ML20085F612
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| ML20085F612 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 11/15/1974 |
| From: | Sewell R CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20085F616 | List: |
| References | |
| AO-17-74, NUDOCS 8308230061 | |
| Download: ML20085F612 (1) | |
Similar Documents at Palisades | |
|---|---|
Category:ABNORMAL OCCURRENCE REPORTS (SEE ALSO LER & RO)
MONTHYEARML20085F6511976-04-12012 April 1976
[Table view]Update to AO AO-75-15 Re Containment Air Cooler Temp Control Valve Body Failure.Spare Valve Procurement Requirement Changed from ASME Section III Stds to ANSI B31.1 Stds. Sys Built to B31.1 Std ML20085E7841975-11-14014 November 1975 Telecopy Message Ao:On 751113,CB Exhaust Valves Leaked in Excess of Total Allowable Rate Back Through Inside Valve. Valves to Be Tagged Shut Until Repaired During Next Plant Shutdown ML20085E7971975-10-30030 October 1975 Telecopy Message Ao:On 751029,interchanged W Prime Curves Resulted in Nonconservative Heat Rate Calculation for Core Limiting Assemblies.Caused by Improper Conversion of Flux to Power by Inca Power Distribution on 730619 ML20085E8231975-10-24024 October 1975 AO 75-024:on 751015,thermal Discharge of Blowdown from closed-cycle Cooling Sys Found Above Permissible Temp Limit. Caused by Shutoff Dilution Pumps During Installation of New Thermal Discharge Monitoring Equipment.Procedure Revised ML20085E8081975-10-15015 October 1975 Telecopy Message Ao:On 751015 Discharge Water Temp Exceeded Tech Spec Limits by 5 Degrees During Temp Monitoring Equipment Installation ML20085F7071975-09-19019 September 1975 Updated AO AO-74-11 Revising Analysis of Occurrence.Loss of Dc Control Power to Bus 1D Feeder Breaker 72-203 Results in Breaker Not Being Able to Operate If Equipment Malfunctions ML20085E8721975-09-18018 September 1975 Telecopy Message AOs 75-022 & 75-021:boron Concentration Found Below Tech Spec Limits & HPSI Safety Injection Valve Found W/Apparent Disc Separation.Valve MOV-3007 to Be Disassembled & Evaluated.Investigation Continues ML20085E8811975-09-15015 September 1975 Telecopy Message Aos:Safety Tank Boric Acid Concentration Found Below Tech Spec Limits & HPSI Valve MOV-3007 Failed. Further Info Will Be Submitted ML20085F7201975-09-0909 September 1975 AO 75-019:on 750830,control Rod 11 Dropped Into Core.Caused by Shorted Clutch Coil.Clutch Replaced ML20085F6891975-09-0808 September 1975 Telecopy Message of AO 75-020:on 750905,control Rod 16 Dropped.Flux Tilt & Ejected Rod Worth Resulting from Dropped Rod within Tech Spec Limits.Clutch Coil Replaced ML20085F7491975-08-28028 August 1975 AO 75-018:on 760817,control Rod 19 Dropped Into Core.Caused by Shorted Clutch Coil.Clutch Replaced.Preventive Maint,To Include Insulation & Component Resistance Measurements on Control Rod Drive Mechanisms,To Be Evaluated ML20085F7671975-08-18018 August 1975 Telecopy AO 75-018:on 750817,control Rod 19 Dropped Into Core.Caused by Shorted Clutch Coil in Control Rod Drive Mechanism ML20085F7961975-08-12012 August 1975 AO 75-016:on 750722,radwaste Batch 75-021 R Discharge Rate Exceeded.Caused by Inaccurate Flow Control Due to Water Loss in One Leg of Flow Controller FIC 1050.Radwaste Release Procedures Revised ML20085F7721975-08-12012 August 1975 AO 75-017:between 750718-28,waste Gas Decay Tank T 101C Lost Pressure.Probably Caused by Small Valve Leak.Tank Will Be Monitored During Next Period of Use Since Tests Did Not Determine Pressure Drop Cause ML20085F8731975-07-25025 July 1975 Telecopy Ao:On 750716,util Water Storage Tank T-91 Removed from Svc to Replace Liner Coating ML20085F8041975-07-24024 July 1975 Telecopy AO 75-016:radwaste Batch Discharge Rate Exceeded During Release of Radwaste Batch 75-021-R.Caused by Malfunctioning Flow Controller FIC 