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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20084K4981976-10-0505 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 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 ML20084S0651975-08-25025 August 1975 Telecopy Ao:On 750825,oil Separator Overflowed Into Spray Canal Releasing Contaminated Water.Caused by Rainfall. Remaining Water in Oil Separator Being Discharged as Controlled Batch Release 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 ML20084S1831975-08-18018 August 1975 Telecopy Ao:On 750817,following Maint Outage,Reducer of Low Flow Feedwater Regulating Valve 2-643 Severed Due to Vibration.Unit Manually Scrammed & Reactor Level Maintained W/Rcic Sys ML20084S2471975-08-15015 August 1975 AO 50-254/74-19:on 750805,reactor High Pressure Scram Switch 1-263-55A Was Isolated.Caused by Switch Left Isolated After Completion of Previous Month Testing.Establishment of Administrative Control Over Valves Initiated ML20084S2231975-08-13013 August 1975 Telecopy Ao:On 750812,ECCS Low Pressure Permissive Sensor PS-2-263-52A Discovered in Isolated condition.PS-2-263-52A Put Into Svc & All Switches Satisfactorily Functionally Tested.Further Info to Be Provided in AO 50-265/75-30 ML20084S2221975-08-11011 August 1975 Telecopy Ao:On 750809,standby Liquid Control Pump 1A Produced Flow Rate Below Tech Spec Limit.Caused by Premature Lifting of Relief Valve RV-1-1105A.Relief Valve Reset. Further Info to Be Provided in AO 50-254/75-20 ML20084S2371975-08-0808 August 1975 AO 50-265/75-28:on 750729,RHR Svc Water Pump 2A Fell Below Required Flow Level & Pump Pressure Limit.Caused by Accumulation of Debris Lodged in Pump Suction & Impeller. Debris Was Removed ML20084S2261975-08-0808 August 1975 AO 50-265/75-27:on 750729,during HPCI Monthly Surveillance Operation Only Able to Attain Pump Flow Below Tech Spec Limit.Caused by Improper Pinning of Pilot Valve Lever Arm. Lever Arm Adjusted ML20084S2541975-08-0505 August 1975 Telecopy Ao:On 750805,reactor High Pressure Scram Switch PS-1-263-55A Was Still Valved Out from Previous Month Surveillance.Switch Was Calibr & Valved in Svc.Further Info to Be Provided in AO 50-254/75-19 ML20084S2591975-08-0404 August 1975 AO 50-265/75-26:on 750725,oxygen Level of Unit 2 Suppression Chamber Exceeded Tech Spec Limit.Caused by Insufficient Nitrogen Available to Inert Primary Containment Due to Leaking Flange.Gasket in Nitrogen Line Replaced ML20084S3311975-08-0101 August 1975 AO 50-254/75-18:on 750724,pressure Switch PS-1-1622B Tripped at Value Exceeding Tech Spec.Caused by Instrument Drift.Pressure Switch Recalibr ML20084S3751975-07-31031 July 1975 AO 50-254/75-17:on 750721,traversing Incore Probe Machine Three Ball Valve Failed to Close When Detector Was Withdrawn to in-shield Position.Caused by Failure of Spring to Close Ball Valve Completely.New Valve Installed ML20084S2321975-07-31031 July 1975 Telecopy Ao:On 750731,4 of 16 HPCI Area High Temp Switches Tripped at Values in Excess of Tech Spec Limits.Switches Calibr.Further Info to Be Provided in AO 50-265/75-29 ML20084S3181975-07-31031 July 1975 AO 50-265/75-25:on 750721,two Hydraulic Snubbers Found to Have Empty Oil Reservoirs.Caused by Several Oil Leaks for One Snubber.Failure of Second Snubber Unknown.One Snubber Fitting Tightened & Other Snubber Replaced ML20084S2421975-07-30030 July 1975 Telecopy Ao:On 750729,RHR Sys Svc Water Pump 2A Failed to Meet Tech Specs Required Flow Rate.Work Request 2794-75 Immediately Issued for Investigation & Repair.Further Info to Be Provded in AO 50-265/75-28 ML20084S2461975-07-29029 July 1975 Telecopy Ao:On 750729,HPCI Sys Could Not Obtain Tech Spec Required Flow Rate.Cause Unknown.Eccs Testing Begun as Investigation.Further Info to Be Provided in AO 50-265/75-27 ML20084S6641975-07-29029 July 1975 AO 50-265/75-24:on 