ML19207B155
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| ML19207B155 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/20/1979 |
| From: | Tollison A CAROLINA POWER & LIGHT CO. |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| Shared Package | |
| ML19207B148 | List: |
| References | |
| LER-79-064-03L, LER-79-64-3L, NUDOCS 7908230459 | |
| Download: ML19207B155 (1) | |
Similar Documents at Brunswick | |
|---|---|
Category:LICENSEE EVENT REPORT (SEE ALSO AO
MONTHYEARML20029E1891994-05-13013 May 1994
[Table view]LER 94-007-00:on 940418,meter Lead Inadvertently Touched Adjacent Terminal Resulting in RCIC Inboard Steam Valve Closure.Caused by Personnel Error.Corrective Action:Meetings Were Held & self-assessments in progress.W/940513 Ltr ML20029D6171994-04-29029 April 1994 LER 94-005-01:on 940330,potential Use of Less Conservative pressure-temp Limit Curves Identified.Caused by Inadequate Procedural Guidance.Corrective Actions:Adverse Condition Rept initiated.W/940429 Ltr ML20029D0051994-04-28028 April 1994 LER 94-005-00:on 940404,two PCIS Group 6 RIP Valves Had Dual Open/Closed (Red/Green) Indications.Cause Was Personnel Error.Corrective Action:Individuals Involved Counseled on event.W/940428 Ltr ML20029C8491994-04-25025 April 1994 LER 94-004-00:on 940329,penetration Leakage in Excess of TS Allowable Limit During Local Leak Rate Testing Identified. Troubleshooting & Analysis of Failure Mechanism in Progress. Suppl to Rept Will Be submitted.W/940425 Ltr ML20046B5601993-07-30030 July 1993 LER 92-004-01:on 920730,RWCU Sys Isolated During Substation E7 de-energization Due to Personnel Error.Preparation of Project Plan for Development of Electrical Load List Using Plant Staff Resources underway.W/930730 Ltr ML20045G5821993-07-0808 July 1993 LER 93-003-00:on 930608,RPS MG a Tripped,Resulting in Successful ESF Actuations & Isolations Due to Defective Procedure.Voltage Adjust Potentiometer for MG a Voltage Regulator Replaced on 930617.W/930708 Ltr ML20045F5201993-07-0202 July 1993 LER 93-010-00:on 930604,hourly Fire Watch TS Surveillance Missed During Radiography Due to HP & Operations Failed to Establish Other Means of Communication W/Radiographers. W/930702 Ltr ML20045D6371993-06-30030 June 1993 LER 93-005-01:on 930214,testing of SBGT Showed That Unthrottled Flow of Single Train Would Exceed TS Rated Flow Limit of 3,330 Cfm.Caused by Design Deficiency.Existing SBGT Heaters Upgraded & Rewired ML20045D7601993-06-30030 June 1993 LER 93-008-01:on 930313,spurious ESF Actuations Occurred Due to on-site Electrical Distribution Sys Voltage Depressions. Design of cross-over Points of Transmission Lines Emanating from Plant Being reviewed.W/930624 Ltr ML20045D1531993-06-21021 June 1993 LER-93-007-00:on 930522,discovered That MSL D High Flow Trip Unit Failed Downscale Due to Personnel Error.Appropriate Operations Personnel counselled.W/930617 Ltr ML20045D5881993-06-17017 June 1993 LER 93-006-00:on 930521,HCU 06-31 Declared Inoperable When CRD Accumulator Low Pressure/High Level Alarm Received in Cr.Hcu 02-23 Inoperable at Time.Hcu 02-23 Restored to Svc & Excess Water Drained from HCU 06-31.W/930617 Ltr ML20044E5241993-05-24024 May 1993 LER 93-007-00:on 930424,discovered That Sampling of Rv Coolant Conductivity Not Performed Due to Misinterpretation of RCS Chemistry Ts.Chemistry Sampling of Rv Coolant re-established.W/930521 Ltr ML20044E5411993-05-20020 May 1993 LER 93-009-00:on 930421,found That Design of SBGTS