1050 ML20085F8631975-07-22022 July 1975 Telecopy Ao:On 750719,MOV-3011 Functioned Improperly During QO-1 Test.Caused by Failure of Spring Return Switch,Ge Type CR 2940 ML20085F3581975-07-11011 July 1975 AOs AO-75-6,AO-75-7 & AO-75-13 Have Been Canceled.Tech Specs Re Heated Discharge Do Not Apply to Svc Water Sys or Other Discharge ML20085F9101975-07-0808 July 1975 AO 75-014:on 750630,bus 1D Failed to Transfer from Station Power to Startup Power.Caused by Failure of Incoming Breaker 152-202 to Close Automatically Due to Diesel Generator Breaker 152.213 Interlock.Synchrocheck Circuitry Repaired ML20085F9271975-07-0202 July 1975 AO 75-014 & RO 75-004:on 750701,bus 1D Failed to Fast Transfer from Station to Startup Power & Control Rod 38 Deviated by 9 Inches,Respectively.Ao Caused by Faulty Auxiliary Contact.Ro Caused by Shorted Capacitor ML20085F9151975-07-0202 July 1975 Telecopy Message AO 75-014:on 750701,bus 1D Failed to Transfer from Station Power to Startup Power.Caused by Faulty Auxiliary Contact on Incoming Bus Breaker.Ro 75-004, on 750701,control Rod 38 Deviated Due to Capacitator Short ML20085F9501975-06-30030 June 1975 AO 75-013:on 750619,plant Discharge Water Temp & Heat Rate Exceeded Tech Spec Limits.Caused by Changing Lower Basin Level.Addl Operating Procedures to Be Formulated for Raising & Lowering Cooling Tower Basin Levels ML20085F9601975-06-23023 June 1975 Telecopy AO 75-013:on 750619,mixing Basin Outfall Exceeded Lake Temp Differential While Adjusting Cooling Tower Makeup to Allow Evaporation Changes.Details Will Follow ML20085F5821975-06-18018 June 1975 Updated AOs AO-21-74,AO-6-75 & AO-7-75,in Response to 750512 Request for Addl Info.Cause of Failure of Diesel Generator 1-1 Air Start Motor Not Determined ML20085F9761975-06-13013 June 1975 AO 75-012:on 750603,required Measurements & Observations Re Closed Cycle Condenser Cooling Sys Chlorination Treatment Not Performed.Caused by Incorrectly Conceived Tech Specs ML20085F9961975-06-0606 June 1975 Telecopy Message AO 75-012:on 750606,difficulty Encountered in Adhering to Tech Spec Section 3.9.7-3.9.9 Re Cooling Tower Chlorination Limits ML20085F9991975-05-30030 May 1975 Telecopy AO 75-011:on 750529,overpower Trip Setpoint on NI005 Found Out of Spec During Surveillance Test MO1 ML20085F3251975-04-28028 April 1975 AO AO-75-9:on 741223,three Reactor Trip Pressure Switches, PS-1801,PS-1802 & PS-1803 Found Out of Calibr.Caused by Use of Incorrect Procedure for Switch Calibr.Instrument Index Revised to Ref Proper Tech Spec Section ML20085F3221975-04-23023 April 1975 AO AO-10-75:on 750413,in-core Readings on Primary Data Logger Failed to Update.Caused by Deficient Software Program.Program Being Analyzed to Find & Correct Deficiency ML20085F3341975-04-18018 April 1975 Telecopy AO AO-75-8:three Containment High Pressure Switches Found Out of Calibr ML20085F3281975-04-17017 April 1975 AO AO-75-8 Has Been Canceled.Review of Temp Measuring Techniques Disclosed Temp Measurements in Error.Revised Measurements Show Discharge Temp within Allowable Limits ML20085F3771975-04-16016 April 1975 AO AO-75-7:on 750406,plant Discharge Effluent Heat Rate & Discharge Temp Increase Found Greater than Tech Spec Limits. Apparently Caused by Plant Procedure Problems & Beginning Operation of Newly Installed Closed Cycle Cooling Sys ML20085F3981975-04-14014 April 1975 AO AO-75-6:on 750404,plant Discharge Effluent Heat Rate Exceeded Tech Specs.Apparently Caused by Plant Procedure Problems & Beginning Operation of Newly Installed Closed Cycle Cooling Sys ML20085F4201975-04-11011 April 1975 AO AO-75-5:on 750411 Unsampled South Filtered Waste Tank W/Laundry Waste Released.Caused by Use of Wrong Batch Card. Tank Release Terminated Until Appropriate Analysis Could Be Made ML20085F3441975-04-0808 April 1975 AO AO-75-8:from 