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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 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 ML20236N6751998-07-0909 July 1998 Part 21 & Deficiency Rept Re Notification of Potential Safety Hazard from Breakage of Cast Iron Suction Heads in Apkd Type Pumps.Caused by Migration of Suction Head Journal Sleeve Along Lower End of Pump Shaft.Will Inspect Pumps ML20198K5081998-01-0606 January 1998 Part 21 Rept Re Transient Analyses at Exposures Prior to End of Cycle.Caused by Component Defect.Notified Commonwealth Edison of Defect & Provided Revised Limits by Siemens Power Corp ML20203B3691997-12-10010 December 1997 Part 21 Rept Re Potential to Exceed Operating Limits.Cycle 8 Delayed Until Fall 1998 ML20134Q0801996-11-27027 November 1996 Part 21 Rept Re Deficiency of Wkm Model 70-13 Pneumatic Actuators Manufactured by Anchor Darling Valve Company Due to Incorrect Calculation of Bench Set & Supply Air Set Points.All Affected Valves Have Been Reviewed & Evaluated ML20128F5011996-10-0404 October 1996 Part 21 Rept & Deficiency Rept Re Wkm Model 70-13 Pneumatic Actuators Mfg by Anchor Darling Valve Co.All Affected Valves Being Reviewed/Evaluated & Design Changes Are Being Initiated as Required ML20117P3141996-09-11011 September 1996 Part 21 Rept Re Deficiency of GE Type RMS-9 Overcurrent Trip Device Programmers ML20082B5271995-03-28028 March 1995 Part 21 Rept Re Notification 9505 Automatic Switch Co Pilot Solenoid Valve Model NP8323A20V.Caused by Failures of MSIVs to Close to Asco Pilot Solenoid Valves.Subj Valves Replaced W/Valcor 3-way Solenoid Valves ML20082E1901995-03-27027 March 1995 Part 21 Rept Re Sticking of B Core Assembly to Plugnut on Automatic Switch Co Dual Solenoid Valve Model NP8323A20V. Unit 2 Valves Replaced.Unit 1 Valves Will Be Replaced ML20069A8631994-05-17017 May 1994 Final Part 21 Rept Re Secondary Containment Isolation Techno Corp Dampers Equipped W/Parker Hannifin Air Cylinders at LaSalle County Station.All Units 1 & 2 Techno Dampers Equipped W/Parker Air Cylinders Replaced ML20070N3451994-05-0202 May 1994 Part 21 Rept Re Failures of Limit Switch Series EA740-86700 Mfg by Namco Controls Co Due to Excessive Amount of Grease on Contact Block & Contact Carrier & Wrong Matl of O-ring. Series EA740-86700 Switches Replaced w/EA740-50100 Switches ML20063D0861994-02-0202 February 1994 Part 21 Rept Re Possible Anomaly W/Namco Controls EA740 & EA750 Series Limit Switches.Investigation in Progress & Has Not Been Concluded.Vendor Will Advise NRC within Next Thirty Days Re Matter as Addl Info Becomes Available ML20059L9861993-11-11011 November 1993 Part 21 Rept Re Deviation Wherein Fully Open Butterfly Valve Located 15 Pipe Diameters Upstream of Sensors Was Disturbing Flow Profile Enough to Cause Ultrasonic Meter to Indicate 3 to 4% Low.Customers Notified & Valve Removed ML20043A6091990-04-27027 April 1990 Part 21 Rept Re Defective Axial Cracks in Pump Shaft in Region Immediately Above Impeller & in Reactor Recirculation Pumps.Probably Caused by Crack Growth as Thermal Fatigue. Technical Advisory Bulletin Will Be Sent to Each Util ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20207J8491986-07-25025 July 1986 Part 21 Rept Re Potential Change in Allowable Operating Repeatability Ranges for 1E Qualified Series 9,8 & 1 Pressure Switches.Licensee Calibr Procedures Should Be Amended to Allow for Cycling (Hysteresis) Effects ML20198R5751986-06-0303 June 1986 Part 21 Rept Re Failure of 103/B212 Type Differential Pressure Switches to Give Scram During 860601 Feedwater Transient.Investigation Continuing ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20128G5101985-05-24024 May 1985 Part 21 Rept Re Heat Numbers to Be Added & Deleted from Sublist Sheet A,Based on Review of NRC ML20127N0621985-05-13013 May 1985 Part 21 Rept Re Incorrect Short Time Delay Band Lever Inadequately Installed in Low Voltage K-line Circuit Breaker Electromechanical Overcurrent Trip Device.Visual Insp to Determine If Correct Lever Installed Recommended ML20099F3921984-11-0808 November 1984 Part 21 Rept Re Hexcel/Mci Pipe Restraints Found W/Average Dynamic Crush