Would Allow Operation That Would Result in Sys Damage If Containment Venting in Progress & Experience Loca.Operating Procedures 1-OP-10 & 1-OP-24 revised.W/930520 Ltr ML20044B6761993-02-22022 February 1993 LER 93-001-00:on 930121,determined That Containment Atmospheric Control Airborne Particulate & Gaseous Radioactivity Monitors Not Seismically Qualified.Suppl to Rept Will Be submitted.W/930227 Ltr ML20029A9111991-02-25025 February 1991 LER 91-001-00:on 910125,reactor Scram Occurred During Calibr of Feedwater Computer Point.Caused by Incorrect Procedure in Summary Sheet.Maint Procedures Reviewed & revised.W/910225 Ltr ML20028H7141991-01-24024 January 1991 LER 90-019-00:on 901226,isolation Signal Caused Reactor Water Cleanup Inlet Inboard Isolation Valve to Automatically Close.Caused by de-energized HPCI Isolation Relay.Riley Scam Temp Switch Units Will Be replaced.W/910124 Ltr ML20024F7461990-12-13013 December 1990 LER 90-020-00:on 901117,primary & Secondary Containment Isolation Signals Received & Standby Gas Treatment Sys auto- Started.Caused by Scan Overload on Microprocessor.Updated Microprocessor Will Be obtained.W/901213 Ltr ML20028H0421990-09-28028 September 1990 LER 90-012-00:on 900830,Unit 2 Reactor Scram Occurred During Reactor Startup.Investigation Continuing.Level Recovered W/O Need for Safety Sys Injection & Unit Designed for Level Transient from Full power.W/900928 Ltr ML20028H0431990-09-28028 September 1990 LER 90-011-00:on 900830,RWCU Sys G31 Received Leak Hi & RWCU Leak Hi Hi Annunciators Although Actual Leak Had Not Occurred.Caused by Air in Instrument 2-G31-FT-N012 Sensing Lines.Investigation to Be conducted.W/900928 Ltr ML20043G0981990-06-15015 June 1990 LER 88-001-06:on 880102,manual Reactor Protection Sys Trip Initiated Due to Decreasing Condenser Vacuum.Cause Still Undetermined.Vendor Insp Revealed Presence of Oil Base Film in Solenoid Valves.Determination Due by 900801.W/900615 Ltr ML20043G0711990-06-13013 June 1990 LER 90-005-00:on 900514,unplanned Closure of HPCI Isolation Valve Occurred During Maint Surveillance Test.Caused by Technician Placing RCIC Instead of HPCI Test Switch to Test Position.Personnel Counseled & trained.W/900613 Ltr ML20043F6291990-06-11011 June 1990 LER 90-008-00:on 900514,HPCI Sys Rendered Inoperable When Control Power Lost to Min Flow Bypass Valve to Suppression Pool.Probably Caused by Design Problem W/Ge Model CR2940 Sockets.Light Bulb & Fuse replaced.W/900611 Ltr ML20043F6181990-06-0808 June 1990 LER 90-007-00:on 900511,identified That Damper Would Fail to Close on Loss of Power to Solenoid Valve & on 900526,damper Found Approx 30 Degrees Open.Caused by Failure of Design to Include Fail Safe Damper.Damper modified.W/900608 Ltr ML20043C9001990-06-0101 June 1990 LER 90-009-00:on 900507,determined That Tech Spec 4.6.1.1 Requirements Not Met After Performing Monthly Periodic Test 2.2.4a.Caused by Inadequate Procedure.Recommended Procedure Revs to Prevent Recurrence Being evaluated.W/900601 Ltr ML20043B7971990-05-25025 May 1990 LER 90-006-00:on 900426,hydraulic Perturbation Occurred on Variable Leg of Instrumentation Used to Sense Reactor Water Level,Causing Isolation of RWCU Sys & Initiation of Standby Gas Treatment Sys.Diaphragm Assembly recalibr.W/900525 Ltr ML20043A6121990-05-11011 May 1990 LER 90-003-01:on 900312,full Group 1 Isolation Signal Received,Resulting in Automatic Closure of Msivs.Caused by Personnel Failing to Follow Procedures.Personnel Counseled & Procedure Separated Into Two tests.W/900511 Ltr ML20012E0581990-03-23023 March 1990 LER 90-002-00:on 900224,Group I Isolation Occurred When Undervoltage Relay Replaced.Caused by Lack of Recognition of Significance of Having Turbine Reset While Performing Electro Hydraulic Control evolutions.W/900323 Ltr ML20012B8071990-03-0909 March 1990 LER 90-001-00:on 900210,determined That Core Spray Loops a & B Inoperable Due to Missed Surveillance.Cause Not Stated. Investigation continuing.W/900309 Ltr ML20012A1671990-03-0202 March 1990 LER 89-013-01:on 890909,HPCI Turbine Auxiliary Oil Pump Developed Shaft Seal Leak of Approx 1 Gpm.Caused by Failure of Shaft Seal.Root Cause of Seal Failure Initiated.Pump Seal replaced.W/900302 Ltr ML20011F5541990-02-22022 February 1990 LER 90-002-00:on 900127,common Control Bldg HVAC Sys Isolated & Transferred to Recirculation Mode as Result of Spurious Actuation of Chlorine Detector.Sensor Connection checked.W/900222 Ltr ML20006E7751990-02-19019 February 1990 LER 88-001-05:on 880102,manual Reactor Protection Sys Trip Initiated Due to Decreasing Condenser Vacuum.Caused by Numerous Leaks on Main Turbine & Main Steam Reheat Interconnecting Piping.Seating Matl installed.W/900219 Ltr ML20011F5311990-02-16016 February 1990 LER 89-026-01:on 891210,common Emergency Bus E3 Unexpectedly Deenergized,Causing Standby Gas Treatment Sys Isolation & Reactor Scram Signal.Caused by Procedural Inadequacy.Isolation Reset & Power restored.W/900216 Ltr ML20006E3681990-02-0909 February 1990 LER 88-006-02:on 880219,numerous Bolt Head Failures of 5/16- Inch X 1/2-inch Silicon Bronze Carriage Bolts Noted in Bus/ Bar Connections of Electrical Switchboards.Caused by Igscc. Bolts Replaced.Reportable Per Part 21.W/900209 Ltr ML20011E1601990-02-0101 February 1990 LER 90-001-00:on 900102,RCIC Removed from Svc & HPCI Rendered Inoperable,Placing Unit in Tech Spec 3.0.3.Caused by Personnel Error.Individual Counseled & Standing Instruction 90-003 issued.W/900201 Ltr ML19354E5651990-01-24024 January 1990 LER 89-021-00:on 891225,electrical Protection Assembly Output Breakers Associated W/Bus a of Reactor Protection Sys Tripped Open.Cause of Trip Unknown.Voltage & Frequency Output of Motor Generator a monitored.W/900124 Ltr ML19354E5611990-01-19019 January 1990 LER 89-025-00:on 891223,sample Lines for Stack Radiation Monitor Froze,Resulting in Samples Not Indicative of Ongoing Releases.Caused by Lack of Insulation on Lines Exiting Stack.Sample Lines insulated.W/900119 Ltr ML19354D8951990-01-16016 January 1990 LER 89-020-00:on 891217,relay in Reactor Protection Sys B Motor Generator Set Control Panel Burned Out,Resulting in Logic Trip of Bus B & Isolation of Standby Gas Treatment Sys.Caused by Circuit malfunction.W/900116 Ltr ML20005F0501990-01-0404 January 1990 LER 89-026-00:on 891210,loss of E3 Bus While Deenergizing Bus 2D for Scheduled Maint Occurred.Caused by Procedural Inadequacy of Plant Electric Sys Operating Procedures.Unit Reset & Sys Returned to normal.W/900104 Ltr ML20042D3551990-01-0202 January 1990 LER 89-019-00:on 891208,Group 6 Isolation Occurred W/Standby Gas Treatment Sys Auto Start During Performance of MST-SCIS21R.Caused by Inadequate Work Practices.Work Crew Counseled.Calibr Procedures May Be revised.W/900102 Ltr ML20005E3461989-12-27027 December 1989 LER 89-024-00:on 891127,17 Primary Containment Isolation Valves Not Tested Per Tech Spec Surveillance Requirement 4.6.1.1.a.Caused by Failure to Recognize