ML20135D448
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| ML20135D448 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island, Callaway, San Onofre, 05000000 |
| Issue date: | 08/15/1985 |
| From: | Casey Smith RAYCHEM CORP. |
| To: | Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| References | |
| REF-PT21-85, REF-PT21-85-385-000 PT21-85-385, PT21-85-385-000, NUDOCS 8509160057 | |
| Download: ML20135D448 (1) | |
Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20217A1691999-09-22022 September 1999
[Table view]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 ML20206H2611999-05-0505 May 1999 Part 21 Rept Re Defect Found in Potter & Brumfield Relays. Sixteen Relays Supplied in Lot 913501 by Vendor as Commercial Grade Items.Caused by Insufficient Contact Pad Welding.Relays Replaced with New Relays ML18066A2771998-08-13013 August 1998 Part 21 Rept Re Deficiency in CE Current Screening Methodology for Determining Limiting Fuel Assembly for Detailed PWR thermal-hydraulic Sa.Evaluations Were Performed for Affected Plants to Determine Effect of Deficiency ML20236N3871998-07-0909 July 1998 Part 21 Rept Re Deficiency Identified in Event 32725, Corrected by Mgp Instruments Inc.Licensee Verified,Affected Equipment Has Been Reworked & Tested at Sce.Design Mod Completed ML18065B1351998-01-0606 January 1998 Part 21 Rept Re Use of Deltstrat Code for RCS Flow Rate Determination.Code Corrects for Temps to Determine Hot Leg Bulk Coolant Temp LD-97-033, Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 9712011997-11-20020 November 1997 Part 21 Rept Re Defect in Potter & Brumfield Mdr Relays, Models 170-1 & 7032.Extended Problem to Include All Mdr Relay Models W/Date Codes 93XX-95XX.Root Cause Analysis, Written Rept & Recommended Corrective Actions Due by 971201 LD-97-028, Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys1997-10-13013 October 1997 Part 21 Rept Re Contamination of Lubricant Which Has Led to Hardening of Lubricant in Certain Potter & Brumfield Mdr Relay Models 170-1 & 7032.Will Distribute Copy of Rept to Utils Having ABB-CE Designed Nuclear Steam Supply Sys ML20211M6491997-10-0808 October 1997 Addenda 1 to Part 21 Rept Re Weldments on Opposed Piston & Coltec-Pielstick Emergency stand-by Diesel gen-set lube-oil & Jacket Water Piping Sys.Revised List of Potentially Affected Utils to Include Asterisked Utils,Submitted ML20211H7911997-09-30030 September 1997 Part 21 Rept Re Failure of Weldment Associated w/lube-oil Piping Sys on 970804 at Millstone,Unit 2.Root Cause Is Not Yet Known.Quality of Weldment Is Being Considered.Listed Util Sites Affected LD-97-024, Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-0041997-08-14014 August 1997 Part 21 Rept Re Error in Energy Redistribution Factor Used in LOCA Analysis for Listed Plants for Which ABB-CE Performed Analysis.Issued Recommendations Info Bulletin 97-004 ML20217H0511997-08-0505 August 1997 Part 21 Rept Re Discovery That Radiation Monitoring Sys Power Supply Circuit Board Subject to Premature Electronic Component Failure ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages LD-97-002, Part 21 Rept Re Piping Line Loss Between SG & MSIV Inlet When MSSVs Area Activated.Recommends That Utils Confirm Proper Adjustment of MSSV Blowdown Settings So as to Preclude Valve Chatter & Related Structural Concerns1997-01-17017 January 1997 Part 21 Rept Re Piping Line Loss Between SG & MSIV Inlet When MSSVs Area Activated.Recommends That Utils Confirm Proper Adjustment of MSSV Blowdown Settings So as to Preclude Valve Chatter & Related Structural Concerns ML20132D8091996-12-18018 December 1996 Part 21 Rept Re Defect of Welds on Weld Nut Holding Filter Assembly Panel.Failure of Weld or Weld Nut Could Allow Filter Assembly Panel to Break