Forwards LER 80-107/03L-0
Person / Time
ML19351F592
Site:	Brunswick
Issue date:	01/07/1981
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19351F593	List: 05000324/LER-1980-107, Forwards LER 80-107/03L-0 05000324/LER-1980-107-03, /03L-0:on 801208,svc Water Sys Primary Coolant Temp Reached 212F.Caused by Removal of Shutdown Cooling Capability for Maint W/Access to Primary Containment Open & Subsequent Heatup of Primary Coolant Due to Decay Heat
References
BSEP-81-0034, BSEP-81-34, NUDOCS 8101130548
Download: ML19351F592 (1)
v • d • e

LER-1980-107, Forwards LER 80-107/03L-0

Event date:
Report date:
3241980107R00 - NRC Website
v • d • e

text

s Carolina Power & Light Company Brunswick Steam Electric Plant P. O. Box 10429 Southport, NC 28461 January 7, 1981 FILE: B09-13516 SERIAL: BSEP/81-0034 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Com,nission Region II, Suite 3100 101 Marietts Street N.W.

Atlanta, GA 30303 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-324 LICENSE NO. DPR-62 LICENSEE EVENT REPORT 2-80-i07

Dear Mr. O'Reilly:

In accordance with Section 6.9.1.9.c of the Technical Specifications for Brunswick. Steam Electric Plant, Unit No. 2, the enclosed Licensee Event Report is submitted. This report fulfills the requirement for a written report within thirty (30) days of a reportable occurrence and is in accordance with the format set forth in NUREG-0161, July 1977.

Ve ly yours, l

A. C. Tollison, Jr., General Manager Brunswick Steam Electric Plant

- RMP/sas

(

- Enclosure cc: A R. A. Hartfield Mr. V. Stello, Jr.

t Yl% \\

810 :! y a a 5.17 s

Licensee Event Report

Brunswick

70 | 71 | 72 | 73 | 74 | 75 | 76 | 77 | 78 | 79 | 80 | 81 | 82 | 83 | 84 | 85 | 86 | 87 | 88 | 89 |

90 | 91 | 92 | 93 | 94 | 95 | 96 | 97 | 98 | 99 | 00 | 01 | 02 | 03 | 04 | 05 | 06 | 07 | 08 | 09 |

