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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
[Table view] |
Text
FROM CENTRAL FILE FAX NO.s 2268 11-27-96 02:07P P.02 in. ne..nie i.o -
ls e 6 V rils Jl i10 id u,...,u.s n,. n, ;., s
- u. s., s a <. aa November 27,1996 United States Nuclear Regulatory Commission Attention: Document Control Desk t
Washington, D.C. 20555
Subject:
LaSalle County Station Units 1 and 2 10 CFR Part 21 Notification 9605 Final Report NRC Docket Numbers 50 373 and 50-374 i
Reference:
Letter from W. T. Subalusky to US Nuclear Regulatory Commission, LaSalle County Station Units 1 and 2,10 CFR Part 21 Notification 9605, dated October 4,1996.
Enclosed is Comed's 10 CFR Part 21 Notification of the deficiency of WKM model 70-13 Pneumatic Actuators manufactured by the Anchor Darling Valve Company and in use at LaSalle County Station. This notification is submitted in accordance with the requirements of 10 CFR 21, Section 21.1(b). An interim notification, reforenced above, had been made in accordance with 10 CFR Part 21 Section 21.21 (a)(2).
I i
If there are any questions or comments concerning this letter, please refer them to me at (815) 357-6761, extension 3600.
Respectfully.
i W. T. Subalusky I!
Site Vice President h
LaSalle County Station Enclosure 7g cc:
A. B. Beach, NRC Region lli Administrator M. P. Huber, NRC Senior Resident inspector - LaSalle D. M. Skay, Project Manager - NRR - LaSalle n a 0 0'2 G F. Niziolek, Office of Nuclear Facility Safety - IDNS l
DCD - Licensing (Hardcopy:
Electronic:
)
'~
Central File l
38A" 28an Zeasa?72 l
S PDR
! FROMs CEN7RAL FILE FAX No.*
2268 11*27-96 02:07P P.03 1
\\
i s
I l
10CFR Part 21 Notification l
10 CFR Part 21 Report (File 96-05) l WKM, MODEL1013 PNEUMATIC ACTUATORS-INCORRECT ElECTIVE DIAPHRAGM AREA
)
Anelicahilits This nuttpcation is submitu: - accordance with the requirements of10CFR Part 21, Section 21.1 (b), An interim notifconon hadbeen previously made on October 4th.
1996 in accordance with 10CFR Part 21 Seaton 21.21(a)(2).
identification of Facilits and Cemnonent LaSalle County Station. Units one and Tuo Commonwealth Edison Chicago. litmois
\\
WKAf. Afodel 70-13 pneumatic actuators (si:es 35, 70,140 l
280)
)
Identinentinn of Camnonent Manufacturer Anchor Darling Valve Company Natine of Defect Anchor Darling Valve Comy~nyperformedefectts e diophragm areo (EUA) testing on the various WKot.
Model 70-13 pneumatic actuators (sizes 33. 70,140. 280). Theprelimnuary test results indicated that the original efective diaphragm area values usedto calculate the bench set andsupply air setpoints were incorrect.
Safety SigniUcunce Potentially, Ihe listed Primary Containment isolation System (PCIS) valve assemblies would not provide adequate xyuem isolation under designed accident condstions. The PCISfunction may not have operated ifrequired i
LaSalle Unit One is in ColdShutdown mode and Urtt Two is in Refuel mode. The PCISfun listed valves is not requiredfor these modes, l
.gjodated Kafety Sienificance-
}
See Licensee Event Report k96-011-00 Time of Discoverv
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September 28.1996 Corrective Actions From the October 4 1996. nordication:
1.) Allafected valves are being reviewed' evaluated. design changes are being initiated as required It should be notedthat Ihe WKM Series 70-13 actuator is currently manufactured by the Anchor Darling Valve Company andsimilar valves may have been previously manufactured under the Muesco" or "B, S
& B" designatiora.
- 2) LaSalle is awaiting the publication ofAnchor Dartmg 'sfinal testing report. A final nonfication will be moda at that time.
l l
Frons CENTRAL FILE FAX HO.s-2268 11-27-96 02:08P P.04
)
e 10 CFR Part 21 Final Reprrt (File 96-05) 2 UodazedCorrective Aertonr i
- 1) Design changesfor all affected Primary Containment Isolation System (PCIS) andReactor cure Isolation System (RCIC*) valves have been initiatedto make the requiredsetting adjustments to enture adequgte design margins. Both units willremain in a condition that doesn't require valve desig untiltheproblem is corrected
- 2) Licensee Event Report n96-01100 i
Title:
- Pneumatic valves with less-than-designedefective diaphragm area results in inadequ\\
closingforces which mov ofact contamment isolation **
SubmitralDate: October 26. I996.
