Submits Special Rept W/Charts Re Coolant Iodine Activity Which Exceeded Tech Specs.Caused by Two Scrams & Increase in Fission Product Inventory in Coolant from Leaking Fuel Element.Leaking Bundles Will Be Removed During Next OutageML20125D515 |
Person / Time |
---|
Site: |
Brunswick ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
---|
Issue date: |
01/03/1980 |
---|
From: |
Tollison A CAROLINA POWER & LIGHT CO. |
---|
To: |
|
---|
References |
---|
ASEP-80-12, NUDOCS 8001140343 |
Download: ML20125D515 (6) |
|
|
---|
Category:REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER)
MONTHYEARBSEP-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 BSEP-94-0103, Special Rept 1-SR-94-002:on 940226,fire Barrier Penetration Between EDG Bldg & Diesel Fuel Oil Day Storage Tank Room Opened.Fire Watch Stationed Prior to Opening Penetration & Remained in Place Until Penetration Fire Seal Operable1994-03-18018 March 1994 Special Rept 1-SR-94-002:on 940226,fire Barrier Penetration Between EDG Bldg & Diesel Fuel Oil Day Storage Tank Room Opened.Fire Watch Stationed Prior to Opening Penetration & Remained in Place Until Penetration Fire Seal Operable BSEP-93-0238, Special Rept SR 1-93-013:on 931117,fire Protection LCO A1-93-F0859 Initiated on Fire Seal R1-2-077.Seal Inoperable to Facilitate Overspeed Trip Setting Testing of HPCI & RCIC Sys.Fire Seal Restored on 9312041993-12-22022 December 1993 Special Rept SR 1-93-013:on 931117,fire Protection LCO A1-93-F0859 Initiated on Fire Seal R1-2-077.Seal Inoperable to Facilitate Overspeed Trip Setting Testing of HPCI & RCIC Sys.Fire Seal Restored on 931204 BSEP-93-0011, Special Rept 1-SR-93-001:on 921216,reactor Bldg Fire Detection Sys Declared Inoperable Due to Continuous Spurious Alarming in Ionization Detectors for More than 14 Days. Sensitivity Testing & Cleaning Implemented1993-01-29029 January 1993 Special Rept 1-SR-93-001:on 921216,reactor Bldg Fire Detection Sys Declared Inoperable Due to Continuous Spurious Alarming in Ionization Detectors for More than 14 Days. Sensitivity Testing & Cleaning Implemented BSEP-93-0005, Special Rept 1-SR-93-002:on 930107,both Fire Suppression Sys Fire Pumps Were Made Inoperable to Allow Replacement of Isolation Valve.Personnel Were Stationed to Monitor Diesel Fire Pump Operation1993-01-19019 January 1993 Special Rept 1-SR-93-002:on 930107,both Fire Suppression Sys Fire Pumps Were Made Inoperable to Allow Replacement of Isolation Valve.Personnel Were Stationed to Monitor Diesel Fire Pump Operation BSEP-93-0007, Special Rept 1-SR-93-002:on 930116,both Fire Suppression Sys Fire Pumps Will Be Made Inoperable for Approx 8 H to Allow Replacement of Isolation Valve (2-FP-V79).Personnel Will Be Stationed to Monitor Diesel Fire Pump Operation1993-01-15015 January 1993 Special Rept 1-SR-93-002:on 930116,both Fire Suppression Sys Fire Pumps Will Be Made Inoperable for Approx 8 H to Allow Replacement of Isolation Valve (2-FP-V79).Personnel Will Be Stationed to Monitor Diesel Fire Pump Operation BSEP-93-0003, Special Rept 1-SR-93-002:on 930107 Both Fire Suppression Sys Fire Pumps Will Be Made Inoperable for Approx 8 H to Permit Replacement of Isolation Valve & Associated Instrument Line. Personnel Will Monitor Diesel Fire Pump Operation1993-01-0606 January 1993 Special Rept 1-SR-93-002:on 930107 Both Fire Suppression Sys Fire Pumps Will Be Made Inoperable for Approx 8 H to Permit Replacement of Isolation Valve & Associated Instrument Line. Personnel Will Monitor Diesel Fire Pump Operation BSEP-92-0054, Special Rept 1-SR-92-010:on 921130,makeup Water Treatment Area Sprinkler Sys Declared Inoperable.On 921212,DG Bldg Southwest Switchgear Room Inoperable.On 921216,Unit 1 Air Lock Doors Blocked Open.On 921217,RWCU Barrier Inoperable1993-01-0606 January 1993 Special Rept 1-SR-92-010:on 921130,makeup Water Treatment Area Sprinkler Sys Declared Inoperable.On 921212,DG Bldg Southwest Switchgear Room Inoperable.On 921216,Unit 1 Air Lock Doors Blocked Open.On 921217,RWCU Barrier Inoperable ML20125C5921992-12-0404 December 1992 Special Rept 1-SR-92-009:on 921031,EDG Bldg 23 Elevation Fire Barrier Doors 108 & 120 Declared Inoperable.Doors Did Not Completely Auto Close After Normal pass-through.Repairs Delayed Due to Unavailability of Replacement Doors BSEP-92-0036, Special