750720,crack Found on Reactor Feedwater Sys Flushing Line 2-3206B-4-C.Caused by Stress Point Due to Improper Blending of Fillet Weld.New Section of Pipe Welded ML20084S3361975-07-28028 July 1975 Telecopy Ao:On 750724,pressure Switch 1-1622B Found to Trip at Value Exceeding Tech Specs Limit.Switch Was Immediately Recalibr.Further Info to Be Provided in AO 50-254/75-18 ML20084S2641975-07-25025 July 1975 Telecopy Ao:On 750725,during Completion of Inerting,Primary Containment Oxygen Concentration Was Not within Tech Spec Limits.Further Info to Be Provided in AO 50-265/75-26 ML20084S6931975-07-25025 July 1975 AO 50-265/75-23:on 750718,high Drywell Pressure Switch 2-1001-89B Failed to Operate.Caused by Dirt & Scale Plugging Pressure Pulsation Damper.Damper Cleaned ML20084S3901975-07-25025 July 1975 AO 50-254/75-16:on 750717,unsampled Laundry Water Added to Floor Drain Sample Tank River.Caused by Operator Error. Radwaste Foreman Must Verify Valve Checkoff List Prior to Discharging to River ML20084S7131975-07-24024 July 1975 AO 50-265/75-22:on 750716,two of Four High Drywell Pressure Switches Exceeded Tech Specs Limit.Caused by Instrument drift.PS-2-1001-88B & C Calibr to Trip at 1.90 Psi ML20084S6261975-07-22022 July 1975 Telecopy Ao:On 750721,traversing Incore Probe (TIP) 3 Ball Valve Failed to Close.Shift Foreman Went to TIP Cubicle & Tapped Valve,Causing Valve to Close.Further Info to Be Provided in AO 50-254/75-17 ML20084S3261975-07-22022 July 1975 Telecopy Ao:On 750721,one Grinnell & One Bergen-Paterson Snubber Found Defective.Work Request Issued for Repair. Further Info to Be Provided in AO 50-265/75-25 ML20084S6791975-07-21021 July 1975 Telecopy Ao:On 750720,water Discovered in MSIV Room.Caused by Crack on Feedwater Flush Line B.Preparations Currently Being Made for Repair of Cracked Line ML20084S6161975-07-18018 July 1975 Telecopy Ao:Laundry Drain Sample Tank Level Dropped & Floor Drain Sample Tank a Level Rose.Caused by Not Verifying Closing of Laundry Tank Discharge Valve.Discharge Immediately Stopped ML20084S6981975-07-18018 July 1975 Telecopy Ao:On 750718,pressure Switch 2-1001-893 Failed to Operate at Any Pressure.Work Request 2640-75 Initiated to Investigate & Correct Problem 1976-10-05
[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 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 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 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 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 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 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 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 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 ML20204B1571999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Quad Cities,Units 1 & 2.With 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 ML20205D1311998-12-31031 December 1998 1998 Decommissioning Funding Status Rept for Yr Ending 981231 for Quad Cities Nuclear Power Station,Units 1 & 2 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 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 ML20196G1241998-11-30030 November 1998 COLR for Quad Cities Unit 1 Cycle 16 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 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 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 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 SVP-98-326, Monthly Operating Repts for Sept 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Quad Cities Nuclear Power Station,Units 1 & 2.With ML20153D0191998-09-18018 September 1998 Part 21 Rept Re Defect in Gap Conductance Analyses for co- Resident BWR Fuel.Initially Reported on 980917.Corrective Analyses Performed Demonstrating That Current Operating Limits Bounding from BOC to Cycle Exposure of 8 Gwd/Mtu