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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 ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified 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 ML20217D5701998-03-20020 March 1998 Part 21 Rept 40 Re Governor Valve Stems Made of Inconel 718 Matl Which Caused Loss of Governor Control.Control Problems Have Been Traced to Valve Stems Mfg by Bw/Ip.Id of Carbon Spacer Should Be Increased to at Least .5005/.5010 ML20198Q6961998-01-12012 January 1998 Part 21 Rept Re Failed Operation of Agastat EGPI004 Relay on 971129,as Reported by Limerick Station.Caused by Insufficient Soldering.Will Notify Customers Who Purchased EPI004 & ETR14XXX004 Relays During June 1996 ML20140A4761997-05-27027 May 1997 Provides Addl Info to 970429 Part 21 Rept Re Potential safety-related Problem W/Asco HV 266000-007J Scram Solenoid Pilot Valves.Corrective Actions Also Listed ML18038A8971994-09-0707 September 1994 Part 21 Rept Re Defect in Latching Mechanism of Potter & Brumfield Relay on C&D High Voltage Shut Down Alarm Assembly Printed Circuit Boards.Pull Test on Relay Reset Button Incorporated Into Receiving Insp Procedures ML20072P6781994-08-29029 August 1994 Part 21 Re Condensers for Four 25 Ton Safety Related Packaged Air Conditioner Units (Acu) for BFN Units 1 & 3. Acus Supplied by Ellis & Watts & Condensers Supplied by Itt. Condensers Returned to Itt to Rerate Shell 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 ML20058G5981993-11-17017 November 1993 Part 21 Rept Re Westronics Recorders,Model 2100C.Signal Input Transition Printed Circuit Board Assembly Redesigned to Improve Recorder Immunity to Electromagnetic Interference.List of Affected Recorders & Locations Encl 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 ML20128N6281993-02-12012 February 1993 Updates 920929 Part 21 Rept Re Failure of Wyle Rept 30081-99 to Provide Sufficient Evidence That Eight Cited Solenoid Valve Assemblies Qualified Per Rev a to Wyle Rept 17514-1.Parts Returned to Util on 930211.Rept Withheld 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 ML20127N2341992-11-25025 November 1992 Interim Part 21 Rept Re Defect in GE RMS-9 Trip Devices W/ Instantaneous Trip Function.Initially Reported on 921027. Util Formally Discontinued Installation of Defective Devices & Investigating Replacement of Units W/Ge 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 ML20116J8651992-11-0909 November 1992 Update to 920929 Part 21 Rept Re Failure of Wyle Rept 30081-99 to Provide Sufficient Evidence That Noted Serial Numbers on Solenoid Manifold Assemblies,Mfg by Automatic Valve Co,Qualified.Util Returned Valves on 921005 ML20116L6001992-10-27027 October 1992 Part 21 Rept Documenting Event 24505 Re GE Ak Circuit breaker,RMS-9 Trip Devices W/Instantaneous Trip Adjustment. Installation of RMS-9 W/Instantaneous Function Discontinued ML20118B8291992-09-30030 September 1992 Potential Part 21 Rept Re Lack of Evidence That Eight Solenoid Manifold Assemblies Mfg by Automatic Valve Qualified to NUREG-0588,Category I Requirements.Return of Suspect Assemblies Requested ML20115C6381992-09-30030 September 1992 Part 21 Rept Re Failure to Provide Sufficient Evidence That Eight Solenoid Manifold Valves,W/Codes GRE-001 Through GRE-008,mfg by Automatic Valve,Qualified to Wyle Rept 17514-1,Rev A.Return of Defective Valves Requested ML20106B8351992-09-24024 September 1992 Part 21 Rept Re Cracked Weld Found in Sample of ASTM A-500 Grade B Steel Tubing Heat T42510 from Coil 924544.Micro Analysis Indicated That Edges of Tubing Did Not Come in Contact from Weld During Mfg Process ML20118B6081992-09-22022 September 