Rept 1-SR-92-008:on 921007 & 09 EDG Bldg 50 Feet Elevation Fire Barrier Seals DG-3-437,472 & 473 Declared Inoperable,Respectively to Support Plant Mod 92-069.Seals Will Be Restored Prior to Startup of Either Unit1992-11-10010 November 1992 Special Rept 1-SR-92-008:on 921007 & 09 EDG Bldg 50 Feet Elevation Fire Barrier Seals DG-3-437,472 & 473 Declared Inoperable,Respectively to Support Plant Mod 92-069.Seals Will Be Restored Prior to Startup of Either Unit BSEP-92-0026, Special Rept 1-SR-92-007:on 920919,conduit Leading to Seal AO-3-014 on Augmented Offgas 50-ft Elevation Declared Inoperable Due to Corrosion at Floor Penetration.Fire Watch Stationed Until Restoration of Fire Barrier Seal1992-10-21021 October 1992 Special Rept 1-SR-92-007:on 920919,conduit Leading to Seal AO-3-014 on Augmented Offgas 50-ft Elevation Declared Inoperable Due to Corrosion at Floor Penetration.Fire Watch Stationed Until Restoration of Fire Barrier Seal BSEP-92-0025, Special Rept 2-SR-92-008:on 920909,crack Found in Thermo-Lag of Penetration Seal in Control Bldg Cable Spread Room During Review of NRC Bulletin 92-001.Seal Not Restored within 7 Days.Fire Watches Stationed in Affected Areas1992-10-12012 October 1992 Special Rept 2-SR-92-008:on 920909,crack Found in Thermo-Lag of Penetration Seal in Control Bldg Cable Spread Room During Review of NRC Bulletin 92-001.Seal Not Restored within 7 Days.Fire Watches Stationed in Affected Areas BSEP-92-0022, Special Rept 1-SR-92-006:on 920904 & 21,secondary Containment Airlock Doors Both Opened to Support Increased Traffic During Outage & Not Restored within 7 Days.Fire Watch Stationed & Remained in Place Until Barrier Restored1992-10-12012 October 1992 Special Rept 1-SR-92-006:on 920904 & 21,secondary Containment Airlock Doors Both Opened to Support Increased Traffic During Outage & Not Restored within 7 Days.Fire Watch Stationed & Remained in Place Until Barrier Restored BSEP-92-0013, Special Rept 2-SR-92-007:on 920823,fire Door 206 on 50-ft Elevation of EDG Bldg Declared Inoperable.Caused by Fire Door Not Latching Consistently Due to Broken Springs.Latch Repaired & Fire Watch Stationed in Area1992-09-28028 September 1992 Special Rept 2-SR-92-007:on 920823,fire Door 206 on 50-ft Elevation of EDG Bldg Declared Inoperable.Caused by Fire Door Not Latching Consistently Due to Broken Springs.Latch Repaired & Fire Watch Stationed in Area ML20105B2461992-09-14014 September 1992 Special Rept:On 920810,fire Barrier Between Control Bldg Stairwell & 23-ft Elevation Cable Spread Room Declared Inoperable to Support Planned Mod.Hourly Fire Watch Will Remain in Place Pending Restoration of Fire Barrier BSEP-92-0006, Special Rept 2-SR-92-006:on 920729,fire Doors in CR Stairwell Area Declared Inoperable to Perform Plant Mod.On 920731,secondary Containment Airlock Doors Both Opened.Fire Watch Stationed,Pending Restoration of Fire Door1992-09-0303 September 1992 Special Rept 2-SR-92-006:on 920729,fire Doors in CR Stairwell Area Declared Inoperable to Perform Plant Mod.On 920731,secondary Containment Airlock Doors Both Opened.Fire Watch Stationed,Pending Restoration of Fire Door BSEP-92-0002, Special Rept 1-SR-92-004:on 920706,control Bldg Computer Room Fire Door Propped Open & Declared Inoperable.On 920709, Containment Airlock Doors Opened for More than 7 Days.Fire Watch Stationed & Remains in Place Pending Restoration1992-08-12012 August 1992 Special Rept 1-SR-92-004:on 920706,control Bldg Computer Room Fire Door Propped Open & Declared Inoperable.On 920709, Containment Airlock Doors Opened for More than 7 Days.Fire Watch Stationed & Remains in Place Pending Restoration BSEP-92-0005, Special Rept 2-SR-92-005:on 920706,fire Barrier Penetration Seal in Reactor Bldg ECCS Piping Room Declared Inoperable. LCO Expected to Expire Before Repairs Completed.Fire Watch Established & Remains in Place Pending Replacement of Seal1992-08-10010 August 1992 Special Rept 2-SR-92-005:on 920706,fire Barrier Penetration Seal in Reactor Bldg ECCS Piping Room Declared Inoperable. LCO Expected to Expire Before Repairs Completed.Fire Watch Established & Remains in Place Pending Replacement of Seal ML20101R1911992-07-10010 July 1992 Special Rept 2-SR-92-004:on 920603,05 & 06,LCOs Initiated Due to Open Fire Barrier Penetration Seal,Hole in East Wall