ML20153C6771998-09-17017 September 1998 Part 21 Rept Re Defect Relative to MCPR Operating Limits as Impacted by Gap Conductance of co-resident BWR Fuel at Facilities.Operating Limit for LaSalle Unit 2 & Quad Cities Unit 2 Will Be Revised as Listed ML20151T2711998-09-0404 September 1998 Safety Evaluation Accepting Licensee Response to NRC Bulletin 95-002 ML20151Y7261998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Quad Cities Nuclear Power Station ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept ML20151Y7301998-07-31031 July 1998 Revised MOR for Jul 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20237A6251998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Quad Cities Nuclear Power Station,Unit 1 & 2 SVP-98-328, Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With1998-07-15015 July 1998 Summary Rept of Changes,Tests & Experiments Completed, Including SEs Covering Period of 971001-980715,per 10CFR50.59 & 10CFR50.71(e).With SVP-98-249, Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 SVP-98-215, Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Quad Cities Nuclear Power Station Units 1 & 2 ML20247N6281998-05-19019 May 1998 Rev 2 to COLR for Quad Cities Unit 2 Cycle 15 ML20216C0561998-04-30030 April 1998 Safe Shutdown Rept for Quad Cities Station,Units 1 & 2, Vols 1 & 2.W/22 Oversize Figures SVP-98-176, Monthly Operating Repts for Apr 1998 for Quad Cities Nuclear Power Station,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Quad Cities Nuclear Power Station,Units 1 & 2 ML20217D0281998-04-22022 April 1998 Part 21 Rept Re Additive Constants Used in MCPR Determination for Siemens ATRIUM-9B Fuel by Core Monitoring Sys Were Found to Be non-conservative.SPC Personnel Notified All Customers w/ATRIUM-9B Lead Test Assemblies ML20217G3951998-04-0808 April 1998 TS 3/4.8.F Snubber Functional Testing Scope Quad Cities Unit 2 TS (Safety-Related) Snubber Population 129 Snubbers SVP-98-128, Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 21998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Quad Cities Nuclear Station Units 1 & 2 1999-09-30
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C C-uad-Cibc4Generat:ng Station Post Office Box 216 Cordova Illinois 61242 (fi;*-[pC)
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October 18, 1974 - \ c;
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q Ns Mr. John F. O' Leary, Director Directorate of Licensing Regulation U. S. Atomic Energy Commission Washington, D. C. 20545
Reference:
Quad-Cities Nuclear Power Station Docket No. 50-254, DPR-29 Appendix A, Sections 1.0.A.3, 1.0.A.5, and 6.6.B.l.a
Dear Mr. O' Leary:
Enclosed please find Abnormal Occurrence Report No. AO 50-254/74-29 for Quad-Cities Nuclear Power Station. This occurrence was previously reported to Region III, Directorate of Regulatory Operations by telephone on October 10, 1974, and to you and Region III, Directorate of Regulatory Operations by telecopy on October 10, 1974.
This report is submitted to you in accordance with the require-ments of Technical Specification 6.6.B.1.a.
Very truly yours, COMMONWEALTH EDISON COMPANY QUAD-CITIES NUCLEAR P WER STATION
/r-Abik N. J. Kalivianakis Station Superintendent NJK/CWS/zr cc: Region III, Directorate of Regulatory Operations J. S. Abel ~
S .A PRY Sf26 RF1HN _
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O REPORT NUMBER: AO 50-254/74-29 REPORT DATE: October 18, 1974 OCCt1RRENCE DATE: October 10, 1974 FACILITY: Quad-Cities Nuclear Power Station Cordova, Illinois 61242 Identification of Occurrence:
Off Gas Detonation, Unit 1 Conditions Prior to Occurrence:
Unit 1 at 520 MWe increasing at 3 MWe/hr.
Unit 2 at 620 MWe increasing at 3 MWe/hr.
Unit 1 off Gas 3165 uci/sec. at the Main Chimney with ,
493 MWe at 0114 a.m.
Unit 2 Off Gas 28,832 uCi/sec at the Main Chimney with 639 MWe at 1:19 a.m.
