECCS Analog Instrumentation Power Supply.Procedure Being Revised ML20040C6981982-01-18018 January 1982 RO 2-82-05:on 820116,while Trying to Start Suppression Pool Cooling,Both Loops of RHR Svc Water Found Inoperable.Caused by Instrument Line Plugging on Suction Pressure Switch in One Loop & Open Circuit Breaker in Other ML20040B4171982-01-14014 January 1982 RO 2-82-9:on 820111,sys in Addition to Those Indicated on Site Drawings Found to Have Been Isolated When Portions of Fire Support Sys Were Isolated to Repair Frozen Pipe Rupture.Wrong Plant Drawings Used to Set Up Fire Watch ML20040C6221982-01-13013 January 1982 Ro:On 811217,gamma Analysis of Nov 1981 Milk Samples Revealed Cs-137 Activity at Reportable Level.Elevation in Activity Due to Mineral Recycling Phenomena Indigenous to Area Observed Since 1972 ML20039F6361981-12-31031 December 1981 RO 1-81-93:on 811231,discovered Required Action Per Tech Spec 3.3.1a Not Taken on 811228 When Reactor Water Level Instrument B21-LT-N017D-1 Found Inoperable.Required Action Taken & Investigation Begun.Instrument Being Repaired ML20010F0461981-08-28028 August 1981 RO 2-81-65:on 810827,2-hr Time Requirement for Repairing Failed HPCI Temp Switch Violated.Caused by Personnel Delay in Issuing Work Order to Repair Instrument.Repairs Made. Investigation Underway ML20010C6971981-08-11011 August 1981 Ro:On 810717,while Performing Maint on Reactor Water Cleanup Sys,Individual Received Excessive Radiation Exposure.Caused by Personnel Error.Personnel Counseled & Disciplinary Action Taken ML20010A2191981-08-0505 August 1981 Ro:On 810804,following Reactor Scram,Safety Relief Valve F013B Was Opened to Relieve Reactor Pressure.Valve Failed to Close Until Pressure Reached,Approx 325 Lb.Investigation Underway ML20009G1081981-07-29029 July 1981 RO 2-84-55:anchor Bolt Testing Required by IE Bulletin 79-02 Not Performed on Control Rod Drive Piping.Caused by Unusual Arrangements for Installation of Piping.Anchor Bolt Repairs & as-built Verifications Table Done ML20009F4921981-07-20020 July 1981 RO 1-81-57:on 810717,during Review of Wiring Diagram for Reactor Core Isolation Cooling,Two non-electronic Switching Sys Div 2 Cables Found Intermixed W/One Switching Sys Cable in Controlled Logic Panel in Control Room.Review Underway ML20009F9201981-06-29029 June 1981 Ro:On 810627,during Normal Reactor startup,A-loop RHR in LPCI Mode Valve Lineup Determined Incorrect.Caused by Possible Personnel Error.Investigation Ongoing to Ascertain Exact Cause Which Will Be Reported in 14-day Followup ML20009G0621981-06-25025 June 1981 Confirms 810625 Conversation Between CS Bohanan & R Butcher Re United Engineers & Constructors,Inc Notification That 38 Control Rod Driveline Gang Pipe Supports Would Fail in as-built Condition During Design Seismic Event ML19350F1571981-06-19019 June 1981 Ro:On 810617,one Set of Lines Found Not Meeting Criteria of IEEE Std 279-1971,Paragraph 4.7.3 for Random Failures.Cause Not Stated.Procedures Will Be Written.Training Will Be Provided to All Operators for Closure of Any Valves ML19347F7901981-05-18018 May 1981 Thirty-day Nonroutine Radiological Environ Event Rept Re Cs-137 Activity at Milk Sampling Stations.Source of Activity Under Evaluation.Followup Rept Expected Soon ML20009G0631981-05-0606 May 1981 Ro:On 810506,investigation on RHR Heat Exchangers Determined That B Heat Exchanger Baffle Was Deformed at Bottom Allowing Bypass Flow.Cause Being Evaluated.Repairs on 