Part 21 Rept Re Possible Defect in Model KMG-HRH Noble Gas Radiation Monitor W/Enhanced Detector Model KDGM-HR. Initially Reported on 860222.Vendor Will Request Utils for Listed Plants to Determine If Monitors DefectiveML20137X389 |
Person / Time |
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Site: |
Millstone, Hatch, Palo Verde, Perry, Cooper, Surry, North Anna, 05000000, Shoreham |
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Issue date: |
02/27/1986 |
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From: |
Colton A KAMAN INSTRUMENTATION CORP. |
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To: |
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
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References |
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REF-PT21-86, REF-PT21-86-107-000 KI-GEN-86-001, KI-GEN-86-1, PT21-86-107, PT21-86-107-000, NUDOCS 8603060210 |
Download: ML20137X389 (3) |
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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 ML20211D6491999-08-25025 August 1999 Part 21 Rept Re Nonconformance within LCR-25 safety-related Lead Acid Battery Cells Manufactured by C&D.Analysis of Cells Completed.Analysis of Positive Grid Matl Shows Nonconforming Levels of Calcium within Positive Grid Alloy ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results B17414, Part 21 Rept Re 980116 Failure of Tachometer Transducer,Id Number TG-25-5,during Surveillance Test.Caused by Bearing Failure Which Could Cause Shaft to Seize & Break.Removed from Svc & Replaced Failed Tachometer Transducer1998-09-0303 September 1998 Part 21 Rept Re 980116 Failure of Tachometer Transducer,Id Number TG-25-5,during Surveillance Test.Caused by Bearing Failure Which Could Cause Shaft to Seize & Break.Removed from Svc & Replaced Failed Tachometer Transducer 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 ML20236Y1231998-08-0707 August 1998 Part 21 Rept Re Gas & Turbine Generator for Dedicated Emergency Power to Vital AC Buses 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 ML20248F3531998-05-21021 May 1998 Part 21 Rept Re Electronic Equipment Repaired or Reworked by Integrated Resources,Inc from Approx 930101-980501.Caused by 1 Capacitor in Each Unit Being Installed W/Reverse Polarity. Policy of Second Checking All Capacitors Is Being Adopted ML20247G6131998-05-13013 May 1998 Part 21 Rept Re Defect Contained in Automatic Switch Co, Solenoid Valves,Purchased Under Purchase Order (Po) 970161. Caused by Presence of Brass Strands.Replaced Defective Valves ML20247B6751998-05-0101 May 1998 Part 21 Rept Re Evaluation & Notification for RELAP4 Excessive Variability at Millstone Unit 2.Caused by Small Changes in Input to RELAP4 That Can Result in Large Changes in Calculated Peak Cladding Temp.Informed NRC of Deviation ML20217A1531998-04-16016 April 1998 Closure to Interim Part 21 Rept Submitted to NRC on 970929. New Date Established for Completion of Level I & 2 Setpoint Project Committed to in .Final Approval of Setpoint Calculations Will Be Completed by 980531 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 ML20198E0631998-01-0707 January 1998 Part 21 Rept Re Shipment by Dubose National Energy Svcs,Inc, of 40 Pieces of 4 inch,90 Degree Elbows Which Did Not Meet ASME Section II SA-234 Requirements 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 ML20217H8711997-10-15015 October 1997 Part 21 Rept Re Potential Safety Hazard for Some 3/4 Sch 40 Pipe Shipped to CP&L & VA Power Corp.Matl Has Been Found to Have Areas Where Wall Thickness Falls Below Minimum Allowed by SA 312 Specification.Customers Have Been Notified 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 ML17309A6211997-09-29029 September 1997 Part 21 Rept Re Final Disposition of Masterflow 713 & Embeco 636 Grout Nonconformance Reported by Master Builders,Inc. Licensee Continuing to Monitor shelf-life of Masterflow 713 & Embeco 636 Grouts Produced at Rancho Cucamonga ML20217D4141997-09-29029 September 1997 Interim Part 21 Rept Re Errors Noted During Preparation of ITS Surveillance Test Procedures Using GE Calculated Setpoints.Setpoint Calculations Will Be Reviewed,Corrected & Approved to Establish Significance of Errors 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 B16531, Part 21 Rept Re GE Commercial Grade Dedication Program