10 | 11 | 12 | 13 | 14 | 15 | 16 | 17 | 18 | 19 | 20 | 21 | 22 | 23 | 24 | 25 |

		Reporting criterion
05000325/LER-1980-001, Forwards LER 80-001/03L-0	Forwards LER 80-001/03L-0
05000325/LER-1980-001-03, /03L-0:on 800102,during Normal Operation, Containment Atmospheric Monitor Had Step Increase of Approx 2%.Caused by Instrument Drift.Instrument Recalibr & Returned to Svc	/03L-0:on 800102,during Normal Operation, Containment Atmospheric Monitor Had Step Increase of Approx 2%.Caused by Instrument Drift.Instrument Recalibr & Returned to Svc
05000324/LER-1980-001, Forwards LER 80-001/03L-0	Forwards LER 80-001/03L-0
05000324/LER-1980-001-03, /03L-0:on 800117,during Attempt to Start RHR Room Cooler 2A,breaker Tripped on Magnetics.Cause Could Not Be Determined Due to Inoperable Room Cooler 2B.Breaker Reset & Closed	/03L-0:on 800117,during Attempt to Start RHR Room Cooler 2A,breaker Tripped on Magnetics.Cause Could Not Be Determined Due to Inoperable Room Cooler 2B.Breaker Reset & Closed
05000324/LER-1980-002, Forwards LER 80-002/03L-0	Forwards LER 80-002/03L-0
05000324/LER-1980-002-03, /03L-0:on 800102,during Normal Reactor Startup,Rod Sequence Control Sys Would Not Allow Rods to Be Pulled Until Rod 34-27 Was Bypassed full-in. Caused by Defective full- in Reed Switch.Switch Will Be Repaired or Replaced	/03L-0:on 800102,during Normal Reactor Startup,Rod Sequence Control Sys Would Not Allow Rods to Be Pulled Until Rod 34-27 Was Bypassed full-in. Caused by Defective full- in Reed Switch.Switch Will Be Repaired or Replaced
05000325/LER-1980-002-03, /03L-0:on 800106,during Normal Operation,Point 4 of Chloride Intrusion Monitor 1-CO-CR24 Was Reading Downscale.Caused by Defective Relay & Dirty Contacts.Relay Replaced,Contacts Cleaned & Recorder Returned to Svc	/03L-0:on 800106,during Normal Operation,Point 4 of Chloride Intrusion Monitor 1-CO-CR24 Was Reading Downscale.Caused by Defective Relay & Dirty Contacts.Relay Replaced,Contacts Cleaned & Recorder Returned to Svc
05000325/LER-1980-002, Forwards LER 80-002/03L-0	Forwards LER 80-002/03L-0
05000324/LER-1980-003, Forwards LER 80-003/03L-0	Forwards LER 80-003/03L-0
05000324/LER-1980-003-03, /03L-0:on 800103,during Reactor Startup,Vessel Conductivity Exceeded 2 Umho for 31-h.Caused by Auxiliary Boilers Being Isolated for Months & Supply Lines Containing Stagnant,High Conductivity Water	/03L-0:on 800103,during Reactor Startup,Vessel Conductivity Exceeded 2 Umho for 31-h.Caused by Auxiliary Boilers Being Isolated for Months & Supply Lines Containing Stagnant,High Conductivity Water
05000325/LER-1980-003, Forwards LER 80-003/03L-0	Forwards LER 80-003/03L-0
05000325/LER-1980-003-03, /03L-0:on 800114,channel Calibr CST Level Switch 1E41-LSL-N002 Found to Actuate at 23 Feet Decreasing.Caused by Switch Out of Calibr.Instrument Calibr & Returned to Svc	/03L-0:on 800114,channel Calibr CST Level Switch 1E41-LSL-N002 Found to Actuate at 23 Feet Decreasing.Caused by Switch Out of Calibr.Instrument Calibr & Returned to Svc
05000325/LER-1980-004, Forwards LER 80-004/03L-0	Forwards LER 80-004/03L-0
05000325/LER-1980-004-03, /03L-0:on 800308,during Normal Plant Operation, Oxygen Channel of Containment Atmospheric Monitor CAC-AT- 1263-2 Experienced 1% Step Change.Caused by Possible Wiring or Connection Problem.Monitor Repair Is Underway	/03L-0:on 800308,during Normal Plant Operation, Oxygen Channel of Containment Atmospheric Monitor CAC-AT- 1263-2 Experienced 1% Step Change.Caused by Possible Wiring or Connection Problem.Monitor Repair Is Underway
05000324/LER-1980-004, Forwards LER 80-004/03L-0	Forwards LER 80-004/03L-0
05000324/LER-1980-004-03, /03L-0:on 800127,during Normal Operations, Containment Atmospheric Monitor CAC-AT-1263 Kept Shutting Down Due to Low Flow Following Inerting Operation of Drywell.Cause Undetermined.Instruments to Be Replaced	/03L-0:on 800127,during Normal Operations, Containment Atmospheric Monitor CAC-AT-1263 Kept Shutting Down Due to Low Flow Following Inerting Operation of Drywell.Cause Undetermined.Instruments to Be Replaced
05000325/LER-1980-005-03, /03L-0:on 800113,while Performing Control Rod Operability Check,Control Rod 42-35 Had No Position Indication at Notch 47.Caused by Fault in Reed Switch in Prototypic Inlet Piping Probe	/03L-0:on 800113,while Performing Control Rod Operability Check,Control Rod 42-35 Had No Position Indication at Notch 47.Caused by Fault in Reed Switch in Prototypic Inlet Piping Probe
05000325/LER-1980-005, Forwards LER 80-005/03L-0	Forwards LER 80-005/03L-0
