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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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, Washington, D. C. 20545
Reference:
Quad-Cities liuclear Po.cr Station, Unit 1, Dorket No. 50-254, DPR 29, Abnormal Occurrence Report Letters of April 25, 1974 & May 30, 1974.
Dea r 11r . O' Leary:
The purpose of this letter is to provide you with further information regarding the above referenced Abnortral Occur-rence Report. The previous letters have described the initial findings and planned Japairs related to fcilurcs of several jet pump components of thc Unit I reactor.
Several design changes were made to the replacement parts to facilitate remote repairs while restoring the jet parrp a u r cr:blie s to the ir origi na 1 functiona 1 requireraents .
'/ne h r s ic jet pump design retaains unchanged. The design changes were incorpora ted primarily in assembly features and techniques.
All repair work to the failed jet pump components was com-pleted on iTune 25, 1974. A discussion of the final repairs f ollo.:s : @)
- 1. Restrainer Gates - Restrainer gate assem'olies for all 23 jct pumps v:ere repl'ced with nev, assemblies .
The entire assemblies were rep] aced rather thEn just the faileS bolts in crder to minimira racia-t .i cn ci:posu re to the mJintenance personnel. Jet pumps 5 and 6 recuired modifications to the stand-ard restrainer gates as is discussed belott.
- 2. Rastreiner rate Uedcms - The restrainer gate t:Cdges for the ncs assemblics are slightly larger (thicN r) to assure that the installation tole ra nce is inintained. A ll newly ins ta lled wedgen met the sptcified installetion tolerance.
- 3. Rortrain?r G 4 nelt Ke c m r s - The r ede s i cine d 1
restre in2 r gr.e nolt haaners were insta lled on 1 > <'
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all 40 restrainer gate bolts. Two tack walds par gate bolt keeper were applied instead of the one weld specified for the original assembly, to provide a greater margin of integrity.
4.
Jet Pumo 5 Restrainer Gate - A standard restrainer gate required special modification in order to facilitate installation on Jet Pump'S, The stand-ard gate was cut in two at a point 450 from the center line of the wedge on the side nearer the hinge pin. A spacer block was then welded be-tween the two parts in order to provide an off-set of approximately 1-3/8". The offset was necessary-to compensate for one side of the jet pump hold down bracket which was bent.. Because of the very close proximity of the hinge pin to the inlet mixer of the jet pump, a new design bolt .aruS keeper were provided in order to avoid interference of the bolt and keeper with the mixer.
- 5. Jet Pump 6 nostra iner Gate A standard restrainer gate was also modified for installation on Jet Pump 6. An extension arm was added to the gate on the hinge pin side. The extension arm had a locator screw assembled in it to replace the locator block and adjusting screw that were broken off. Tha ext onsion is assembled to a new ria"'gr g"ta belt and the caluLine Linge pin, and is secured by a new design nut. The nut is prevented from rotating by a keeper which is tack welded to the extension arm. The bolt is ~~
kept from rotating via a Right-Hand and Left-Hand thread design feature. The locator screw was adjusted to mate with the belly band on the inlet mixer assembly and tack welded in position.
The second locator screw on Jet Pump 6 had been found with a broken tack weld and was not properly positioned in its locator block. This screw was returned to its proper location as indicated by the original tack wald and a new tack wald was applied.
- 6. Jet Pumo 7 Locator Screw - Jet Pump 7 was found with one locator screw missing from its mounting block. A new locator screw was designed to facili-tate remote assembly and installed, adjusted and tack welded in position.
- 7. neam noit Petainers - Beam Bolt retainers were found missing from the beam bolt assemblies of Jet Pumps 10, 15 and 16. These retainers were not replaced since their only function is to prevent the beem bolt assembly from falling from the inlet-mixer during assembly or disassembly.
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Any future disassembly of those inlet mixers will require that the beam bolt assemblics be removed as separate assemblics.
- 8. Beam Bolt Assemblies - The beam bolts for all 20 jet pumps were retensioned using the procedure developed during the jet pump repairs to Unit 2 in 1972. This procedure requires a minimum bolt rotation at a torque value of 50 f t.-lbs. which provides assurance that the specified tension is applied.
Following retencioning of the beam bolts, the beam bolt keepers were secured with 4 tack welds per keeper instead of the original 2 tack welds per keeper to provide a greater margin of integrity.
- 9. Jet Pump _7 Instrument Li ne - A previously repor-ted failure of the flow instrument line for Jet Pump 7 was identified as a severed line during this outage. Because of the engineering and mock-up required to develop the necessary tools to repair the instrument line, the fix for the severed line on Jet Pump 7 was not available for the current outage. It is planned to operate .
during the next cycle with the instrument line Oc it c ne1, end to Pry en repair it during tha next refueling outage.
- 10. Missing and Loose Pa rts - Table 1 is a complete c-index of all parts known to be either missing or loose in the vessel along with their disposition to da'te. Inspection of the Table shows that the following loose parts remain in the vessel:
A. 1 Retainer for beam bolt " L" Shaped piece 1/8" thick, 2" wide, one section 2" long, one section 3" long.
B. 2 Bolts for above retainer 3 /4 " long x 1/2 " d ia .
C. Small piece masking tape 4" x 2" D. LPRM Spring reel guide piece 1" d ia . x 2" long E. Short piece of walding rod 6" long F. Sleeve from ref ueling chield-cylinder 3/4" dia .
gate (cattle chute) 1/2" long 7.n obvious concern involved with these lost pieces in that asscciated with potential fuel bundle flow
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patJe. 4, ,
blockage . A G.E. Topical Report (1) states that it would take more than a 90% area blockage to cause a MCUFR less than 1.0. The like lihood of the pi.eces under consideration significantly blocking the fuel bundle flow is very small. Be-cause of the high density of the pieces involved, it is expected that were they to be introduced into the reactor lower plenum, the velocities there would not be high enough to lif t the pieces to the core support plate. Thus, the probability of fuel bundle flow blockage is very small. (2)
If the lost pieces become fragmanted into small pieces, these could become lodged in the fuel bundle spacers, which could cause local cladding failures. However, if cladding failures do occur, the resultant radiation releases wouldthe be appro-sensed by the plant radiation monitors, and priate actions would take place. The health and safety of the public would not be jeopardized as the of fsite releases would remain within the 10CFR20 limits.