Applicability of Testing.Test Rev completed.W/891227 Ltr ML20011D8411989-12-15015 December 1989 LER 89-009-01:on 890617,manual Reactor Scram Initiated Per NRC Bulletin 88-007 Due to Loss of Recirculation Pumps, Causing Loss of Offsite Power & Containment Isolation. Caused by Personnel Error.Hpci Sys secured.W/891215 Ltr ML20011D2251989-12-14014 December 1989 LER 89-023-00:on 891116,reactor Shutdown When Drywell to Suppression Chamber Vacuum Breaker Opened.Caused by Excessive Vibration & Lack of Proper Space Between Actuator Arm & Piston.Procedures Will Be revised.W/891214 Ltr ML19332E9001989-12-0707 December 1989 LER 89-022-00:on 891110,automatic Isolation of Units 1 & 2 Common Control Bldg HVAC & Emergency Air Filtration Sys Occurred.Cause Not Determined.Detectors auto-reset & Sys Returned to Normal svc.W/891207 Ltr ML19332D5791989-11-27027 November 1989 LER 89-018-00:on 891101,determined That Safety Relief Valves Did Not Actuate within Required +/- 1.0% of Setpoints.Cause Not Determined.Setpoints recertified.W/891127 Ltr ML19332C3861989-11-21021 November 1989 LER 89-021-00:on 891022,inadvertent LOCA Initiation Signal Occurred During Monthly Channel Calibr & Functional Test. Caused by Technician Miscommunication.Involved Technicians counseled.W/891121 Ltr ML19327C2021989-11-14014 November 1989 LER 89-019-01:on 890914,determined That Svc Water Sys May Not Have Met Design Requirements Under worst-case Conditions.Caused by Inadequate Component design.Cross-tie Valves Installed.Also Reported Per Part 21.W/891114 Ltr ML19324C3171989-11-0707 November 1989 LER 89-020-00:on 891011,HPCI F006 Valve Motor Control Ctr Indicating Light Socket Shorted & Blew Control Power Fuse for Valve.Caused by Inward Force Applied to Bulb During Removal.Lamp,Socket & Fuse replaced.W/891107 Ltr ML19324C1041989-11-0606 November 1989 LER 89-017-00:on 891010,low Level Signals Occurred,Causing Group 1 Isolation,Core Spray Initiation Signal & auto-start of Common Emergency Diesel Generators.Caused by Perturbation of Ref Leg.Procedures revised.W/891106 Ltr ML19327B9861989-11-0606 November 1989 LER 89-017-01:on 890624,HPCI Sys,Steam Line Break Delta Pressure High Signal,Channel A,Isolation Occurred.Root Cause Investigation Underway.Work Request/Job Order Initiated Requesting Verification of readings.W/891106 Ltr ML19354D4401989-11-0101 November 1989 LER 89-016-01:on 890614,determined That Some Valves Listed in Table 1 of LER Not Tested Per Tech Specs.Caused by Failure to Establish Proper Procedural Controls.Valve Acceptance Criteria Basis Sheets updated.W/891101 Ltr 1994-05-13 Category:RO) MONTHYEARML20029E1891994-05-13013 May 1994
[Table view]LER 94-007-00:on 940418,meter Lead Inadvertently Touched Adjacent Terminal Resulting in RCIC Inboard Steam Valve Closure.Caused by Personnel Error.Corrective Action:Meetings Were Held & self-assessments in progress.W/940513 Ltr ML20029D6171994-04-29029 April 1994 LER 94-005-01:on 940330,potential Use of Less Conservative pressure-temp Limit Curves Identified.Caused by Inadequate Procedural Guidance.Corrective Actions:Adverse Condition Rept initiated.W/940429 Ltr ML20029D0051994-04-28028 April 1994 LER 94-005-00:on 940404,two PCIS Group 6 RIP Valves Had Dual Open/Closed (Red/Green) Indications.Cause Was Personnel Error.Corrective Action:Individuals Involved Counseled on event.W/940428 Ltr ML20029C8491994-04-25025 April 1994 LER 94-004-00:on 940329,penetration Leakage in Excess of TS Allowable Limit During