Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20087L5711976-02-0202 February 1976 AO 76-3:during Refueling Outage from 751116-760108,nine Valves Exhibited Leak Rate in Excess of 2000 Cc/Minute. Caused by Loose Body to Bonnet Joint.Bolting Tightened ML19312C2161976-01-0707 January 1976 Abnormal Occurrence AO-269/75-15:on 751219,borated Water Storage Tank Level Indication Failed.Caused by Failure of Trace Heating to Level Instrumentation Air Lines.Station Mod Initiated to Provide Power for Heat Tracing ML19312C2011975-12-11011 December 1975 Abnormal Occurrence AO-269/75-14:on 751127,tritium Released in Excess of Allowable Limits.Caused by Personnel Misreading Max Release Rate Recommendations.Personnel Advised of Extreme Care Necessary When Interpreting Operations Info ML19312C1971975-11-21021 November 1975 Abnormal Occurrence Rept AO-269/75-13:on 751108,Keowee Hydro Unit 1 Failed to Autostart.Caused by Electrical Malfunction of Breaker.Malfunctioning Generator Supply Breaker Removed, Cleaned & Repaired.Keowee Unit 2 Tested & Returned to Svc ML19317F0601975-11-10010 November 1975 AO-287/75-12:on 751028,reactor Bldg Air Sampling Line Inlet Valve 3PR-7 Failed to Close During Engineered Safeguards Actuation Testing.Caused by Personnel Error.Breaker Closed & Valve Tested for Operability ML19317D9851975-10-21021 October 1975 Abnormal Occurrence Rept AO-269/75-12:on 751007,borated Water Storage Tank Drained to Spent Fuel Pool.Caused by Operator Error.Operator Counseled Re Proper Procedure ML19312C8641975-10-20020 October 1975 AO-270/75-20:on 751006,temp Detector in Reactor Protective Sys Channel a Failed.Caused by Faulty Resistance Temp Detector.Resistance Temp Detector to Be Replaced Next Shutdown.Channel a Returned to Svc 751201 ML19312C9391975-10-17017 October 1975 AO-270/75-19:on 751017,pipe Connecting Unit 2 Component Drain Pump Discharge Header to Turbine Bldg Trench Leading to Units 1 & 2 Turbine Bldg Sump Found Leaking.Caused by Incorrect Installation of Line Discharging to Sump ML19316A6171975-09-0808 September 1975 AO-270/75-17:on 750824,component Cooling Sys Activity Increased.Caused by Letdown Cooler a Leak.Letdown Cooler a Removed from Svc & Repairs in Progress.Redundant Cooler Placed in Svc ML19312C8511975-09-0808 September 1975 AO-270/75-18:on 750825,loss of Required Overlap Between Operating Control Rod Groups.Caused by Dropping Group 7 Rods & Withdrawing Group 6.Power Supplies Examined & No Problems Identified.Required Overlap Immediately re-established ML19316A4111975-08-25025 August 1975 Abnormal Occurrence Rept AO-269/75-11:on 750811,backup Emergency Power Source Improperly Removed from Svc for Charge.Caused by Personnel Error.Situation Discussed W/Superintendent Re Need for Shift Supervisor Approval ML19316A5931975-08-22022 August 1975 AO-270/75-16:on 750808,operable Bldg Spray Train Not Provided During Startup.Caused by Personnel Error.Control Operator Relied on Out of Normal Checklist.Deficiencies in Personnel Performance Pointed Out.Startup Procedure Changed ML19317F1711975-08-21021 August 1975 Abnormal Occurrence Rept AO-287/75-11:on 750807,Control Rod Drive Breaker 10 Failed to Trip.Caused by Breaker Maladjustment.Break Cleaned,Lubricated & Adjusted ML19316A5881975-08-19019 August 1975 AO-270/75-15:on 750805,trip Point Decrease Noted.Caused by Faulty Amplifier in Channel D Power Imbalance Circuit. Channel D Remains in Manual Bypass Until Amplifier Replaced. Surveillance Program Adequate ML19316A5821975-08-11011 August 1975 AO-270/75-13:on 750728,string of Keowee & Switching Station Batteries