Loose Under Seismic Stress & Cause Damage to Other Components in Charger ML20132C0751996-12-13013 December 1996 Part 21 Rept Re Testing of Six HFD3045 & HFD3060 Molded Case Circuit Breakers w/125 Volt DC Shunt Trip Devices.Identified Incorrectly Installed DC Shunt Trip Units & Are in Process of Being Returned to Vendor ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology LD-96-009, Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power1996-04-15015 April 1996 Part 21 Rept Re Potential Instrumentation Decalibr at Low Power.Affected Utils Should Ensure That Log Power Channels Properly Calibr & cross-correlated to Linear Power Channels at 100% Reactor Power ML20086N9981995-07-21021 July 1995 Part 21 Rept Re Mdr Relays W/Potentially Damaged Internal Contact Arms ML20082D9011995-01-27027 January 1995 Final Part 21 Rept Re Valves Installed W/Shim Between Yoke & Adapter Plate Involved in Jan 1994 Incident.Caused by Operational Problems Involving Maint Procedures.Ltr Sent to Affected Utils.Item Not Reportable Under 10CFR21 ML20080D5921994-12-28028 December 1994 Submits Followup to 940418 Part 21 Re Investigation W/ Respect to Jan 1994 Incident at Prairie Island Generating Plant Involving Crane Design Gate Valves 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 ML20072S9581994-08-30030 August 1994 Part 21 Rept Re Crane Design Gate Valves Involved in Jan 1994 Incident at Praire Island Nuclear Generating Plant. Historical Records Do Not Contain Info Addressing Total Number of Configuration Mfg by Crane ML20065G4671994-04-0101 April 1994 Part 21 Rept Re Failure of Support Studs on Discharge Piping Bracket to Turbocharger That Provide Support for Air Inlet Housing ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head LD-93-139, Part 21 Rept Re Error in Input to Large Break LOCA Analysis. Paint Thickness Factor of Ten Larger than Intended Used for One of Walls in Containment.Caused by Wrong Value Transcribed & Used in LOCA Analysis1993-09-24024 September 1993 Part 21 Rept Re Error in Input to Large Break LOCA Analysis. Paint Thickness Factor of Ten Larger than Intended Used for One of Walls in Containment.Caused by Wrong Value Transcribed & Used in LOCA Analysis ML20056D7071993-07-15015 July 1993 Part 21 Rept Re Reportable defect-75 PSIG Relief Check Valve 1 Npt,Emd 9521844,Kepner 416C-1-75 ML20128C3971993-01-28028 January 1993 Suppl to 921217 Final Part 21 Rept Re Defect on Cast Steel Cylinder Heads.One Addl Part (1A-7680) Discovered Which Was Supplied to Util.Copy of Rept Also Sent to Affected Util ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20125C7161992-12-0707 December 1992 Part 21 Rept Re Possibility for Malfunction of Declutching Mechanisms in SMB/SB-000 & SMB/SB/SBD-00 Actuators. Malfunction Only Occurs During Seismic Event.Balanced Levers May Be Purchased from Vendor.List of Affected Utils Encl ML20127P5861992-11-23023 November 1992 Followup to 921005 Part 21 Rept Re Potential Defect in SB/SBD-1 Housing Cover Screws.Procedure Re Replacement of SBD-1 Spring Cover Bolts Encl.All Fasteners Should Be Loosened & Removed.List of Affected Utils Encl ML20087B8551991-11-0808 November 1991 Part 21 Rept 10CFR21-0058 Re Camshaft Bearing Block Assembly Mounting Bolts Found to Be Shorter than Required Length.All Engines Where Camshaft Work Was Performed Will Be Inspected. All Bolts Shorter than 4.531 Inches Will Be Replaced ML20087D1631991-11-0808 November 1991 Rept 10CFR21-0059 Re One Broken Stud & Three Cracked Studs Found at Drivegear End of Left Bank Camshaft Flange.Caused by Sulphide Inclusions.All Broken or Cracked Dowel Bolts Should Be Replaced ML20087B7491991-10-11011 October 1991 Part 21 Rept Re Failure of Seven Camshaft Bearing Block Assembly Mounting Bolts in Diesel Generator.Caused by