|
---|
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 U-603204, Final Part 21 Rept 21-99-003 Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier Trentec for Westinghouse Breaker 1AP05EH.Issue Determined Not Reportable Per 10CFR211999-04-30030 April 1999 Final Part 21 Rept 21-99-003 Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier Trentec for Westinghouse Breaker 1AP05EH.Issue Determined Not Reportable Per 10CFR21 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 U-603182, Part 21 Rept Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier, Trentec.Condition Rept 1-99-01-136 Was Initiated to Track Investigation & Resolution of Issue1999-03-12012 March 1999 Part 21 Rept Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier, Trentec.Condition Rept 1-99-01-136 Was Initiated to Track Investigation & Resolution of Issue U-603115, Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps in Supplying SR Parts to Npps.Issue Is Not Reportable Under 10CFR21. Dedication Process Did Not Affect Ability of Components1998-12-0404 December 1998 Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps in Supplying SR Parts to Npps.Issue Is Not Reportable Under 10CFR21. Dedication Process Did Not Affect Ability of Components U-603114, Part 21 Rept 21-98-049 Re W Dhp Circuit Breaker Refurbished by Nuclear Logistics,Inc Which Failed to Operate.Caused by Trip Latch out-of-adjustment & Incorrectly Sized Ratchet Lever Assembly Bushing.Breakers Were Returned to Vendor1998-11-25025 November 1998 Part 21 Rept 21-98-049 Re W Dhp Circuit Breaker Refurbished by Nuclear Logistics,Inc Which Failed to Operate.Caused by Trip Latch out-of-adjustment & Incorrectly Sized Ratchet Lever Assembly Bushing.Breakers Were Returned to Vendor ML20154E2171998-09-28028 September 1998 Follow-up Part 21 Rept Re Defect with 1200AC & 1200BC Recorders Built Under Westronics 10CFR50 App B Program. Westronics Has Notified Bvps,Ano & RBS & Is Currently Making Arrangements to Implement Design Mods ML20236X2351998-08-0505 August 1998 Part 21 Rept Re Defect Associated W/Westronics 1200AC & 1200BC Recorders Built Under Westronics 10CFR50,App B Program.Beaver Valley,Arkansas Nuclear One & River Bend Station Notified.Design Mod Is Being Developed U-603033, Part 21 Rept 21-98-039 Re Shrinkage of Medium & High Density Silicone Seals Designed & Installed by Bisco Using Dow Corning Sylgard 170 Matl.Caused by Coefficient of Thermal Expansion.Will Inspect & Rework/Repair Suspected Seals1998-07-20020 July 1998 Part 21 Rept 21-98-039 Re Shrinkage of Medium & High Density Silicone Seals Designed & Installed by Bisco Using Dow Corning Sylgard 170 Matl.Caused by Coefficient of Thermal Expansion.Will Inspect & Rework/Repair Suspected Seals ML20236E7991998-05-26026 May 1998 Final Part 21 Rept Re W Dhp Circuit Breaker Auxillary Switch Operating Assembly Anomalies.Caused by Loss of Breaker Safety Function.Dhp Circuit Will Be Inspected 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 U-603004, Part 21 Rept Re 980107 Determination That Itt Barton Model 580A Series Differential Pressure Indicating Switches Operating Forces Too Low.Manufacturing Sys Allowed Switches to Be Mixed.Evaluation Concludes Issue Not Reportable1998-05-15015 May 1998 Part 21 Rept Re 980107 Determination That Itt Barton Model 580A Series Differential Pressure Indicating Switches Operating Forces Too Low.Manufacturing Sys Allowed Switches to Be Mixed.Evaluation Concludes Issue Not Reportable ML20216A9601998-05-0808 May 1998 Part 21 Rept Re Failure of 12 Volt DC Inverter Power Supply. Caused by Inadequately Sized Output Transistor Pair Combined W/Degraded Capacitors.Licensee Plans to Replace All Output Transistors & Degraded Capacitors U-602995, Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps During Use of Portable Metal Analyzer.Util Identified Discrepancies Which Are Acceptable W/Some Exception of Some Replacement Parts1998-05-0505 May 1998 Part 21 Interim Rept 21-98-021 Re Deficiencies in Matl Dedication Process Used by Goulds Pumps During Use of Portable Metal Analyzer.Util Identified Discrepancies Which Are Acceptable W/Some Exception of Some Replacement Parts U-602994, Part 21 Rept Re Final Rept 21-98-008,on 980113,reliance Electric Motors Supplied by Rockwell International for Hydrogen Recombiner Cooling Fans Do Not Have nameplate- Specified High Temperature