750406-07,indicated Temp of Mixing Basin Discharge More than 5 F Above Indicated Temp of Plant Intake Water.Caused by Excess Amount of Water Going Over Cooling Tower Pump Makeup Basin Overflow ML20085F4271975-04-0707 April 1975 Telecopy AO AO-75-5:on 750401,unsampled Liquid Waste Tank of Laundry Waste Released.Caused by Two Tank Analyses on Same Tank.Tank Release Stopped & Analysis of Tank Contents Made. Tank Released on 750403 ML20085F3881975-04-0606 April 1975 Telecopy AO AO-75-7:on 750406,plant Discharge Effluent from Mixing Basin Exceeded Tech Spec Limit.Caused by Cracking Open of Condenser Inlet Valve MOV-5301 to Reduce Hotwell Temp to Avoid Thermal Shocking Condenser Tubes ML20085F4081975-04-0404 April 1975 Telecopy AO AO-75-6:on 750404,plant Discharge Effluent Heat Rate Exceeded Tech Specs.Caused by Diversion of Dilution Water Through Unused Side of Condenser.Personnel Unaware of Difference in Temp Between Inlet Water & Basin Outfall ML20085F4511975-03-27027 March 1975 Update to AO AO-4-75,revising Analysisi of Occurrence.Util Discovered 102 restraints,12 Restraint Replacements & 74 Restraint Mods Required or Added for Addl Conservatism. Sys Studied Listed ML20085F4561975-03-17017 March 1975 AO AO-4-75:on 750307,util Determined Certain Seismic Class I Piping Sys Restraints Do Not Comply W/Fsar Design Criteria. Investigation Into Cause Underway.Sys Studied Listed ML20085F5181975-02-0404 February 1975 AO AO-2-75:on 750126,vol Control Tank Gas Lost to Auxiliary Bldg.Caused by Bank Pressure Due to Venting of Vol Control Tank Which Blew Loop Seal on Evaporator Vacuum Pump Air Water Separator ML20085F5091975-02-0404 February 1975 AO AO-3-75:on 750122,leak in Component Cooling Water to Svc Water Header Discovered.Cause Not Stated.Leak Developed 750116.Leaking Tube Plugged ML20085F5231975-01-31031 January 1975 AO AO-75-1:on 741206,allowable Leak Rate Exceeded on Purge Air Supply Valve CV-1808 During Test.Caused by Lack of Sufficient Lubricant Aggravated by Unusual Svc Condition. Packing Properly Greased & Leakage Reduced ML20085F5151975-01-28028 January 1975 AO Telecopy 75-2:on 750126,vol Control Tank Gas Lost to Auxiliary Bldg.Caused by Discharge of Orificed Recirculation Line from Vacuum Pump Back to Evaporator,Causing Erratic Evaporator Operation ML20085F5061975-01-26026 January 1975 AO 75-3:on 750122,leak Suspected in One Component Cooling Water Hx.Component Cooling Water a Isolated.Leak Developed on 750116.Caused by Leaking Tube.Tube Plugged ML20085F5361974-12-26026 December 1974 AO AO-28-74:on 741215,north Filtered Waste Tank of Laundry Waste Released W/O Prior Sampling.Caused by Technician Error.Wrong Tank Identification Wrote on Batch Card When Transposing Data ML20085F5391974-12-17017 December 1974 Telecopy AO AO-74-28:on 741215,north Filtered Waste Tank of Laundry Waste Released W/O Prior Sampling.Caused by Technician Error.Technician Wrote Down Incorrect Tank Identification on Batch Card ML20085F5471974-12-12012 December 1974 AO AO-27-74:on 741130,released to Plant Vent Stack from Waste Gas Surge Tank.Caused by Waste Gas Surge Tank Leakage, Due to Leaky Relief Valve.Valve Repaired & Pressure Tested ML20085F5521974-12-0202 December 1974 AO AO-74-27:on 741130,waste Gas Surge Tank Vented to Plant Stack.Continuous Stack Monitor Alarmed.Caused by Malfunction of Waste Gas Surge Tank Pressure Relief Valve.Total of 40 Mci Released in 3 Cubic Meters Radioactive Gases ML20085F5291974-11-18018 November 1974 Updated AO AO-24-74 Re Greater than Allowed Ph Difference Between Lake Inlet & Outlet Water.Caused by Cooling Tower Acid Injection Sys Continuing to Operate After Pump Shut Off Due to Incorrect Relocation of Sample Probe 1976-04-12 Category:TEXT-SAFETY REPORT MONTHYEARML18066A6901999-11-0101 November 1999