Simultaneously Removed from Svc.Caused by Operator Error.Charging Procedure for Battery Sys Revised to Require Control Operation Confirmation Prior to Charging ML19317F2351975-07-25025 July 1975 AO-287/75-09 on 750713,power Level Cutoff Exceeded During Transient Xenon Condition.Caused by Failed Module within Turbine Bypass Valve Controls.Turbine Bypass Valve Control Section Replaced & Functional Check Performed ML19317F0541975-07-25025 July 1975 AO-287/75-10:on 750714,during Instrument Surveillance Test Both Level Tramsmitters for Borated Water Storage Tank Discovered Out of Calibr by Greater than Calibr Tolerance. Caused by Incorrect Initial Calibr ML19312C2091975-07-18018 July 1975 Abnormal Occurrence Rept AO-269/75-09:on 750708,effluent Discharge Isolation Valve LWD-132 Failed to Close During Source Check.Caused by Differential Pressure Created by Condensate Monitor Pump Lifting Valve Off Seat ML19312C1881975-07-18018 July 1975 Abnormal Occurrence Rept AO-269/75-08:on 750704,while Keowee Hydro Unit 1 Inoperable,Emergency Power Sources Not Provided.Caused by Dispatcher Error.Keowee Unit 2 Returned to Svc & Tested.Lee Combustion Turbine Utilized ML19312C1911975-07-0909 July 1975 AO-269/75-07:on 750624,leak Detected in Reactor Coolant Letdown Line Relief Valve HP-43.Caused by Lifting of Line Relief Valve.Limit Switch on Valve 2HP-12 Replaced & Limit Switch Location Being Changed to Prevent Recurrence ML19317F0831975-07-0303 July 1975 AO-287/75-08:on 750619,reactor Bldg Engineered Safeguards Pressure Transmitter Was Discovered Out of Calibr.Caused by Drift of Pressure Transmitter.Channel C of Pressure Transmitter Recalibr.Surveillance Will Continue ML19317F0421975-06-27027 June 1975 AO-287/75-07:on 750613,excessive RCS Cooldown Rate Occurred During Maint Shutdown.Caused by Operator Error.Evaluation Performed to Determine Max Allowable Cooldown Rate.Valve 3RC-66 Removed,Repaired & Replaced ML19312C1791975-06-12012 June 1975 Abnormal Occurrence Rept AO-269/75-06:on 750528,reactor Bldg High Pressure Trip Switch Setpoints Found Set Improperly. Caused by Omission from Sys Recalibr.Switches Reset & Instrument Procedures Revised ML19317D8721975-05-20020 May 1975 Abnormal Occurrence Rept AO-269/75-05:on 750506,during Liquid Waste Release,Process Radiation monitor,RIA-33, Failed.Caused by Water Leaking from Gasket Into Detector Junction Box.Box Repaired & Gasket Replaced ML19317D8651975-05-14014 May 1975 Abnormal Occurrence Rept AO-269/75-04:on 750430,during Emergency Start Test,Keowee Unit 1 Tripped Due to Low Thrust Bearing Oil Level Signal.Caused by Instability in Control Sys for Keowee Unit 2 While Operating in Unloaded Condition ML19317F2251975-04-11011 April 1975 AO-287/75-06:on 750327,inadvertent Isolation of Keowee Underground Feeder Occurred During Emergency Start Test. Caused by Deficiency in Test Procedure.Test Procedure Modified to Assure Breaker Is Closed at All Times ML19317D8481975-04-10010 April 1975 Abnormal Occurrence Rept 269/75-03:on 750326,B&W Informed Util of Defects in Fuel Rod of Spent Fuel Assembly 1A10.No Safety Hazard.Diagram of Defects Encl ML19317F4181975-03-12012 March 1975 AO-287/75-04:on 750226,engineered Safeguards Logic Buffer Failed.Caused by Intermittent Failure of Mercury Whetted Relay Contacts on Logic Buffer Analog Channel 1 Output. Buffer Replaced.Surveillance Program Adequate ML20087K9381975-03-0808 March 1975 AO 50-266/75-4:on 750226,air Ejector Discharge Gas Monitor R15 Pegged High,Then Dropped Low.Operator Manually Secured RCS Letdown & Went to Auxiliary Bldg to Assist in Locating