Strength Values Below Acceptable Values. Initially Reported on 841101.Replacement Program in Progress ML20096A5441984-08-21021 August 1984 Part 21 Rept Re Ground Fault Failures of Actuation Solenoids for Crosby Safety Relief Valves PRC 84-24.Problem Still Considered Germane Condition.Memo of 840808 Telcon Updating 840615 Interim Rept Encl ML20083J7731983-12-22022 December 1983 Final Deficiency Rept Re Defective GE Hma Relays.Initially Reported on 830805.Two Relays Found to Have Insufficient Armature Clearance.Adjustments Made ML20082Q6921983-12-0202 December 1983 Final Deficiency Rept 83-07 Re Design Calculation for Fire Water Sys.Initially Reported on 831102.Preliminary Calculations Completed.Final Rept Will Be Submitted Approx 20 Days Prior to Exceeding 5% Power ML20085K6361983-10-12012 October 1983 Final Deficiency Rept 83-06 Re Asco Solenoid Valves in Control Rod Drive Sys.Initially Reported on 830912.Valves W/Defective Solenoid Plunger Housings Replaced & Spare Parts in Inventory Examined.Plant Operable ML20077N6151983-09-0101 September 1983 Interim Deficiency Rept 83-05 Re Potentially Defective GE Hma Relays Mfg in 1974.Initially Reported on 830805.Two Relays Found W/Insufficient Armature Clearance.Clearance Adjusted.Final Rept Expected by 830923 ML20076A8221983-08-0808 August 1983 Corrects Final Deficiency Rept 83-01 Re Riley Temp Indicating Switches.Riley Temp Switches Not Recalibr to Modified Calibr Procedure.Calibr to Be Done Prior to Fuel Load ML20077A8961983-07-15015 July 1983 Final Rept Re Potentially Defective Figures 425,426 & 428 Spring Hangers Mfg by Elcen Metal Products Co.Initially Reported on 830617.Review Revealed Spring Hanger Installed at Facility Not Type in Question.Item Closed ML20024B7771983-07-0707 July 1983 Final Deficiency Rept 83-03 Re Medium Voltage Circuit Breakers of Same Type Installed at Limerick Which Inadvertently Closed After Completion of Spring Charging Due to Slipped Close Latch,Discussed in Brown Boveri ML20072A7371983-06-0303 June 1983 Final Deficiency Rept Re Problems W/Riley Temp Switches. Initially Reported on 830316.Based on Engineering Evaluation by Riley,Switches Accurately Perform Intended Function When Calibr W/Modified Procedure ML20083L9751983-05-27027 May 1983 Part 21 Rept Re Failure of Circuit Breakers During Environ Testing.Test Results Indicate That Temp Sensitivity Problem May Be Generic to All Ite Imperial Corp thermal-magnetic Circuit Breakers Calibr for 40 C Svc ML20074A3101983-05-0404 May 1983 Part 21 Rept Re Defect in Shielded Multiconductor Cable Installed in HVAC Control Panels.Mcc Powers Personnel Attached Hold Tags to 13 HVAC Control Panels W/Defect. Evaluation Being Conducted ML20073T1421983-05-0303 May 1983 Updated Interim Deficiency Rept Re Offset & Module Problems of Riley Temp Indicating Switches in Leak Detection Sys. Calibr Procedure Modified.Final Resolution of Module Problem (Hardware Mod) in Progress.Final Rept Expected by 830601 ML20073S6731983-05-0202 May 1983 Interim Deficiency Rept 83-01 Re Temp Offset Problems Experienced W/Riley Temp Switches Installed in Leak Detection Sys.Calibr Procedure Modified & Switches Recalibr. Final Rept Will Be Submitted by 830601 ML20024B7841983-04-28028 April 1983 Followup Interim Rept Re Potential Deficiency in 5HK Switchgear Supplied by Brown Boveri.Circuit Breaker Inadvertently Closed & Tripped Following Spring Charging. Light Spring Added to Close Latch ML20074A2041983-04-26026 April 1983 Interim Deficiency Rept Re Misapplication of Ite Gould Circuit Breakers in post-LOCA Hydrogen Recombiners Supplied by Rockwell Intl.Initially Reported on 830328.Matter Under Investigation.Final Rept by 830808.Reported Per Part 21 ML20074A3191983-04-18018 April 1983 Part 21 Rept Re Defect in Shielded Multiconductor Cable Installed in HVAC Control Panels.All Suspect Panels Inspected & Nonconformance Rept Will Be Issued for Applicable Sites ML20073F6751983-04-0707 April 1983 Final Const Deficiency Rept 82-07 Re Shop Welding by Unauthorized Welders.Zack Co Officially Withdrew Part 21 Rept on 820914 Based on Results of Investigation ML20072P7311983-03-30030 March 1983 Revised Final Deficiency Rept 81-06 