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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217A1691999-09-22022 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 ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected ML20141K7711997-03-10010 March 1997 Preliminary Part 21 Rept Re Parsons Peebles/Electric Products Generators W/Modified Bearing Insulation.Util Implemented Mod to Add Insulation to Outer Spacer Ring ML20132D8091996-12-18018 December 1996 Part 21 Rept Re Defect of Welds on Weld Nut Holding Filter Assembly Panel.Failure of Weld or Weld Nut Could Allow Filter Assembly Panel to Break Loose Under Seismic Stress & Cause Damage to Other Components in Charger ML20086T1761995-07-19019 July 1995 Part 21 Rept Re Potential Problem W/Type 51s & 87T Relays. Potential Problem Identified as Defective Tap Block. Recommends That Users Identified on Attachment 1 Page Verify Testing Per Instruction Listed on Encl Product Advisory Ltr ML20083R7961995-04-24024 April 1995 Interim Part 21 Rept Re Contact Failure of Square D Type Kpd Relay Used in Diesel Generator Control Panel.Relays Replaced at Plant.Review of Matter Expected to Be Completed on 950508 ML20082D9011995-01-27027 January 1995 Final Part 21 Rept Re Valves Installed W/Shim Between Yoke & Adapter Plate Involved in Jan 1994 Incident.Caused by Operational Problems Involving Maint Procedures.Ltr Sent to Affected Utils.Item Not Reportable Under 10CFR21 ML20080D5921994-12-28028 December 1994 Submits Followup to 940418 Part 21 Re Investigation W/ Respect to Jan 1994 Incident at Prairie Island Generating Plant Involving Crane Design Gate Valves ML20077C2801994-11-21021 November 1994 Deficiency Rept Re Defective Yokes P/N 342849 Mfg by Copes- Vulcan,Inc.Affected Utilities Notified & Defective Yokes Will Be replaced.Copes-Vulcan Also re-inspected All Yokes in Inventory & Verified Yokes Acceptability ML20072S9581994-08-30030 August 1994 Part 21 Rept Re Crane Design Gate Valves Involved in Jan 1994 Incident at Praire Island Nuclear Generating Plant. Historical Records Do Not Contain Info Addressing Total Number of Configuration Mfg by Crane ML20065G4671994-04-0101 April 1994 Part 21 Rept Re Failure of Support Studs on Discharge Piping Bracket to Turbocharger That Provide Support for Air Inlet Housing ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20035E4861993-04-0707 April 1993 Part 21 Rept Re K-400 Circuit Breaker Failed to Meet Certain Rating Requirements Based on ANSI C37.16.Licensees Scheduled Tests on Modified Arc Chutes in Several Different Modes at KEMA-Powertest Lab in Chalfont,Pa ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20028H3531990-12-13013 December 1990 Part 21 Rept Re Cable Assemblies Failing to Meet IEEE-383 Section 3 Flammability Tests.Results of Tests Conducted on 901206 Encl.Corrective Actions Include Applying Flame Retardant Covering to Cable or Cable Replacement ML20055J0741990-07-24024 July 1990 Part 21 Rept Re Error in Westinghouse ECCS Decay Heat Model. Initially Reported on 900712.Error Resulted in Nonconservative Decay Heat Source & Does Not Constitute Actual Operational Safety Concern.Meeting Scheduled NRC-90-3528, Part 21 Rept Re Potential Problem in Decay Heat Model of Wcobra/Trac Computer Code.Model Corrected & Calculations Initiated.Recalculations of App K Analyses for Plants Will Be Completed by 9007231990-07-16016 July 1990 Part 21 Rept Re Potential Problem in Decay Heat Model of Wcobra/Trac Computer Code.Model Corrected & Calculations Initiated.Recalculations of App K Analyses for Plants Will Be Completed by 900723 ML13316A0481990-04-0303 April 1990 Part 21 Rept Re Drum Brake on Retrofit Crane Trolley Not Setting After drive-train Failure.Caused by Improper Design of Slide.Slide Replaced W/New Design Which Prevents Jamming of Mechanism.Instructions Sent to Utils ML13316A0471990-04-0303 April 1990 Part 21 Rept Re Problem Found During Test of X-SAM Sys in England.Drawings of Mechanical Component Called Slide Revised & Slides at Installations