of Reactor Bldg & Opening of Fire Door 102,respectively.Fire Watches Established & Penetration Seal Restored ML20097D7331992-06-0505 June 1992 Special Rept 2-SR-92-003:on 920507,08,10,12,15,27 & 29 LCO Exceeded Time Estimated for Completion of Work Initiated. Appropriate Fire Watches Established During Stated Times ML20098D8301992-05-22022 May 1992 Special Rept 1-SR-92-002:on 920421,7-day LCO Initiated Due to Fire Door 115 Being Opened to Accommodate Outage Work. on 920430,7-day LCO Initiated Due to Interlock on Fire Door 203 Being Placed Under Clearance to Support Outage Work ML20096E0361992-05-0808 May 1992 Special Rept 2-SR-92-002:on 920324,generated LCO for Radioactive Gaseous Effluent Monitoring Instrumentation Incomplete in That Requirements of TS 3.3.5.3 Not Invoked. Monitor Inoperable for More than 7 Days ML20092M1861992-02-24024 February 1992 Special Rept:On 920113,inoperable Fire Detectors in Zone 14 Identified.Caused by Lack of Replacement Detectors.Work Order Initiated to Repair Detector ML20092M9961992-02-24024 February 1992 Special Rept 1-SR-92-001:on 920109,14-day LCO Initiated Due to Inoperable Fire Detectors in Zone 14.Replacement Detectors Installed on 920207.On 920119 14-day LCO Exceeded Due to Inoperable Fire Detectors in Zone 10 ML20091P4451992-01-27027 January 1992 Special Rept 1-92-001:on 920106,main Turbine Stop Valve Limit Switch Failure Resulted in Inadvertent Primary Electrical Lockout Which Initiated Auto Start Signal to All EDGs ML20086S8281991-12-27027 December 1991 Ro:On 910822,indefinite Primary Containment Isolation Sys TS Limiting Condition for Operation Occurred After Unsuccessful Attempts to Quantify Leakage on-line.Caused by Mfg Flaws in Lower Wedge of Stanchion.Upper & Lower Wedges Replaced ML20091G7021991-12-12012 December 1991 Special Rept:On 911112,14-day LCO on Fire Detection Instrumentation for Reactor Bldg Refuel Floor Expired.Lco Not Cancelled within 14-day Time Period Since Source of Spurious Alarms Could Not Be Determined.Sys to Be Replaced ML20085K5071991-10-25025 October 1991 Special Rept 2-SR-91-003:on 910919,LCO Initiated Due to Removal of North Hatch on ECCS mini-steam Tunnel Roof in Reactor Bldg.On 911004,LCOs Initiated to Open Penetrations. Appropriate Fire Watches Established ML20082P8941991-09-0505 September 1991 Special Rept:On 910722,seismic Monitoring Triaxial time-history Accelograph 2ENV-XT-823-2 Found Inoperable. Preliminary Trouble Shooting Indicated Open Circuit in Connector.Repair Deferred Until Refueling Outage Scheduled ML20077G9491991-06-26026 June 1991 Special Rept 1-SR-91-003:on 910527,7-day Limiting Condition for Operation Exceeded to Repair Latching Mechanism on Fire Door 303 at Penetration Seal R1-3-009.Door Repaired & Fire Watches Maintained BSEP-91-0177, Special Rept 1-SR-91-001:on 910326,limiting Conditions for Operation Initiated Due to Inoperable Fire Doors.Caused by Routine Usage.Fire Doors 207,107 & 214 Repaired & Restored on 910402.Station Fire Watches Were Maintained1991-04-25025 April 1991 Special Rept 1-SR-91-001:on 910326,limiting Conditions for Operation Initiated Due to Inoperable Fire Doors.Caused by Routine Usage.Fire Doors 207,107 & 214 Repaired & Restored on 910402.Station Fire Watches Were Maintained BSEP-91-0020, Special Rept 1-SR-90-005:on 901130,Zone 1 of Svc Water Bldg Fire Detection Sys Declared Inoperable Due to Spurious Alarms on Main Control Room Annunicator.Caused by Defective Pull Station.Fire Detection Panel Replaced1991-01-10010 January 1991 Special Rept 1-SR-90-005:on 901130,Zone 1 of Svc Water Bldg Fire Detection Sys Declared Inoperable Due to Spurious Alarms on Main Control Room Annunicator.Caused by Defective Pull Station.Fire Detection Panel Replaced BSEP-90-0827, Special Rept 1-SR-90-004:on 901121,7-day Time Frame of LCO Exceeded.Caused by Fire Barrier Penetration Seal Out of Svc for Inservice Insp Work.Until Work Completed,Hourly Fire Watch Patrol Will Remain in Effect1990-12-20020 December 1990 Special Rept 1-SR-90-004:on 901121,7-day Time Frame of LCO Exceeded.Caused by Fire Barrier Penetration Seal Out of Svc for Inservice Insp Work.Until Work Completed,Hourly Fire Watch Patrol Will Remain in Effect BSEP-90-0799, Special Rept 1-SR-90-003:on 901016,reactor Bldg Fire Detection Sys Zone 14 Instrumentation Declared