Local Leak Rate Testing Identified. Troubleshooting & Analysis of Failure Mechanism in Progress. Suppl to Rept Will Be submitted.W/940425 Ltr ML20046B5601993-07-30030 July 1993 LER 92-004-01:on 920730,RWCU Sys Isolated During Substation E7 de-energization Due to Personnel Error.Preparation of Project Plan for Development of Electrical Load List Using Plant Staff Resources underway.W/930730 Ltr ML20045G5821993-07-0808 July 1993 LER 93-003-00:on 930608,RPS MG a Tripped,Resulting in Successful ESF Actuations & Isolations Due to Defective Procedure.Voltage Adjust Potentiometer for MG a Voltage Regulator Replaced on 930617.W/930708 Ltr ML20045F5201993-07-0202 July 1993 LER 93-010-00:on 930604,hourly Fire Watch TS Surveillance Missed During Radiography Due to HP & Operations Failed to Establish Other Means of Communication W/Radiographers. W/930702 Ltr ML20045D6371993-06-30030 June 1993 LER 93-005-01:on 930214,testing of SBGT Showed That Unthrottled Flow of Single Train Would Exceed TS Rated Flow Limit of 3,330 Cfm.Caused by Design Deficiency.Existing SBGT Heaters Upgraded & Rewired ML20045D7601993-06-30030 June 1993 LER 93-008-01:on 930313,spurious ESF Actuations Occurred Due to on-site Electrical Distribution Sys Voltage Depressions. Design of cross-over Points of Transmission Lines Emanating from Plant Being reviewed.W/930624 Ltr ML20045D1531993-06-21021 June 1993 LER-93-007-00:on 930522,discovered That MSL D High Flow Trip Unit Failed Downscale Due to Personnel Error.Appropriate Operations Personnel counselled.W/930617 Ltr ML20045D5881993-06-17017 June 1993 LER 93-006-00:on 930521,HCU 06-31 Declared Inoperable When CRD Accumulator Low Pressure/High Level Alarm Received in Cr.Hcu 02-23 Inoperable at Time.Hcu 02-23 Restored to Svc & Excess Water Drained from HCU 06-31.W/930617 Ltr ML20044E5241993-05-24024 May 1993 LER 93-007-00:on 930424,discovered That Sampling of Rv Coolant Conductivity Not Performed Due to Misinterpretation of RCS Chemistry Ts.Chemistry Sampling of Rv Coolant re-established.W/930521 Ltr ML20044E5411993-05-20020 May 1993 LER 93-009-00:on 930421,found That Design of SBGTS Would Allow Operation That Would Result in Sys Damage If Containment Venting in Progress & Experience Loca.Operating Procedures 1-OP-10 & 1-OP-24 revised.W/930520 Ltr ML20044B6761993-02-22022 February 1993 LER 93-001-00:on 930121,determined That Containment Atmospheric Control Airborne Particulate & Gaseous Radioactivity Monitors Not Seismically Qualified.Suppl to Rept Will Be submitted.W/930227 Ltr ML20029A9111991-02-25025 February 1991 LER 91-001-00:on 910125,reactor Scram Occurred During Calibr of Feedwater Computer Point.Caused by Incorrect Procedure in Summary Sheet.Maint Procedures Reviewed & revised.W/910225 Ltr ML20028H7141991-01-24024 January 1991 LER 90-019-00:on 901226,isolation Signal Caused Reactor Water Cleanup Inlet Inboard Isolation Valve to Automatically Close.Caused by de-energized HPCI Isolation Relay.Riley Scam Temp Switch Units Will Be replaced.W/910124 Ltr ML20024F7461990-12-13013 December 1990 LER 90-020-00:on 901117,primary & Secondary Containment Isolation Signals Received & Standby Gas Treatment Sys auto- Started.Caused by Scan Overload on Microprocessor.Updated Microprocessor Will Be obtained.W/901213 Ltr ML20028H0421990-09-28028 September 1990 LER 90-012-00:on 900830,Unit 2 Reactor Scram Occurred During Reactor Startup.Investigation Continuing.Level Recovered W/O Need for Safety Sys Injection & Unit Designed