Docket n030-373 I
- 3) in the interim report it uas stated that LaSalle uas awaiting the publication ofAnchor Darling Testing Report and would be making afinal notification at that time. At that time. Anchar Darlin i
projected datefor completion ofthe report was the mid-October timeframe. As the result ofrecent conversations between Anchar Darling andComEd, it is now LaSalle 's understanding that the project completion date ofthefinal report has beenpushed back to an endofNovember timeframe. in addition.
it is Anchor Darling's statedintention not to release thefinalreport to LaSalle County Station.
\\
}
i Conclunon
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LaSalle County Station 's Licensee Event Report #96-011-00, will befollowed by a supplementalrep i
be issuedby December 2.1996. The supplementalreport wallprovide an updatedassessmen
\\
consequences ofthe esent and will be based upon an analysis ofas-found testing data ofthe ufected valves All questions relatedto the results ofEfective Diaphragm Area (EDA) lesting should be addressed to the Anchor Darling Corporation.
l i
l t
i d
i i
PCIS Valves appear in BoldItalics and are marked with an asterisk *,
1
Frons CENTRAL FILE FAX NO.s 2268 11-27-96 02:08P P.05
~
l
['
10 CFR Part 21 Final Report (File 96-05) 3 Number and I ncation of All Defcetive Components Original Name Plate Data l
Tag /EPN MFGR.
Type Diaph.
Fail Mode Supplier (Sq.in.)
1833F019 W.K M 7018 9DRT 70 Close RR Inboard Process Sample Stop*
Controls 1833F020 W-K M 70-18 9DRT 70 Close RR Outboard Process Sample $ top
- Controls 1E51F004 W-K-M 70-29-1DRT 70 Close RCIC Baro Condenser Cond Pump Controls Discharge to RBEDT Upstream Stop 1E51F005 W-K-M 70-29-1DRT 70 Close RCIC Baro Condenser Cond Pump Controls Disenarge to RBEDT downstream Stop 1E51F025 W-K-M 7018 90RT 70 Close RCIC Steam Supply Drain Pot Outlet ControIs Upstream stop 1E51F026 W-K-M 70-18 9DRT 70 Close RCIC Steam Supply Drain Pot Outlet s
Controls Downstream stop 1E51F054 WKM 70-18-9DRT 70 Close RCIC Steam Supply Drain Pot Steam Controls trap TIN 001A W K-M 70-291DRTS 70 Close DrywellSuction Upstream Isolation *_
Controls flN001B W K-M 70 291DRTS 70 Close Drywell Suction Downstream
- Controls Isolation 1IN017 WKM 70-291DRTS 35 Close DrywellPneumatic to Drywell*
Controls flN074 WKM 70-291DRTS 35 Close DWPneumatic Dryer Downstream
- Controls Purge Outlet flN075 W-K-M 70-291DRTS 35 Close DWPneumatic Oryer Upstream
- Controls Purge Outlet 1N62F019A W-K-M 70-291DRTS 140 Close A Offgas Cond. Drain Level Cent Stop Controls 1N62F0198 W-K-M 70-29-1DRTS 140 Close B Offgas Cond. Drain Level Cont Stop Controls 1N62F019C W-K-M 70-29-1DR T S 140 Close C B/Up Offgas Cond. Drain Level Cont Controls Stoo 1N62F019D W-K M 70-291DRTS 140 Close A B/Up Offgas Cond. Drain Level Cont Controls Stop 1N62F025A W-K-M 70-29-1 DRTS 280 Close A Offgas cooler Cond inlet stop Controls 1N62F0258 W-K-M 70-29-1DRTS 280 Close B Offgas Cooler Cond Inlet stop Controls 1N62F042 W-K-M 70 29-1DS 280 Open Offgas Charcoaf Absorber Train inlet Controls Stop l
1N62F043 W-K41 70-29-1DR TS 280 Close Offgas Charcoal Absorber Train Controls Bypass Stop 1N62F047 W-K-M 70 29-1DRTS 280 Close Offgas Charcoal Absorber Train 2 i
Controls Bypass Stop 1N62F048 W-K-M 70-29-1DS 280 Open Offgas Charcoal Absorber Train 2 Inlet Controts Stop l
1N62F049 W-K-M 70-291DRTS 280 Close Offgas Charcoal Absorber Train 1 Controls Bypass Stop 1N62F057 W K-M 70-291DRTS 280 Close Offgas Discharge to Stack i
Controls i
PCIS Vakes appear in BoldItalics and are marked with an usterM *.
rpons CENT L FILE FAX NO.