Suspected Leak ML19317F3641975-02-24024 February 1975 AO-287/75-03:on 750209 Proper Overlap Between Control Rod Groups 6 & 7 Not Provided.Caused by Failure to Monitor Individual Rod Positions Necessitated by Faulty Indication Switch.Potential Sequence Problems Reviewed W/Personnel ML19317F1271975-02-18018 February 1975 AO-287/75-01 on 750203,reaction Protective Sys Channel C Indicated Low Reactor Coolant Temp.Caused by Steam Leaking from Feedwater Valve in Penetration Room & Condensing on Resistance Temp Detector.Penetration Room Purged ML20087L0911975-02-18018 February 1975 AO 75-3:on 750208,mechanical Latching Mechanism on Redundant Solenoid Trip Vent Valve 2018C on Main Steam Stop Valve a Failed to Unlatch When Solenoid Deenergized.Caused by Improper Rotation of Rollers as Designed ML19317F2431975-02-0909 February 1975 AO-287/75-02:on 750205,during Maint Shutdown,Unsuccessful Attempts to Open Valve 3LP-18 Revealed Fuse Failure in Control Power Transformer.Caused by Either Voltage Surge or Defective Fuse.Blown Fuse Replaced ML20087L2091975-01-28028 January 1975 AO 75-1:on 750120,first of 4 Tanks of Sludge Lancing Waste Sampled & Iodine Levels Found Approx 9 Times Max Permissable Concentration.Caused by Fuel Cladding Leaks Plus Small primary-to-secondary Leak in Steam Generator a ML19317D9321975-01-21021 January 1975 Abnormal Occurrence Rept 269/75-01:on 750107,Channel a Reactor Coolant Pressure Buffer Amplifier Did Not Respond to Input.Caused by Faulty Operational Amplifier.Component Replaced ML19317F0931974-12-26026 December 1974 AO-287/74-11:on 741210,failure to Monitor Reactor Quadrant Power Tilt Occurred During 40% Power Physics Testing.Caused by Operator Error.Operations Supervisors Instructed in Measurement of Quadrant Power Tilt ML19317F0891974-12-0404 December 1974 AO-287/74-10:on 741119,ac Vital Instrumentation Bus Energized from Improper Source.Caused by Personnel Error. Inverter Replaced by Use of Regulated Ac Source. Interpretation of Tech Spec Reviewed W/Operating Personnel ML19317F0281974-11-29029 November 1974 AO-287/74-09:on 741114,personnel Hatch Gasket Failed During Hatch Leak Rate Test.Caused by Knife Edge of Door Off Center of Gasket.Hatch Inner Door Repaired & Hatch Successfully Completed Requirements for Leak Test ML19317F0191974-11-29029 November 1974 AO-287/74-08:on 741114,reactor Protective Sys Bistable Failed Following Flux Trip Setpoint Change.Cause Not Stated.High Flux Bistable Replaced & Proper Operation Verified ML20087L2661974-11-22022 November 1974 Ao:On 741009,while Personnel Exiting Containment Via 66 Ft Level Personnel Airlock,Air Heard Escaping Following Closing of Inner Door.Caused by Open 3/8-inch Valve on Pressure Gauge Instrument Line.Valve Removed.Served No Purpose ML19317F1031974-11-14014 November 1974 AO-287/74-07:on 741102,Channel a Pressure Transmitter, RC3A-PT1,found Out of Calibr.Caused by Drift in High Pressure Trip Setpoint.Pressure Transmitter Recalibr to Require Specs:Will Be Checked on Monthly Basis ML19317F1631974-11-12012 November 1974 AO-287/74-06:on 741029,leak in LPIS Piping in Decay Heat Removal Room Discovered.Caused by Failure of Piping Due to Low Pressure Injection Discharge Header Vibration.Sample Line Repaired & Vibration Coil Added ML19317F0681974-11-0707 November 1974 AO-287/74-05:on 741024,core Flood Discharge valve,3CF-1, Electrical Breaker Discovered Open & Tagged W/Padlock in Place But Not Locked.Caused by Personnel Error.Padlocks Now Rechecked After Locking ML19317D8831974-10-25025 October 1974 Abnormal Occurrence AO-269/74-17:on 741012,room