Use of Shorter Bolts W/Shorter Tolerance.Issue Under Review ML20087B7641991-10-11011 October 1991 Part 21 Rept Re Eight Camshaft Locating Studs in Diesel Engine Found Broken & Three Studs Found Cracked.Caused by Fatigue Loading & Torsional Vibration.Justification for Continued Operation Encl ML20070A6861991-01-17017 January 1991 Part 21 Rept Re Failure of 4.16 Kv vertical-lift Switchgear Cell Mounted,Auxiliary Contacts to Operate on Demand During Testing of Auxiliary Standby Switchgear at Facility. Initially Reported on 901101.New Test Link Sent to Facility L-91-002, Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl1991-01-0404 January 1991 Supplemental Part 21 Rept Re GE Reactor Trip Breakers Used in safety-grade Equipment.Initially Reported on 901228.List of Plants Supplied w/C-E Breakers Encl ML20028H3531990-12-13013 December 1990 Part 21 Rept Re Cable Assemblies Failing to Meet IEEE-383 Section 3 Flammability Tests.Results of Tests Conducted on 901206 Encl.Corrective Actions Include Applying Flame Retardant Covering to Cable or Cable Replacement ML20062D9351990-11-0101 November 1990 Part 21 Rept Re Failure of 4.16 Kv Vertical Lift Switchgear, cell-mounted Auxiliary Contacts to Operate on Command During Testing of Standby Switchgear at Plant.Caused When Maladjusted Test Link Inserted Between Breaker & Switch NRC-90-3528, Part 21 Rept Re Potential Problem in Decay Heat Model of Wcobra/Trac Computer Code.Model Corrected & Calculations Initiated.Recalculations of App K Analyses for Plants Will Be Completed by 9007231990-07-16016 July 1990 Part 21 Rept Re Potential Problem in Decay Heat Model of Wcobra/Trac Computer Code.Model Corrected & Calculations Initiated.Recalculations of App K Analyses for Plants Will Be Completed by 900723 ML20043F3431990-06-0808 June 1990 Part 21 Rept Re Circumferential Grove of Varying Depth Up to 0.200 Inches on Inside Surface of Journal Above Attachment Weld to Impeller.Failure of Journal Could Result in Major Damage to Pump.Disassembly Scheduled Over Next 18 Months ML20012C1051990-03-0707 March 1990 Part 21 Rept Re Several Failures of Fairbanks Morse Engine Div Piston Pins/Bushings on Upper Pistons.Caused by Incorrect Surface Pattern on Piston Pins.Piston Pins Under Listed Purchase Orders to Be Removed & Replaced ML20012A9011990-02-27027 February 1990 Suppls 900213 10CFR21 Rept Re Chilled Water Sys Operation. Evaluation of Crystal River Determined That Postulated High Energy Line Break in Intermediate Bldg May Be Subj to Steam Loads Higher than Normal Loads,Causing Rising Water Temp 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 ML18153C1011990-02-0202 February 1990 Part 21 Rept Re Two of Three Pc Cards in GE Type SLV11A1 Over/Undervoltage Relays Failing to Produce Output.Short Between Leads Would Result in Damage to Component 1C5. Sketch of Threshold Detection Board Encl ML17223A7451990-01-26026 January 1990 Part 21 Rept Re Backup Rings Furnished in Spare Parts Seal Kits & in 25 Gpm 4 Way Valves as Part of Actuators Made of Incorrect Matl.Rings Should Be Viton & Have Been Identified as Buna N 1999-09-22 Category:TEXT-SAFETY REPORT MONTHYEARML20217E2691999-09-30030 September 1999
[Table view]Monthly Operating Rept for Sept 1999 for Callaway Plant,Unit 1.With ML20217G4461999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pingp.With ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20217E3381999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Songs,Units 2 & 3 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 ML20212A3361999-09-14014 September 1999 1999 Biennial RERP Exercise, for Callaway Plant. Pages 7,8 & 9 (of 9) in Mini Scenario 1 Section of Incoming Submittal Not Included ML20212D0711999-09-14014 September 1999 Safety Evaluation Re GL 88-20, Individual