2268 11-27-96 02:09P P 06
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l 10 CFR Part 21 Final Report (File 96-05) e 4
1N62F394 Muesco 70-13-1 D 280 Open Offgas Charcoal Absorber Train 1 Outlet Stop 1RE024 W*K M 70 29-1DRTS 70 Close DWEquipment Drain Inboard' Controls Isoletion
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1RE025 W.K-M 70 29-1DRTS 70 Close DW Equipment Drain Outboard
- Controls isolation 1RE026 W K-M 70 291DRTS 35 Close DW Equipment Drain Sump Recirc~
Controls Valve 1RE029 W K-M 70-291DRTS 35 Close DWEquipment Drain Sump
- Controls Discharge Valve 1RF012 WKM 70-291DRTS 70 Close DWFloor Drain InboardIsolation*
Controls 1RF013 W-K M 70-29-1DR TS 70 Close DWFloor Drain OutboardIsolation*
Controls 2B33F019 W-K M 7018 90RT TO Close RR Inboard Process Sample Stop*
Controls 2833F020 WKM 7018 9DRT TO Close RR Outboard Process Sample Stop*
Controls 2E51F004 W-K-M 70-291DRT 70 Close l
Controls RClC Baro Condenser Cond Pump Discharge to RBEDT Upstream Step 2E51F005 W-K-M 70-29-1DRT 70 Close RClO Baro Condenser Cond Pump Controls Discharge to RBEDT downstream Stop l
2E51F025 W-K-M 70-18 90RT 70 Close RCIC Steam Supply Drain Pot Outlet Controls Upstream stop 2E51F026 W-K-M 70-18-90RT 70 Close RCIC Steam Supply Drain Pot Outlet Controls Downs' ream stop 2E51F054 W-K-M 70-18 9DRT 70 Close RCIC Steam Supply Drain Po: Steam Controls R
l ZIN001A W-K-M 70 291DRTS 70 Close Drywell Suction Upstream isolaten*
Controls 21N001B WKM 70-29-1DR TS 70 Close Drywell Suction Downstream *
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Controls Isolation 2iN017 WKM 70 291DRTS 35 Close DrywellPneumatic to Drywell' Controls 2iN074 W-K-M 70 291DRTS 35 Close DWPneumatic Dryer Downstream
- Controls Purge Outlet 21N075 W K-M 70 2w-nUKIS 35 Close DWPneumatic Dryer Upstream
- l Controls Purge Outlet 2N62F019A W-K-M 70 29-1DRTS 140 Close A Offgas Cond. Drain Level Cont Stop Controls 2N62F019B W-K-M 70-29-1DRTS 140 Close B Offgas Cond. Drain Level Cont Stop Controls 2N62F019C W-K-M 70 29-1DRTS 140 Close C B/Up Offgas Cond. Drain Level Cont l
Controls Stop j
2N62F019D W-K-M 70-29-1DRTS 140 Close A 8/Up Offgas Cond. Drain Level Cont l
Controls Stop l
2N62F025A W-K M 70-29-1DRTS 280 Close A Offgas Cooler Cond Ir.let Stop Controls 2N62F025B W-K-M 70-291DRTS 280 Close B Offgas Cooler Cond Inlet stop Controts 2N62F042 W-K-M 70-29-1DS 260 Open Oftgas Charcoal Absorber Train Inlet Controts Stop 2N62F043 W-K-M 70 29-1DRTS 280 Close Offgas Charcoal Absorber Train Controls Bypass Stop PCIS Valves appest in Bold Italics and are marked witts an asterisk *-
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l FROMs CENTRAL FILE FAX NO.8 2268 11-27-96 02:09P P.07 10 CFR Part 21 Final Report (File 96-05) 5 2N62F047 W K-M 70-291DRTS 280 Close Offgas Charcoal Absorber Train 2 Controis Bypass Stop i
2N62F048 W K-M 70-29-1DS 280 Open Offgas Charcoal ADsorber Train 2 inlet l
Controls I
2N62F049 W-K-M 70-29-1DRTS 280 Close Offgas Charcoal Absorber Train i Stop i
Controls Bypass Stop 2N62F057 W.K-M 70-29-1DRTS 280 Close Controls Offgas Discharge to Stack 2N62F394 Muesco 70-13-1D 280 Open Offgas Charcoal Absorber Train 1