Bearings.Fan Motors Acceptable1998-04-29029 April 1998 Part 21 Rept Re Final Rept 21-98-008,on 980113,reliance Electric Motors Supplied by Rockwell International for Hydrogen Recombiner Cooling Fans Do Not Have nameplate- Specified High Temperature Bearings.Fan Motors Acceptable U-602979, Final Part 21 Rept 21-97-059 Re Discrepancies Found During Receipt Insp of Three Refurbished safety-related W Dhp Circuit Breakers.Util Completed Evaluation,Per 10CFR21 & Concludes That Condition Is Not Reportable1998-04-0707 April 1998 Final Part 21 Rept 21-97-059 Re Discrepancies Found During Receipt Insp of Three Refurbished safety-related W Dhp Circuit Breakers.Util Completed Evaluation,Per 10CFR21 & Concludes That Condition Is Not Reportable U-602968, Interim Part 21 Rept 21-97-055 Re Westinghouse Dhp Circuit Breaker Auxiliary Switch Operating Assembly Anomalies. Initially Reported on 980116.Util Currently Evaluating Suppliers Response to Questions Re Issue1998-03-24024 March 1998 Interim Part 21 Rept 21-97-055 Re Westinghouse Dhp Circuit Breaker Auxiliary Switch Operating Assembly Anomalies. Initially Reported on 980116.Util Currently Evaluating Suppliers Response to Questions Re Issue 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 U-602960, Part 21 & Deficiency Rept Re Commerical Grade Dedication Program of Sentry Equipment Corp.Initially Reported on 980217.IP Performed an Addl Assessment at Sentry Facility on 980226.Next Rept Will Be Submitted by 9804111998-03-12012 March 1998 Part 21 & Deficiency Rept Re Commerical Grade Dedication Program of Sentry Equipment Corp.Initially Reported on 980217.IP Performed an Addl Assessment at Sentry Facility on 980226.Next Rept Will Be Submitted by 980411 U-602954, Interim Part 21 rept,21-98-008 Re Identification That Bearings Installed in Hydrogen Recombiner B Cooling Fan Motor 0HG04CB Were Not Same as Bearings Specified on Motor Nameplate.Will Complete Evaluation of Issue by 9805131998-03-0909 March 1998 Interim Part 21 rept,21-98-008 Re Identification That Bearings Installed in Hydrogen Recombiner B Cooling Fan Motor 0HG04CB Were Not Same as Bearings Specified on Motor Nameplate.Will Complete Evaluation of Issue by 980513 U-602952, Part 21 Interim Rept 21-98-001:ITT Barton Model 580A Series Dp Indicating Switch Operating Force Concerns.Initially Reported on 980107.Evaluation of Subj Issue Will Be Completed by 9805301998-03-0606 March 1998 Part 21 Interim Rept 21-98-001:ITT Barton Model 580A Series Dp Indicating Switch Operating Force Concerns.Initially Reported on 980107.Evaluation of Subj Issue Will Be Completed by 980530 U-602939, Part 21 Interim Rept 21-97-060 Re Sentry Equipment Corp Commercial Grade Dedication Program Deficiencies.Evaluation of Issue Will Be Completed by 9804041998-02-17017 February 1998 Part 21 Interim Rept 21-97-060 Re Sentry Equipment Corp Commercial Grade Dedication Program Deficiencies.Evaluation of Issue Will Be Completed by 980404 U-602932, Interim Part 21 Rept 21-97-059 Re Several Discrepancies Found During Receipt Insp of Three safety-related W Dhp Circuit Breakers.Sent Subject Circuit Breakers to Nuclear Logistics Inc for Refurbishment1998-02-13013 February 1998 Interim Part 21 Rept 21-97-059 Re Several Discrepancies Found During Receipt Insp of Three safety-related W Dhp Circuit Breakers.Sent Subject Circuit Breakers to Nuclear Logistics Inc for Refurbishment U-602925, Part 21 Rept 21-97-058 Re Oil Leaking Around Diaphragm of Replacement Pressure Reducing/Dump Valve Installed on Itt Barton Hydromotor Actuator.Caused by Poor Workmanship of Valve at Time of Manufacture.Valves Sent to Vendor1998-02-0606 February 1998 Part 21 Rept 21-97-058 Re Oil Leaking Around Diaphragm of Replacement Pressure Reducing/Dump Valve Installed on Itt Barton Hydromotor Actuator.Caused by Poor Workmanship of Valve at Time of Manufacture.Valves Sent to Vendor U-602920, Part 21 Interim Rept 21-97-044/047/048 Re 970929 Failure of safety-related Battery Charger.Caused by Inadequate Soldered Wire Connections.Util Will Issue Rept of Issues IAW Provisions of 10CFR21 & 10CFR50.73 by 9802171998-01-28028 January 1998 Part 21 Interim Rept 21-97-044/047/048 Re 970929 Failure of safety-related Battery Charger.Caused by Inadequate Soldered Wire Connections.Util Will Issue Rept of Issues IAW Provisions of 10CFR21 & 10CFR50.73 by 980217 U-602910, Part 21 Interim