Being Determined to Be Inadequate in Ability to Demonstrate Seismic Capability of Specific Relay.Returned Relays to GE Facility for Repair1997-07-0303 July 1997 Part 21 Rept Re GE Commercial Grade Dedication Program Being Determined to Be Inadequate in Ability to Demonstrate Seismic Capability of Specific Relay.Returned Relays to GE Facility for Repair ML18153A1431997-06-10010 June 1997 Part 21 Rept Re Possible Machining Defect in Certain Stainless Steel Swagelok Tube Fitting Bodies.Facilities Have Been Notified About Possible Problem ML20140D6581997-06-0606 June 1997 Part 21 Rept Re GE Model Ifcs Relays Procured from GE Delivered W/Loose Hardware & Unsuitable for Use at Unit 1 ML20140A9661997-05-29029 May 1997 Part 21 Rept Re Ksv Emergency Diesel Generator Power Piston Failure.Caused by Jacket Water in Combustion Chamber. Recommends That Users Verify That Crown Thickness at Valve Cutout Be 100 Minimum 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 ML20210E3591997-03-27027 March 1997 Part 21 Rept Re Sorrento Electronics Inc Has Determined Operation & Maint Manual May Not Adequately Define Requirements for Performing Periodic Surveillance of SR Applications.Caused by Hardware Failures.Revised RM-23A ML20137F3221997-03-26026 March 1997 Part 21 Rept Re Perry Nuclear Power Plant Experiencing False Trip of K600S K-Line Low Voltage Circuit Breaker w/SS-5 Solid State Trip Device.Breaker Removed from Svc & Returned to Abb for Analysis ML20137G6261997-03-25025 March 1997 Svcs Part 21 Rept Re Emergency Generators Installed at Zion Station Which Developed Significant Drop in Crankcase Lube Oil Level.Caused by Crack in Liner Wall,Allowing Jacket Water to Enter Chamber B16149, Part 21 Rept Re Cracked Fuse Ferrule Defects Due to Administrative Error in Ltr Detailing Commitments Re Issue. Corrected Copy of Commitments Associated W/Ltr Provided1997-01-14014 January 1997 Part 21 Rept Re Cracked Fuse Ferrule Defects Due to Administrative Error in Ltr Detailing Commitments Re Issue. Corrected Copy of Commitments Associated W/Ltr Provided ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause B16030, Part 21 Rept Re Stocked safety-related Fuses Issued from Storeroom for Installation Which Had Cracked Ferrules in Longitudinal Direction on 960911.Procurement & Warehouse Groups Completed Inspecting Fuses in Warehouse1996-12-13013 December 1996 Part 21 Rept Re Stocked safety-related Fuses Issued from Storeroom for Installation Which Had Cracked Ferrules in Longitudinal Direction on 960911.Procurement & Warehouse Groups Completed Inspecting Fuses in Warehouse ML20135D8011996-11-26026 November 1996 Part 21 Rept Re Two Safety Related Valves Supplied by Velan Valve Corp Were Not in Compliance W/Originally Supplied QA Documentation.Returned Valves to Velan in May 1996 & on 961120 Velan Advised That Valves Had Been Misplaced ML20134N4061996-11-22022 November 1996 Part 21 Rept Re Fifteen Different Fuse Types from Three Different Mfgs Found to Have Axial Cracks Due to Brass Being Susceptible to Defect.Functional Testing Should Be Performed on Sample of Fuses ML20134H3361996-11-0505 November 1996 Part 21 Rept Re Defective Inner Thrust Bearing 1801461-01 Used in PSA 35 Mechanical Shock Arrestor Used as Restraint on Piping Sys for Nuclear Generating Plant.Lot of Defective Parts Located & Isolated to Three Customers ML18065B0111996-10-18018 October 1996 Part 21 Rept Re Application of Certain Aspects of ABB-CE Safety Analysis Methodology ML20115D2001996-07-0909 July 1996 Part 21 Rept Re Mfg Defect of Enterprise DSR-4 & DSRV-4 Edgs,Originally Mfg by Calcon Corp.Amot Control Corp Purchased Calcon Product Line & Maintains Design & Production.Valves Returned to Cooper Energy Svcs on 960131 ML20113D4201996-05-15015 May 1996 Part 21 Rept Re Certain Lots of Commercial Grade Potentiometers in Transmeters Have Been Supplied W/Lubrication in Noncompliance W/Engineering Spec Requirements ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs LD-96-014, Part 21 Rept Re Response to NRC Notice on Nonconformance. Licensee Will Direct Cognizant Personnel Reviewing Deviation or Failure to Comply for Basic Components Delivered to Customers,To Document Whether/Not Facts Indicate Evaluation1996-04-26026 April 1996 Part 21 Rept Re Response to NRC Notice on Nonconformance. Licensee Will Direct Cognizant Personnel Reviewing