Will Be Replaced W/Ones of New Design to Eliminate Problem ML20012C1051990-03-0707 March 1990 Part 21 Rept Re Several Failures of Fairbanks Morse Engine Div Piston Pins/Bushings on Upper Pistons.Caused by Incorrect Surface Pattern on Piston Pins.Piston Pins Under Listed Purchase Orders to Be Removed & Replaced ML20012A9011990-02-27027 February 1990 Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp ML20011F1941990-02-22022 February 1990 Part 21 Rept Re ABB 27/59 Relay Catalog Series 211L.Solder Connections to Printed Wiring Runs on Bottom of Circuit Board Deteriorated Due to Thermal Stress.No Actual Failure Occurred & Relays to Be Changed at Next Outage ML20011F5971990-02-22022 February 1990 Part 21 Rept Re Solder Connections in ABB 27/59 Relays Deteriorated Due to Thermal Stress,Causing Bonding of Printed Wiring Pattern to Glass Epoxy Circuit Board.Interim Circuit Board W/Larger Pads & Higher Wattage Will Be Used ML18153C1011990-02-0202 February 1990 Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N ML20006A3611990-01-17017 January 1990 Part 21 Rept 152 Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generator Sys Supplied to Listed Sites by Cooper Industries.Qualified Replacement Valve in Process of Being Specified.Info Will Be Available by 900215 ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced B13420, Part 21 Rept Re Fire Zone R 600 Volt Cable from Rockbestos Co.During performance-based Audit of Rockbestos,Acceptable Supporting Documentation in Rept Which Qualified Similar Product, Fire Wall SR, Could Not Be Found1990-01-0202 January 1990 Part 21 Rept Re Fire Zone R 600 Volt Cable from Rockbestos Co.During performance-based Audit of Rockbestos,Acceptable Supporting Documentation in Rept Which Qualified Similar Product, Fire Wall SR, Could Not Be Found ML13316A0401989-11-28028 November 1989 Part 21 Rept 151 Re Intake Rocker Arm Assembly of Standby Diesel Generator.Deficiency Covers Potential Interface Between Connector Push Rod & End Socket of Rocker Arm. Initially Reported on 891013.Rocker Arm Sketch Encl ML19325E0861989-10-16016 October 1989 Followup Part 21 Rept Re Class 1E Battery Chargers W/ Transformers Running at Temps Exceeding Those Used in Qualification Rept When Operating at or Near Full Load Rating of Equipment.Listed Corrective Actions Underway NRC-89-3462, Part 21 Rept Re Potential of Ambient Compensated Molded Case Circuit Breakers to Deviate from Published Info. Instantaneous Trip Check Will Be Instituted on All Class 1E Thermal/Magnetic Ambient Breakers Prior to Shipment1989-10-0909 October 1989 Part 21 Rept Re Potential of Ambient Compensated Molded Case Circuit Breakers to Deviate from Published Info. Instantaneous Trip Check Will Be Instituted on All Class 1E Thermal/Magnetic Ambient Breakers Prior to Shipment ML19325C9521989-09-29029 September 1989 Part 21 Rept Re Potential Common Failure of SMB-000 & SMB-00 Cam Type Torque Switches Supplied Prior to 1981 & 1976. Vendor Recommends That Switch W/Fiber Spacer Be Replaced ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating ML20246P7111989-07-17017 July 1989 Part 21 Rept Re Quench Cracks in Bar of A-SA-193 Grade B7 Component.Quench Cracks Found in One Bar of Matl.Listed Purchasers Informed of Potential Defect.Next Rept Will Be Submitted When Addl Info Becomes Available ML20247D3011989-07-12012 July 1989 Part 21 Rept 10CFR21-0047 Re Control Wiring Insulation of Inner Jacket Used on General Motors Diesel Generator Sets Identified as 999 or MP Series.Encl List of Owners of Units Notified ML20245B6651989-06-15015 June 1989 Part 21 Rept 150 Re Potential Defect in Component of Dsr Standby Diesel Generator.Cause of Failure Determined to Be Combination of Insufficient Lubrication to Bushings.Listed Course of Action Recommended at Next Scheduled Engine Maint ML20246K6681989-05-30030 May 1989 Part 21 Rept Re Defects Discovered in Nbfd & BF-type Relays Ordered from Westinghouse.Relays Returned to Mfg to Perform Extensive Functional Testing of Relays