Re Crosby Safety Relief Valve IMF-2 Solenoid Valve.Solenoids Have Had Qualified Collet/Yoke Assembly Installed,Closing Out Undervoltage Concern.Valves Qualified Per NUREG-0588 ML20069E4501983-03-16016 March 1983 Final Deficiency Rept Re Significant Deviation from Performance Specs for Sor,Inc Pressure Switches Installed as Part of ECCS Interlock Mod.Initially Reported on 830216. All Leaking O-rings Replaced ML20069E6671983-03-16016 March 1983 Interim Deficiency Rept 83-01 Re Significant Deviation from Performance Specs for Riley Temp Switches in Leak Detection Sys.Initially Reported on 830215.Two Units Returned to GE for Evaluation.Temp Module Resolution Expected by Apr 1983 ML20074A2221983-03-11011 March 1983 Part 21 Rept Re Failure of post-LOCA Hydrogen Recombiner Component During IEEE-323 Qualification Program.Circuit Breaker Not Properly Selected for Specific Application.Plant Operators Notified of Deviation ML20071E9191983-03-0101 March 1983 Final Deficiency Rept 82-08 Re Electrical Penetration Assemblies.Initially Reported on 820817.Replacement Modules Will Be Installed by 830501 ML20070R8521983-01-24024 January 1983 Interim Deficiency Rept 82-08 Re Electrical Penetration Assembly Butt Splices.Replacement Modules for Awg Cable Modules 2 & 6 Ordered from Conax.Final Rept Will Be Provided on or About 830303 ML20028E6511983-01-21021 January 1983 Final Deficiency Repts 82-10 & 11 Re Rigid Strut Pins Mfg by Elcen.Initially Reported on 821223.Test Results Indicate No Load Capacity Data Values Violated.If Such Pins Were Used,Design Margins Not Exceeded ML20073J5211982-12-14014 December 1982 Part 21 Rept Re Likely Failure of post-LOCA Hydrogen Recombiner Component,Dpst Toggle Switch 12TSI-2 Due to Aging & Radiation.Field Bulletins Issued to Install Jumpers Bypassing Switch ML20079J7921982-12-14014 December 1982 Interim Deficiency Rept Re Inadequate Pressure Transducers/ Transmitters Mounted on post-LOCA Hydrogen Recombiners. Initially Reported on 821119.Final Rept Will Be Submitted by 830211.Also Reported Per Part 21 ML20066J5131982-11-18018 November 1982 Final Deficiency Rept Re Overtorqued Anchor Bolts on ECCS Pump Foundation.Initially Reported on 821019.Recheck of Torque Values to Be Performed by 821206.Sargent & Lundy 821110 Evaluation of Anchor Bolt Status Encl 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217C9121999-10-12012 October 1999 SER Input Authorizing Licensee Proposed Request to Modify Definition of Core Alteration in Section 1.0 of TS & Update Sections 3/4.1,3.4.3 & 3/4.9 to Reflect Proposed Definition Change 05000373/LER-1999-003-04, :on 990902,reactor Scram on Low Reactor Water Level,Was Received.Caused by Personnel Error.Appropriate Disciplinary Action Taken with non-licensed Operator1999-10-0404 October 1999
- on 990902,reactor Scram on Low Reactor Water Level,Was Received.Caused by Personnel Error.Appropriate Disciplinary Action Taken with non-licensed Operator
ML20212M2601999-10-0101 October 1999 Safety Evaluation Supporting Amends 134 & 119 to Licenses NPF-11 & NPF-18,respectively ML20217F9091999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for LaSalle County Stations,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 05000374/LER-1999-002-06, :on 990821,automatic Scram Occurred Due to Failure of Reactor Water Level Control.Caused by Inadequate Maint on 2A Tdrep Servo Valve 2FW163AA.Repaired Servo Valve1999-09-20020 September 1999
- on 990821,automatic Scram Occurred Due to Failure of Reactor Water Level Control.Caused by Inadequate Maint on 2A Tdrep Servo Valve 2FW163AA.Repaired Servo Valve
05000374/LER-1999-001-07, :on 990804,failure to Comply with Suppression Chamber - Drywell Vacuum Breaker TS Action Statement Was Noted.Caused by Mgt Deficiency.Permanent Procedure to Visually Verify Vacuum Breaker Closed Was Written1999-09-0303 September 1999
- on 990804,failure to Comply with Suppression Chamber - Drywell Vacuum Breaker TS Action Statement Was Noted.Caused by Mgt Deficiency.Permanent Procedure to Visually Verify Vacuum Breaker Closed Was Written