1992 Part 21 Rept Re Crack in Weld Seam on Wall Section of ASTM A-500 Grade B Steel Tubing Found by Tva/Bechtel.Caused by Not Enough Contact or No Contact Near Tube Outside Diameter.Mill Operators Should Be Reinstructed ML20115B7401992-09-22022 September 1992 Part 21 Rept Re Crack in Weld Seam of One End of Sample Taken of 4 X 4 X 1/2 ASTM-500 Grade B Tubing Supplied by Consolidated Power Supply.Appropriate Personnel Reinstructed on Importance of Weld Quality ML20118B4391992-09-11011 September 1992 Part 21 Rept Re Degradation in Abb Type 27N Undervoltage Relays Used in Electrical Switchgear.Recommends That Users Review Applications Requiring Exposures Greater than 1E03 Rads TID W/Time Delay Function Option ML20090L8801992-03-18018 March 1992 Part 21 Re Cracked Piston Castings Received from Acme Foundry,Fairbanks Morse & General Casting.Magnetic Particle Insp of All Pistons Will Be Performed.List of Affected Plants Encl ML20079A9791991-04-0505 April 1991 Part 21 Rept Re Failure to Comply W/Purchase Orders When Shipping 12 3000 Socket Weld Unions,Astm B247 Alloy 6061-T6 & Three 150 Pipe Flanges,Astm B62 Cast Brass.Matl Supplied Following Commercial Program ML20059M1751990-09-24024 September 1990 Supplemental Part 21 Rept 1 Re Defect in Coltec Industries, Inc Connecting Rod Assemblies Nuts/Bolts on Model 38TD8-1/8 Emergency Generators.Initially Reported on 851120.Nuts/bolts for Assemblies at Stated Plants Inspected & Replaced 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 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 ML20012C2401990-02-16016 February 1990 Part 21 Rept Re Defective Pieces of ASTM A500 Square Tubing Mfg by UNR-Leavitt.Initially Reported by Licensee on 900215. Limited Number of 29 Pieces Determined to Actually Be Defective,Per TVA Visual Insp.Matl Will Be Returned ML20006A7141990-01-19019 January 1990 Updated Final Significant Deficiency Rept 107 Re Defective Agastat GP Relays.Initially Reported on 831129.Use of Subj Relays Does Not Represent Safety Concern & Not Reportable as Operational Concern.Test Program Developed 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 ML19354D7171989-12-19019 December 1989 Part 21 Rept Re Use of Electrical Components & Cabling in Air Conditioning Units Not Environmentally Qualified. Initially Reported on 890920.Nonqualified Cable Will Be Replaced & Control Panel Relocated ML20247Q1331989-09-20020 September 1989 Part 21 Rept Re Defect W/Two Air Conditioning Units Provided by Ellis & Watts.Caused by Undocumented Electrical Components & Cabling in Units.Tva Will Use Addl Procurement Receipt Insps of safety-related Matl ML20245G0411989-08-0808 August 1989 Advises That Corrective Actions for Significant Deficiency & Part 21 Rept Re Unqualified Nupro Valve Seals Completed & Resolved,Per 890707 Rept.Only 98 Nupro Test Valves Furnished on GE Racks & Addl 17 Valves Provided for Other Racks 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 ML20246J6411989-07-0707 July 1989 Supplemental Part 21 & Deficiency Rept L2-89-44 Re Nupro Test Valves,Installed on Instrument Line Racks Furnished by Ge,Not Remaining Leak Tight During DBA Conditions.Initially Reported on 890608.Root Cause Analysis Will Be Performed ML20245K9061989-06-30030 June 1989 Significant Deficiency Repts L2-89-08,38,43 & 45-48 Re Safe Shutdown Analysis.Corrective Actions Completed & Significant Deficiencies Considered Resolved ML20244A5101989-06-0707 June 1989 Final Significant Deficiency Rept SDR-L2-89-39 Re Failure of Stainless Steel Midlock Ferrules.Caused by Isolated Stress Corrosion Cracking Not Affecting Other Penetration Ferrules in Penetration 20JX222 Replaced ML20247N7731989-05-31031 