Installed & QA Audit of Vendor to Evaluate Relay Dedication Process Scheduled ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves ML20244D8161989-04-13013 April 1989 Part 21 Rept Re Failure of Rosemount Transmitters.All Failed Transmitters Replaced,Inservice Test Procedure Prepared & Monthly Test of All 12 Transmitters in RCS Throughout Cycle 2 Operation Will Be Performed.Review Continuing ML20247P7991989-04-0404 April 1989 Part 21 Rept Re Atmospheric Dump Valves.Cause of Failure Speculative But Result of Piston Ring That Failed to Seal. Resolution to Problem Requires Increasing Pilot Valve Capacity & Reworking of Plug to Enlarge Pilot Flow Area ML13316A0321988-12-22022 December 1988 Part 21 Rept Re Spot Welds on DB-50 Reactor Trip Breaker Secondary Contact Bracket Observed to Be Separated.Initially Reported on 881213.Utils Have Been Advised That Secondary Contact Bracket May Be Modified by Drilling Holes in Welds ML13316A0331988-12-20020 December 1988 Part 21 Rept Re Potential Problem W/Repair Kits Provided for Specific Pressure Regulator in Air Start Sys of Dsrv Standby Diesel Generator.Recommends Kits Be Removed from Stock & Disposed of Immediately ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML20205F3211988-10-10010 October 1988 Part 21 Rept Re Potential Deviation from Tech Spec Concerning Ry Indicators Due to Operating Temp Effect on Analog Meter Movement.Initially Reported on 881006.Customers Verbally Notified on 881006-07 ML20207P0451988-10-0505 October 1988 Part 21 Rept 146 Re Defect in Left Intercooler Inlet Adapter on Standby Diesel Engine Generator.Recommends Utils Inspect Left Intake Manifold Drain as Part of Operating Plan.Addl Info Expected by 881015 ML20207P0151988-10-0404 October 1988 Part 21 Rept Re Fuel Nozzle Tips in Standby Diesel Generator KSV-20-T W/Cracks Permitting Diesel Fuel to Be Sprayed Into Cylinders.Heavy Vapors Observed Emitting from Breathers on Some Cylinder Heads 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217G4461999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pingp.With 05000266/LER-1999-007, :on 990831,cable Tray Fire Stops Do Not Meet App R Exemption Requirements Occurred.Caused by Improper Installation of Approved Plant Mod.New Mod Has Been Initiated to Provide Three H Rated Fire Barrier1999-09-30030 September 1999
- on 990831,cable Tray Fire Stops Do Not Meet App R Exemption Requirements Occurred.Caused by Improper Installation of Approved Plant Mod.New Mod Has Been Initiated to Provide Three H Rated Fire Barrier
NPL-99-0569, Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbnp,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 ML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 05000266/LER-1999-004, :on 990420,fuel Oil Transfer Pump Cable in AFW Pump Room Was Noted Outside App R Design Basis.Caused by Error in Design of New Fuel Oil Transfer Sys.Condition Rept CR 99-1140 Was Initiated1999-09-0202 September 1999
- on 990420,fuel Oil Transfer Pump Cable in AFW Pump Room Was Noted Outside App R Design Basis.Caused by Error in Design of New Fuel Oil Transfer Sys.Condition Rept CR 99-1140 Was Initiated
NPL-99-0051, Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with ML20216E7151999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pingp,Units 1 & 2. with ML20211J2851999-08-26026 August 1999 Safety Evaluation Supporting Amends 146 & 137 to Licenses DPR-42 & DPR-60,respectively ML20211D3981999-08-24024 August 1999 Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively ML20211A7641999-08-11011 August 1999 Safety Evaluation Supporting Amends 190 & 195 to Licenses DPR-24 & DPR-27,respectively ML20211C2531999-08-0404 August 1999 Unit 1 ISI Summary Rept Interval 3,Period 2 Refueling Outage Dates 990425-990526 Cycle 19 971212-990526 ML20210Q4891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pingp,Units 1 & 2. with ML20211B5971999-07-31031 July 1999 Cycle 20 Voltage-Based Repair Criteria 90-Day Rept NPL-99-0449, Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with 05000282/LER-1999-007-01, :on 990625,loss of CR Special Ventilation Function Was Noted.Caused by Broken Door Latch Pins on CR Chiller Door.Ts Amend Request to Establish Allowed OOS Time Was Submitted1999-07-23023 July 1999