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2RE024 WKM 70 29-1DRTS 70 Close DW Equipment Drain inboard
- Outlet Stop Controls Isolation l
2RE02$
WKM 70-291DRTS 70 Close CW Equipment Drain Outboard *
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Controls isolation 2RE026 WKM 70-29-1DRTS 35 Close DW Equipment Drain Sump Recirc*
i Controls Valve 2RE029 W M.M 70 2910RTS 35 Close OWEquipment Otuin Sump
- Controls Discharge Valve i
2RF012 W-K-M 70-291DRTS 70 Close DWFloorDrain inboartfisolation*
Controls 2RF013 W.K-M 70-2910RTS 70 Close DWFloorDrain OutboardIsolation*
Controls Contacts Mark Smnh AOVComponent Engmeer LaSalle County Stanon Commonweahh Edison 2601 North list Re>ad Marseilles, Illinois 61341
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(815) 337-6761 I
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PCIS Valves appear in Bold Italics and are marked with an asterisk
e s,
GENERAL INFORMATION or OTHER i
EVENT NUMBER:
31093 LICENSEE: LASALLE COUNTY STATION NOTIFICATION DATE: 10/04/96 CITY:
REGION: 3 NOTIFICATION TIME: 15:35 [ET]
COUNTY:
STATE: IL EVENT DATE:
09/28/96 LICENSE #:
AGREEMENT: Y EVENT TIME:
12 : 00 [CDT)
DOCKET:
LAST UPDATE DATE:
11/27/96 NOTIFICATIONS NRC NOTIFIED BY: MR. SUBALUSKY HQ OPS OFFICER:
DOUG WEAVER VERN HODGE NRR EMERGENCY CLASS: NOT APPLICABLE 10 CFR SECTION:
CCCC 21.21 UNSPECIFIED PARAGRAPH EVENT TEXT PART 21 NOTIFICATION ON WKM MODEL 70-13 PNEUMATIC ACTUATORS l
ANCHOR DARLING VALVE COMPANY PERFORMED EFFECTIVE DIAPHRAGM AREA (EDA)
TESTING ON THE VARIOUS WKM MODEL 70-13 PNEUMATIC ACTUATORS (SIZES 35, 70, 140, 280).
THE PRELIMINARY TEST RESULTS INDICATED THAT THE ORIGINAL EFFECTIVE DIAPHRAGM AREA VALUES USED TO CALCULATE THE BENCH SET AND SUPPLY AIR SET POINTS WERE INCORRECT.
THESE ACTUATORS ARE USED ON VARIOUS PRIMARY CONTAINMENT ISOLATION VALVES AND THESE VALVES MAY NOT PROVIDE ADEQUATE SYSTEM ISOLATION UNDER DESIGN ACCIDENT CONDITIONS.
LASALLE UNIT ONE IS IN COLD SHUTDOWN AND UNIT TWO IS IN TFr " -"JJL MODE.
- UPDATE RECEIVED BY FAX AT 1508 ON 11/27/96, TAKEN BY WEAVER * *
AND REACTOR CORE ISOLATION SYSTEM (RCIC) VALVES HAVE BEEN INITIATED TO MAKE THE REQVIRED SETTING ADJUSTMENTS TO ENSURE ADEQUATE DESIGN MARGINS.
BOTH l
UNITS WILL REMAIN IN A CONDITION THAT DOESN'T REQUIRE VALVE DESIGN OPERATION UNTIL THE PR.OBLEM IS CORRECTED.
THE LICENSEE SUBMITTED AN LER ON THIS TOPIC ON 10/28/96.
AN UPDATED LER WILL BE SUBMITTED ON 12/2/96.
THE HOO NOTIFIED VERN HODGE OF THIS UPDATE.
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F R 0 f18 CENTRAL FILE F 5t X NO..
2268 11-27-96 02:07P P.01 i
l Date 11/27/96
( Number of paaes includino cover sheet 7 I
TO:
NuclearRegulatory FROM:
W. T. Subalusky I
Commission LaSalle County Nuclear
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OPS Center Power Station l
i Phone 815-357-6761 FAX Phone 301-616-5151 Fax Phone 815-357-6761, ext. 2502 VERIFICATION 301 816 5100 RE:
LaSalle County Station Units 1 and2 10CFR Part 21 Notification 9605 FinalReport l
REMARKS;
@ Urgent D Foryourreview 0 Reply ASAP D Please Comment Attached are the above-entitled documents including cover letter; and 10CFR Part 21 Notification.
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