May 1989 Supplemental Significant Deficiency Rept Re Safe Shutdown Analysis self-assessment ML20247Q7341989-05-31031 May 1989 Significant Deficiency Rept L2-89-34 Re Tavis Pressure Differential Transmitters Installed W/O Connecting Internal Heaters.Initially Reported on 890418.Heaters Will Be Connected on All Tavis Pressure Differential Transmitters ML20246F9051989-05-15015 May 1989 Significant Deficiency Rept L2-89-23 Re Essential Equipment Located in Unanalyzed Environ.Installation of Conduit Seals or Reorientation of Conduit Runs Planned to Avoid Moisture Intrusion Into Electrical Equipment Prior to Startup ML20246M3681989-05-0808 May 1989 Significant Deficiency Rept L2-89-06 Re Unavailability of Suppression Pool Indication Due to App R Fire.Caused by Design Error Resulting from Lack of Procedural Guidance. Reportability Evaluation Initiated ML20246K2201989-05-0202 May 1989 Part 21 Rept Re EMD Air Start Motors/Ingersoll Rand 150 Bmp Model D.Initially Reported on 890404.Problem Not Considered 10CFR21 Finding by Div Based on Encl Investigation Rept & Corrective Actions Taken by Power Sys Div.Matter Closed ML20248F6101989-04-13013 April 1989 Interim Significant Deficiency Rept L2-88-11 Re Inadequate Degraded Grid Undervoltage Relay Setpoints.Event Discussed W/Engineer Involved to Ensure Procedural Adherence & New Undervoltage Relays Will Be Installed ML20248F3571989-04-0303 April 1989 Interim Significant Deficiency Rept SDR-L2-89-17 Re Unavailability of Feedwater Maint Isolation Valve to Support RCIC Operation in Event of App R Fire.Initially Reported on 890303.Cause Under Investigation.Rept to Be Submitted ML20248F9451989-03-28028 March 1989 Part 21 Rept Re Replacement of Circuit Boards for Safeguard Battery Chargers.Initially Reported on 890323.C&D Power Sys Provided Instructions to Change Out 600 Ohm Fixed Resistor w/500 Ohm Variable Resistor in Charger Circuitry ML20246H0951989-03-10010 March 1989 Significant Deficiency Rept L2-88-10 Re Improper Installation of Temporary Support Brackets in safety-related 4 Kv Switchgear.Support Brackets Removed from Switchgear Cubicle Prior to Startup & Procedures Revised ML20235F8601989-02-17017 February 1989 Interim Significant Deficiency Repts SDR-L2-89-03,04 & 05 Re Unavailability of HPCI & RCIC Sys Due to App R Fire. Initially Reported on 890117.Corrective Actions Under Review & Will Be Reported by 890531 ML20247G2481989-02-0606 February 1989 Part 21 Rept Re Hydro Test of Inboard Isolation Valve.Disc in Valve in RHR Sys Not Tested for Pressure Retention Capability During ASME Test.Item Not Reportable Per Part 21 ML20196B8281988-12-0202 December 1988 Final Significant Deficiency Rept 250-2 Re Use of Insulated Wire by Westinghouse in safety-related Motor Starters. Initially Reported on 881020.Defective Components Reworked & Corrected.Action to Prevent Recurrence Not Necessary 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML18039A9041999-10-15015 October 1999 LER 99-010-00:on 990917,automatic Reactor Scram on Turbine Stop Valve Closure Occurred.Caused by High Water Level in Main Steam Moisture Separator 2C2.Unit 2C2 Reservoir Level Transmitter & Relays Were Replaced & Tested Satisfactorily ML18039A8981999-10-14014 October 1999 LER 99-009-00:on 990915,manual Reactor Scram Was Noted Due to EHC Leak.Caused by Failure of Stainles Steel Tubing Connection.Removed Damaged Tubing & Connection Plug ML18039A8951999-10-0808 October 1999 LER 99-008-00:on 990905,HPCI Was Inoperable Due to Failed Flow Controller.Caused by Premature Failure of Capacitor 2C3.Replaced Controller & HPCI Sys Was Run IAW Sys Operating Instructions