ML20212C4501999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for LaSalle County Station,Units 1 & 2.With ML20210R0671999-07-31031 July 1999 Monthly Operating Repts for July 1999 for LaSalle County Station,Units 1 & 2.With 05000373/LER-1999-002-05, :on 990623,TS Re Rod Operability Surveillance Was Missed.Caused by Personnel Error.Counseled Responsible Individual1999-07-23023 July 1999
- on 990623,TS Re Rod Operability Surveillance Was Missed.Caused by Personnel Error.Counseled Responsible Individual
ML20210C1681999-07-0909 July 1999 Seventh Refueling Outage ASME Section XI Summary Rept ML20209H1501999-06-30030 June 1999 Monthly Operating Repts for June 1999 for LaSalle County Station,Units 1 & 2.With ML20207E9111999-06-0303 June 1999 Safety Evaluation Supporting Amends 133 & 118 to Licenses NPF-11 & NPF-18,respectively ML20195J7871999-05-31031 May 1999 Monthly Operating Repts for May 1999 for LaSalle County Station,Units 1 & 2.With ML20209E1431999-05-31031 May 1999 Cycle 8 COLR, for May 1999 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 05000373/LER-1999-001-02, :on 990407,main Control Room,Auxiliary Electrical Equipment Room & Switchgear Room Ventilation Sys Were Found Outside Design Basis.Caused by Inadequate Initial Design.Placed Vx Sys Heat Recovery Fans in Stop Position1999-05-0707 May 1999
- on 990407,main Control Room,Auxiliary Electrical Equipment Room & Switchgear Room Ventilation Sys Were Found Outside Design Basis.Caused by Inadequate Initial Design.Placed Vx Sys Heat Recovery Fans in Stop Position
ML20206N2071999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for LaSalle County Station,Units 1 & 2.With 05000374/LER-1997-039, :on 971024,unanalyzed Condition Resulted from Free End of SRV Discharge Pipes Not Being Analyzed for Seismic Loads.Caused by Inadequate Review Process.Tailpipe Restraints Analyzed.With1999-04-0202 April 1999
- on 971024,unanalyzed Condition Resulted from Free End of SRV Discharge Pipes Not Being Analyzed for Seismic Loads.Caused by Inadequate Review Process.Tailpipe Restraints Analyzed.With
ML20205R2721999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for LaSalle County Station,Units 1 & 2.With ML20205L8301999-03-31031 March 1999 Administrative Technical Requirements App B (Amend 26) LaSalle Unit 2 Cycle 8 COLR & Reload Transient Analysis Results, for Mar 1999 ML20205L8421999-03-31031 March 1999 Rev 2 to EMF-96-125, LaSalle Unit 2 Cycle 8 Reload Analysis ML20205L8391999-03-22022 March 1999 Rev 2 to 960103, Neutronics Licensing Rept for LaSalle Unit 2,Cycle 8 ML20204B4071999-03-16016 March 1999 Safety Evaluation Supporting Amends 131 & 116 to Licenses NPF-11 & NPF-18,respectively ML20204C8141999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for LaSalle County Station,Units 1 & 2.With ML20205K5061999-02-16016 February 1999 Corrected Safety Evaluation Supporting Amend 115 to License NPF-18,including Two Proposed Changes Inadvertently Ommitted.Section 3.1 Lists Proposed Changes to TS Table 3.3.2-2 ML20203H9321999-02-12012 February 1999 Safety Evaluation Supporting Amends 130 & 114 to Licenses NPF-11 & NPF-18,respectively 05000373/LER-1995-015-01, :on 950824,TS Fire Protection Valve Surveillance Was Missed.Caused by Insufficient Review of TSs During Mod Process.Revised Fire Protection Design Checklist1999-01-19019 January 1999
- on 950824,TS Fire Protection Valve Surveillance Was Missed.Caused by Insufficient Review of TSs During Mod Process.Revised Fire Protection Design Checklist
ML20205M7061998-12-31031 December 1998 Unicom Corp 1998 Summary Annual Rept. with ML20199E4601998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for LaSalle County Station,Units 1 & 2.With ML20207C7371998-12-31031 December 1998 Annual Rept for LaSalle County Station for Jan 1998 Through Dec 1998 ML20198B3801998-12-14014 December 1998 SER Accepting one-time Request for Relief from Certain Provisions of Section XI of ASME Boiler & Pressure Vessel Code,Per 10CFR50.55a for Certain Plant Safety/Relief Valves ML20206N2261998-12-0909 December 1998 LER 98-S03-00:on 981116,protected Area Was Entered Without Current Authorization for Unescorted Access Due to Programmatic Deficiency Error.Changed Badge Control Process ML20197K0981998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for