05000324/LER-1980-005-03, /03L-0:on 800105,during Normal Operation,Found Isolation Valve for Pressure Switch 2-E11-PS-N010D Shut. Cause Unknown.Counselled Personnel on Necessity to Follow Procedures to Ensure Proper Instrumentation Svc	/03L-0:on 800105,during Normal Operation,Found Isolation Valve for Pressure Switch 2-E11-PS-N010D Shut. Cause Unknown.Counselled Personnel on Necessity to Follow Procedures to Ensure Proper Instrumentation Svc
05000324/LER-1980-005, Forwards LER 80-005/03L-0	Forwards LER 80-005/03L-0
05000325/LER-1980-006-03, /03L-0:on 800225,while Working on Trouble Ticket Re Position Indication for RIP Valve 49B,discovered Valve Not Closing Fully When Given Closing Signal.No Cause Stated. Valve Will Be Repaired During 1980 Refueling Outage	/03L-0:on 800225,while Working on Trouble Ticket Re Position Indication for RIP Valve 49B,discovered Valve Not Closing Fully When Given Closing Signal.No Cause Stated. Valve Will Be Repaired During 1980 Refueling Outage
05000325/LER-1980-006, Forwards LER 80-006/03L-0	Forwards LER 80-006/03L-0
05000324/LER-1980-006, Forwards LER 80-006/03L-0	Forwards LER 80-006/03L-0
05000324/LER-1980-006-03, /03L-0:on 800103,during Normal Startup,Control Rod 26-07 Had No Position Indication at Notch 48.During 800109 Startup,Rod 34-35 Had No Indication at Notch 7.Caused by Faulty Reed Switches in Prototypical Inlet Piping Probes	/03L-0:on 800103,during Normal Startup,Control Rod 26-07 Had No Position Indication at Notch 48.During 800109 Startup,Rod 34-35 Had No Indication at Notch 7.Caused by Faulty Reed Switches in Prototypical Inlet Piping Probes
05000324/LER-1980-007-03, /03L-0:on 800204,when Plant Batteries Were Placed in Equalize,Steam Leak Detection a Logic Topaz Inverter, Model 125-GW 12560,tripped.Caused by Improper Setting on Inverter High Voltage Trip.Inverter Trips Recalibr	/03L-0:on 800204,when Plant Batteries Were Placed in Equalize,Steam Leak Detection a Logic Topaz Inverter, Model 125-GW 12560,tripped.Caused by Improper Setting on Inverter High Voltage Trip.Inverter Trips Recalibr
05000324/LER-1980-007, Forwards LER 80-007/03L-0	Forwards LER 80-007/03L-0
05000325/LER-1980-007, Forwards LER 80-007/03L-0	Forwards LER 80-007/03L-0
05000325/LER-1980-007-03, /03L-0:on 800114,during Normal Operation,Torus Level Indicator CAC-LI-3342 on Remote Shutdown Panel Was Not in Agreement W/Others in Control Room.Caused by Air Trapped in Demineralizer Water Line to Ref Leg.Instrument Recali	/03L-0:on 800114,during Normal Operation,Torus Level Indicator CAC-LI-3342 on Remote Shutdown Panel Was Not in Agreement W/Others in Control Room.Caused by Air Trapped in Demineralizer Water Line to Ref Leg.Instrument Recalibr
05000324/LER-1980-008-03, /03L-0:on 800110,while Performing Reactor Core Isolation Cooling Instrument Check,Reactor Core Isolation Cooling Trip & Throttle Valve MOV-V8 Would Not Trip.Caused by Burned Solenoid.Solenoid Repaired	/03L-0:on 800110,while Performing Reactor Core Isolation Cooling Instrument Check,Reactor Core Isolation Cooling Trip & Throttle Valve MOV-V8 Would Not Trip.Caused by Burned Solenoid.Solenoid Repaired
05000324/LER-1980-008, Forwards LER 80-008/03L-0	Forwards LER 80-008/03L-0
05000325/LER-1980-008-03, /03L-0:on 800115,while Attempting to Start RHR Svs Water Pump 1D to Check for Flange Leaks,Low Suction Pressure Annunciator Would Not Clear,Making B Loop Inoperable.Caused by Failure to re-energize Circuit 19	/03L-0:on 800115,while Attempting to Start RHR Svs Water Pump 1D to Check for Flange Leaks,Low Suction Pressure Annunciator Would Not Clear,Making B Loop Inoperable.Caused by Failure to re-energize Circuit 19
05000325/LER-1980-008, Forwards LER 80-008/03L-0	Forwards LER 80-008/03L-0
05000325/LER-1980-009, Forwards LER 80-009/03L-0	Forwards LER 80-009/03L-0
05000325/LER-1980-009-03, /03L-0:on 800120,during Normal Operation,Control Operator Noticed Containment Atmospheric Monitor Had Step Change for No Apparent Reason.No Cause Determined.Components of Monitor Replaced & Recalibr	/03L-0:on 800120,during Normal Operation,Control Operator Noticed Containment Atmospheric Monitor Had Step Change for No Apparent Reason.No Cause Determined.Components of Monitor Replaced & Recalibr
05000324/LER-1980-009, Forwards LER 80-009/03L-0	Forwards LER 80-009/03L-0
05000324/LER-1980-009-03, /03L-0:on 800114,during Normal Operation, Containment Atmospheric Monitor CAC-AT-1259-1 Failed Upscale.Caused by Loose Ground Connection on Span Potentiometer.Connection Tightened	/03L-0:on 800114,during Normal Operation, Containment Atmospheric Monitor CAC-AT-1259-1 Failed Upscale.Caused by Loose Ground Connection on Span Potentiometer.Connection Tightened