Deviation or Failure to Comply for Basic Components Delivered to Customers,To Document Whether/Not Facts Indicate Evaluation 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 ML20086A2751995-06-27027 June 1995 Part 21 Rept Re Several Incidents of Instrument Drift in Excess of Specified Limits for Rosemount Pressure Transmitter Model 1154SH9.Other Licensees Advised to Be Alert to Differences in Pressure Indication ML20083R9101995-04-26026 April 1995 Final Part 21 Rept Re Kepco,Inc Model RMX24-D-20804 Power Supplies in Which Transistors Q15 &/Or Q16 Failed to Open & R1 Was Open.Replacement of Transmitters w/XSIS-095 Along W/ Replacement of Electrolytic Capacitors Provides Solution ML20077D3431994-11-29029 November 1994 Part 21 Rept Re Suspect Master Connecting Rods & Contains Info Location in Engine for Rods ML20078G3051994-11-0909 November 1994 Rev to Part 21 Rept Re Potential Problem W/Master Power Connecting Rods.Vendor Recommends Listed Utils Perform Visual Insp of Master Rods to Determine Applicability of Rept ML18153B0841994-09-26026 September 1994 Suppl to 940902 Initial Part 21 Rept Re Defect W/Governor Valves Used in turbine-driven Pumps Mfg by Dresser-Rand to Formally Addresss Written 30 Day Rept Requirement of 10CFR21(c)(3)(ii) 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 ML18153B0601994-09-0202 September 1994 Initial Part 21 Rept Re Steam Drive AFW Pump Governor Valve Mfg by Dresser-Rand.Maint Procedure to Stroke Governor Valve Stem Performed Weekly & Monitoring of Corrosion Build Up in Gland Seal Leakoff Area Performed Weekly 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 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217P5391999-10-25025 October 1999 Rev 0,Change 1 to Millstone Unit 1 Northeast Utils QA Program ML20217N9281999-10-20020 October 1999 Special Rept:On 991003,PZR PORV Actuation Mitigated RCS low- Temp Overpressure Transient.Caused by a RCP Facilitating Sweeping of Entrained Air Out of RCS Loops.Operating Procedure 2-OP-5.1 Will Be Revised ML20217H3631999-10-14014 October 1999 Rev 0 to COLR for North Anna 2 Cycle 14 Pattern Su ML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20217D3061999-10-13013 October 1999 SER Accepting Licensee Proposed Changes to Edwin I Hatch Nuclear Plant Emergency Classification Scheme to Add Emergency Action Levels Related to Operation of Independent Spent Fuel Storage Installation ML18152A2811999-10-12012 October 1999 Technical Basis for Elimination of Nozzle Inner Radius Insps (for Nozzles Other than Reactor Vessel),Technical Basis for ASME Section XI Code Case N-619. ML20217C8721999-10-0606 October 1999 Rev 21,change 3 to MP-02-OST-BAP01, Nuqap Topical Rept, App F & G Only ML20212J9251999-10-0101 October 1999 Safety Evaluation Accepting Licensee Relief Request IWE-3 for Second 10-year ISI for Plant ML20217D6851999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for North Anna Power Station,Units 1 & 2.With B17896, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 1.With B17894, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 2.With B17898, Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Millstone Nuclear Power Station,Unit 3.With HL-5845, Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Ei Hatch Nuclear Plant.With ML17300B3811999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pvngs,Units 1,2 & 3.With 991007 Ltr ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico PY-CEI-NRR-2437, Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Pnpp,Unit 1.With ML20217G7461999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Cooper Nuclear Station ML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML20212K9781999-09-30030 September 1999 Safety Evaluation Accepting USI A-46 Implementation Program ML18152B3531999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Surry Power Station,Units 1 & 2.With 991012 Ltr ML20216J4341999-09-24024 September 1999 Mnps Unit 3 ISI Summary Rept,Cycle 6 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 ML20212A6641999-09-13013 September 1999 Safety Evaluation Authorizing Relief Request RR-V-16 for Third 10 Yr Interval Inservice Testing Program ML20211N2611999-09-0808 September 1999 Safety Evaluation Concluding That Proposed Irradiation of Fuel Rods Beyond Current Lead Rod Burnup Limit & Clarification of Terminology with Respect to