Containing Low Pressure Injection Pumps 1B & 2B Flooded.Caused by Open Drain Valves.Evaluation of Sump Pump Reliability to Be Performed.Sump Pump Monitoring Alarm to Be Installed ML19308B0591974-10-23023 October 1974 Abnormal Occurrence AO-269/74-05:on 741008,RCS Letdown Flow to a Bleed Holdup Tank Caused Increased Vent Header Pressure.Caused by Operation of Gas Compressors During Performance of Mod Work.Control Operator Stopped RCS Flow ML19317D9351974-10-23023 October 1974 AO-269/74-16:on 741008,contents of a Gaseous Waste Decay Tank Released to Auxiliary Bldg During Increased Vent Header Pressure.Caused by Operation of a Gaseous Waste Compressor & B Gaseous Waste Decay Tank During Release ML19317F0801974-10-22022 October 1974 AO-287/74-04:on 741007,flow Instrumentation Indicated RCS Flow Imbalance.Cause Unknown.Reactor Operations at Full Flow Limited to Sys Flows Not Exceeding Core Life Valve & Restricted to Power Levels Less than 80% of Full Power ML19317D8281974-10-22022 October 1974 Abnormal Occurrence Rept AO-269/74-15:on 741007,core Flood Tank Pressure Not Increased Prior to Increasing RCS Pressure.Caused by Omission of Procedural Step.Checkoff for Procedure OP/1/A/1102/01 Revised ML19308A7301974-10-18018 October 1974 Supplemental Abnormal Occurrence Rept AO-269/74-12A Re Event on 740806.Describes Further Tests Performed 740819-0901 to Determine Cause of Low Boron Concentration.No Mechanism Identified for Cause of Dilution in Incore Flood Tank ML19317D9201974-10-18018 October 1974 Revised Abnormal Occurrence Rept AO-269/74-14:on 741005,4 Gallon Per Minute Reactor Coolant Leak Found.Caused by Leaking Diaphragm in Pressure Switch 1PS-364.Switch Isolated & Removed,Piping Capped 1976-02-02
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARNPL-99-0569, Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with ML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 NPL-99-0051, Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with NPL-99-0449, Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with ML20196J4251999-06-30030 June 1999 Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 ML20209D2691999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbnps,Units 1 & 2 ML20196F3341999-06-22022 June 1999 Safety Evaluation for Implementation of 422V+ Fuel Assemblies at Pbnp Units 1 & 2 ML20195F9781999-06-10010 June 1999 Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1 NPL-99-0328, Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with ML20209D2751999-05-31031 May 1999 Revised MORs for May 1999 for Pbnps,Units 1 & 2 ML20196F3521999-04-30030 April 1999 Non-proprietary WCAP-14788, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt - NSSS Power) NPL-99-0273, Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With NPL-99-0193, Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with NPL-99-0134, Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with ML20207D6751999-02-22022 February 1999 Assessment of Design Info on Piping Restraints for Point Beach Nuclear Plant,Units 1 & 2.Staff Concludes That Licensee Unable to Retrieve Original Analyses That May Have Been Performed to Justify Removal of Shim Collars ML20206R9001999-01-13013 January 1999 SER Accepting Nuclear Quality Assurance Program Changes for Point Beach Nuclear Plant,Units 1 & 2 ML20206P1501999-01-0505 January 1999 LER 98-S03-00:on 981207,security Officer Discovered Uncontrolled Safeguards Info Drawing.Caused by Failure to Follow Established Procedures & Policies.Drawing Was Controlled by Site Security.With ML20216F9931998-12-31031 December 