Plant Exam for Severe Accident Vulnerabilities ML20212A1471999-09-13013 September 1999 Special Rept:On 990904,condenser Monitor Was Declared Inoperable.Difficulties Encountered During Component Replacement Precluded SCE from Restoring Monitor to Service within 72 H.Alternate Method of Monitoring Was Established ML20211N0511999-09-0303 September 1999 SER Approving Exemption from Certain Requirements of 10CFR50.44 & 10CFR50 App A,General Design Criterion 41 to Remove Requirements from Hydrogen Control Systems from SONGS Units 2 & 3 Design Basis ML20211N0451999-09-0202 September 1999 Safety Evaluation Concluding That Util Has Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant That Are Susceptible to Pressure Locking & Binding ML20212A0201999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Callaway Plant,Unit 1.With ML20216E7151999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pingp,Units 1 & 2. with ML20211Q8201999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Songs,Units 2 & 3. with ML20211D3981999-08-24024 August 1999 Safety Evaluation Supporting Requested Actions to Licenses DPR-42 & DPR-60,respectively ML20211H8621999-08-23023 August 1999 Safety Evaluation Accepting Licensee Requests for Relief RR-E-2-03 - RR-E-2-08 from Exam Requirements of Applicable ASME Code,Section Xi,For First Containment ISI Interval ML20210P4731999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 2 ML20210P4791999-08-11011 August 1999 COLR Cycle 10 Songs,Unit 3 ML20210P0441999-08-10010 August 1999 Safety Evaluation Granting Licensee Requests for Relief (ISI-13 - ISI-18) from Requirements of Section XI of 1989 Edition of ASME B&PV Code,For Second 10-year Interval ISI at Plant,Unit 1 ML20210Q8331999-08-0505 August 1999 Rev 4 to Callaway Cycle 10 Colr ML20211C2531999-08-0404 August 1999 Unit 1 ISI Summary Rept Interval 3,Period 2 Refueling Outage Dates 990425-990526 Cycle 19 971212-990526 ML20210T9481999-08-0303 August 1999 Informs Commission Re Status of Issues Related to Risk Informed Decision Making That Were Raised During Staff Review of License Amend Approving Electrosleeve SG Tube Repair Method for Ue Callaway Plant,Unit 1 ML20210T4451999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Callaway Plant,Unit 1.With ML20216D8791999-07-31031 July 1999 Rev 3 to Callaway Cycle 10 Colr ML20210Q6521999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Songs,Units 2 & 3 ML20211B5971999-07-31031 July 1999 Cycle 20 Voltage-Based Repair Criteria 90-Day Rept ML20210Q4891999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pingp,Units 1 & 2. with ML20210H6531999-07-30030 July 1999 SER Accepting Relief Request to Second Ten Year Inservice Insp Plant for Plant,Unit 1 ML20210L2771999-07-30030 July 1999 SONGS Unit 3 ISI Summary Rept 2nd Interval,2nd Period Cycle 10 Refueling Outage U3C10 Site Technical Services ML20209J1131999-07-15015 July 1999 Safety Evaluation of Topical Rept NSPNAD-8102,rev 7 Reload Safety Evaluation Methods for Application to PI Units. Rept Acceptable for Referencing in Prairie Island Licensing Actions ML20209H0881999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Callaway Plant,Unit 1.With ML20209C9281999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Songs,Units 2 & 3. with ML20196H8621999-06-30030 June 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data, June 1999 Rept ML20209F9811999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With ML20196F4081999-06-23023 June 1999 Revised Pages 71,72 & 298 to Rev 7 of NSPNAD-8102, Prairie Island Nuclear Power Plant Reload Safety Evaluation Methods for Application to PI Units ML20195D3061999-06-0202 June 1999 Safety Evaluation of TR SCE-9801-P, Reload Analysis Methodology for San Onofre Nuclear Generating Station,Units 