05000325/LER-1980-010-03, /03L-0:on 800122,while Performing Main Steam Line High Radiation Functional Check,Drawer 1D12-RM-K603B Found Out of Calibr.Instrument Drift Is Recurring Problem. Drawer Recalibr & Returned to Svc	/03L-0:on 800122,while Performing Main Steam Line High Radiation Functional Check,Drawer 1D12-RM-K603B Found Out of Calibr.Instrument Drift Is Recurring Problem. Drawer Recalibr & Returned to Svc
05000325/LER-1980-010, Forwards LER 80-010/03L-0	Forwards LER 80-010/03L-0
05000324/LER-1980-010-03, /03L-0:on 800114,during Normal Plant Operation, Nuclear Engineer Performed OD-1 & Found Max Critical Power Ratio to Exceed Limit.Caused by Low Power Range Monitor Having Two Levels Bypassed & Problems W/Core Flow Input	/03L-0:on 800114,during Normal Plant Operation, Nuclear Engineer Performed OD-1 & Found Max Critical Power Ratio to Exceed Limit.Caused by Low Power Range Monitor Having Two Levels Bypassed & Problems W/Core Flow Input
05000324/LER-1980-010, Supplemental LER 80-010/03L-1:on 800114,during Normal Plant operation,OD-1 Determined That Max Critical Power Ratio Was Below Tech Specs for Bundle 43-28.Caused by Problems W/Low Power Range Monitor & Core Flow Input.Power Redu	Supplemental LER 80-010/03L-1:on 800114,during Normal Plant operation,OD-1 Determined That Max Critical Power Ratio Was Below Tech Specs for Bundle 43-28.Caused by Problems W/Low Power Range Monitor & Core Flow Input.Power Reduced
05000325/LER-1980-011-03, /03L-0:on 800121,during 10-minute Run of HPCI Auxiliary Oil Pump,Stoppage Occurred When Switch Moved from Start to Auto Position.Caused by Loose Wire on RTGB Control Switch.Wire Reattached & Tightened	/03L-0:on 800121,during 10-minute Run of HPCI Auxiliary Oil Pump,Stoppage Occurred When Switch Moved from Start to Auto Position.Caused by Loose Wire on RTGB Control Switch.Wire Reattached & Tightened
05000325/LER-1980-011, Forwards LER 80-011/03L-0	Forwards LER 80-011/03L-0
05000324/LER-1980-011-03, /03L-0:on 800110,when Time Was Entered on Computer After Reinitialization,Computer Had Software Stall & Could Not Be Kept on Line,Causing Temp Recorder CAC-7R-1258 to Be Inoperable.New Points Added to Sys	/03L-0:on 800110,when Time Was Entered on Computer After Reinitialization,Computer Had Software Stall & Could Not Be Kept on Line,Causing Temp Recorder CAC-7R-1258 to Be Inoperable.New Points Added to Sys
05000324/LER-1980-011, Forwards LER 80-011/03L-0	Forwards LER 80-011/03L-0
05000325/LER-1980-012-03, /03L-0:on 800224,during Normal Plant Operation,Rip Valves,Variable Leg Isolation for Torus Level Transmitter & Variable Leg for Torus Level Pressure Switch Shut & Could Not Be Opened.Caused by Failure of Svc Air Compressors	/03L-0:on 800224,during Normal Plant Operation,Rip Valves,Variable Leg Isolation for Torus Level Transmitter & Variable Leg for Torus Level Pressure Switch Shut & Could Not Be Opened.Caused by Failure of Svc Air Compressors
05000325/LER-1980-012, Forwards LER 80-012/03L-0	Forwards LER 80-012/03L-0
05000324/LER-1980-012-03, /03L-0:on 800116,while Performing Torus Water Level Calibr & Functional Check,Level Switch E41-LSH-NOI5A Would Not Actuate.Caused by Switch Out of Calibr.Instrument Recalibr	/03L-0:on 800116,while Performing Torus Water Level Calibr & Functional Check,Level Switch E41-LSH-NOI5A Would Not Actuate.Caused by Switch Out of Calibr.Instrument Recalibr
05000324/LER-1980-012, Forwards LER 80-012/03L-0	Forwards LER 80-012/03L-0
05000324/LER-1980-013-03, /03L-0:on 800116,during Normal Operation, Containment Atmospheric Monitor CAC-AQH-1260 Monitor Breaker Had Tripped on Magnetics Rendering CAC-AQH-1262-2 Inoperable.Caused by Short in Power Lead.Lead Taped	/03L-0:on 800116,during Normal Operation, Containment Atmospheric Monitor CAC-AQH-1260 Monitor Breaker Had Tripped on Magnetics Rendering CAC-AQH-1262-2 Inoperable.Caused by Short in Power Lead.Lead Taped
05000325/LER-1980-013-03, /03L-0:on 800125,while Performing Reactor Low Water Level 2 & 3 Channel Calibr & Functional Check,Low Pressure Switch 1B21-LITS-N031A-2 Failed to Actuate.Caused by Instrument Drift.Instruments to Be Replaced	/03L-0:on 800125,while Performing Reactor Low Water Level 2 & 3 Channel Calibr & Functional Check,Low Pressure Switch 1B21-LITS-N031A-2 Failed to Actuate.Caused by Instrument Drift.Instruments to Be Replaced
... further results

05000324/LER-1980-107, Forwards LER 80-107/03L-0

text

Dear Mr. O'Reilly:

Navigation menu

Search