ML20217F9671999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20217D1211999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Lgs,Units 1 & 2. with ML18039A8751999-09-30030 September 1999 LER 99-005-00:on 990901,SR for Standby Liquid Control Sampling Was Not Met.Caused by Deficient Procedure for Chemical Addition to Standby Liquid Control.Revised Procedure.With 990930 Ltr ML20212E6341999-09-23023 September 1999 Suppl to SE Resolving Error in Original 990802 Se,Clarifying Fact That Licensee Has Not Committed to Retain Those Specific Compensatory Measures That Were Applied to one-time Extension 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 ML20212D3831999-09-20020 September 1999 Safety Evaluation Supporting Proposed Rev to Withdrawal Schedule for First & Third Surveillance Capsules for BFN-3 RPV ML20212A8861999-09-13013 September 1999 Safety Evaluation Authorizing First & Second 10 Yr Interval Inservice Insp Plan Requestss for Relief RR-01 ML20212A4481999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Limerick Generating Station,Units 1 & 2.With ML18039A8821999-08-31031 August 1999 Increased MSIV Leakage Tech Spec Change Submittal - Seismic Evaluation Rept. ML20212B8561999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Browns Ferry Nuclear Plant.With ML20211E9891999-08-20020 August 1999 LGS Unit 2 Summary Rept for 970228 to 990525 Periodic ISI Rept Number 5 ML18039A8391999-08-0606 August 1999 BFN Unit 2 Cycle 10 ASME Section XI NIS-1 & NIS-2 Data Repts. ML20210N1221999-08-0202 August 1999 Safety Evaluation Accepting Licensee Request for Relief from ASME B&PV Code,Section XI Requirements.Request 3-ISI-7, Pertains to Second 10-year Interval ISI for Plant,Unit 3 ML20210L7051999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Limerick Generating Station,Units 1 & 2.With ML20210R0931999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML18039A8201999-07-26026 July 1999 LER 99-004-00:on 990625,facility Core Spray Divisions I & II Inoperable at Same Time Due to Personnel Error.Electrical Supply Breaker to Core Spray Division II Pump 3B Returned to Normal Racked in Position ML18039A8171999-07-20020 July 1999 LER 99-007-00:on 990623,discovered That SR for Monitoring of Primary Containment Oxygen Concentration Had Not Been Met. Caused by Failure of Operators to Adequately Communicate. Required Surveillances Were Performed.With 990720 Ltr ML18039A8161999-07-19019 July 1999 LER 99-006-00:on 990618,noted That Main Steam SRV Exceeded TS Setpoint Tolerance.Caused by Pilot Vlve disc-seat Bonding.Util Replaced All 13 SRV Pilot Cartridges with Cartridges Certified to Be Witin +/-1%.With 990719 Ltr ML20209J0771999-07-16016 July 1999 Safety Evaluation Concluding That Licensee Provided Adequate Information to Resolve ampacity-related Points of Concern Raised in GL 92-08 for BFN & That No Outstanding Issues Re GL 92-08 Ampacity Issues for Browns Ferry NPP Exist ML18039A8121999-07-12012 July 1999 LER 99-005-00:on 990617,ESF Actuation & HPCI Declared Inoperable.Caused by Personnel Error.Reset HPCI & Returned Sys to Operable Status with 25 Minutes.With 990712 Ltr ML20209D7741999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Limerick Generating Station,Units 1 & 2 ML20209H4381999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20209G0211999-06-30030 June 1999 GE-NE-B13-02010-33NP, Evaluation of Limerick Unit 2 Shroud Cracking for at Least One Fuel Cycle of Operation ML18039A8101999-06-28028 June 1999 LER 99-004-00:on 990530,safety Features Sys Actuations Occurred Due to RPS Trip.Caused by Failure of MG Set AC Drive Motor Starter Contractor Coil.Licensee Placed 2B RPS Bus on Alternate Feed & Half Scram Was Reset ML20196F8811999-06-23023 June 1999 Safety Evaluation Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power Operated Gate Valves ML18039A8071999-06-14014 June 1999 LER 99-003-00:on 990515,automatic Reactor Scram Due to Turbine Trip Was Noted.