- on 990625,loss of CR Special Ventilation Function Was Noted.Caused by Broken Door Latch Pins on CR Chiller Door.Ts Amend Request to Establish Allowed OOS Time Was Submitted
ML20209J1131999-07-15015 July 1999 Safety Evaluation of Topical Rept NSPNAD-8102,rev 7 Reload Safety Evaluation Methods for Application to PI Units. Rept Acceptable for Referencing in Prairie Island Licensing Actions ML20209F9811999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20196J4251999-06-30030 June 1999 Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 ML20209D2691999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbnps,Units 1 & 2 ML20196F4081999-06-23023 June 1999 Revised Pages 71,72 & 298 to Rev 7 of NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units ML20196F3341999-06-22022 June 1999 Safety Evaluation for Implementation of 422V+ Fuel Assemblies at Pbnp Units 1 & 2 ML20195F9781999-06-10010 June 1999 Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1 ML20195D6151999-06-0202 June 1999 Safety Evaluation Supporting Amends 145 & 136 to Licenses DPR-42 & DPR-60,respectively ML20195G5181999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With . Page 3 in Final Rept of Incoming Submittal Was Not Included NPL-99-0328, Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with ML20209D2751999-05-31031 May 1999 Revised MORs for May 1999 for Pbnps,Units 1 & 2 05000301/LER-1999-003-01, :on 990505,licensee Personnel Discovered That Refueling Interval Surveillance of Emergency Lighting Required by TS 15.4.6.A.3 Was Not Conducted.Cause Unknown. Task Sheet call-ups for Both Procedures Have Been Created1999-05-28028 May 1999
- on 990505,licensee Personnel Discovered That Refueling Interval Surveillance of Emergency Lighting Required by TS 15.4.6.A.3 Was Not Conducted.Cause Unknown. Task Sheet call-ups for Both Procedures Have Been Created
ML20207B5931999-05-26026 May 1999 SER Accepting Licensee Proposed Alternative to ASME Code for Surface Exam (PT) of Seal Welds on Threaded Caps for Unit 1 Reactor Vessel Head Penetrations for part-length CRDMs 05000266/LER-1999-004, :on 990420,discovered That Fuel Oil Transfer Pump Cable in AFW Pump Room Outside App R Design Basis. Caused by Cable Routing Discrepancy.Fire Rounds Increased & Procedures Being Developed to Facilitate Using G-05 EDG1999-05-20020 May 1999
- on 990420,discovered That Fuel Oil Transfer Pump Cable in AFW Pump Room Outside App R Design Basis. Caused by Cable Routing Discrepancy.Fire Rounds Increased & Procedures Being Developed to Facilitate Using G-05 EDG
ML20196L2501999-05-13013 May 1999 Rev 0 to PINGP Unit 1 COLR Cycle 20 05000282/LER-1999-005-01, :on 990508,containment Inservice Purge Sys Was Not Isolated During Heavy Load Movement Over Fuel.Caused by Missing Procedure Step in D58.1.6.PINGP 1224 Was Initiated to Communicate Event & Forestall Repeating Event1999-05-0808 May 1999
- on 990508,containment Inservice Purge Sys Was Not Isolated During Heavy Load Movement Over Fuel.Caused by Missing Procedure Step in D58.1.6.PINGP 1224 Was Initiated to Communicate Event & Forestall Repeating Event
05000266/LER-1999-003, :on 990406,TS SR for ECCS & Containment Spray Was Not Fully Implemented.Caused by Conservative Interpretation of Valve Impact.Revised Procedures.With1999-05-0606 May 1999
- on 990406,TS SR for ECCS & Containment Spray Was Not Fully Implemented.Caused by Conservative Interpretation of Valve Impact.Revised Procedures.With
NPL-99-0273, Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With ML20196F3521999-04-30030 April 1999 Non-proprietary WCAP-14788, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt - NSSS Power) ML20206L6191999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pingp,Units 1 & 2. with ML20206A5031999-04-23023 April 1999 Safety Evaluation Supporting Amends 189 & 194 to Licenses DPR-24 & DPR-27,respectively 05000301/LER-1999-002-01, :on 990323,discovered That Red Channel of SG Pressure Indication Passes Through Fire Zone.Caused by 1983 Modification Oversight.Twice Per Shift Fire Round Has Been Established for Fire Zone Pending Cable Routing Correction1999-04-16016 April 1999