Inoperable. Hourly Fire Watch Patrol in Effect1990-11-29029 November 1990 Special Rept 1-SR-90-003:on 901016,reactor Bldg Fire Detection Sys Zone 14 Instrumentation Declared Inoperable. Hourly Fire Watch Patrol in Effect BSEP-90-0782, Special Rept 1-SR-90-002:on 901028,7-day Time Frame of LCO Exceeded for Fire Door 203.Fire Watches Remained Stationed Until LCO Canceled on 9010291990-11-21021 November 1990 Special Rept 1-SR-90-002:on 901028,7-day Time Frame of LCO Exceeded for Fire Door 203.Fire Watches Remained Stationed Until LCO Canceled on 901029 BSEP-89-0766, Special Rept 2-SR-89-003:on 890731,fire Barrier Limiting Condition for Operation Initiated for Door 301 to Permit Frame & Door Replacement to Correct Misalignment & Sticking Problem.Time Frame Exceeded.Restoration Expected by 8909081989-08-15015 August 1989 Special Rept 2-SR-89-003:on 890731,fire Barrier Limiting Condition for Operation Initiated for Door 301 to Permit Frame & Door Replacement to Correct Misalignment & Sticking Problem.Time Frame Exceeded.Restoration Expected by 890908 BSEP-89-0735, Special Rept 2-SR-89-002:on 890717,fire Barrier Limiting Condition for Operation Initiated to Allow Replacement of Door & Door Frame to Correct Misalignment & Sticking Problem.Time Frame Exceeded.Restoration Expected by 8908311989-08-0101 August 1989 Special Rept 2-SR-89-002:on 890717,fire Barrier Limiting Condition for Operation Initiated to Allow Replacement of Door & Door Frame to Correct Misalignment & Sticking Problem.Time Frame Exceeded.Restoration Expected by 890831 BSEP-89-0637, Special Rept 1-SR-89-002:on 890606,fire Barrrier Limiting Condition for Operation Initiated for Fire Door 303 to Permit Replacement of Door & Frame to Correct Misalignment & Sticking1989-06-30030 June 1989 Special Rept 1-SR-89-002:on 890606,fire Barrrier Limiting Condition for Operation Initiated for Fire Door 303 to Permit Replacement of Door & Frame to Correct Misalignment & Sticking BSEP-89-0494, Special Rept 2-SR-89-001:on 890422,limiting Condition for Operation Initiated Due to Two Inoperable Fire Barrier Penetration Seals in Common Augmented Offgas Bldg.On 890429, 7-day Time Frame Exceeded.Work Request Initiated1989-05-24024 May 1989 Special Rept 2-SR-89-001:on 890422,limiting Condition for Operation Initiated Due to Two Inoperable Fire Barrier Penetration Seals in Common Augmented Offgas Bldg.On 890429, 7-day Time Frame Exceeded.Work Request Initiated BSEP-88-1228, Special Rept 1-SR-88-003:on 881120,7-day Time Frame for Limiting Condition for Operation Exceeded.Caused by Fire Door 211 Being out-of-svc to Prevent Wear & Possible Damage to Locking Seals & Interlocks1988-11-28028 November 1988 Special Rept 1-SR-88-003:on 881120,7-day Time Frame for Limiting Condition for Operation Exceeded.Caused by Fire Door 211 Being out-of-svc to Prevent Wear & Possible Damage to Locking Seals & Interlocks BSEP-88-0854, Special Rept 1-SR-88-001:limiting Condition for Operation (LCO) Established on 880405 for Fire Protection Deluge Valve 1-FP-DV-22 to Sprinkler Sys.Specified 14-day Time Frame of LCO Exceeded on 880419.Fire Watches Remain in Effect1988-09-0101 September 1988 Special Rept 1-SR-88-001:limiting Condition for Operation (LCO) Established on 880405 for Fire Protection Deluge Valve 1-FP-DV-22 to Sprinkler Sys.Specified 14-day Time Frame of LCO Exceeded on 880419.Fire Watches Remain in Effect BSEP-88-0850, Special Rept 2-SR-88-002:on 880119,unit Reactor Bldg Fire Detection Sys Zone 14 Instrumentation Declared Inoperable Due to Erroneous Fire Alarms.Limiting Condition for Operation Initiated.Sys Returned to Svc1988-09-0101 September 1988 Special Rept 2-SR-88-002:on 880119,unit Reactor Bldg Fire Detection Sys Zone 14 Instrumentation Declared Inoperable Due to Erroneous Fire Alarms.Limiting Condition for Operation Initiated.Sys Returned to Svc BSEP-88-0853, Followup Special Rept:On 871228,limiting Condition for Operation to Permit Fire Suppression Sprinkler Header from Svc Exceeded.Caused by Unavailability of Addl Flow Switch 2-FP-FS-4059 in Plant Supply Sys.Switch Repaired1988-09-0101 September 1988 Followup Special Rept:On 871228,limiting Condition for Operation to Permit Fire Suppression Sprinkler Header from Svc Exceeded.Caused by Unavailability of Addl Flow Switch 2-FP-FS-4059 in Plant Supply