Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20084N6461977-03-31031 March 1977 Followup AO 50-249/75-44A:on 751125,offgas Activity Increased.Ge Insp Revealed Major Defect in Fuel Assembly DD-418.Assembly Removed from Reactor ML20084K4981976-10-0505 October 1976 Updates AOs 50-265/74-3,50-265/74-13,50-265/74-16 & 50-265/74-19 Re low-low Reactor Water Level Switch LIS-2-263-728 Failure.Surveillance Interval Changed to Monthly.Switch Installation Delayed Pending Analog Trip Sys ML20084E3631976-06-29029 June 1976 Supplemental AO 50-237/75-11A:on 750127,core Spray Injection Line through-wall Cracks Discovered.Stainless Steel Portion of Core Spray Piping from Vessel Nozzle to Second Isolation Valve Replaced w/SA-333 Grade 6 Carbon Steel ML20084N6831976-06-29029 June 1976 Supplemental AO 50-249/1975-42A:motor Operated Valve 3-1501-5D Failed to Open During Testing Due to Thermal Overload Trip.Caused by Undersized Overload Heaters.Overload Heater Will Be Replaced W/Larger Capacity Unit ML20084D1191976-04-13013 April 1976 AO 50-237/75-39A:on 750612,diesel Generator Experienced Starting Failures.Possibly Caused by Two Gouged & Burred Areas on Ring Gear.Ring Gear Repaired ML20084D1541976-01-14014 January 1976 AO 50-237/75-38A Supplementing AO-50-237/75-38 Re Failure of MO-2-1301-2 Valve to Operate.Apparently Caused by Excessive Cycling of Valve.Valve Stem Probably Experienced Metal Fatigue Due to Multiple Actuations ML20084S2291975-12-19019 December 1975 Supplementary Ao:Four Temp Switches Were Found to Trip at Values Exceeding Tech Specs Limits.Caused by Sensors Placed Too Closely to HPCI Turbine & Steam Piping.Different Temp Sensor Will Be Installed ML20090E4581975-12-17017 December 1975 Supplemental AO 50-237/75-44:diesel Generator Failed to Start.Caused by Air Relay Valve Failure Due to Sticking O-rings.O-rings Replaced ML20084N6541975-12-11011 December 1975 AO 50-249/75-44:on 751125,offgas Increase Exhibited Which May Have Represented Abnormal Degradation of Fuel Cladding.Cause Unknown.Investigation Underway ML20090E4321975-11-20020 November 1975 AO 50-237/75-52:on 751116,MSIV AO 2-203-1C Closing Time Found Below Tech Spec Section 3.7.D.1.Caused by Out of Adjustment Hydraulic Bleedoff Valve.Bleedoff Valve Readjusted ML20084S5561975-11-19019 November 1975 Preliminary Ao:On 751109,traversing Incore Probe (TIP) Ball Valve 2 Failed to Close.Manual Attempts to Close Valve Failed.No Cause Stated.Addl Info Will Be Submitted in AO 50-265/75-45 ML20084S5851975-11-17017 November 1975 AO 50-265/75-44:on 751107,RCIC Turbine Tripped.Caused by Failure of Hydraulic Fluid servo-valve Actuator.Actuator Replaced & Overspeed Trip Mechanism Repaired ML20084S5731975-11-10010 November 1975 Preliminary Ao:On 751107,reactor Core Isolation Cooling (RCIC) Sys Turbine Tripped.Caused by Failure of Hydraulic Fluid servo-valve actuator.Servo-valve Actuator Will Be Replaced.Addl Info Will Be Submitted in AO 50-265/75-44 ML20090E4751975-11-0606 November 1975 AO 50-237/75-51:on 751031,torus Water Level Exceeded Tech Spec Limit During HPCI Sys Surveillance.Caused by Operator Failure to Verify Proper Valve Lineup.Water Pumped from Torus Until Level Dropped Below Tech Spec Limits ML20084S5931975-10-30030 October 1975 Ao:On 751029,RHR Sys 2 Supply from Emergency Diesel & Core Spray Sys 2 Bus/Logic Power Failure Alarms Received.Caused by Switch 12 in Off Position.Switch Returned to on Position. Addl Info Will Be Submitted in AO 50-265/75-43 ML20084S6021975-10-28028 October 1975 