2B RHR Heat Exchanger in Progress ML20003H5311981-04-30030 April 1981 Ro:On 810425,during Repair of RHR Heat Exchanger 1B,loss of Shutdown Cooling Was Experienced After Starting of Second RHR Svc Water Pump on RHR Heat Exchanger 1A.Caused by Loadings in Excess of Design Capability ML20003H3591981-04-23023 April 1981 Ro:On 810406 & 13,gamma Analyses of Weekly Milk Samples in Environ Radiological Monitoring Program Detected Excessive Cs-137 Activity.Cause Unknown.Extra Samples Being Taken. Summary of Releases,Environ Samples & Dose Projections Encl ML20003F6761981-04-15015 April 1981 RO 1-80-46:on 810314,snubber on Steam Condensing Line to Loop a RHR Heat Exchanger Was Discovered Broken.Caused by Water Hammer Causing Pipe Motion & Snubber Failure.Broken Snubber Replaced & Addl Snubbers Are Being Checked ML19350C6711981-03-30030 March 1981 RO 1-81-34:on 810328,two Snubbers & Two Pipe Guides Found Damaged on HPCI Injection Line.Damaged Snubbers & Pipe Guides Being Repaired & Other Supports Examined.Support Repair Completion Expected by 810331 ML19350C7461981-03-27027 March 1981 RO 1-81-42:on 810327,TIP Ball Isolation Valve Determined to Be Inoperable When TIP Machine de-energized.TIP Machine Returned to Normal Svc.Problem Corrected ML20008F4341981-03-0606 March 1981 RO 2-81-41:on 810306,while Performing Function Test of Accessible Snubbers,Failure Rate of Approx 20% Identified. Cause Not Stated.Investigation Continues ML19341C6571981-02-24024 February 1981 Ro:On 810223,analysis Indicated That Ten Supports on Control Rod Driveline Vent Line Would Fail in as-built Condition During Designed Seismic Event.On 810220 RCIC Tripped W/O Receiving Permission ML20003B6801981-02-19019 February 1981 Special Rept for ETS 5.4.26:on 801222,stack Sample Pump Found Not Running During Routine Filter Change.Caused by Blown Main Power Fuse.Fuse Replaced & Sys Returned to Svc. Pump Low Flow Alarm Switches Adjusted & Tested ML19341A9711981-01-15015 January 1981 Special Rept:While Performing Periodic Test of Fire Barrier Penetration seals,300 Seals Were Found in Nonfunctional Condition.Caused by Inadequate Sealing During Installation. Seals Identified & Mapped for Repairs ML20002C1701981-01-0505 January 1981 Ro:On 810103 During Normal Reactor Startup & Heatup W/ Reactor Pressure at 717 Psig,Safety Relief Valve B21-F013G Lifted,Causing Feed Pump to Trip.Low Level Reactor Scram Resulted.Pilot to F013G Replaced ML19340D6701980-12-29029 December 1980 Fourteen-day Rept:On 801215,failure to Install Particulate Filter Holder Rendered Reactor Bldg Exhaust Monitor Inoperable.Caused by Personnel Error.Holder Replaced & Operating Procedures Revised to Ensure Monitor Checks 1993-08-09 Category:LER) MONTHYEARML20046D0641993-08-0909 August 1993
[Table view]Special Rept SR 1-93-001:on 930706,fire Protection LCOs A1-93-F0553,A1-93-F0554 & A1-93-F0555 Initiated on Fire Seals R1-2-037,R1-2-038 & R1-2-039,respectively.Caused by Discovery of Improper Sealant.Firewatches Established ML20046B5431993-07-30030 July 1993 Special Rept SR 1-93-010:on 930623,LCO A2-93-F0517 Initiated on Fire Seal DG-2-083.Caused by Welding Lead Routed Through Seal Resulting in Inoperability.Fire Sealed Restored & LCO Cancelled on 930723 ML20045G6281993-07-0808 July 1993 Special Rept:On 930525,fire Protection LCO A1-93-F0456 Initiated When Reactor Bldg Zone 4 Fire Detection Sys Discovered Inoperable.Hourly Fire Watch Established & Compensatory Measures Remain in Effect