Sys.Switch Repaired BSEP-88-0625, Suppl to Special Rept:On 860307,two Designated Fire Barrier Limiting Conditions for Operation Initiated.Plant Mod Will Be Installed During Upcoming Refueling/Maint Outage to Resolve Subj Differential Pressure Problem1988-06-20020 June 1988 Suppl to Special Rept:On 860307,two Designated Fire Barrier Limiting Conditions for Operation Initiated.Plant Mod Will Be Installed During Upcoming Refueling/Maint Outage to Resolve Subj Differential Pressure Problem BSEP-88-0475, Special Rept 2-SR-88-004:on 880414,14 Day Time Frame Exceeded for Limiting Condition for Operations.Caused by Problems W/Acquisition of Replacement Parts.Repairs Made & Sprinkler Header Returned to Svc1988-05-13013 May 1988 Special Rept 2-SR-88-004:on 880414,14 Day Time Frame Exceeded for Limiting Condition for Operations.Caused by Problems W/Acquisition of Replacement Parts.Repairs Made & Sprinkler Header Returned to Svc BSEP-88-0474, Special Rept 1-SR-88-001:on 880419,14 Days Time Frame of Limiting Condition for Operation (LCO) Exceeded.Caused by Temporary Unavailability of Replacement Parts.Lco Will Remain in Effect Until Repairs Completed1988-05-11011 May 1988 Special Rept 1-SR-88-001:on 880419,14 Days Time Frame of Limiting Condition for Operation (LCO) Exceeded.Caused by Temporary Unavailability of Replacement Parts.Lco Will Remain in Effect Until Repairs Completed BSEP-88-0165, Special Rept:On 880119,reactor Bldg Fire Detection Sys Zone 14 Instrumentation Inoperable Due to Erroneous Fire Alarms.Caused Not Determined.Time Frame of 14 Days of Involved LCO Exceeded on 8802021988-03-0303 March 1988 Special Rept:On 880119,reactor Bldg Fire Detection Sys Zone 14 Instrumentation Inoperable Due to Erroneous Fire Alarms.Caused Not Determined.Time Frame of 14 Days of Involved LCO Exceeded on 880202 BSEP-88-0094, Special Rept 1-SR-88-002:on 880126,limiting Condition for Operation (LCO) Initiated for Fire Door 203 in Reactor Bldg to Permit Opening Door to Help Prevent Wear & Possible Damage to Locking Seals & Interlocks.Lco Exceeded on 8802021988-02-10010 February 1988 Special Rept 1-SR-88-002:on 880126,limiting Condition for Operation (LCO) Initiated for Fire Door 203 in Reactor Bldg to Permit Opening Door to Help Prevent Wear & Possible Damage to Locking Seals & Interlocks.Lco Exceeded on 880202 BSEP-88-0037, Special Rept 2-SR-88-001:on 880110,7-day Time Frame of Fire Barrier Limiting Condition for Operation for Fire Door 203 Exceeded.Fire Watches Established & Will Be Maintained During Remainder of Refueling/Maint Outage1988-01-19019 January 1988 Special Rept 2-SR-88-001:on 880110,7-day Time Frame of Fire Barrier Limiting Condition for Operation for Fire Door 203 Exceeded.Fire Watches Established & Will Be Maintained During Remainder of Refueling/Maint Outage BSEP-87-1095, Ro:On 870119,one of Four Fuel Loading Chambers Not in Location Where hands-on Inventory Could Be Performed at Site.Chamber Declared Loss Following Investigation.Chamber Was Probably Inadvertently Shipped to Burial Facility1987-09-25025 September 1987 Ro:On 870119,one of Four Fuel Loading Chambers Not in Location Where hands-on Inventory Could Be Performed at Site.Chamber Declared Loss Following Investigation.Chamber Was Probably Inadvertently Shipped to Burial Facility 1998-10-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217N3271999-10-21021 October 1999 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
[Table view] |
Text
e , <
Carolina Power & Light Company x.. .. ; a -, . . , . . , -
Brunswick Steam Elcetric Plant P. O. Box 458 Southport, N. C. 28461 January 3, 1980 FILE: B3516.2 SERIAL: 3SEP/80-12 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Co= mission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 BRUNSWICK STEAM ELECTRIC PLANT, UNIT NO. 2 LICENSE NO. DPR-62 DOCKET NO. 50-324 SPECIAL REPORT PER TECHNICAL SPECIFICATIONS 6.9.2c
Dear Mr. O'Reilly:
At 0855 on November 19, 1979, Unit No. 2 scrammed following approximately two months of high power operation. During the subsequent startup, the reactor scrammed again at 0425 on Nove=ber 20, 1979. Coolant iodine activity, already increasing after the first scram, exceeded the Technical Specification limit of 0.2 pC1/gm I131 , dose equivalent. The maximum iodine activity was 0.414 pC1/gm.