Reconstituted Fuel Assemblies Acceptable ML20211N8401999-09-0202 September 1999 Rev 21,change 1 to Northeast Utils QA TR, Including Changes Incorporated Into Rev 20,changes 9 & 10 ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 B17879, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 2.With B17874, Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Millstone Nuclear Power Station,Unit 3.With B17878, Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Mnps,Unit 1.With HL-5836, Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Edwin I Hatch Nuclear Plant.With ML20216E5011999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Naps,Units 1 & 2. with ML20211J2561999-08-31031 August 1999 Safety Evaluation Accepting Elimination of Augmented ISI Program for Pressurizer Spray Lines at North Anna Unit 2 ML20211J2421999-08-31031 August 1999 Safety Evaluation Supporting Removal of Augmented Insp Program on RCS Bypass Lines from Licensing Basis of North Anna,Units 1 & 2 ML18152B6651999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Surry Power Station Units 1 & 2.With 990915 Ltr ML20212C5001999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Cooper Nuclear Station PY-CEI-NRR-2429, Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pnpp,Unit 1.With ML17300B3271999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Pvngs,Units 1,2 & 3 ML20211G9631999-08-30030 August 1999 SER Accepting Licensee Response to GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML17313B0751999-08-27027 August 1999 LER 99-002-00:on 990730,test Mode Trip Bypass for EDG Output Breakers Not Surveilled.Cause Under Investigation.Operations Personnel Conservatively Invoked SR 3.0.3 for SR 3.8.1.13. with 990827 Ltr ML18152B4421999-08-27027 August 1999 LER 99-006-00:on 990802,determined That Plant Was Outside of App R Design Basis Due to Fire Barrier Deficiencies. Caused by Original Plant Design Deficiencies.Fire Watches Were Established & Mods Have Been Completed.With 990827 Ltr ML18152B4411999-08-27027 August 1999 LER 99-005-00:on 990731,effluent Radiation Monitors Were Declared Inoperable.Caused by Degraded Heat Trace Circuits for Monitors Sample Suction Line.Degraded Heat Trace Circuit Was Replaced & Addl Heat Trace Is Being Installed ML20211D6491999-08-25025 August 1999 Part 21 Rept Re Nonconformance within LCR-25 safety-related Lead Acid Battery Cells Manufactured by C&D.Analysis of Cells Completed.Analysis of Positive Grid Matl Shows Nonconforming Levels of Calcium within Positive Grid Alloy ML18151A3981999-08-13013 August 1999 SPS Unit 2 ISI Summary Rept for 1999 Refueling Outage. ML18152B3771999-08-13013 August 1999 LER 99-004-00:on 990714,TS Violation Due to non-safety Related Fans Effect on CR Boundary Was Noted.Cause of Event Has Not Yet Been Determined.Cable Spreading Room Doors Were Operned to Reduce Pressure in Rooms ML20210T0791999-08-13013 August 1999 Safety Evaluation Concluding That Revised Withdrawal Schedules for North Anna Units 1 & 2 Satisfy Requirements of App H to 10CFR50 & Therefore Acceptable ML20210J9631999-08-0202 August 1999 SER Finding That Licensee Established Acceptable Program to Verify Periodically design-basis Capability of safety-related MOVs at Edwin I Hatch Nuclear Plant,Units 1 & 2 ML20210J9271999-08-0202 August 1999 SER Finds That Licensee Performed Appropriate Evaluations of Operational Configurations of safety-related power-operated Gate Valves to Identify Valves at Plant,Susceptible to Pressure Locking or Thermal Binding ML20211A6561999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 2 B17856, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 1.With B17858, Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Millstone Nuclear Power Station,Unit 3.With 1999-09-08
[Table view] |
Text
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Komen instrumentation Corporetton 1500 Garden of the (sods Road P.o. Box 7463 Colorado Springs, CO 80933 (303)599-1500 KAMAN February 27,1986 KI-GEN-86-001 US NRC Director, Office of Inspection and Enforcement Washington, D.C. 20555 Gentismen:
In conformance with applicable requirements and provisions of 10CFR21, Kaman Instrumentation Corporation (KI) hereby provides notification of a possible defect in the operation of a noble gas radiation monitor supplied to our clients which may relate to a potential safety hazard.