ML20045F2471993-06-30030 June 1993 Suppl Special Rept 1-93-004,summarizing Results of Investigation & Providing Updated Status W/Regard to Repair of Deluge Valve 20 Due to Failure of Latch Arm Gasket. Temporary Repair Package Issued ML20045B9571993-06-15015 June 1993 Suppl Special Rept 1-93-004 Re 930212 Failure of Latch Arm Gasket on Deluge Valve 20,resulting in Leak in Valve Pit.Due to Repeated Failures of Replacement Gaskets,Valve Will Not Be Repaired & Operable by 930415,as Stated in 930329 Ltr ML19346B5661993-06-10010 June 1993 Special Rept SR 1-93-008:on 930504,LCO A1-93-F0430 Initiated Due to Fire Seal R1-2-081 Being Inoperable Due to Damaged Boot Seal.Applicable Fire Detectors Verified Operable & Hourly Fire Watch Established ML20044C1081993-03-11011 March 1993 Special Rept SR 2-93-0002:on 930209,reactor Bldg Fire Door 206 Declared Inoperable to Allow Equipment Cables & Lighting to Be Run Through Door.Compensatory Measures Remained in Effect Until Door Restored on 930223 ML20028H7211991-01-24024 January 1991 Special Rept 2-SR-91-001 on 910106,monitor High Range Pump Would Not Initiate & Stabilize Flow.Monitor Declared Inoperable & Alternate Sampling Initiated.Job Order Issued on 910108 to Troubleshoot to Locate Failed Components ML20012D5731990-03-19019 March 1990 Special Rept 2-SR-90-002:on 900214,fire Barrier Limiting Condition for Operation (LCO) Initiated for Fire Door 206 to Permit Mac Test Equipment Cords to Be Run Into Area, Exceeding Lco.Functional Status Restored on 900308 ML20012D5681990-03-19019 March 1990 Special Rept 2-SR-90-001:on 900210,limiting Condition for Operation Exceeded When Fire Door 206,located at Penetration Seal R2-2-070,opened to Permit Running Electrical Cords. Fire Watches in Effect Until Door Restored on 900308 ML20005H2491990-01-12012 January 1990 Special Rept 1-SR-89-004:on 891130,limiting Condition for Operation Established for Sprinkler Sys of North & South RHR & HPCI Room.Caused by Need to Resolve Engineering Design Concerns.Resolution Determined ML20005G1461990-01-0404 January 1990 Special Rept 1-SR-90-001:on 900103,technician Opened Cabinet Door to 4,160 Volt Contactor Cabinet for motor-driven Fire Pump,Resulting in Operating Fire Pump Trip.Technician Immediately Closed Cabinet Door.Power Supplies Reenergized ML20005D9541989-12-14014 December 1989 Special Rept 2-SR-89-006:on 891114,reactor Bldg Fire Detection Sys Zone 14 Instrumentation Declared Inoperable Due to Erroneous Fire Alarms.Tech Spec 6.9.2 14-day Time Frame Exceeded.Repairs Expected to Be Completed by 900330 ML19351A5841989-12-12012 December 1989 Special Rept 1-SR-89-003:on 891115,7-day Time Frame of Limiting Condition for Operation for Designated Fire Barrier Exceeded.Door Repaired & Returned to Svc ML19332E6031989-12-0101 December 1989 Special Rept 2-SR-89-005:on 891106 & 08,specified 7-day Time Frame for Fire Barrier Limiting Condition for Operation Exceeded for Fire Doors 112 & 004,respectively.Caused by Doors Not Being Repaired in Required Time ML19324B4211989-10-25025 October 1989 Followup Ro:On 890422,limiting Condition for Operation Initiated Re Two Inoperable Fire Barrier Seals in Common Augmented Offgas Bldg.Caused by Corrosion in Base Metal Hatch.Replacement Parts Obtained to re-establish Operation ML19325C4681989-10-0303 October 1989 Special Rept 2-SR-89-004:on 890922,7-day Time Frame for Limiting Condition of Operation Exceeded.Fire Watches Will Be Maintained Until Door