Reactor po'wer was held to < 10% until the iodine activity returned within specifications. High coolant activity was caused by the two reactor scrams and subsequent increase in fission product inventory in the coolant coming from a leaking fuel element. The Unit No. 2 fuel bundles will be sipped during the next refueling cutage and the leaking bundles removed from the core. This event was reported on December 6, 1979, with LER 2-79-99.
Very truly yours, 4 Nh - .
. A. C. To111 son, Jr., General Manager Brunswick Steam Electric Plant JLK/RMP/bd Encfosures 90017239 cc: Mr. R. A. Hartfield 9 yMr. V. Stello 007 8001140 } 4
%. U N IT 4: 1 XEACTCR fWE R cnd CLE A N-Up Ftow Hss7eg.y at.aj.... . . . . . . . . . . . ..p.._, .
...y.._.. 3._.
...r... . . . . . . _ . . . . . . . . . . . . .t.-_..
7
. .a, ....
-.....a.- .a.._.
. . .J,.._._.
.+.._.. ._..._....._n ..
. +. .
..p 3 ,
. _.._. ? y~[iff I
_.. .n._ . ;7
...-_-.._,..i_..._.
_.u . : . - . _.4_.
g .
m Q '~ ' g
...L y (3
~7 y p . , . . _ . _ _
__._..p._._. , _ . 7 7.. .._ p ___ __ ._,.._.
_.__r... ~r-----1 --+ - - - - - - - - - - -. '- -
n --
+., .4 .,_ ! ~~. } . .. . . i
_e.+
_ -! ,~T I
i
. t' .>_-....'-_.---.7. - ,i
,, l {-- ; j .-._.}
i a
-t...._-.
_ 7. . . . ._ .
- ._
- e__. i...}
l
- p. w
- _ _ _ . h
. _ . . _ . . . 7_;- . _ .
9
, 7.~
r ~4, -
i
- ~ * - - f i--'-----* "- T*'--*- !
7__._ _y. _.
j_._.~.-_.4_-.-_ 4_-____,.
i i.- '
I e I a !
-J4 y- l
% { _. !
y_ -. .. . . ~ l'
-_. . +h _ _ r 3
r .
-3, _ +. . .__ ;
_4 4_ _ _
2 ! 4- _ . . .. ._ i.-- t 0 ' ' ; _-.___..
E M _ f' %- -
a
_. . p _ .
f_ .._w
' _r
. . .-. . . _ - ~
o g
i.._____.,.
1
.u_..._._-...__L .
_._-___._r_---_._.__ , .
g3 . g _._. ,__p ._.. ---- .-,--..- .
7 p, K 0 .
U* _. d - _. ! .
DW
. _ ~ .
a>kPd ,_
g -.
.,__ .._t I
_q _.
p...__
v_ .
,T 10 0 j l ._._ 1 3
' .t
[- .
l _ _ .
__4__
i
.q .
, } { -
1 l ! ! .I _ ___. ! .- .
p p ; ___p .._. _ .1 -
p .. ,
p._._ , g
, , _._.._._p__.._._. --.g O
, , 2
, f
- L }_._.._m,._... _.
.y v3
' 9 4_ % .-.4 . - - _ _ . ... O
, ._ q , j . ; j - _ . . ...
.d
..... ._._q...-.._. . a g 2 -
_ _ _ . . _ _ _ _ . . . *lW E
'f- f j .
r i ~....
' ._._7_...
L f - --__. , _ _ -
I v, _.
h .
,_..-,--..{
.._4. .
{ _ s m i 42 10 0 - , - - ,
2u . * ~ - * --y -- - ~ - - - -
az 7
1 -- . . - _ . _ _ ,
H l _ . . . . .
t
.7
~ ' * ~ " ~ - ~
22,, -. f y_ -
y--
- ,. ~.~..
-a pa [
me L i 7
. 6 4 _ _ . . . ., __1..
y- l - _.~. _ j ._7. . p . . _ __ _ .
ep g n
.s . .
.__ _p ._ . _. _ . . . _ . .
_I . _ , _ _ . __. . . _ .. .. __... J,
,,, Q C,
_ . _ _ - L 1 ._
H . . . . . .
fMTN . _ . . .._.
.q - . . .
- Eo g ~ _ . _ ,
,g g j_ . _.____._.7 __ __ y
_ _ +
-7__
}
o , _7
_. l
_4
,I--
_.}_+
n-
_ { .
p.
_-._e a ._.
_ -. q
.. g -
..t
( - . . _ . _.
.._..._...(_...__.
i I i
~_ . _- .
r O .._._____._L.-...;-_.-_._{...._..'6 "
, y _
_.i 4- - .4 p.~*"- ~_ i oOO-g_..p3 9 . g . . -- -. %
9 I iO
,_ i
_ _- t_-___---*
1
. g -_ . . pggg._._.J4yHs._..o
_._.o- _.
at'
, (gj
.__.L.- t , C- - - -- ig.- ...'._ w, H H .H,~. ~ . f_._.- t, _. . ._- . - ' N
..t_,_. . . ., ----F-- .
