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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
[Table view] |
Text
e l
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ti O Conunomssaltt>Emeon O
3
- Quad-Cities Noctest Power Station l PostOmcaBox 216
) Cordova.litmors 61242
- Telephone 309/654 224r I
I i
ll NJK-75-23 . . . ...
t !
li j Teslecopy- Region- f il, Attention: Mr. C. FeIerabend i
J- Janua ry - 10, 1975- -
l
! J.. Xeppler, Regional Director l Directorate of Regulatory Operations 3
Region. t il
- U. S. Atomic Energy Commission
! 799 Roosevelt Road j G1ca: Ellyn, IIlinois 60337' ,
\
e
! Reference r Quad-Cities Nuclear Power Station, Unit 1
- Docket No. 50-25%, DPR-20
! Appendix. A. Sections 1.0. A.5. and 6.6,a.11 a.
i' j
Dear Mr. Keppler:
! The purpose- of this letter is to provide you.with notification of an Ah- ,
! normal Occurrence as required, by Technical Spect fication. 6.6.8~.1.a within:.
i.
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the occurrence .
\
! WIthiquad-C1 ties Unit 1 in, the ColdsShutdown Condition-, weld. examinations l were conducted on the reactor recirculation discharge bypass lines. Two j weld- cracks were identified, at the Junction of each. of' the discharge.by-
- pass valve. (M0-1-0202.~7 A&B) four-inch downstreme sections and the 28-
j inch discharge h4ader.- Two indications have been~ found at the junction i of the upstream four-inch; section and the 28 inch: line. Final.amelyses 6
- and, plans are not complete
- at this time..
I l This occurrence was discussed by" telephone with. Mr. Feierabend of your
! office on January- 10, 1975 Fur:ther infonnation wl1-1 be provided by Ah-l normal. Occurrence Report AO 50-254/75-3 which.will be..submi tted within. i
- 10. days of the date of this occurrence. i l
') ;
Very- truly yours, I COMMONWEALTH' EDISON COMPANY j QUAD-ClTlES. NUCLEAR POWER STATION:
3 i
l!
J. Kalivianakis[
} N j Station Superintendent i
i NJK/LFG/lk.
k i cc: Directorate.of Licensing l J. S. Abei l 8306290185 751017
.I _
3 " ^ DUCK 05000254 /h- h _ __ ___ _
/7 t/. s o o nu, y s :. l mmMFMfMamm DIRECTORATE OF REGULATORY OPERATIONS
?
1+o . REGION III -h-
- f 5 d 799 ROOSEVELT ROAD p yrtgpwoug _
GLEN ELLYN. ILLINOIS 6o137 (312) 858-2660 o t h' , 2
!)
(/,/ 9 A. R0 Inspection Report No. i-Transmittal Date : 4 Distribution: Distribution:
R0 Chief, FS&EB R0 Chief, FS&EB -f RO:HQ (5) RO:HQ (4) .-
DR Central Files L:D/D for Fuels & Materials s Regulatory Standards (3) DR Central Files ]
Licensing (13) RO Files i R0 Files -
e B. RO Inquiry Report No. Y I
Transmittal Date :
(
Distribution: Distribution:
R0 Chief, FS&EB R0 Chief, FS&EB [
RO:HQ (5) RO:HQ J DR Central Files DR Central Files 7 Regulatory Standards (3) R0 Files -
Licensing (13) i R0 Files ,
C. Incident Notification From: Commonwealth Edison Co., Docket No. 50-254 5 (Licensee & Docket No. (or License No.)
Transmittal Date : bN '
a Distribution: Distribution: -
RO Chief,_FS&EB_ R0 Chief, FS&EB g RO:HQ (4) RO:HQ (4) 4 Licensing (4) L:D/D for Fuels & Materials i DR Central Files DR Central Files A R0 Files R0 Files
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- . T Honorable Joshua Eilberg , .
. J House of Representatives .
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Dear Mr. E11 berg. ,
~
a, .. . - - .
E . . . -
The following'181in reply to your letter of October 10,,1974, to . l Mr. Robert D., Ofjfeill'regarding cracks identified in auxiliary piping of ~. three bo.ilin.g water r. eac' tor facilities.; ,,3 a 0- --
.. ~ . . < , ,.'.1 .n ; : c<~^
y
Aftercrackbwerefoundinmid-Septecher1974infour,relativelysmall-
~
(4-inch diameter),bypans' links.,in r.e. act '
vater reactors in Illinois ~and a third,or. .c. o.olant' systems'at.two boi. ling
-- : ~
in Connecticut, the AEC on e .-
g- Septe$ber 19 ' notified 'alfftiliti%h'aYin(one or.cora operhting. boiling' '^
~
"c .
water reactors 'to czanine" these. bypass lines for evidence of cracks f '
within 60 days. AEC's notification covered _a total of 21 boiling water ~. >' '
g j reactors with AEC licenses authorizing their_ operation.. , .dt - y ,. ' t 9 , . . .r . .. .s ..
. ,r ' -
~
I Fifteen of the facilities, including the three whero cracks.were found ' '
O initially, have similar bypass piping systems. As of October 18,'tvelva ,
of theso had coupleted detailed examinations of their bypass piping V
systems. No additional cracks have been , identified in the 4-inch bypass b lines.
The utility operator of one of.the facilities in this category , . c - -
reported to AEC that examination of their piping system had been conducted ? -
I in December 1973, and the plant had not yet commenced power operation.c.~ - ~
AEC has not required reexamination of this facility.3Theiremaining two " " '
I facilities plan' examinations of their piping systems 1974.
by.mid-Novemberj '
j o
- s. : N.J -
. - 'N'
. e . m' , - . - .. .,
. ::. ^ 7 ;n .. . :: ? -
Six additional' operating boiling' . water. reactors of e,arlier' design eitheru....
(( do not hive' the bypass" piping syste:s ofjoncern'or~haveja' markedly dif-2
[' forent piping configuration (generally ' smaller) from those where cracks
- have been identified. . AEC is ,not rcquiring an' examination of the piping .
systems of these facilities 'at this' time.n The utility operators of four .
~
of these plants h'ave, however, notified the.AEC of plans to examine at , . - -
least portion's of their' piping ' systems'. ~
~
r
'fo. % 2,(d-
' .: n.-g i.:. s ,< ,m , c
- ?
'G .
The AEC Regulatory staff has been informed by' its licensecs, assisted
~
by the Ceneral Electric Company and AEC's Argonne National Laboratory [] f{ h.[
that preliminary findings indicate stress-assisted corrosion, caused, V _ .-
the cracks identified in mid-September. However, the sources of the i d - - ,
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