Returned to Svc & Limiting Condition for Operation Canceled ML20023B5141983-04-28028 April 1983 Ro:On 830325,fire Barrier Limiting Condition for Operation Generated to Permit Accessing Fire Door in Augmented Offgas Bldg.Caused by Temporary Routing of Flush Lines for Plant Mod.Mod Work Completed on 830411 ML20023B5801983-04-26026 April 1983 Ro:Review of Fire Protection Sys Documentation Revealed 17 Sys Limiting Conditions for Operation Exceeding Respective Time Frames Not Reported to Nrc.Plant Operations Instructions Revised & Special Training Provided ML20028G6401983-02-10010 February 1983 RO 2-83-16:on 830209,emergency Bus E-2 de-energized to Allow Maint on 4,160-volt Switchgear,Thereby Removing One of Two Power Supplies to Motor Driven Fire Pump.Pump Redundant Battery Source Had Less than Required Voltage ML20027E6581982-11-0404 November 1982 RO 1-82-127:on 821103,required Diesel Generator Quick Starts for Diesel Generators 2,3 & 4 Not Performed within 12-h Requirement.Caused by Personnel Error.Investigation in Progress.Quick Starts Immediately Performed ML20027D2741982-10-22022 October 1982 RO 1-82-112:on 821021,continuous Fire Watch Not Maintained as Required by Tech Spec 3.7.7.2.Caused by Misunderstanding on Part of Fire Watch.Fire Watch Established Until Sys Restored to Svc.Event Remains Under Investigation ML20041A5311982-02-0505 February 1982 Ro:On 820205,chlorine Isolation Sys Would Not Isolate Control Bldg Emergency Ventilation Sys W/Control Switch in on Position.Switch Placed in Preferred Position & Tagged, Pending Review of Sys Logic ML20040E5881982-01-25025 January 1982 RO 1-82-03:on 820118,reactor Recirculation Pump Tripped During Testing of Associated Logic Circuits.Pump Restarted Using Incorrect Procedure.Procedures Will Be Revised to Reflect STS ML20040E6721982-01-25025 January 1982 Ro:During Reactor Startup,Automatic Start & Injection of 1A & 1B Core Spray Sys Occurred While Performing Ground Hunting on Dc Electrical Sys.Caused by Loss of Div 2 ECCS Analog Instrumentation Power Supply.Procedure Being Revised ML20040C6981982-01-18018 January 1982 RO 2-82-05:on 820116,while Trying to Start Suppression Pool Cooling,Both Loops of RHR Svc Water Found Inoperable.Caused by Instrument Line Plugging on Suction Pressure Switch in One Loop & Open Circuit Breaker in Other ML20040B4171982-01-14014 January 1982 RO 2-82-9:on 820111,sys in Addition to Those Indicated on Site Drawings Found to Have Been Isolated When Portions of Fire Support Sys Were Isolated to Repair Frozen Pipe Rupture.Wrong Plant Drawings Used to Set Up Fire Watch ML20040C6221982-01-13013 January 1982 Ro:On 811217,gamma Analysis of Nov 1981 Milk Samples Revealed Cs-137 Activity at Reportable Level.Elevation in Activity Due to Mineral Recycling Phenomena Indigenous to Area Observed Since 1972 ML20039F6361981-12-31031 December 1981 RO 1-81-93:on 811231,discovered Required Action Per Tech Spec 3.3.1a Not Taken on 811228 When Reactor Water Level Instrument B21-LT-N017D-1 Found Inoperable.Required Action Taken & Investigation Begun.Instrument Being Repaired ML20010F0461981-08-28028 August 1981 RO 2-81-65:on 810827,2-hr Time Requirement for Repairing Failed HPCI Temp Switch Violated.Caused by Personnel Delay in Issuing Work Order to Repair Instrument.Repairs Made. Investigation Underway ML20010C6971981-08-11011 August 1981 Ro:On 810717,while Performing Maint on Reactor Water Cleanup Sys,Individual Received Excessive Radiation