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram ML18039A8011999-06-14014 June 1999 LER 99-001-00:on 990515,automatic Reactor Scram Occurred Due to Tt.Caused by Failure of Mechanical Trip Cylinder to Latch When Hydraulically Reset.Operations Crew Stabilized Reactor Following Scram.With 990614 Ltr ML18039A8021999-06-14014 June 1999 LER 99-002-00:on 990501,SRs for Single CR Withdrawal During Cold SD Were Not Adequately Implemented.Caused by Procedural Inadequacy.Revised Applicable Plant Surveillances.With 990614 Ltr ML20195G4651999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Lgs,Units 1 & 2 ML20196B8051999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Browns Ferry Nuclear Plant,Units 1,2 & 3.With ML20207H8331999-05-31031 May 1999 Non-proprietary Rev 0 to 1H61R, LGS - Unit 2 Core Shroud Ultrasonic Exam ML20209D7791999-05-31031 May 1999 Revised Monthly Operating Repts for May 1999 for Limerick Generating Station,Units 1 & 2 ML18039A7791999-05-0606 May 1999 LER 99-003-00:on 990408,declared Plant HPCI Sys Inoperable Due to Loose Wire.Caused by Failure to Properly Tighten Screw at Some Time in Past.Loose Wire Was Tightened ML20195B3021999-05-0606 May 1999 Rev 0 to PECO-COLR-L2R5, COLR for Lgs,Unit 2 Reload 5 Cycle 6 ML18039A7761999-04-30030 April 1999 Revised Surveillance Specimen Program Evaluation for TVA Browns Ferry Unit 3. ML20195G4761999-04-30030 April 1999 Revised Monthly Operating Repts for Apr 1999 for Lgs,Units 1 & 2 ML20206R0731999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Bfnp.With ML20206N2901999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Limerick Generating Station,Units 1 & 2.With ML18039A7561999-04-23023 April 1999 Bfnp Risk-Informed Inservice Insp (RI-ISI) Program Submittal. ML20206D8971999-04-22022 April 1999 Rev 2 to PECO-COLR-L1R7, COLR for Lgs,Unit 2 Reload 7, Cycle 8 ML18039A7671999-04-0808 April 1999 Rev 0 to TVA-COLR-BF2C11, Browns Ferry Nuclear Plant Unit 2 Cycle 11 Colr. ML18039A7461999-04-0707 April 1999 LER 99-001-00:on 990308,determined That Two Trains of Standby Gas Treatment (SGT) Were Inoperable.Caused by Trip C SGT Blower Motor Breaker.Initiated Shutdown of Plant,Reset C SGT Blower Motor Breaker & Declared Train Operable ML20205F9341999-04-0101 April 1999 Safety Evaluation Authorizing Licensee 990108 Relief Request PV-38,from Requirements of ASME BPV Code Section XI IST Testing,Valve Program for Plant,Units 1,2 & 3 ML20205N8341999-04-0101 April 1999 Part 21 Rept Re Automatic Switch Co Nuclear Grade Series X206380 & X206832 Solenoid Valves Ordered Without Lubricants That Were Shipped with Std Lubrication to PECO & Tva.Affected Plants Were Notified ML20205S0601999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with Status Change from Previous Update,990331 ML20205S0661999-03-31031 March 1999 Rept on Status of Public Petitions Under 10CFR2.206 with No Status Change from Previous Update,990331, Atlas Corp ML20205T5441999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Bfnp.With 1999-09-30
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AutomaticSwitch Cu FLORHAM PARK, NEW JERSEY 07932 e NJ (201) 966-2000 / NY-(212) 3440765 F AX- (201) 966 2628 ass M April 1,1999 Documents Control Desk United States Nuclear Regulatory Commission Washington, DC 20555
Subject:
ASCO Nuclear Gr ' ": ries X206380 & X206832 Solenoid Valves Gentlemen:
Enclosed is the text of a letter sent to Philadelphia Electric Company and TVA regarding the subject valves.