for Level Transient from Full power.W/900928 Ltr ML20028H0431990-09-28028 September 1990 LER 90-011-00:on 900830,RWCU Sys G31 Received Leak Hi & RWCU Leak Hi Hi Annunciators Although Actual Leak Had Not Occurred.Caused by Air in Instrument 2-G31-FT-N012 Sensing Lines.Investigation to Be conducted.W/900928 Ltr ML20043G0981990-06-15015 June 1990 LER 88-001-06:on 880102,manual Reactor Protection Sys Trip Initiated Due to Decreasing Condenser Vacuum.Cause Still Undetermined.Vendor Insp Revealed Presence of Oil Base Film in Solenoid Valves.Determination Due by 900801.W/900615 Ltr ML20043G0711990-06-13013 June 1990 LER 90-005-00:on 900514,unplanned Closure of HPCI Isolation Valve Occurred During Maint Surveillance Test.Caused by Technician Placing RCIC Instead of HPCI Test Switch to Test Position.Personnel Counseled & trained.W/900613 Ltr ML20043F6291990-06-11011 June 1990 LER 90-008-00:on 900514,HPCI Sys Rendered Inoperable When Control Power Lost to Min Flow Bypass Valve to Suppression Pool.Probably Caused by Design Problem W/Ge Model CR2940 Sockets.Light Bulb & Fuse replaced.W/900611 Ltr ML20043F6181990-06-0808 June 1990 LER 90-007-00:on 900511,identified That Damper Would Fail to Close on Loss of Power to Solenoid Valve & on 900526,damper Found Approx 30 Degrees Open.Caused by Failure of Design to Include Fail Safe Damper.Damper modified.W/900608 Ltr ML20043C9001990-06-0101 June 1990 LER 90-009-00:on 900507,determined That Tech Spec 4.6.1.1 Requirements Not Met After Performing Monthly Periodic Test 2.2.4a.Caused by Inadequate Procedure.Recommended Procedure Revs to Prevent Recurrence Being evaluated.W/900601 Ltr ML20043B7971990-05-25025 May 1990 LER 90-006-00:on 900426,hydraulic Perturbation Occurred on Variable Leg of Instrumentation Used to Sense Reactor Water Level,Causing Isolation of RWCU Sys & Initiation of Standby Gas Treatment Sys.Diaphragm Assembly recalibr.W/900525 Ltr ML20043A6121990-05-11011 May 1990 LER 90-003-01:on 900312,full Group 1 Isolation Signal Received,Resulting in Automatic Closure of Msivs.Caused by Personnel Failing to Follow Procedures.Personnel Counseled & Procedure Separated Into Two tests.W/900511 Ltr ML20012E0581990-03-23023 March 1990 LER 90-002-00:on 900224,Group I Isolation Occurred When Undervoltage Relay Replaced.Caused by Lack of Recognition of Significance of Having Turbine Reset While Performing Electro Hydraulic Control evolutions.W/900323 Ltr ML20012B8071990-03-0909 March 1990 LER 90-001-00:on 900210,determined That Core Spray Loops a & B Inoperable Due to Missed Surveillance.Cause Not Stated. Investigation continuing.W/900309 Ltr ML20012A1671990-03-0202 March 1990 LER 89-013-01:on 890909,HPCI Turbine Auxiliary Oil Pump Developed Shaft Seal Leak of Approx 1 Gpm.Caused by Failure of Shaft Seal.Root Cause of Seal Failure Initiated.Pump Seal replaced.W/900302 Ltr ML20011F5541990-02-22022 February 1990 LER 90-002-00:on 900127,common Control Bldg HVAC Sys Isolated & Transferred to Recirculation Mode as Result of Spurious Actuation of Chlorine Detector.Sensor Connection checked.W/900222 Ltr ML20006E7751990-02-19019 February 1990 LER 88-001-05:on 880102,manual Reactor Protection Sys Trip Initiated Due to Decreasing Condenser Vacuum.Caused by Numerous Leaks on Main Turbine & Main Steam Reheat Interconnecting Piping.Seating Matl installed.W/900219 Ltr ML20011F5311990-02-16016 February 1990 LER 89-026-01:on 891210,common Emergency Bus E3 Unexpectedly Deenergized,Causing Standby Gas