1998 Piedmont Municipal Power Agency 1998 Annual Rept NPL-99-0008, Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with NPL-99-0091, 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with1998-12-31031 December 1998 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with ML20198E6381998-12-17017 December 1998 LER 98-S02-00:on 981130,security Access Was Revoked Due to Falsification of Criminal Record.Individual Was Escorted from Protected Area & Unescorted Access Was Restricted. with ML20198C7671998-12-10010 December 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME BPV Code,1986 Edition,Section XI Requirement IWA-2232, to Use Performance Demonstration Initiative Program During RPV Third 10-yr ISI for Plant,Unit 2 NPL-98-1006, Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20195J5101998-11-16016 November 1998 Proposed Revs to Section 1.3 of FSAR for Pbnp QA Program ML20198J5941998-11-0303 November 1998 1998 Graded Exercise,Conducted on 981103 NPL-98-0948, Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With NPL-98-0880, Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored1998-10-21021 October 1998 Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored ML20154M9121998-10-14014 October 1998 Unit 1 Refueling 24 Repair/Replacement Summary Rept for Form NIS-2 ML20154L6751998-10-14014 October 1998 Unit 1 Refueling 24 ISI Summary Rept for Form NIS-1 ML20153G4601998-09-30030 September 1998 USI A-46 Seismic Evaluation Rept, Vols 1-2 NPL-98-0826, Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML17354B0971998-09-0909 September 1998 Part 21 Rept Re Possible Machining Defect in Certain One Inch Stainless Steel Swagelok Front Ferrules,Part Number SS-1613-1.Caused by Tubing Slipping Out of Fitting at Three Times Working Pressure of Tubing.Notified Affected Utils ML15261A4681998-09-0404 September 1998 Safety Evaluation Supporting Amends 232,232 & 231 to Licenses DPR-38,DPR-47 & DPR-55,respectively ML20151W3851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbnp Units 1 & 2 ML20151W4541998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 1 ML20151W4471998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 2 NPL-98-0653, Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20236Q3161998-07-10010 July 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements PTP-3-01 & PTP-3-02 ML20236L6771998-07-0707 July 1998 Safety Evaluation Approving Wepco Implementation Program to Resolve USI A-46 at Point Beach NPP Units 1 & 2 ML20151W4261998-06-30030 June 1998 Corrected Page to MOR for June 1998 for Pbnp Unit 2 NPL-98-0558, Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 2 ML20248F7441998-05-31031 May 1998 Reactor Vessel Working Group,Response to RAI Regarding Reactor Pressure Vessel Integrity ML20151W4221998-05-31031 May 1998 Corrected Page to MOR for May 1998 for Pbnp Unit 2 NPL-98-0481, Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4011998-04-30030 April 1998 Corrected Page to MOR for April 1998 for Pbnp Unit 2 NPL-98-0356, Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20217F3131998-04-17017 April 1998 Safety Evaluation Accepting Proposed Alternative to ASME Code for Surface Exam of Nonstructural Seal Welds,For Plant, Unit 1 ML20216D7071998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3981998-03-31031 March 1998 Corrected Page to MOR for March for Pbnp Unit 2 NPL-98-0209, Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable1998-03-30030 March 1998 Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable 1999-09-30
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