Exposure.Caused by Personnel Error.Personnel Counseled & Disciplinary Action Taken ML20010A2191981-08-0505 August 1981 Ro:On 810804,following Reactor Scram,Safety Relief Valve F013B Was Opened to Relieve Reactor Pressure.Valve Failed to Close Until Pressure Reached,Approx 325 Lb.Investigation Underway ML20009G1081981-07-29029 July 1981 RO 2-84-55:anchor Bolt Testing Required by IE Bulletin 79-02 Not Performed on Control Rod Drive Piping.Caused by Unusual Arrangements for Installation of Piping.Anchor Bolt Repairs & as-built Verifications Table Done ML20009F4921981-07-20020 July 1981 RO 1-81-57:on 810717,during Review of Wiring Diagram for Reactor Core Isolation Cooling,Two non-electronic Switching Sys Div 2 Cables Found Intermixed W/One Switching Sys Cable in Controlled Logic Panel in Control Room.Review Underway ML20009F9201981-06-29029 June 1981 Ro:On 810627,during Normal Reactor startup,A-loop RHR in LPCI Mode Valve Lineup Determined Incorrect.Caused by Possible Personnel Error.Investigation Ongoing to Ascertain Exact Cause Which Will Be Reported in 14-day Followup ML20009G0621981-06-25025 June 1981 Confirms 810625 Conversation Between CS Bohanan & R Butcher Re United Engineers & Constructors,Inc Notification That 38 Control Rod Driveline Gang Pipe Supports Would Fail in as-built Condition During Design Seismic Event ML19350F1571981-06-19019 June 1981 Ro:On 810617,one Set of Lines Found Not Meeting Criteria of IEEE Std 279-1971,Paragraph 4.7.3 for Random Failures.Cause Not Stated.Procedures Will Be Written.Training Will Be Provided to All Operators for Closure of Any Valves ML19347F7901981-05-18018 May 1981 Thirty-day Nonroutine Radiological Environ Event Rept Re Cs-137 Activity at Milk Sampling Stations.Source of Activity Under Evaluation.Followup Rept Expected Soon ML20009G0631981-05-0606 May 1981 Ro:On 810506,investigation on RHR Heat Exchangers Determined That B Heat Exchanger Baffle Was Deformed at Bottom Allowing Bypass Flow.Cause Being Evaluated.Repairs on 2B RHR Heat Exchanger in Progress ML20003H5311981-04-30030 April 1981 Ro:On 810425,during Repair of RHR Heat Exchanger 1B,loss of Shutdown Cooling Was Experienced After Starting of Second RHR Svc Water Pump on RHR Heat Exchanger 1A.Caused by Loadings in Excess of Design Capability ML20003H3591981-04-23023 April 1981 Ro:On 810406 & 13,gamma Analyses of Weekly Milk Samples in Environ Radiological Monitoring Program Detected Excessive Cs-137 Activity.Cause Unknown.Extra Samples Being Taken. Summary of Releases,Environ Samples & Dose Projections Encl ML20003F6761981-04-15015 April 1981 RO 1-80-46:on 810314,snubber on Steam Condensing Line to Loop a RHR Heat Exchanger Was Discovered Broken.Caused by Water Hammer Causing Pipe Motion & Snubber Failure.Broken Snubber Replaced & Addl Snubbers Are Being Checked ML19350C6711981-03-30030 March 1981 RO 1-81-34:on 810328,two Snubbers & Two Pipe Guides Found Damaged on HPCI Injection Line.Damaged Snubbers & Pipe Guides Being Repaired & Other Supports Examined.Support Repair Completion Expected by 810331 ML19350C7461981-03-27027 March 1981 RO 1-81-42:on 810327,TIP Ball Isolation Valve Determined to Be Inoperable When TIP Machine de-energized.TIP Machine Returned to Normal Svc.Problem Corrected ML20008F4341981-03-0606 March 1981 RO 2-81-41:on 810306,while Performing Function Test of Accessible Snubbers,Failure Rate of Approx 20% Identified. Cause Not Stated.Investigation Continues ML19341C6571981-02-24024 