AO 50-265/75-42:on 751018,differential Pressure Across B Train of Standby Gas Treatment Sys Exceeded Tech Spec Limit. Caused by Fouling of High Efficiency Prefilter.Filter Changed & Tested Satisfactorily ML20084S6191975-10-27027 October 1975 AO 50-265/75-41:on 751018,while Performing Monthly Diesel Generator Surveillance Test,Diesel Generator Reactive Power Meter in Control Room Pegged Full Scale.Megawatt Output Load Erratic.Operator Tripped Diesel.Caused by Equipment Failure ML20084S7771975-10-24024 October 1975 AO 50-265/75-38:on 751014,weld Exams Indicated Crack on B Loop of Rx Recirculation Discharge Bypass Line.Caused by Intergranular Stress Assisted Corrosion.Both Bypass Lines Will Be Removed ML20084S6741975-10-24024 October 1975 AO 50-265/75-39:on 751016,one Bergen-Patterson & Two Grinnell Hydraulic Snubbers Found W/Empty Oil Reservoirs. Apparently Caused by Equipment Failure.Snubbers Will Be Repaired or Replaced ML20084S6471975-10-24024 October 1975 AO 50-265/75-40:on 751016,while Performing Routine Surveillance,Three High Drywell Pressure Scram Switches Found to Exceed Tech Spec Limit.Apparently Caused by Instrument Drift.Pressure Switches Recalibr & Tested ML20084S2071975-10-20020 October 1975 Telecopy Ao:On 751020,radwaste Discharge Batch 3709 Discharged at Rate Which Exceeded Tech Spec Limit.Further Info to Be Provided in AO 50-254/75-22 ML20084N6881975-10-20020 October 1975 AO 50-249/75-42:on 750920,motor Operated LPCI Suction Valve 3-1501-5D Failed to Open Twice During Testing. Apparently Caused by Defective Valve Motor.Valve Motor Will Be Replaced ML20084S6121975-10-20020 October 1975 Telecopy AO 50-265/75-42:on 751018,differential Pressure Across B Train Particulate Filters of Standby Gas Treatment Sys Exceeded Tech Specs.Caused by Smoke from Small Fire Created by Onsite Welders.Work Request Issued ML20084S6291975-10-18018 October 1975 Telecopy AO 50-265/75-41:on 751017,during Monthly Surveillance Testing of Diesel Generator,Electrical Flash Burned Out Diode Rectifier Array of Generator Exicitation Circuitry.Output Breaker Tripped.Generator Inoperable ML20084S7821975-10-17017 October 1975 AO 50-265/75-37:on 751007,minor Leakage from B Feedwater Flush Line Observed.Caused by Equipment Failure.Flush Line Being Repaired ML20084S6831975-10-17017 October 1975 Telecopy AO 50-265/75-39:on 751016,two Grinnell & One Bergen-Patterson Hydraulic Snubbers Found Defective.Cause Not Stated.Work Request Issued for Repair ML20084S6561975-10-17017 October 1975 Telecopy AO 50-265/75-40:on 751016,during Routine Monthly Surveillance,Three High Drywell Pressure Switches Found to Exceed Tech Spec Limit.Cause Not Stated.Instruments Recalibr & Tested Satisfactorily ML20090E4781975-10-17017 October 1975 AO 50-237/75-49:on 751009,LPCI Loop Selection Logic Circuitry Failed to Select Preferred B Loop.Caused by Out of Calibr Differential Switch 261-34 & Electrically Shorted Switch 261-34D.Mod to Provide Signal Dampening Initiated ML20090E4471975-10-17017 October 1975 AO 50-237/75-48:on 751007,through-wall Crack Discovered in Drywell/Torus Nitrogen Purge Line 1604-18.Caused by Rapid & Uneven Contraction of Line Tee Connection Due to Liquid Nitrogen Impingement Resulting from Boiler Failure ML20084S2181975-10-15015 October 1975 Telecopy Ao:On 751014,two High Drywell Pressure Scram Switches Found in Isolated Condition.Further Info to Be Provided in AO 50-254/75-21 ML20084N8331975-10-15015 October 1975 Supplemental AO 50-249/75-22:plant Mod Being Initiated to