ML20084J162
From kanterella
| ML20084J162 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 11/24/1972 |
| From: | Stephenson B COMMONWEALTH EDISON CO. |
| To: | Giambusso A US ATOMIC ENERGY COMMISSION (AEC) |
| References | |
| BBS-72-7, NUDOCS 8305120209 | |
| Download: ML20084J162 (2) | |
Similar Documents at Quad Cities | |
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Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20084K4981976-10-0505 October 1976
[Table view]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 Category:TEXT-SAFETY REPORT MONTHYEARML20217A9931999-09-30030 September 1999
[Table view]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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