The suspect monitor is a Kaman model KMG-HRH with detector enhancement model KDGM-HR, part no. 952397-003. The monitor is designed to measure fresh equilibrium noble gas fission product mixtures to 1x10+5 micro Curies /cc as specified in REGULATORY GUIDE 1.97 Revision 3.
On 02/21/86, 09:30 am MST, a Mr. Rod Berquist of North Anna Power Station -Mineral, Virginia, notified Kaman Instrumentation of a defect in their model KMG-HRH radiation monitors. The North Anna monitors indicated a saturated detector condition at approximately 3x10+3 micro Curies /cc.
Investigation indicated a possible defect might exist in like monitors supplied to other clients and that all would be notified by phone to be followed by written notification.
On 02/22/86, 09:40 am MST, Mr. Bill Jones of the US NRC Emergency Response Center in Washington D.C. was notified of the possible defect in the KMG-HRH radiation monitor. An explanation of the possible defect was given and a list of stations having these monitors was provided. Stations having these monitors were also notified on 02/22/86.
The following information relating to this potential safety hazard is provided as required in 10CFR21.21(3), parts i through viii, to the extent known:
8603060210 PDR ADOCK h PDR h 45 Page 1
$h'f/ I O
)k
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February 27,1986
.KI-GEN-86-001 (1) Name and address of individual informina the Commission Mr. Allan M. Colton, President Kaman Instrumentation Corporation 1500 Garden of the Gods Road
. Colorado Springs, Co. 80907 (ii) Identification of the basic component supplied.
Radiation monitor model KMG-HRH with enhanced detector model KDGM-HR, part no. 952397-003.
(iii) Identification of firm supplying the basic component.
Kaman Instrumentation Corporation Address same as in (i)
(iv) Nature of failure to comply.
( As explained in preceding text. )
(v) Date the informatio.n of defect was obtained.
02/21/86 at 09:30 am MST, by Mr. Rod Berquist of North Anna Power Station - Mineral, Virginia.
(vi) Number and location of basic components in use or supplied.
- North Anna Power Station (3 monitors)
Mineral, Virginia
- Surry Power Station (2 monitors)
Surry, Virginia
- Cooper Power Station (4 monitors)
Brownville, Nebraska
- Shoreham Power Station (2 monitors)
Wading River, New York
Baxley, Georgia
- Perry Power Station (3 monitors)
Perry, Ohio Page 2
l jo. .
February 27, 1986 KI-GEN-86-001
- Millstone Unit 1 (1 monitor)
Waterford, Connecticut
- Millstone Unit 2 (1 monitor)
Waterford, Connecticut
- Millstone Unit 3 (2 monitors)
Waterford, Connecticut
- Palo Verde Unit 1 (3 monitors)
Wintersburg, Arizona
- Palo Verde Unit 2 (3 monitors)
Wintersburg, Arizona
- Palo Verde Unit 3 (3 monitors)
Wintersburg, Arizona (v11) Corrective action, responsible oraanization, and time to complete the action.
Kaman Instrumentation will request in writing that each power station conduct tests to determine if a possible defect exists with their model KMG-HRH monitors. Upon notification of a defect, Kaman Instrumentation will provide the modification to properly indicate detector saturation above the required 1x10+5 micro Curles/cc.
The estimated time to correct a reported defect for a given plant is 4 weeks after notification of the defect.
(viii) Advice relating to defect beina alven to purchasers.
Readings obtained during DBE conditions may be invalid.
If detector saturation is indicated, steps should be taken to obtain samples of the monitored effluent for analysis by other means.
We believe this information to be complete as required under 10CFR21 part 21. Please contact Mr. Frank Bergamo, Customer Service Manager - Radiation Monitoring, if additional information is required. Mr. Bergamo may be reached at ph. (303) 599-1659.
Sincerely, Allan .Colton President Kaman Instrumentation c.c. Roger Patterson M5505 EW-W enclosures: 2 copies copy to each power station Page 3 i