Eliminate Valve Seat Failures Due to Cryogenic Stress ML20084S7681975-10-14014 October 1975 Telecopy Ao:On 751014,crack Indication Confirmed on B Loop in heat-affected Zone on Pipe Side of pipe-to-weldolet Weld. Repair Plans Incomplete.Addl Info Will Be Submitted in AO 50-265/75-38 ML20090E4821975-10-0909 October 1975 AO 50-237/75-46:on 750929,reactor Scrammed on High Drywell Pressure During Drywell Inerting Process.Caused by Operator Valving Error,Allowing Nitrogen Flow to Bypass Inerting Pressure Control Valve Into Drywell.Operators Cautioned ML20090E4811975-10-0909 October 1975 AO 50-237/75-45:on 750929,HPCI Turbine Failed to Trip at Designated Reactor Coolant Level.Caused by Open Circuit in Turbine Trip Solenoid Valve Coil Due to Failure of Cold Solder Joint within Coil.Hpci Trip Solenoid Valve Replaced ML20084S7851975-10-0707 October 1975 Telecopy Ao:On 751007,pipe Crack Found on Feedwater Flush Line 2-3206B-4-C at Main Feedwater Line 2-3204B-18-C.Minor Leakage Did Not Affect Reactor Inventory.Repairs Initiated. Addl Info Will Be Submitted in AO 50-265/75-37 ML20084N6711975-10-0707 October 1975 AO 50-249/75-43:on 750927,leak Discovered in Drain Line from Feedwater Heater 3D3 to Heater 3C3.Caused by Poor Weld Installation of Drain Line Pipe Support.Crack Ground Out & Pipe Rewelded ML20090E4641975-10-0202 October 1975 AO 50-237/75-44:on 750923,diesel Generator Failed to Start.Caused by Operator Failure to Follow Monthly Insp Procedure & QC Procedure for safety-related Component Replacement.Air Start Sys Inspected & Seal Ring Replaced ML20090E4701975-09-19019 September 1975 AO 50-237/75-43:on 750911,diesel Generator Cooling Water Pump Main Breaker Tripped.Caused by Excessive Heat Buildup within Breaker Housing.Breakers on Buses Replaced & Cover Plates Removed for Ventilation ML20084N6911975-09-16016 September 1975 AO 50-249/75-41:on 750908,intermediate Range Monitors 11, 12,14,16 & 18 Failed to Respond During Plant Startup. Apparently Caused by Personnel Accidentally Loosening Cables.Cables Replaced ML20090E4911975-09-0808 September 1975 AO 50-237/75-42:on 750829,diesel Generator Cooling Water Pump Tripped,Followed by Diesel Generator Trip on High Temp. Cause Not Established.Investigation of Cooling Water Pump & Associated Breakers Continuing ML20084N8411975-09-0404 September 1975 AO 50-249/75-37:on 750826,pressure Switches PS3-263-53A,53B & 53C Had Setpoints Above Tech Spec Limit.Apparently Caused by Setpoint Drift Due to Long Periods at Zero Pressure. Setpoints Reset ML20084N7771975-09-0404 September 1975 AO 50-249/75-38:on 750826,pressure Switches 3-263-52A1 & 52A2 Found W/Setpoints Above Tech Spec Limit.Apparently Caused by Setpoint Drift Due to Long Periods of Inactivity. Switches Reset ML20084N7281975-09-0404 September 1975 AO 50-249/75-40:on 750827,during Routine Instrument Surveillance,Pressure Switches PS3-263-51A & 51B Had Setpoints Above Tech Spec Limit.Caused by Drifting Due to Long Periods at Zero Pressure.Switches Reset ML20084N7481975-09-0303 September 1975 AO 50-249/75-39:on 750826,overload Relay Tripped Twice on Motor Operated Isolation Valve 3-220-1.Caused by Defective Overload Relay.Relay Replaced ML20084N7941975-09-0202 September 1975 AO 50-249/75-36:on 750823,reactor High Pressure Sensors 263-55A,55B & 55C Found W/Setpoints Above Tech Spec Limit. Apparently Caused by Extended Periods at Zero Pressure. Switches Reset ML20084R9871975-08-31031 August 1975 Telecopy of AO 50-265/75-36:on 750831,during Shutdown, Instability Was