- on 990323,discovered That Red Channel of SG Pressure Indication Passes Through Fire Zone.Caused by 1983 Modification Oversight.Twice Per Shift Fire Round Has Been Established for Fire Zone Pending Cable Routing Correction
NPL-99-0193, Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with ML20205N1081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pingp,Units 1 & 2. with ML20205B3351999-03-17017 March 1999 Safety Evaluation Supporting Amends 143 & 134 to Licenses DPR-42 & DPR-60,respectively ML20205Q5101999-03-15015 March 1999 Inservice Insp Summary Rept Interval 3,Period 1 & 2 Refueling Outage Dates 981109-1229 Cycle 19,970327-981229 05000301/LER-1999-001-01, :on 990211,EDG Output Breaker Failed to Remain Closed During Surveillance Testing.Caused by Breaker Control Switch Failing to React Quickly.Modified Closing Circuit for EDG Output1999-03-10010 March 1999
- on 990211,EDG Output Breaker Failed to Remain Closed During Surveillance Testing.Caused by Breaker Control Switch Failing to React Quickly.Modified Closing Circuit for EDG Output
05000306/LER-1999-001-01, :on 990206,TS Required Reactor Protection Logic Test Was Missed.Caused by Personnel Error.Sd Banks Were Inserted at 0544,RT Breakers Were Opened & Test Was Performed.With1999-03-0808 March 1999
- on 990206,TS Required Reactor Protection Logic Test Was Missed.Caused by Personnel Error.Sd Banks Were Inserted at 0544,RT Breakers Were Opened & Test Was Performed.With
ML20207L3471999-03-0202 March 1999 Safety Evaluation Supporting Amends 187 & 192 to Licenses DPR-24 & DPR-27,respectively ML20207K2751999-03-0202 March 1999 Safety Evaluation Supporting Amends 188 & 193 to Licenses DPR-24 & DPR-27,respectively ML20207D5691999-03-0101 March 1999 Safety Evaluation Supporting Amends 186 & 191 to Licenses DPR-24 & DPR-27,respectively NPL-99-0134, Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with 1999-09-30
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, FLUIDPOWER GROUP June 21, 1984 United States Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, IL 60137 (312) 790-5500 Attention: Mr. James G. Keppler
Subject:
Anker-Holth, Baxter Fluid Power Grot:p Report (10CFP Part 21) dated June 5, 1984 Subsequent Notification of Problem / Defect Wisconsin Electric Power Company Point Beach Nuclear Plant Northern States Power Company Prairie Island #1 and #2
Dear Mr. Keppler:
Baxter Fluid Power has completed the review of all of its other previous designs and herewith issues the subsequent report per 10CFR Part 21 to the report issued and dated June 5, 1984.
Two (2) additional locations have been determined to have potential problen/de-fccts upon completion of our review, due to the downrating of the self aligning ball bushings, as purchased from and supplied by the Torrington Company, sub-sequent to the manufacture of the hydraulic suppressors (snubbers).
These locations are:
- 1. Wisconsin Electric Power Point Beach Nuclear Plant 800,000 pound rating Quantity (8) supprecsors Anker-Ilolth Part Number 21.16620.013 using Torrington bushing 40SBB64
- 2. Northern States Power Prairio Island Numbers 1 and 2 90,000 pound rating Quantity (2) suppressors
'0 0' Anker-!!olth Part Number 25.05620.001
$N00 using Torrington Bushing 12SF20 JUN 25 984 00 y At time of manufacture of part number 21.16620.013 in 1969, the Torrington bushing o (40SBB64) had a load rating of 1,600,000 pounds, which subsequent to snubber man-h ufacture has been downrated to 533,000 pounds. At tine of manufacture of part 00 number 25.05620.001 in 1971, the Torrington buching (12SF20) had a load rating of 156,000 pounds, which subsequent to manufacture has been downrated to 52,000 pounds.