Treatment Sys Isolation & Reactor Scram Signal.Caused by Procedural Inadequacy.Isolation Reset & Power restored.W/900216 Ltr ML20006E3681990-02-0909 February 1990 LER 88-006-02:on 880219,numerous Bolt Head Failures of 5/16- Inch X 1/2-inch Silicon Bronze Carriage Bolts Noted in Bus/ Bar Connections of Electrical Switchboards.Caused by Igscc. Bolts Replaced.Reportable Per Part 21.W/900209 Ltr ML20011E1601990-02-0101 February 1990 LER 90-001-00:on 900102,RCIC Removed from Svc & HPCI Rendered Inoperable,Placing Unit in Tech Spec 3.0.3.Caused by Personnel Error.Individual Counseled & Standing Instruction 90-003 issued.W/900201 Ltr ML19354E5651990-01-24024 January 1990 LER 89-021-00:on 891225,electrical Protection Assembly Output Breakers Associated W/Bus a of Reactor Protection Sys Tripped Open.Cause of Trip Unknown.Voltage & Frequency Output of Motor Generator a monitored.W/900124 Ltr ML19354E5611990-01-19019 January 1990 LER 89-025-00:on 891223,sample Lines for Stack Radiation Monitor Froze,Resulting in Samples Not Indicative of Ongoing Releases.Caused by Lack of Insulation on Lines Exiting Stack.Sample Lines insulated.W/900119 Ltr ML19354D8951990-01-16016 January 1990 LER 89-020-00:on 891217,relay in Reactor Protection Sys B Motor Generator Set Control Panel Burned Out,Resulting in Logic Trip of Bus B & Isolation of Standby Gas Treatment Sys.Caused by Circuit malfunction.W/900116 Ltr ML20005F0501990-01-0404 January 1990 LER 89-026-00:on 891210,loss of E3 Bus While Deenergizing Bus 2D for Scheduled Maint Occurred.Caused by Procedural Inadequacy of Plant Electric Sys Operating Procedures.Unit Reset & Sys Returned to normal.W/900104 Ltr ML20042D3551990-01-0202 January 1990 LER 89-019-00:on 891208,Group 6 Isolation Occurred W/Standby Gas Treatment Sys Auto Start During Performance of MST-SCIS21R.Caused by Inadequate Work Practices.Work Crew Counseled.Calibr Procedures May Be revised.W/900102 Ltr ML20005E3461989-12-27027 December 1989 LER 89-024-00:on 891127,17 Primary Containment Isolation Valves Not Tested Per Tech Spec Surveillance Requirement 4.6.1.1.a.Caused by Failure to Recognize Applicability of Testing.Test Rev completed.W/891227 Ltr ML20011D8411989-12-15015 December 1989 LER 89-009-01:on 890617,manual Reactor Scram Initiated Per NRC Bulletin 88-007 Due to Loss of Recirculation Pumps, Causing Loss of Offsite Power & Containment Isolation. Caused by Personnel Error.Hpci Sys secured.W/891215 Ltr ML20011D2251989-12-14014 December 1989 LER 89-023-00:on 891116,reactor Shutdown When Drywell to Suppression Chamber Vacuum Breaker Opened.Caused by Excessive Vibration & Lack of Proper Space Between Actuator Arm & Piston.Procedures Will Be revised.W/891214 Ltr ML19332E9001989-12-0707 December 1989 LER 89-022-00:on 891110,automatic Isolation of Units 1 & 2 Common Control Bldg HVAC & Emergency Air Filtration Sys Occurred.Cause Not Determined.Detectors auto-reset & Sys Returned to Normal svc.W/891207 Ltr ML19332D5791989-11-27027 November 1989 LER 89-018-00:on 891101,determined That Safety Relief Valves Did Not Actuate within Required +/- 1.0% of Setpoints.Cause Not Determined.Setpoints recertified.W/891127 Ltr ML19332C3861989-11-21021 November 1989 LER 89-021-00:on 891022,inadvertent LOCA Initiation Signal Occurred During Monthly Channel Calibr & Functional Test. Caused by Technician Miscommunication.Involved Technicians counseled.W/891121 Ltr ML19327C2021989-11-14014 November 1989 LER 89-019-01:on 890914,determined That