Based on the results of an evaluation conducted by Automatic Switch Company (ASCO) in cooperation with Philadelphia Electric Company (Limerick Station), ASCO has concluded that there is a possibility some nuclear grade valves ordered "without lubricants" were supplied with our standard lubrication. This occurred as a result of the misinterpretation, by assembly personnel, of directions in the manufacturing procedure for this special construction. The manufacturing / assembly procedure has been modified to clarify the instructions, and ASCO Quality Assurance has incorporated additional inspection criteria to verify the lubricant free construction.
The non-conformance would affect only a limited number of specific ASCO valves manufactured before 1997.
Over the years, there have been isolated repons of these valves " sticking", or not shifling when de-energized. One or more of the utilities experiencing this problem attributed this
" sticking" to the lubricant used in these valves. However, ASCO has conducted extensive laboratory testing, and we were unable to duplicate the reported " sticking" We believe, rather, that system contamination caused these reported problems.
Several utilities remained unconvinced and asked us to produce a " lubricant free" version of several ofour nuclear grade solenoid valves. Although we didn't feel this was necessary, we agreed to accommodate the few utilities requesting "without lubricant" constructions.
Since this lubrication was used in the qualification of these valves, ASCO does not believe that the presence of our standard lubrication in valves ordered without lubricanton could potentially constitute a safety hazard or is repcitable under 10CFR part 21.
9904190176 990401 PDR
" Gl{ d [OIb S
ADOCK 05000259 PDR if
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1 Thousands of the qualified valves of this type with lubrication have been used in many nuclear plants for safety related applications over the last 20 years. No design or generic problems have been attributed to these qualified valves.
tioivever, as a courtesy, ASCO is notifying its customers, since there is a possibility that we did not comply with purchase order requirements, and we are providing you with a copy of our letter for your information.
Very truly yours, AUTOMATIC SWITCli COMPANY VALVE SERVICE DEPARTMENT l
l i
aspM I,
AutomaticSwitch Cc.
FLORHAM PARK, NEW JERSEY 07932 e NJ-(201) 966-2000 / NY.(212) 344-3765 FAX: (201) 966 2628 April 1,1999 Philadelphia Electric Co. (Peco)
Limerick Generating Station Documents Control Evergreen & Sanatoga Rds.
Limerick Township, PA 19468
Subject:
ASCO Nuclear Grade Series X206380 & X206832 Solenoid Valves Gentlemen, Based on the results of an evaluation conducted by Automatic Switch Company (ASCO) in cooperation with Philadelphia Electric Company (Limerick Station), ASCO has concluded that there is a possibility some nuclear grade valves ordered "without j
lubricant" vere supplied with standard lubrication. This occurred as a result of the misinterpretation of directions in the manufacturing procedure for this special {
j construction by assembly personnel. Tne manufacturing / assembly procedure has been {
modified to clarify the instructions. Additionally, ASCO Quality Assurance has l incorporated additional inspection criteria to verify the lubricant free construction.
The non-conformance would affect only a limited number of specific ASCO valves manufactured before 1997. Valve catalog numbers, ASCO order numbers and your purchase order numbers are shown on the attached list to identify each purchase.
l Since this lubrication was used in the qualification of these valves, ASCO does not believe that the presence of our standard lubrication in valves ordered without lubrication could potentially constitute a safety hazard or is reportable under 10CFR part 21. (
Thousands of the qualified valves of this type with lubrication have been used in many nuclear plants for safety related applications over the last 20 years. No design or gerHe problems have been attributed to these qualified valves.
l However, as a courtesy, ASCO is notifying our customers, since there is a possibility that we did not comply with purchase order requirements. A copy of this letter is being sent to the NRC for their information.
t
- y. .
Although most of these special valves have been installed and are approaching the end of E.Q. life, ASCO will support the requests ofnuclear plants for the lubricant free construction.