[Table view]Rev 5 to Palisades Nuclear Plant Colr. ML18066A6761999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Palisades Nuclear Plant ML18066A6271999-09-0202 September 1999 LER 98-011-01:on 981217,inadequate Lube Oil Collection Sys for Primary Coolant Pumps Was Noted.Caused by Design Change Not Containing Appropriate Level of Rigor.Exemption from 10CFR50,App R Was Requested.With 990902 Ltr ML18066A6351999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Palisades Nuclear Plant ML18066A6771999-08-31031 August 1999 Operating Data Rept Page of MOR for Aug 1999 for Palisades Nuclear Plant ML18066A6221999-08-20020 August 1999 LER 99-002-00:on 990722,TS Surveillance Was Not Completed within Specified Frequency.Caused by Failure to Incorporate Revised Frequency Into Surveillance Schedule in Timely Manner.Verified Implementation.With 990820 Ltr ML18066A6061999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Palisades Nuclear Plant.With 990803 Ltr ML18066A5201999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Palisades Nuclear Plant.With 990702 Ltr ML18066A4841999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Palisades Nuclear Plant.With 990603 Ltr ML18066A6371999-04-30030 April 1999 Revised Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant ML18068A5941999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Palisades Nuclear Plant.With 990503 Ltr ML18066A4161999-04-0101 April 1999 Rev 4 to COLR, for Palisades Nuclear Plant ML18066A4501999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for Palisades Nuclear Plant.With 990402 Ltr ML18066A4671999-03-31031 March 1999 Rev 0 to SIR-99-032, Flaw Tolerance & Leakage Evaluation Spent Fuel Pool Heat Exchanger E-53B Nozzle Palisades Nuclear Plant. ML18068A5351999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Palisades Nuclear Plant.With 990302 Ltr ML18066A3931999-01-31031 January 1999 Monthly Operating Rept for Jan 1999 for Palisades Nuclear Plant.With 990202 Ltr ML18066A3781999-01-20020 January 1999 LER 98-013-00:on 981222,safeguards Transfer Tap Changer Failure Caused Inadvertant DG Start.Caused by Failed Motor Contactor.Contactor Was Replaced.With 990120 Ltr ML20206F6131998-12-31031 December 1998 1998 Consumers Energy Co Annual Rept. with ML18066A3651998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Palisades Nuclear Plant.With 990105 Ltr ML18066A3421998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Palisades Nuclear Plant.With 981202 Ltr ML18066A3301998-11-11011 November 1998 Part 21 Rept Re Potential Safety Hazard Associated with Wrist Pin Assemblies for FM-Alco 251 Engines at Palisades Nuclear Power Plant.Caused by Insufficient Friction Fit Between Pin & Sleeve.Supplier of Pin Will No Longer Be Used ML18068A4921998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Palisades Nuclear Plant.With 981103 Ltr ML18068A4851998-10-29029 October 1998 LER 97-011-01:on 971012,starting of Primary Coolant Pump with SG Temps Greater than Cold Leg Temps Occurred.Caused by Inadequate Procedures & Operator Decision.Sop Used for Starting Primary Coolant Pump Enhanced ML18066A3181998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Palisades Nuclear Plant ML18066A2901998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Palisades Nuclear Power Plant.With 980903 Ltr ML18066A3191998-08-31031 August 1998 Revised Monthly Operating Rept Data for Aug 1998 for Palisades Nuclear Plant ML18066A2831998-08-18018 August 1998 LER 98-010-00:on 980721,reactor Manually Tripped.Caused by Failure of Coupling Which Drives Feedwater Pump Main Lube Oil Pump.Main Lube Oil Pump Coupling & Associated Components Replaced & Satisfactorily Tested ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20237E0301998-07-31031 July 1998 ISI Rept 3-3 ML18066A2701998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Palisades