Construction Activities in progress in the Off Gas Filter Building 1B SJAE in service 1B Off Gas Filter in Service Description of Occurrence:
At 10:04 a.m. on October 10, 1974, several personnel who were in the vicinity of the main chimney, in the off gas filter i - building,.and in the west side of the Turbine Building heard a loud " Boom". Control' Room Alarms were received for SJAE OFF
. GAS IIIGH FLOW, OFF GAS FILTER HIGH DP, SJAE lA LIQUID DRAIN HIGH LEVEL, SJAE 1B LIQUID DRAIN HIGH LEVEL, and SJAE lA LIQUID DRAIN LOW LEVEL. Shortly thereafter, the main chimney radiation monitors showed a step increase from approximately 30,000~uci/sec to approximately 100,000 uCi/sec. These indications led to .
the conclusion that an off gas detonation had occurred. The station procedure for off gas detonations was then followed.
At 10:07 a.m., a condition ABLE was declared and load reduction was initiated on Unit 1 to help maintain condenservacuum with erratic air ejector operation.- Unit 1 load was 399 MWe at 10:10 a.m. Personnel in the vicinity of the chimney checked the 4 off gas filter building and evacuated the personnel in that building. About three minutes later, an area-radiation monitor in_the off gas filter building alarmed. At 10:12 a.m., the station siren was sounded to effect an evacuation of the Turbina Building. The Station Environs Team was activated to investigate off site radiological consequences of the in'cident.
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o . .
O The 1A steam jet air ejector was placed in service and the 1B steam jet air ejector was removed from service and isolated by 10:30 a.m. Within approximately ten minutes, the main chimney radiation monitors decreased approaching pre-incident levels.
Also, the area radiation monitor alarms in the area of the SJAE rooms were cleared. The 1A off gas filter was placed in '
service and the la off gas filter was removed from service and isolated by 10:50 a.m. A check of the off gas filter building piping revealed a flow path of off gas to a pipe on which grinding was taking place at the time of the off gas detonation. The pipe, which had been ground through, was isolated at approximately 11:00 a.m. Condition ABLE was officially terminated at 11:04 a.m. A later inspection confirmed that the 1B SJAE rupture disc was ruptured, thus allowing off gas to enter the SJAE room, causing local area radiation monitors to alarm, and decreasing off gas hold up time to the chimney caus-ing an increase in off gas radiation at the main chinney monitors.
The 1A off gas filter was tested for efficiency and was de-termined to be defective at 2:00 p.m. An orderly shutdown was initiated, the turbine was tripped at 5:30 p.m., and the Unit was in shutdown mode at 9:15 p.m. on October 10, 1974.
DESIGNATION OF APPARENT CAUSE OF OCCURRENCE:
Installation / Construction The cause of this off gas detonation is attributed to construction personnel grinding through an unpurged and improperly isolated section of off gas piping in the new off gas filter building.
At the time of detonation, a modification was being made on the new piping. The personnel working on the job were under the impression that the subject piping had never been placed in service and thus could not contain off gas. Subsequent exami-nation showed that a flow path did e::ist from the off gas filter bypass line to the grinding location. This filter bypass line was in service.
Contributing factors include failure of construction personnel to notify operations personnel of work being done, failure to have the line taken out of service properly before beginning work, and failure to purge a'line possibly containing explosive l
. gases before beginning work. !
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ANALYSIS OF OCCURRENCE:
The of f gas detonation resulted in:
- 1. Rupture of the 1B SJAE rupture disc.
- 2. Rupture of the 350 psi 2" rupture disc on the off gas discharge pipe upstream of the holdup line.
- 3. Demolition of the 1B Off Gas Filter.
- 4. Apparent Fire damage to the 1A off gas filter, probably due to small leakage of one of the filter isolation valves.
There were no personnel injuries and no excessive personnel radiation exposures related to this incident.
The wind was from the south during this incident at up to approximately 6 mph. On site environs station No. 1 is located due north of the station. The recording area radiation monitor at this location showed an increase during this incident as shown in attachment "A".
These results correspond to the indicated chimney radiation monitor increase from approximately 30,000 uCi/sec to 100,000 uCi/
sec as shown in attachment ' B".