LaSalle County Station,Unts 1 & 2.With ML20196B1441998-11-23023 November 1998 Safety Evaluation Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Bindings 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 ML20195D3191998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for LaSalle County Station.With ML20154H6781998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for LaSalle County Nuclear Power Station,Units 1 & 2 05000373/LER-1998-016-02, :on 980823,APRM Reactor Scram & Rod Block Setpoints Found to Be non-conservative After Calibr Due to Human Performance Error.Flow Converter Correctly Calibr in Accordance with Procedure LIS-NR-1071998-09-22022 September 1998
- on 980823,APRM Reactor Scram & Rod Block Setpoints Found to Be non-conservative After Calibr Due to Human Performance Error.Flow Converter Correctly Calibr in Accordance with Procedure LIS-NR-107
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 ML20153C7621998-09-18018 September 1998 Safety Evaluation Acceping NRC Bulletin 95-002, Unexpected Clogging of RHR Pump Strainer While Operating in Suppression Pool Cooling Mode 05000373/LER-1998-015-02, :on 980819,manual Reactor Scram Occurred Following Level Control Transient.Caused by Failure of Control Card Associated with Bailey Rwl Cs.Replaced Failed Card with Refurbished Unit.With1998-09-18018 September 1998
- on 980819,manual Reactor Scram Occurred Following Level Control Transient.Caused by Failure of Control Card Associated with Bailey Rwl Cs.Replaced Failed Card with Refurbished Unit.With
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 05000373/LER-1998-013-01, :on 980817,reactor Water Cleanup Isolations Occurred Due to Inadequate Operating Procedure Guidance. Caused by Human Error.Revised Operating Procedures for RT Sys1998-09-16016 September 1998
- on 980817,reactor Water Cleanup Isolations Occurred Due to Inadequate Operating Procedure Guidance. Caused by Human Error.Revised Operating Procedures for RT Sys
05000373/LER-1997-023, :on 970626,inadequate Channel Functional Testing of RPS Was Noted.Caused by Procedure Deficiencies. Revised Procedures & Appropriate Testing Has Been Completed. with1998-09-11011 September 1998
- on 970626,inadequate Channel Functional Testing of RPS Was Noted.Caused by Procedure Deficiencies. Revised Procedures & Appropriate Testing Has Been Completed. with
ML20151W0241998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for LaSalle County Station.With 05000373/LER-1998-012-01, :on 980729,reactor Scram During Scram Discharge Volume Surveillance Occurred.Caused by Inadequate Procedures.Revised Subject Surveillance Procedure Accordingly1998-08-28028 August 1998
- on 980729,reactor Scram During Scram Discharge Volume Surveillance Occurred.Caused by Inadequate Procedures.Revised Subject Surveillance Procedure Accordingly
ML20237E2921998-08-21021 August 1998 Special Rept:On 980811,channel 5 of Lpms Became Inoperable. Caused by Channel Failed pre-amplifier Located Inside Primary Containment at Inboard Side of Electrical Penetration E-19.Initiated Repairs of Channel ML20237E2331998-08-21021 August 1998 Revised Pages of Section 20 of Rev 66 to CE-1-A, QA Topical Rept 05000373/LER-1998-009-02, :on 980721,Div III EDG Actuated During Removal of Sys Auxiliary Transformer from Service.Caused by Failure to Use Operating Procedure by Personnel.Div III Was Placed in Proper Configuration for SAT to Remain de-energized1998-08-20020 August 1998
- on 980721,Div III EDG Actuated During Removal of Sys Auxiliary Transformer from Service.Caused by Failure to Use Operating Procedure by Personnel.Div III Was Placed in Proper Configuration for SAT to Remain de-energized
1999-09-30
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Text
comnu,nweanh niison compiny labile Generating station 2&)I North list Road mrwilles. 11.61361 9757 Td Hl5M7 6"61 March 28,1995 United States Nuclear Regulatory Commission Washington, D.C. 20555 Attention:
Document Control Desk
Subject:
LaSalle County Station Units 1 and 2 10CFR Part 21 Notification 9505
~
Automatic Switch Company (ASCO)
Pilot Solenoid Valve Model # NP8323 A20V NRC Docket Numbers 50-373 and 50-374.