, . . _h l
2 3. . .._. . ...__L...4 ,
.. ~. _ ,,e ~ _ _ . . _ . , , - _
4_ ! --. *
.ip .
. . rga g[ . _.. __ . . -_ . 1 -. i . i .. _ .. . .1, 4 1 g(--r,s ee
...._..a..f. oA ;a
- . . _ . . . . . . . . . t
. .i....
. . ...j .
] p. g . p, ;. ?
r, J.
_ . . . t. .- .
,, , , , _.....-4-. _. . . l
.} -.
s, . . ..
j _+ e ..
nr u
.. ...q g
. [A g y
..d,..-.
. . i _. y .. ..,,,.. ._2 -.. ._._,.,. ._... . ,- ..
_ . . . .., . 9 bes/ . . _ . . .5 *
, . . . . . . . . . _ . . ., .'. 4 . . . . ,
... .L. .. , ...+4.. .-- . . . . . , . . a. j .. .. , -. .t .,. . _. . . . .
. . [ i . l
? . .
, ,. 4 .
- /g ohg ooos ud ooon H /x ooon nh ooon Hb ooos coos
'j- h0AE REPAE3ENTI4Tsou -
\
a w- , g 0 88g l
s2 l l .
So I i l . . ,
l-- i ,i-
. 'a -- -
i 48 , i ! -l
. 44 ,
t I i l I t
_, 1 .I I
i 42 I I I i 1
.a
_i _
i-_
i i i i Ii' __
L l
. 3a l .I i i i l l l l ! l
. 36 l "l l l l l j ). --
l }
24 - l l 1: l 1 i i l l 32 l j l l l l l ; l l 2- 1 l l } 1 1 I ,
I i i l l 2s
~~
l 1 l l l1 1 21 13 14 ts: 16l 17 l- i 2s l i , i I l i i t , I
(
6 C.' 24 i i ! i. l l
.I l 22 l l l l
1 i l I )
.M i I
' I I I .j_
l
. _d i I i !
[ ; i se i I i l i 1 I 16 I l h l l l l { l' 'l _ i 14 _
l l l l l I [ i i
12 I i- l; i 1 Ji - - = ._
l- l _
1 to '
I I l l l l i1- i i i i i i i
i i
~'~
02 - j j-
,u n
1 i l l 1 01 03 05 07 00 11 13 15 17 19 21 23 :S 27 29 31 33 35 37 39 41 43 45 47 49 51 ENCLOSURE 2 ', .
q,c ,, , ,
U . .
RMos 900i7241
. qona .
k
ORE bA>J- U P OY SINGS
._DMD
~
O
'P O d
Wyr d
,J 3
l l
Pt:t.Pi r P :' EXPO?UPC N S iv 190 ll/8I7_9 D O_kff.
~
' f ib !
2 3 4 5 6 7 AVE j RNG 1 hghr ! ut 3096. 5319. 4471.
g _f 12 4817. 4247. 5262. 44 f:2. 4Sb5. C4 4' 11 RH2. 7 57'/ . 9430. 804/. 30 E 5563. 9359 ??'JT . l "I' O'i . 50r10. 7172- 11919 inpE.NcfTf.
- l Tatt24rd "n 1'?/a. o99". C??6 -
9 12667. 10440. 1010/. 1'370. 110'/2. ~742. 12L55. 'OM2.OM"?P l C 13346. 10070. I'Ji?O. 1200L 12147. ? 30. 10219. 11619. h F M 7 ' 9 ". /. ? t '.* ? c a _ d '. ' '. 4 ': C900_ ' W O_ ' d f' 1 ' t j '.t t. d i, 1-in??
M E,,,,_ l 6 11373. 11660. 14667. 1 'c? 61. 12372. ?S35. 10'/84. !2405.
?COS. 14180. 1263'l . S hou Tbn l U 14660. 11921, 14907. 13240. 13064.
.. 15a1A. 1;h inrAy_ d -" :r A 'a700 o?' ' . 14:e? i ? c'?
3 15188. 12673. l'1370. 13697. G00. 9400. 146/2. 'i210'5.
2 13697. 11709. 14047. 126L9. 12S12. 8473. 13305. 11 % .
, 1 en4( . en?e 3n e r .'. OnSO. 'nco . w o'. m e "- .h*gg h AVE 12253. 10180. 12692. 11130. 11146. 7547. 12093 d
2 5RE S'+ ' * ' "' * "' '" r ' " C T ' ~ ~ "'D
- 8 8/ %l'79 tsgg gyg t
2 3 4 5 6 7 AVE TJG 1 tVt.
4415, 5431. 4042. 4638. 3193. 5375. h534. Top of Core.,
$lMng 12 4994 9259. 7357. 9711, 8308. 8324. 57h5. 0459. 8150.
g 11 10-12119 r102 35. 12579-10940--10803. 7fr19r119ttfr10403. O'r#J & map N.M 9 130h0. 10005. 13464. 11717. 11710. 8010. 12701. 11249.