This indicated increase is due to a combination of factors caused by the decrease in holdup time. The shorter holdup time caused an increase in the 22 fission product gases. The decrease in holdup also caused a change in composition which would' affect monitor calibration. Also, the shorter holdup allowed N13 to become a contributing factor.
Initial environs team samples showed minimal environmental implica tions . These were confirmed by an extensive environmental sampling program performed by Eberline Instrument Corporation on the afternoon of October 10, 1974. These results are enclosed as attachement "C".
CORRECTIVE ACTION Immediate corrective action was taken as described in " Description
, of Occurrence." Other follow-up action included replacing both off gas filters, and replacing both ructure discs. In addition, the instruments involved in monitoring the off gas holdup pipe were checked for damage and calibrated as required.
Immediately following the incident, a meeting was held between the Station Superintendent, the Commonwealth Edison Station l Construction Representative, and Contractor personnel involved.
It was again made clear that station procedures must be followed and that adherance to station procedures could have prevented this incident.
1 O .
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FAILURE DATA !
l Although this is the third off gas detonation to have occurred at Quad-Cities Station, the causes of previous detonations are attributed to ungrounded filters and possible unknown factors.
This occurrence was due to personnel error and not equipment failure or malfunction and the cause was readily explainable.
It should be noted that environmental implications on the health and safety of the public in this case were minimal, as expected
~ based on actual samples, calculations, and previous experiences.
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ENNRCiNE INSTRkiENT CORPORATION [h: !
PLEACE REPLY TO: MIDWESTERN FACILITY 245 HOOSEVELT ROAD WEST CHICAGO, ILLINOIS 60185 PHONE (312) 2319400 E
$ jf. Ah2M' io. l 6 ^? e5
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kl953-1973,/
15 October 1974 Quad Cities Nuclear Power Station P.O. Box 216 ,
Cordova, Illinois 61242 Attention: Mr. N. J. Kalevianakis
Dear Mr. Kalevinnakis:
The attached sheets list data obtained during the special environmental sample collection program of 10/10/74. We have also included your copy of the sample collection data sheet. These data confirm previous verbal reports of results, and are discussed below.
Gamma Isotopic Analyses - Soil Cs-137 was the only fission product gamma emitter detected. Concentra-tions for all stations sampled except Q-03 were within the range expected (0.1 - 0.4 pCi/ge) from worldwide fallout. Soil from Q-02 had a Cs-137:
concentration of 1.1 0.2 pCi/gm. While this value (which was confirmed by separate analyses of two aliquots of the sample) is somewhat higher than expected, in the absence of other (especially fresh) fissica pro-ducts, we feel this activity is unlikely to be due to station operations, but the possibility does exist.
Gamma Isotopic Analyses - Vegetation
> Cs-137 was detected in low concentration (0.3 0.2 pCi/go) at Q-15, but was not detected in vegetation samples collected ~elsewhere. As with the soil samples, this van the only fission product ga=ma emitter detected.
Here, too, plant operations are a possible, but not probable, source of this radioactivity.
Gamma Isotopic Analyses - Air Particulates, No fission product gamma emitters were detected in any air particulate filter at a system sensitivity of 0.01 pCi/m 3 (30). Naturally occurring
- Be-7 was detected in all samples of this type and naturally occurring K-40 in some.
Airborne I-131
'A composite of all charcoal cartridges co11ceted.(8) counted for 500 min-utes on the GeLi system. A small, but clearly detectable number of counts were observed in the 364 KcV cnergy peak, but could not be quantified N.