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0 h Anker-Horth,2723 Conner Sum 4 Port Hurr>n. Mchge U S A 48060 feephorw ath 985 7t81 TW* 8t0 23160'n EMG tuo Accomutators Inc.,27a Cwer sne 4 Pon Hean Men an s us A 48000 Trepnce osa) 9as 7mt IWx eso ni 60 n V$4Y viceroy huid Power,262 twuki FloM Fie.ch o On'ro. CeMa MJW iHS Telephone (4?O 675 7020 Tom 06 989201 f O'v@Ong of Bas?nr IpChNW705 COfpO'1?'On i O
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U. S. Nuclear Regulatory Commission June 21, 1984 PAGE 2 As noted in the June 5, 1984 report, the safety hazard crr:ated by a failure of the self aligning ball bushing is the potential non-functioning of the appropriate suppressor due to critical mis-alignment from failure.
Also, as noted in the June 5, 1984 report, as of May 31, 1984, Baxter Fluid Power, Anker-Holth completed the formal conveyance of all design rights, documents, and data to Paul-Munroe Hydraulics, Inc.,1701 West Sequoia, Orange, California 92668 (Contact: Mr. John McCabe) 714-978-9600.
Recommended corrective action is to replace the existing Torrington self-aligning ball bushing (40SF64), existing load rating of 533,000 pounds (snubber rating of 800,000 pound) and Torrington bushing (12SF20), existing load rating of 52,000 pounds (snubber rating of 90,000 pound), with a new self aligning ball bushing having a load rating exceeding the load rating of the respectivo suppressor.
These new bushings are Paul-Munroe Ilydraulics, Inc. part numbers pA-89492 and PA89493 respectively.
The notea par
- numbers PA-89492 and pA-89493 are directly and dimensionally interchangeable with the existing bushings.
The length of time to complete the above noted recommended correctivo action, is as stated previously, ostimated at up to one year (twelve months) allowing for sufficient time to procure the replacement parts, schedulo the suppressor facility for outage, remave the suppressors from their mountings, de-contam-inate as required, replace the bushings, and re-install.
We feel the above will complete the necessary requirements to maintain the noted suppressors at their originally designed, manufactured, and installed load capacity ratings.
Sincerely, ANKER-IIOLTl!
Baxter Fluid powerGro p 1/
t}b ,
Max R. Newhart Vice-president operations
!!RN amk CC: File The Torrington Company 59 Field Street Director of Inspection Torrington, CT 06790
& Enforcement (3 copies) Attn: fir. J. II. (Jack) Williams Vice-president paul Munroo flydraulics, Inc. (203) 402-9511 1701 West Sequoia Orange, CA 92668 Mr. Clyde Landrum Attn: Mr. John McCabo Chief Engincor, lloavy Boarings (714) 978-9600 Mr. Jack Convoy Chief Et@incorg_ Noodle Bearings
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.U. S. Regulatory Cousilasion June 21, 1984 1 PAGE 3 Carolina Power & Light i H. B. Robinson Plant P. O. Box 790 Hartsville, SC 29550 Attn: Mr. Rick Dayton (803) 383-4524 Ext 354 Northern States Power Company (Red Wing, MN) 612-388-4761 Prairie Island Nuclear Generating Plant Units #1 crd #2 Prairie Island, 28 55066 Attn Ken Albrecht Quality control Manager (612) 388-1121 United States Nuclear Regulatory Conunission Mail Stop EW-359 Washington, D.C. 20555 Attne Mr. Michard Kiessel (301) 492-8119 Wisconsin Electric Power Company Point Beach Nuclear Plant 6610 Nuclear Moad I Two Rivers, W8 54241 l Attna Mr. B. E. Duenkel I
-(414) 755-2321 )
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