Experienced on Feedwater Control Sys Which Caused 3/4 Inch Drain Lines to Sever from Low Flow Feedwater Regulating Valve.No Radioactive Matl Released ML20084S0391975-08-31031 August 1975 Telecopy Ao:On 750830,while Performing Monthly RCIC Operability Surveillance Test RCIC Would Not Reach Normal Conditions.Possibly Caused by Overspeed Mechanism.Required Testing of HPCI Sys Initiated ML20084S0041975-08-31031 August 1975 Telecopy Ao:On 750830,while Testing Operability of HPCI Sys, Auxiliary Oil Pump Kept Tripping & HPCI Turbine Failed to Start.Orderly Shutdown Was Initiated.Further Info to Be Provided in AO 50-265/75-35 ML20084N8661975-08-29029 August 1975 AO 50-249/75-35:on 750821,circuit Breaker 152-3403 Failed to Trip During Breaker Trip Test.Caused by Failure of Trip Coil.Breaker Replaced ML20084S0991975-08-25025 August 1975 Telecopy Ao:On 750824 Grinnel Snubber Had Empty Fluid Reservoir & Bergen-Paterson Snubber Had Leaking Accumulator. Replacement Parts Installed Prior to Reactor Startup on 750825.Further Info to Be Provided in AO 50-265/75-32 1977-03-31
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data SVP-99-204, Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20249C8491999-09-30030 September 1999 1999 Third Quarter Rept of Completed Changes,Tests & Experiments Evaluated,Per 10CFR50.59(b)(2), for Dresden Nuclear Power Station. with ML20217A1691999-09-22022 September 1999 Part 21 Rept Re Engine Sys,Inc Controllers,Manufactured Between Dec 1997 & May 1999,that May Have Questionable Soldering Workmanship.Caused by Inadequate Personnel Training.Sent Rept to All Nuclear Customers ML20212J0501999-09-21021 September 1999 Safety Evaluation Re Licensee Implementation Program to Resolve USI A-46 at Plant,Per GL 87-02,Suppl 1 SVP-99-179, Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20210L8661999-08-0202 August 1999 Safety Evaluation Accepting License 60-day Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20210R6081999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Dresden Nuclear Power,Units 1,2 & 3.With SVP-99-155, Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20210D3071999-06-30030 June 1999 Corrected Page 8 to MOR for June 1999 for DNPS Unit 3 ML20209J3481999-06-30030 June 1999 1999 Second Quarter Rept of Completed Changes,Tests & Experiments, Per 10CFR50.59.With ML20209E1291999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With SVP-99-148, Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20195K1481999-06-16016 June 1999 Safety Evaluation Authorizing Relief Request RV-23A for Duration of Current 10 Yr IST Interval on Basis That Compliance with Code Requirements Would Result in Hardship Without Compensating Increase in Level of Quality & Safety ML20195G6381999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With SVP-99-123, Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20195B2591999-05-19019 May 1999 Rev 66a to CE-1-A,consisting of Proposed Changes to QAP for Dnps,Qcs,Znps,Lcs,Byron & Braidwood Stations ML20206N2821999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With SVP-99-102, Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with1999-04-30030 April 1999 Summary Rept of Changes,Tests & Experiments Completed, Covering Period 990201-0430. with SVP-99-104, Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20205Q5291999-04-16016 April 1999 SER Concluding That Quad Cities Nuclear Power Station,Unit 1,can Be Safely Operated for Next Fuel Cycle with Weld O2BS-F4 in Current Condition