Svc Water Sys May Not Have Met Design Requirements Under worst-case Conditions.Caused by Inadequate Component design.Cross-tie Valves Installed.Also Reported Per Part 21.W/891114 Ltr ML19324C3171989-11-0707 November 1989 LER 89-020-00:on 891011,HPCI F006 Valve Motor Control Ctr Indicating Light Socket Shorted & Blew Control Power Fuse for Valve.Caused by Inward Force Applied to Bulb During Removal.Lamp,Socket & Fuse replaced.W/891107 Ltr ML19324C1041989-11-0606 November 1989 LER 89-017-00:on 891010,low Level Signals Occurred,Causing Group 1 Isolation,Core Spray Initiation Signal & auto-start of Common Emergency Diesel Generators.Caused by Perturbation of Ref Leg.Procedures revised.W/891106 Ltr ML19327B9861989-11-0606 November 1989 LER 89-017-01:on 890624,HPCI Sys,Steam Line Break Delta Pressure High Signal,Channel A,Isolation Occurred.Root Cause Investigation Underway.Work Request/Job Order Initiated Requesting Verification of readings.W/891106 Ltr ML19354D4401989-11-0101 November 1989 LER 89-016-01:on 890614,determined That Some Valves Listed in Table 1 of LER Not Tested Per Tech Specs.Caused by Failure to Establish Proper Procedural Controls.Valve Acceptance Criteria Basis Sheets updated.W/891101 Ltr 1994-05-13 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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(7 77)LICENSEE EVENT REPORT
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$7 CAT $8 CON'T$0R$Xl@l 0 5l Ol -l Ol 3l 2l 4 @l0 17 13 l1 17 19 gj 0l 8 l2 l 0 7 l9 l@o 1 7 8 60 61 DOCK ET NUMB E R 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONCF.QUENCES h O 2 ICarolina Power & Licht Connany received noef ff enrinn fenm Canavn1 Plocevic rh,e nn n ed o a lexisted in the Technical Specifications (3.2.3.b) for the MCPR Limit frou End-of-CveleI o 4 I l(EOC) minus 2000 MWD /ST to EOC. This Technical Snecification is not exnected to be-1 o s Icome applicable until approximately October 1979: consequent 1v these limits have not I lo is lbeen exceeded. The old limits and new limits supplied by C.E. are as follows:
0 7l Fuel Type Was Should Be Fuel Type Was Should Be Fuel Type Was Should Be I o a 17 X 7 1.21 1.22 8X8 1.27 1.29 8 X 8R 1.27 1.29!7 8 9 80 E CODE SU8CO E COMPONENT CODE SUBCOD'E SU DElR lB l@ l Blh l A h l F l U l E l L l X l X lh lZ lh Z l h o 9 7 8 9 10 11 12 13 18 19 20 SE QUENTI AL OCCURRENCE REPORT REVISION LE R. RO'ENT YE AR REPORT NO.
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33 3S 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS G TTl l General Electric explained that the error was attributable to the n :e of incorrect J Wy Ivoid coefficient data, and has identified action to prevent recurrence through inter- I
[TTTl Inal procedures. A revision to Technical Specifications is being prepared to establisa l g Lthe proper limits by EOC minus 2000 MWD /ST.
lU_L4_] I I 7 8<a 80 5bS% POWER OTHER STATUS DISCO RY Of SCOVERY DESCRIPTION y@ l 0l 9 5 l@l NAllDl@lVendor Notification
-li s ACTIVITY CO TENT RELEASED OF RELEASE AMOUNT OF AC TIVITY LOCATION OF RELEASE y y @ l Z l@l NA ll NAlPERSONNEL EXPOS ES cESCRiPriON h NUMBER TvPEl0 0 l 0 l@l Z l@l NAl_1 7 PERSONN E INJURIES DESCRIPTION @
NUYBER q<, rMOW Q l0 0l0l@l NA (7 8 9 11 12 80 LOSS OF OR DAMAGE TO FACILITY TYPE DESCRIPTION Whl NA 1 9 7 8 9 10 80 ISSU E DESCRIPTION
[hl NA 70 b c) 3*2 0")i , , , , i iiiiiil; 7 8 9 10 68 69 80 ;;;NAVE OF PREPARER A. C. To111 son, Jr.
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