The conclusion of the analysis of the inspections and repairs of the failed jet pump components is that the failures ware fatigue failures caused by excessive vibration. The vibra-tion was due to several of the jet pump beam bolt assemblies not being tencicned to meet thn original design requirements.
t e o u li a rc.c nt s Fina lly , the failurc to mcct the cr2g'm i duivo is attributed to improper field installation of the compo-nen,ts involved . y-.
The Unit 1 refueling outage remains in progress as of this date. Startup of the Unit is tentatively scheduled for July 16, 1974.
Very truly yours, COMMON /?EALTH EDISON COMPMW QUAD-CITIE$ NUCLEAR PONER STATION
- V ? l. ,' . .
a N. J . Kalivianakis Station Superintendent NJK/ REQ /sa a cc: Region III, Directorate of Regulatory Oparations J. S. Abel Attachmont: Table 1, Index of Missing and Loose Parts NSDO-10174, May 1970, G.J. Sca te na , " Consequences of a (1)
Postulated Flow Blockage Incident in a Boiling Wa ter Reactor".
(2) Quad Cities Station, Unit 2, Special Report No. 2, "Je t Pump Operability".
(3) Supporting Documentat ion - Quad-Citics Station, Work Request Numbcr 1802-74. .
QUAD CITIES HCC:. EAR PONER STATION U20:T 1 y>- SPRIMG 1974 I.UFUELING OUTAGE ,
g INDEX OF IIISSJHG AND LOOSE PARTS PART ORIGINA L DATE OF DATE OF STATUS
- DISCOVERY RETRIEVA L DISPOSITION .
JP 5 Pestrai ner gate bolt head Missing 4-16-74 By 4-23-74 To GE - VNC JP 5 Res traine r ga te bolt head Missin_g_ 4-16-74 5-25-74 To GE - VIC JP G U :rtrainer gate bolt head N i s s i t3q_ 4-16-74 5-2 5 - 7/'
JP 5 Rentrainer bolt keeorr To GE - V?]C Missinci 4-1G-74 Bv 4-23 -74 To GE - V"C JP 3 Pastra iner bolt keeper 4-1G-74 By 4-23-74
.i. . _M i s._s__i .n ~t To GE - VNC UP 6 Po. trainer bolt keoorr Missing 4-16-74 5-25-74 To GE - VICC J P G 'c; e d a -
Mianing 4-16-74 Bv_4-23-74 To GE - V?!C JP 6 0ladaa bale M i n s i nci 4-1G-74 Ev 4-23-74 To GR - VNC L. T D G '..cdo.- coring Minninn1 4-16-74 Bv 4-23-74 To CE - Vi!C
. . .:t r a m.
d r:o haic (la ter veri fied f rom J P Sl L P. . : 1 e nd x onnocLor Loont 4-16-74 Ev 4-23-74 To CR - VNC
~~ ~ ~ ~ ~ ~ A 11 Of f 4-20-74 5-20-74 Fue1 Pool JP 6 Enm. Lor block l Misninci 5-22-74 5-25-74 To GE - VNC screw 5-22-74 f' JPJ P 6 Locator 7 r,ctator blockblock a d -j adiustin u s t ing s c i. ew Missint:
Minsina 5-22-74 5-25-74 To GE - VNC 5-23-74 To GM - VNC JP 10 Pat ~nar for b?an bolt Missina 5-23-74 5-23-74 T_o_ G E - V__N_C_
Retairar for beam bolt (la ter verificd from JP Loose 5-23-74,J 5-23-74 To GE - VNC Rotainer for beam bolt (later verified from JP 15L_l Leone 5-23-74
,J .. P 10 neit for above retainer 16)_I M i s s inci 5-23-74 5-23-74 To GE - VNC
.JP
- Li Bolt for above retainer I Missinc] 5-23-74
'JP 16 Bolt for above retainer _
_[ Misning 5-23-74 i M21 ding Rod : Loose 5-23-74 lFi]a r-(_gv li nd o r [la ter ve r: fi ed as part of vib. inst.)__
Leone Loose 5-23-74 5-23-74 5-23-74 5-23-74 Fuel Pool To GE - VNC h-Roll duct tane .'lisring 6-1-74 6-23-74 Radwaste Sa Fe ;v c1io froin Cha in Fu11 Hois t Mi_ .< ing _ _6-12-74 6-22-74 Radwa s te
[ Pin from above sa fe ty clip Missing 6-12 74 7-1-74 Radwaste M . :#. j na t a nc 2__sm. a_ll
- - - - ci e ce Loose 7-1-74 G r r i r.c Roel T,PRM naide niece ;
Missing 6-29-74 S i n ew f ro.n ca t t le chute _ . _ _
I M ia n i n g__ __G-2_4 -7 4 __
- Mi sing means not in normal location and unaccoun:Od for.
Loose means observed, but source unknown.
t 4
1