- 1. If valves have not been installed, they can be retumed to ASCO for no charge replacement.
- 2. If valves are installed in critical applications where problems have occurred, contact ASCO to discuss replacement issues.
Your contact for questions or replacements is Ken Thomas, Sr. Service Engineer at 973-966-2265.
Very tmly yours, AUTOMATIC SWITCH COMPANY VALVE SERVICE DEPARTMENT
/rd I
i
1
. . 1 PHILADELPHIA ELECTRIC COMPANY ASCO NO. CUST. P.O. NO. CATALOG NO. QUANTITY 394818 PL204070 X206380-3RF,15385 5 PIL387007 325872 PL204070 X206380-3RF,15385 9 REL387004 467331-001 PL376113-008 X206380-3RF,15385 38 664993-001 PL376113 X206380-3RF,15385 4 REL387028 345398 PL204070 X206380-6RVF,15385 1 REL348006 673057-001 PL376113 X206832-6RVF,15385 2 REL348036 689380-001 PL376113 X206832-6RVF,15385 12 REL348041 327844 PL204070 X206832-6RVF,15385 4 REL348003 684274-001 PL376113 X206832-3RVU,15385 10 REL348041 673817-001 PL376113 X206832-3RVU,15385 1 REL348039 482432 PL204070 X206832-3RVU,15385 3 REL348013
AutomaticSwiich CD.
FloRHAM PARK, NEW JERSEY 07932 e to-(201) 966 2000 / NY-(212) 344-3765 FAX. (201)966-2628 spM April 1,1999 TVA Browns Ferry Nuclear Plant Documents Control c/o Browns Ferry Project Athens, AL 35611
Subject:
ASCO Nuclear Grade Series X206380 & X206832 Solenoid Valves Gentlemen, Based on the results of an evaluation conducted by Automatic Switch Company (ASCO) in cooperation with Philadelphia Electric Company (Limerick Station), ASCO has concluded that there is a possibility some nuclear grade valves ordered "without lubricant" were supplied with standard lubrication. This occurred as a result of the misinterpretation of directions in the manufacturing procedure for this special construction by assembly personnel. The manufacturing / assembly procedure has been modified to clarify the instructions. Additionally, ASCO Quality Assurance has incorporated additional inspection criteria to verify the lubricant free construction.
The non-conformance would affect only a limited number of specific ASCO valves manufactured before 1997. Valve catalog numbers, ASCO order nu.abers and your purchase order numbers are shown on the attached list to identify each purchase.
Since this lubrication was used in the qualification of these valves, ASCO does not believe that the presence ofour standard lubrication in valves ordered without lubrication could potentially constitute a safety hazard or is reportable under 10CFR part 21.
Thousands of the qualified valves of this type with lubrication have been used in many nuclear plants for safety related applications over the last 20 years. No design or generic problems have been attributed to these qualified valves.
However, as a courtesy, ASCO is notifying our customers, since there is a possibility that we did not comply with purchase order requirements. A copy of this letter is being sent to the NRC for their infornmtion.
Although most of these special valves have been installed and are approaching the end of
, E.Q. life, ASCO will support the requests of nuclear plants for the lubricant free construction.
- 1. If valves have not been installed, they can be returned to ASCO for no charge replacement.
- 2. If valves are installed in critical applications where problems have occuned, contact ASCO to discuss replacement issues. l l
l Your contact for questions or replacements is Ken Thomas, Sr. Service Engineer at j 973-966-2265. I Very truly yours, AUTOMATIC SWITCH COMPANY t
VALVE SERVICE DEPARTMENT .
/rd 1
l i
TVA (BROWNS FERRY)
ASCO NO. CUST. P.O. NO. CATALOG NO. OUANTITY 689325-001 92NMB44952C X206832-3RF,15385 26 RELRD369777 583188 P-96N2R-155186-000 X206832-3RF,15385 10 REL00000000 328793 P-92NMB44952C-000 X206802-3FF,15385 2 REL1026098 l
I I
l 1
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