P.523. 1337S, 11397, iw m@s e41 8 13724. 11237. 14154. 12h18. 12483.
7 13973r11381ritd82-12629r12787. ;695 r1355G r12005. gwof -
6 14732. 12012, 15011. 132?7. 13h36. 9169. 14162. 12703.
5 15093, 122Gl. 15243, 135P3. 13737. 9356. 143C9. 12938. -S her+ Ton i 1535 ?r12M 3r15 C 00r13 '122 -1*;09 CMG06r14 C 53-23253.
3 15516. 13011. 15003. 14031. 14304. 9783, 14 G71. 13454.
2 14011. 12734. IhCCh. 12976, 12S70 3818. 13403. 12240.
-i 9254. 9377--10018. J 3 51.- 3279. 5592. :7, 75. 335 r 6.How of -Core.
.WE 12582. 10l,99. 13005. 11!. 3 3. 11460. 7027. 12244.(1m>2z.] ,
.90017242 ENCLOSURE 2
\
OFF-GAS ANALYSES
~
Prior to the incident, the following Unit 2 Steam Jet Air Ejector (SJAE) off-gas levels were measured:
DATE. REACTOR OFF-GAS POWER (%) uci/sec at SJAE 11/ 2/79 91.4 16,666 11/.9/79 90.8 16,316 11/16/79 93.2 17,700 During the incident, the reactor was either sub-critical.or at <10% power;-
consequently, off-gas levels were quite low during this time period
(<1000uct/sec.). After returning to power operation, an off-gas analysis was performed on Unit 2:
DATE REACTOR OFF-GAS POWER (%) uci/sec at SJAE 11/26/79 95.3 24,396 All of these off-gas levels are within the applicable Technical Specifica-tion limits.
90017243
+_
Enclosure 3
Unsr 2 REne roa- cootanr zoo,na Arantisus r*30 DATE TenE ITj Ci/mi) I%Ci/ [ IhG3=l[ Th(4b8) NYm(eo#o7,I(e 1 9N -
E ilco onas 3.7a6 E af I.Goq E.3 1299E-3 1372 E-3 7. S c 1 E tj ggc2 g sj
- #/a7 osoy Q.395'E *J f.??2 E-3 9 044E */ 2-r 49 E-3 7.aa4 E-9 4.tSq E-y e e /# 9 33 o f.oo7 E-x a456 E-3 9.fso E-3 4liOA 3.fs5 E-3 1.296 E-R.
II/ao oa55 3 5o9 E-2. 1.458 E-3 f.496 E-1 */.857E-6 2.oso E-3 a.9 4 */ E - 2, 11 f tlao o925 1834 E-l 183o E-3 3 99& E-A 4 f10 A 4 Nog 124g E- g It lao 1340 1479 E-8 al.142 E-3 al.699 E-1 < ItD A Q.89G E 'S I.sti E- g Illao 1655 & l.809 E-I 7 959 E-3 533fE-R <!40D 3 998 E-3 f.91a E- I IIlao n965 3.993 E- l 3 309 E 'k I.186 E-I 4 non S. osse-s si.I35 s-I 80 lao 3330 3.999 E-g 3.o39 g x I.189 E-t < HDD H.G e *lE-% 4 !4o E-I 18/af 023o a.9a3 E-I F-Tao E-3 3 661E-2 < NDa 3 99F E-3 3.869 E-( ,
is l'At osaf 2.o99 g- 3 7.6*/6 E -3 S.33oE a 8 GG# E-4 1. tao E-3 2.aSi E-I illat 09so 1.ala5 E-g E.ota E-2. 3.'b3S E-K < h 0A 4.888 E ~ 4 l-Saa E- I 3 fan so3o I.f 98 E-I f.'a8G E-2. 3.28o E-2 4 NDA S.44GE-9 l-a91 E-l w
o 8813.1 sMaso 9 419 E-g 7 8coE-3 a.o* 8 E-x S.III E-9 sl. 3 4 9 E ai 1 000 E-I o
DIlai asn4S 2.3G9 g-x I.OG8 2-3 Al.'kIS E-3 L'.259 5 4 a.609 E-9 3.stg7 E-x
, N j ii/aA 02o5 1. f a3 E-R F 382 E 3/ 2.oata. E-3 3.073 E-3 3 349 E 2/ 1 8FS E-2.
A :ala6 14 oo I.956 E-c, 1 473 E-3 6 534 E-'i 2.30o E-3 S 254 E 41 2.o23 E-3 it/wM ooso 1992.E-3 #.0F3 E-3 6.085E-4 l Gar E-3 S.l?9 E-9 2.23o E-3
" TOTA 1. ~TrME IN EXCESS OP o.ap(i/ m. 9 I-131 A>se EGutVALEeJT - 13,3 ffgs, ,
4 -. I" Reac4er Scram occurred af- ~ 02SS on 88h9179 44- a"* Reac4or Scra m occurred a f- 04as ow. # # /ao/>y9 ENCLOSURE 4 s s