2 & 3. Rept Acceptable ML20195G5181999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Prairie Island Nuclear Generating Plant,Units 1 & 2.With . Page 3 in Final Rept of Incoming Submittal Was Not Included ML20195H4831999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Callaway Plant,Unit 1.With ML20195H5491999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Songs,Units 2 & 3 ML20207B5931999-05-26026 May 1999 SER Accepting Licensee Proposed Alternative to ASME Code for Surface Exam (PT) of Seal Welds on Threaded Caps for Unit 1 Reactor Vessel Head Penetrations for part-length CRDMs ML20196L2501999-05-13013 May 1999 Rev 0 to PINGP Unit 1 COLR Cycle 20 ML20196L3221999-05-11011 May 1999 SONGS Unit 2 ISI Summary Rept 2nd Interval,2nd Period Cycle-10 Refueling Outage ML20206H2611999-05-0505 May 1999 Part 21 Rept Re Defect Found in Potter & Brumfield Relays. Sixteen Relays Supplied in Lot 913501 by Vendor as Commercial Grade Items.Caused by Insufficient Contact Pad Welding.Relays Replaced with New Relays ML20206R7111999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Callaway Plant Unit 1.With ML20206S7281999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Songs,Units 2 & 3 ML20206L6191999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Pingp,Units 1 & 2. with ML20205Q6221999-04-19019 April 1999 Safety Evaluation Authorizing Proposed Alternative to Use Wire Penetrameters for ISI Radiography in Place of ASME Code Requirement ML20205Q5561999-04-19019 April 1999 Safety Evaluation Accepting Relief for Request from Certain ASME Section Requirements for Containment Insp ML20205R0371999-04-16016 April 1999 SER Approving Proposed Deviation from Approved Fire Protection Program Incorporating Technical Requirements of 10CFR50,App R,Section III.0 That Applies to RCP Oil Fill Piping ML20205G2611999-04-0101 April 1999 Special Rept:On 990328,3RT-7865 Was Removed from Service. Monitor Is Scheduled to Be Returned to Service Prior to Mode 4 Entry (Early May 1999) Which Will Exceed 72 H Allowed by LCS 3.3.102.Alternate Method of Monitoring Will Be Used ML20205Q0981999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Songs,Units 2 & 3 1999-09-30 |
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B Chemelex Division 7bSS By Road PO Box 6036 le evvve 4 tE?N 4%J Tem JJ 4K4 Rednood Cay CA 94063 jg$ g y August 15, 1985 2,/
Mr. Tolbert Young USNRC, Office of Inspection and Enforcement 0,Y Wau 1450 Maria Lane, Suite 260 Walnut Creek, California 94596 RD: Raychem Auto-Trace 20PTV1 Electric Heat Trace
Dear Mr. Young:
As our Mr. James Gemperle informed you, we determined that certain lots of Auto-Trace 20PTV1 Self-Regulating Electric Heat Tracers and associated derivatives may have slightly lower than specified power output. These products are used to maintain elevated temperatures in pipes and vessels. As noted in Mr. Gemperle's letter, the effect of low power output may only be a slightly higher duty cycle; for applications where the heat tracer is on 100 percent of the time, it would mean a lower maintenance temperature.
We have informed licensees who received the questionable lots of material, advised them of the nature of the problem, and of the procedure to determine if there is any effect on their operations.
The licensees informed pursuant to 10CFR21 are:
Northern States Power Prairie Island Nuclear Generating Plant Southern California Edison Company San Onofre Nuclear Generating Station Calloway Plant, Portland, Missouri If you require additional information regarding this matter, do not hesitate to call me at 415) 361-3276.
Yours truly,
, tI )
Clifford G. Smith Quality Program Manager Process Division 8509160057 850815 PDR ADOCK 05000206 S PDR I Q
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