Nuclear Plant.W/980803 Ltr ML18066A2311998-06-30030 June 1998 Monthly Operating Rept for June 1998 for Palisades Nuclear Plant ML18066A2261998-06-30030 June 1998 LER 98-009-00:on 980531,small Pinhole Leak Found on One of Welds,During Leak Test Following Replacement of Pcs Sample Isolation Valves.Caused by Welder Error.Leaking Welds Repaired ML18066A3061998-06-18018 June 1998 SG Tube Inservice Insp. ML20249C4951998-06-17017 June 1998 Rev 1 to EA-GEJ-98-01, Palisades Cycle 14 Disposition of Events Review ML18066A1781998-06-0909 June 1998 LER 98-008-00:on 980511,noted That Procedure Did Not Fully Satisfy Requirement to Test High Startup Rate Trip Function. Caused by Misunderstanding of Testing Requirements.Revised TS Surveillance Test Procedure & Reviewed Other Procedures ML18066A1711998-06-0101 June 1998 Part 21 Rept Re Impact of RELAP4 Excessive Variability on Palisades Large Break LOCA ECCS Results.Change in PCT Between Cycle 13 & Cycle 14 Does Not Constitute Significant Change Per 10CFR50.46 ML18066A1741998-05-31031 May 1998 Monthly Operating Rept for May 1998 for Palisades Nuclear Plant.W/980601 Ltr ML18066A2321998-05-31031 May 1998 Revised MOR for May 1998 for Palisades Nuclear Plant ML18068A4701998-05-31031 May 1998 Annual Rept of Changes in ECCS Models Per 10CFR50.46. ML18065B2451998-05-13013 May 1998 LER 98-007-00:on 980413,HPIS Sys Was Noted Inoperable During TS Surveillance Test.Caused by Performance of Flawed Procedure.Operators & Engineers Will Be Trained to Improve Operational Decision Making Through Resources & Knowledge ML18066A2331998-04-30030 April 1998 Revised MOR for Apr 1998 for Palisades Nuclear Plant ML18068A3461998-04-30030 April 1998 Monthly Operating Rept for Apr 1998 for Palisades Nuclear Plant.W/980501 Ltr ML18066A3411998-04-22022 April 1998 Rev 0 to EMF-98-013, Palisades Cycle 14:Disposition & Analysis of SRP Chapter 15 Events. ML18065B2071998-03-31031 March 1998 Monthly Operating Rept for Mar 1998 for Palisades Nuclear Plant.W/980403 Ltr ML20217C2741998-03-31031 March 1998 Independent Review - Is Consumers Energy Method (W Method) of Determining Palisades Nuclear Plant Best Estimate Fluence by Combining Transport Calculation & Dosimetry Measurements Technically Sound & Does It Meet Intent of Pts ML18066A2341998-03-31031 March 1998 Revised MOR for Mar 1998 for Palisades Nuclear Plant ML18068A3041998-02-28028 February 1998 Monthly Operating Rept for Feb 1998 for Palisades Nuclear Plant.W/980302 Ltr ML18066A2351998-02-28028 February 1998 Revised MOR for Feb 1998 for Palisades Nuclear Plant ML18065B1641998-02-0505 February 1998 Rev 0 to Regression Analysis for Containment Prestressing Sys at 25th Year Surveillance. ML18067A8211998-01-31031 January 1998 Monthly Operating Rept for Jan 1998 for Palisades Nuclear Plant.W/980203 Ltr 1999-09-30 |
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ru November 15, 197h Re: Docket 50-255 Directorate of Licensing License DPR-20 US Atomic Energy Commission Palisades Plant Washington, DC 20545 A0-17-74 Additional Information Gentlemen:
Our letter of September 9,1974 submitted Abnormal Occurrence Report A0-17-74 on cracking of a letdown line vent pipe. This letter is written to provide the results of the laboratory examination, which we indicated would be submitted when they became available.
The metallurgical examination of a fracture section of the stainless letdown line revealed that the tube failed in a fatigue manner at the heat-affected zone of the veld joint.
Since this vent has been completely removed, we plan no further action.
Yours very truly, Ralph B. Sewell (Signed)
DAB / map Ralph B. Sewell Nuclear Licensing Administrator CC: JGKeppler, USAEC 8309230061 741115 PDR ADOCK 05000255 S PDR db yo' 11749 COPY SEN1' REGION
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