w^ P. O. BOX 2103 AlHPORT ROAD SAN TA FE, NEW MEXICO 87501 PHONE (505) 0821881 TWX 9'0-985 0678
t GA30fA ISOTOPIC ANALYSES OF SOIL, VEGETATION AND AIR PARTICULATE SAMPLES COLLECTED 10/10/74 ,
pCi/g* Soil pCi/g* Vegetation Air Particulates pCi/m 3, Station Cs-137 Others(1) Cs-137 Others(1) Fission Products Gamma Emitters Q-01 0.3 0.1 <.03 <0.37 <0.37 <0.01 Q-02 0.4 1 0.1 <.03 - -
<0.01 Q-03 Q-12 1.1 0.2 0.2 0.1
<.03
<.03
<0.21
<0.18
<0.21
<0.18
<0.01
<0.01 lll Q-13 <0.03 <.03 <0.30 <0.30 <0.01 Q-14 0.2 ! 0.1 <.03 <0.20 <0.20 <0.01 Q-15 0.3 ! 0.1 <.03 0.27 0.18 <0.20 <0.01 Q-16 0.1 2 0.1 <.03 <0.20 <0.20 <0.01
- All quoted uncertainties are 2a, "<" data are 3a.
(1) Spectra are computer scanned from ~1 to ~2000 kev, with special attention to fission product
, nuclides. Naturally occurring gamma emitters such as K-40, radium and its daughters, and Be-7 i f were present in most samples but are not included in "others" above.
l RADI0 IODINE (I-131) IN CHARC0AL CARTRIDGES COLLECTED 10/10/74 gg)
Station: 0-01 0-02 0-03 0-12 0-13 0-14 Q-15 0-16 I-131 pCi/m 3 <.04 <.04 <.04 <.04 <.04 <.04 <.04 <.04 ION CHAMBER READINGS
, 10/10/64 '
Station mR/ Week
- Q-01 FS 2.8 Q-13 5.6 (1) 2.1 Q-02 2.1 FS Q-14 2.8 2.8 Q-03 2.0 2.1 Q-15 2.5 1.4 Q-12 1.4 1.4 Q-16 2.8 2.8
- Readings were taken after 5 days' exposure and are presented normalized to 7 days' exposure.
(1) Apparently anomalous reading.
,n ,
. . .. o o Mr. N. J. Kalevianakis Page 2 15 October 1974 -
Airborne I-131 (Continued) because the system cannot be calibrated for this non-standard geometry.
Analyses of individual cartridges on a 4" x 4" NaI(Tl) crystal with a single-channel spectrometer set for I-131 ga=nas indicated that the I-131 concentration was <0.04 pC1/m3 (3a) corrected for decay to time of sampling at all stations. The apparent presence of I-131 in the com-posite is probably either an artifact or real, but detected only because the composite is eight times as large as an individual sample.
Ion Chamber Readings Adopting the usual convention of accepting the lower of the two ion chambers as the reporting value and normalizing to a seven-day exposure, Q-14, Q-16 and Q-01 indicate doses somewhat higher than usual. These increases may be due to station operations, but in view of the wide variability of ion chamber data is probably not statistically demon-strable.
Cross Beta in Air Particulates Gross beta concentrations in air particulate filter samples collected were, for all stations sampled, well within the values expected for these samples. The spread of concentrations observed was very small .
indicating similar concentrations in the whole area sampled. There is no indication that radicactivity attributable to station operations was present in any of these samples.
Summary of Stations Sampled Station Location Time of Sampling Q-01 Nitrin .
1655 Q-02 Clinton 1730 Q-03 Sikkema Farn 1635 Q-12 Hanson's Landing 1800 Q-13 Low Moor 1815 Q-14 On-Site, North 1540 Q-15 On-Site, East 1500 Q-16 On-Site, South 1530 Sincerely yours, EBERLINE INSTRUMENT CORPORATION
// W 3
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t Trautman MT:md Manager, Midwest Facility cc: John Golden, CECO Rich Flessner, Quad Cities' [
. Attach.
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.. l GROSS BETA CONCENTRATIONS IN AIR PARTICULATE FILTERS Collected 10/10/74 Station m3 pCi/m 3( 2a)
Q-01 216 0.05 1 0.01 Q-02 210 0.05 0.01 Q-03 210 0.06 1 0.01 Q-12 210 0.06 0.01 Q-13 210 0.05 0.01 Q-14 210 0.06 0.01 L Q-15 210 0.06 ! 0.01 Q-16 210 0.06 0.01 W
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f-V/ cst Chicag2, I!!iniis 50185 SAMPLE COLLECTION DATA SHEET
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