Enclosed in Exhibit B is Comed's 10CFR Part 21 Notification of the deficiency of ASCO Dual Solenoid Valve Model # NP8323 A20V, manufactured by the Automatic Switch Company and in use at LaSalle Station.This notification is submitted in accordance with the requirements of 10CFR 21, Section 21.l(b),21.3a(3), and 21.3d(4).
If there are any questions or comments concerning this letter, please refer them to me at (815) 357-6761, extension 3600.
Respectgl,1y, R. E. Querio Site Vice President LaSalle County Station i
cc:
J. B. Martin, Regional Administrator, Region Ill W. D. Reckley, Project Manager, NRR P. G. Brochnun, Senior Resident Inspector, LaSalle D. L Farrar, Nuclear Regulatory Services Manager, NORS Central file 040135 9504050191 950328 PDR ADOCK 05000373 f[$,g S
PDR u w,meemrm,
ca, j.
Exhibit B ENC-QE-40 Revision 9 Page 1 of 3 To:
Nuclear Licensing Manager
Subject:
Part 21 Notification 9505-Regarding Automatic Switch Company (ASCO) Pilot Solenoid Valve Model # NP8323A20V LaSalle Site Support Engineering has evaluated the subject document and determined that the defect / noncompliance is reportable under the requirements of 10CFR Part 21. The attached report has been prepared for submittal to the NRC, and should be submitted by 3'2D 0 to the NRC Operations Center.
Questions regarding this report should be directed to William C. Kirchhoff x2927.
/
-/fb NED Engineer
(_ A
=c[
3 2 ; 9f NED Suptf/ Supe b/rf~/ s-2 7-9 s NED Manager President and Chief Operating Officer Senior Vice President, Nuclear Operations Vice President BWR Operations Vice President PWR Operations Vice President Nuclear Engineering and Construction General Manager Nuclear Services General Manager Quality Programs and Assessments i
Nuclear Station Managers Nuclear Engineering Manager Safety Assessment Manager Manager of Quality Assurance / Nuclear Safety Part 21 Coordinator ENC Regulatory Assurance Supervisor 1
~
Exhibit B ENC-QE-40 Revision 9 Page 2 of 3 10CFR 50 Part 21 Notification Deficiency of ASCO Dual Solenoid Valve Model # NP8323A20V, Manufactured by the Automatic Switch Company and used at LaSalle County Station Part 21 file # 9505
- Applicability This notification is submitted in accordance with the requirements of 10CFR 21, Section 21.1(b),
21.3a(3), and 21.3d(4).
- ldentification of Facility and Component This defective component was identified only at Commonwealth Edison's LaSalle County Station.
The effected solenoid valves are used on Main Steam Isolation Valves (MSIV) 1(2)B21-F022 A/B/C/D and 1(2)B21-F028 A/B/C/D as part of the actuating mechanism.
- ldentification of Component Manufacturer The ASCO Dual Solenoid Valve Model #NP8323A20V is manufactured by the Automatic Switch Company (ASCO).