Because Structural Integrity of Weld Will Be Maintained ML20205J6011999-04-0707 April 1999 Safety Evaluation Accepting Proposed Merger of Calenergy Co, Inc & Midamerican Holdings Co for Quad Cities Nuclear Power Station,Units 1 & 2 ML20206B1901999-03-31031 March 1999 First Quarter Rept of Completed Changes,Tests & Experiments Per 10CFR50.59 for Dresden Nuclear Power Station. with ML20205N7491999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With SVP-99-071, Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20205C5671999-03-19019 March 1999 Simulator Four-Yr Certification Rept ML20207D2341999-03-0101 March 1999 Post Outage (90 Day) Summary Rept, for ISI Exams & Repair/Replacement Activities Conducted 981207-1205 ML20207M6921999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Dresden Nuclear Power Station,Units 1,2 & 3.With ML20204B1571999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Quad Cities,Units 1 & 2.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced SVP-99-021, Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With1999-01-31031 January 1999 Quarterly Summary SER of Changes,Tests & Experiments Completed, Covering Period of 981101-990131,IAW 10CFR50.59 & 10CFR50.71(e).With ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20199D3261998-12-31031 December 1998 10CFR50.59 SER for 1998-04 Quarter, of Changes,Tests & Experiments.With ML20199C8951998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Dnps,Units 1,2 & 3 ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with SVP-99-007, Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Quad Cities Nuclear Power Station,Units 1 & 2,IAW GL 97-02 & TS 6.9.With ML20205D1311998-12-31031 December 1998 1998 Decommissioning Funding Status Rept for Yr Ending 981231 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20196D9651998-11-30030 November 1998 Safety Evaluation Supporting Relief Requests CR-21 & CR-24, Respectively.Relief Request CR-23,proposed Alternative May Be Authorized,Per 10CFR50.55a & Relief Request CR-22 Was Withdrawn by Licensee ML20197G8591998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Dresden Nuclear Power Station.With ML20196G1241998-11-30030 November 1998 COLR for Quad Cities Unit 1 Cycle 16 ML20196C8731998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-30-1, Fracture Mechanics Evaluation on Observed Indications at Two Welds in Recirculation Piping of Quad Cities,Unit 1 Station ML20196C8391998-11-30030 November 1998 Rev 0 to GE-NE-B13-01980-030-2, Assessment of Crack Growth Rates Applicable to Induction Heating Stress Improvement (IHSI) Recirculation Piping in Quad Cities Unit 1 SVP-98-364, Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20196A9761998-11-20020 November 1998 Safety Evaluation Re Licensee 180-day Response to GL 95-07, Thermal Binding of Safety-Related Power-operated Gate Valves ML20196J0061998-11-19019 November 1998 Rev 66 to Topical Rept CE-1-A, QA Program ML20196A4191998-11-19019 November 1998 Safety Evaluation Accepting QA TR CE-1-A,Rev 66 Re Changes in Independent & Onsite Review Organization by Creating NSRB SVP-98-346, Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With SVP-98-358, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With1998-10-31031 October 1998 Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period on 980716-1031.With ML20195D2861998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Dresden Nuclear Power Station.With 1999-09-30
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