February 1981 Ro:On 810223,analysis Indicated That Ten Supports on Control Rod Driveline Vent Line Would Fail in as-built Condition During Designed Seismic Event.On 810220 RCIC Tripped W/O Receiving Permission ML20003B6801981-02-19019 February 1981 Special Rept for ETS 5.4.26:on 801222,stack Sample Pump Found Not Running During Routine Filter Change.Caused by Blown Main Power Fuse.Fuse Replaced & Sys Returned to Svc. Pump Low Flow Alarm Switches Adjusted & Tested ML19341A9711981-01-15015 January 1981 Special Rept:While Performing Periodic Test of Fire Barrier Penetration seals,300 Seals Were Found in Nonfunctional Condition.Caused by Inadequate Sealing During Installation. Seals Identified & Mapped for Repairs ML20002C1701981-01-0505 January 1981 Ro:On 810103 During Normal Reactor Startup & Heatup W/ Reactor Pressure at 717 Psig,Safety Relief Valve B21-F013G Lifted,Causing Feed Pump to Trip.Low Level Reactor Scram Resulted.Pilot to F013G Replaced ML19340D6701980-12-29029 December 1980 Fourteen-day Rept:On 801215,failure to Install Particulate Filter Holder Rendered Reactor Bldg Exhaust Monitor Inoperable.Caused by Personnel Error.Holder Replaced & Operating Procedures Revised to Ensure Monitor Checks 1993-08-09 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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-Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461-0429 January 13, 1982 e x
FILE: B09-13516.2 #
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SERIAL: BSEP/82 _ IVED 9- -
Mr. James P. O'Reilly, Director ; # d/lfig 798gg [
U. S. Nuclear Regulatory Commission Region II, Suite 3100- 9 7 101 Marietta St.reet, N.W.
Atlanta, GA 30303 4 to BRUNSWICK STEAM ELECTRIC PLANT, UNIT NOS. 1 AND 2 LICENSE NOS. DPR-71 AND DPR-62 DOCKET NOS. 50-325 AND 50-324 30-DAY NONROUTINE RADIOLOGICAL ENVIRONMENTAL EVENT REPORT 7
Dear Mr. O'Reilly:
Results of gamma an'alysis of monthly composited milk samples, collected during November 1981, as part of Brunswick Steam Electric Plant's Environmental Radiological Monitoring Program, detected Cs-137 at a concentration of 142 5' pC1/1 at milk sampic station No. 35. The analysis was completed on December 17, 1981. Station No. 37 (control station) revealed Cs-137. activity at a concen '
tration of 7.19 i 3.16 pCi/1. The Cs-137 activity found in this sample consti-tutes a 30-day reportable event in accordance with Brunswick Technical Specifi-cations, Appendix B, Section 5.4.2b, pertinent to environmental sampling.
An evaluation of the Brunswick plant release data has indicated that the observed . elevation of Cs-137 activity in the milk is not attributable to Brunswick plant' operations.
The elevated levels of Cs-137 in the milk of this cow have been observed since the pre-operational Radiological Surveillance Program began in 1972. It is believed that these levels of Cs-137 are due to a unique mineral. recycling phenomena that is indigenous to this area. This was reported to the U.S.
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James P. O'Reilly 2 January 13, 1982 l
l Nuclear Regulatory Commission in Followup Report on Nonroutine Environmental Radiological Event, dated July 24, 1981 (Serial BSEP/81-1400), pertaining to elevated 1cvels of Cs-137 in milk at sample station No. 35.
Very truly yours,
'Q C. R. Dietz, Gehdral Manager Brunswick Steam Electric Plant RMP/tt Enclosure cc: Mr. V. Stello, Jr.
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