The ASCO Model # NP8323A20V valve is a dual coil, three-way solenoid valve used at LaSalle as a pilot valve which controls the opening and closing of the MSIV's. A root cause investigation i
has attributed two recent failures of the MSIVs to close to the ASCO pilot solenoid valves. In particular, intemal sticking of the "B" core assembly to the plugnut, which prevented the valves from changing state. It is believed that a foreign material acted as an adhesive film. This substance was determined to be Nyogel 775A grease it is unknown how the Nyogel 775A came to this location. According to information provided by ASCO, Nyogelis used in the valve. Entry of Nyogel 775A from sources extemal to the valve were investigated and considered implausible.
- Safety Significance Failure of the ASCO NP8323A20V pilot solenoid valve to shift position when de-energized would prevent the automatic or manual fast closure of the main steam isolation valves. The safety function of the MSIVs as described in LaSalle's Technical Specification Basis Section 3/4.4.7 Main Steam Line Isolation Valves describes the safety function as minimizing potential leakage paths from the containment in case of a steamline break to limit release of fission products and to ensure that the core is not uncovered following line breaks. The MSIV's function is also described in the Technical Specification Basis 3/4.6.3 Primary Containment isolation Valves to i
Exhibit B ENC-QE-40 Revision 9 Page 3 of 3 ensure that the containment atmosphere will be isolated from the outside environment in the event of a release of radioactive material to the containment atmosphere or pressurization of the containment.
' Time of Discovery February 18,1995
- Corrective Actions Unit Two
- Outboard ASCO Pilot Solenoid valves have been replaced with Valcor 3-way solenoid valves as had been previously scheduled for this current outage (L2R06).
- Inboard ASCO Pilot Solenoid valves have been replaced with new ASCO valves assembled without grease.
Unit One
- Engineering has performed an operability evaluation and recommended increasing the testing frequency of the MSIV'c to 60 days. The cycling of the valves is believed to break the cohesion (binding formation) which decreases the sticking probability. Operating has chosen a more conservative testing frequency of 30 days.
- LaSalle plans for next Unit One refueling outage include the replacement of the inboard ASCO valves with new ASCO valves assembled without grease and the replacement of the outboard ASCO valves with Valcor solenoid valves.
- Number and Location of All Defective Components The effected solenoid valves are used on Main Steam isolation Valves (MSIV) 1(2)B21-F022 A/B/C/D and 1(2)B21 F028 A/B/C/D.
- Technical Contacts William C. Kirchhoff, LaSalle Site Support Engineering Charles J. Bohan, LaSalle Site Support Engineering Questions Pertaining to this notification should be addressed to:
Eric Stockhan NETS Part 21 Coordinator Commonwealth Edison Company 1400 Opus Place, Suite 400 Downers Grove, IL 60515 (708) 663-7437
s'
.o PART 21
SUMMARY
SHEET In acccidance with Part 21 you, as an officer of CECO, are being informed of the following situation:
A defect in the ASCO NP8323A20V Dual Solenoid valve manufactured by the Automatic Swich Company was identified. These ASCO valves are used at LaSalle as a pilot valve which controls the opening and closing of the MSIVs. A root cause investigation has attributed two recent failures of the MSIVs to close to the ASCO pilot solenoid valves. In particular, internal sticking of the "B" core assembly to the plugnut, which prevented the valves from changing state.
It is believad that this foreign material acted as an adhesive film. This substance was determined to be Nyogel 775A grease. It is unknown how the Nyogel 775A came to this location.
According to information provided by ASCO, Nyogelis used in the valve. Entry of Nyogel 775A from sources extemal to the valve were investigated and considered implai'sible.
LaSalle is the only user in the CECO system that uses this model valve. Failure of the ASCO NP8323A20V pilot solenoid valve to shift position when de-energized would prevent the automatic or manual fast closure of the main steam isolation valves Corrective Actions:
Unit Two
- Outboard ASCO Pilot Solenoid valves have been replaced with Valcor 3-way solenoid valves as had been previously scheduled for this current refueling outage (L2R06).
' Inboard ASCO Pilot Solenoid valves have been replaced with new ASCO valves assembled without grease.
Unit One
- Engineering has performed an operability evaluation and Operating has increased the testing frequency of the MSIVs to every 30 days. The cycling of the valves is believed to break the cohesion (binding formation) which decreases the sticking probability.
- LaSalle plans for next Unit One refueling outage include the replacement of the inboard ASCO valves with new ASCO valves assembled without grease and the replacement of the outboard ASCO valves with Valcor solenoid valves.
If you require further information regarding this notification, please direct them to William C.
Kirchhoff, LaSalle Site Support Engineering, extension 2927.
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