Rept 21-97-055,identified Adverse Trend in Auxiliary Switch Operating Assembly Anomalies in W Dhp Circuit Breakers on 971120.Condition Rept 1-97-11-388 Initiated to Track Investigation & Resolution1998-01-16016 January 1998 Part 21 Interim Rept 21-97-055,identified Adverse Trend in Auxiliary Switch Operating Assembly Anomalies in W Dhp Circuit Breakers on 971120.Condition Rept 1-97-11-388 Initiated to Track Investigation & Resolution U-602894, Final Part 21 Rept Re Discrepancies Between GE BWR Reactor Design Requirements Documents & Sys Vendor Manuals.Util Completed Evaluation & Concluded That Issue Is Not Reportable Per 10CFR21 as Reported in 971029 Rept1997-12-18018 December 1997 Final Part 21 Rept Re Discrepancies Between GE BWR Reactor Design Requirements Documents & Sys Vendor Manuals.Util Completed Evaluation & Concluded That Issue Is Not Reportable Per 10CFR21 as Reported in 971029 Rept ML20203H9891997-12-12012 December 1997 Part 21 Rept Re Potential Manufacturing Defect of Enterprise DSR-4 & DSRV-4 Edgs.Cooper Energy Svcs Supplied 1A-7840 Adjusting Screw to Affected Utils & Sites.River Bend Station Replaced W/Acceptable Assemblies U-602876, Interim Part 21 Rept Re 970929 Discovery of Deviations in safety-related Battery Chargers.Evaluation of Conditions Under Part 21 Continuing.Update on Resolution Progress Will Be Provided by 9801291997-12-0303 December 1997 Interim Part 21 Rept Re 970929 Discovery of Deviations in safety-related Battery Chargers.Evaluation of Conditions Under Part 21 Continuing.Update on Resolution Progress Will Be Provided by 980129 U-602855, Part 21 Rept Re Discrepancies Between GE BWR Design Requirements Documents & Sys Vendor Manuals.Util Does Not Have Firm Date for Resolving Issue But Will Provide Update on Resolution Progress by 9712181997-10-29029 October 1997 Part 21 Rept Re Discrepancies Between GE BWR Design Requirements Documents & Sys Vendor Manuals.Util Does Not Have Firm Date for Resolving Issue But Will Provide Update on Resolution Progress by 971218 U-602823, Part 21 Rept Re Improper Clearance for W Model 50DHP350 Circuit Breaker Arc Chute Rear Arc Horn.Caused by Installation of Arc Chute Having Potential to Cause Line Pole to Deflect.Replace Deficient Arc Chutes1997-08-28028 August 1997 Part 21 Rept Re Improper Clearance for W Model 50DHP350 Circuit Breaker Arc Chute Rear Arc Horn.Caused by Installation of Arc Chute Having Potential to Cause Line Pole to Deflect.Replace Deficient Arc Chutes ML20149F6031997-07-18018 July 1997 Part 21 Rept Re R47 Incorrectly Installed on Electric Power Assembly.Recommends Evaluation of Timing Delay Requirements Applicable to Reactor Protective Sys 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 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 ML20136D5641997-03-0707 March 1997 Part 21 Rept Re Transformer Not Being Stable in No Load Condition & Tripping When Lightly Loaded U-602704, Part 21 Rept Re Regulated Power Transformer 1AP75ERT Tripping Several Times.Caused by Addition of Step Load from Low or No Load Condition.Will Disconnect Four Potentially Affected Transformers from Div 2 Electrical Sys1997-02-27027 February 1997 Part 21 Rept Re Regulated Power Transformer 1AP75ERT Tripping Several Times.Caused by Addition of Step Load from Low or No Load Condition.Will Disconnect Four Potentially Affected Transformers from Div 2 Electrical Sys 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 U-602677, Part 21 Rept Re Failure of Westinghouse Dhp Circuit Breaker to Close on Demand During Surveillance Test.Inspected, Cleaned,Adjusted & Lubricated Motor cut-off Switch & Spring Charge Indicator Mechanism in Subject Breaker1996-12-20020 December 1996 Part 21 Rept Re Failure of Westinghouse Dhp Circuit Breaker to Close on Demand During Surveillance Test.Inspected, Cleaned,Adjusted & Lubricated Motor cut-off Switch & Spring Charge Indicator Mechanism in Subject Breaker 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 U-602634, Part 21 Rept Re Failure of Itt Barton Hydramotor Actuator Pump to Develop Hydraulic Pressure During Testing.Initially Identified on 960306.Pump Withdrawn from Stores & Installed During Actuator Overhaul1996-09-20020 September 1996 Part 21 Rept Re Failure of Itt Barton Hydramotor Actuator Pump to Develop Hydraulic Pressure During Testing.Initially Identified on 960306.Pump Withdrawn from Stores & Installed During Actuator Overhaul ML20116B9251996-07-25025 July 1996 Part 21 Rept Re Failure Analysis Concerning Pump Assembly NS109761EQX07 ML20115J3981996-07-22022 July 1996 Interim Part 21 Rept Re 3/4 Schedule 80 Pipe Furnished to Consolidated Power Supply.Investigation Revealed Only One Nuclear Customer Involved in Sale of Matl 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 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 U-602580, Part 21 Rept Re Itt Barton Hydramotor Actuator Pump Assembly Failed to Develop Hydraulic Pressure During Testing.Caused by Pump Not Being Fitted Properly1996-05-0808 May 1996 Part 21 Rept Re Itt Barton Hydramotor Actuator Pump Assembly Failed to Develop Hydraulic Pressure During Testing.Caused by Pump Not Being Fitted Properly U-602579, Part 21 Rept Re Ideal Generators Installed W/Edgs Having Greater Generator Rotor Mass than Originally Calculated. Evaluated Impact of Issue of Generator Frequency & Torsional Vibration Prior to Interim Rept1996-05-0202 May 1996 Part 21 Rept Re Ideal Generators Installed W/Edgs Having Greater Generator Rotor Mass than Originally Calculated. Evaluated Impact of Issue of Generator Frequency & Torsional Vibration Prior to Interim Rept ML20108D1441996-05-0101 May 1996 Part 21 Rept Re Failure of Pump Assembly for Itt Barton Series NH95 Hydramotor Actuator.Did Not Develop Pressure Because Was Not Fitted Properly.Pump Assembly Has Been Returned to Itt Barton for Insp U-602564, Interim Part 21 Rept 21-96-001 Re Egds Rotor Mass Greater than Originally Calculated.Revised Calculation Shows Larger Rotor Mass & Rotational Inertia1996-03-13013 March 1996 Interim Part 21 Rept 21-96-001 Re Egds Rotor Mass Greater than Originally Calculated.Revised Calculation Shows Larger Rotor Mass & Rotational Inertia U-602532, Final Part 21 Rept 21-95-018 Re Failure of Power Shield Type SS-13 Solid State Trip Devices (Sstd) Mfg by Asea Brown Boveri,Ite,Gould & Brown Boveri.Util Inspected & Reworked,As needed,12 Type SS-13 Sstds in safety-related Breakers1995-12-20020 December 1995 Final Part 21 Rept 21-95-018 Re Failure of Power Shield Type SS-13 Solid State Trip Devices (Sstd) Mfg by Asea Brown Boveri,Ite,Gould & Brown Boveri.Util Inspected & Reworked,As needed,12 Type SS-13 Sstds in safety-related Breakers 1999-09-22
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K1231999-10-14014 October 1999 Revised Positions for DBNPS & Pnpp QA Program ML20217F9921999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Grand Gulf Nuclear Station,Unit 1.With 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 ML20212J2011999-09-30030 September 1999 Safety Evaluation Supporting Transfer of Dl Ownership Interest in Pnpp to Ceico U-603277, Monthly Operating Rept for Sept 1999 for Clinton Power Station,Unit 1.With1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Clinton Power Station,Unit 1.With RBG-45144, Monthly Operating Rept for Sept 1999 for River Bend Station. with1999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for River Bend Station. with ML20212F5641999-09-23023 September 1999 SER Concluding That All of ampacity-related Concerns Have Been Resolved & Licensee Provided Adequate Technical Basis to Assure That All of Thermo-Lag Fire Barrier Encl Cables Operating within Acceptable Ampacity Limits 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 ML20211Q3171999-09-0909 September 1999 Safety Evaluation Accepting BWROG Rept, Prediction of Onset of Fission Gas Release from Fuel in Generic BWR, Dtd July 1996 ML20216G1201999-09-0909 September 1999 Rev 3 to Rbs,Cycle 9 Colr RBG-45110, Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for River Bend Station, Unit 1.With ML20216E4881999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Grand Gulf Nuclear Station.With 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 U-603267, Monthly Operating Rept for Aug 1999 for Clinton Power Station,Unit 1.With1999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Clinton Power Station,Unit 1.With RBG-45087, Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection1999-08-0606 August 1999 Special Rept:On 990510,LPCI a & LPCS Injected Into Rv for Less than Two Minutes.Caused by Electrical Transient in One of ECCS Power Supplies.Operators Verified Reactor Cavity Level & Closed Injection Valves to Stop Injection ML20210K4721999-08-0303 August 1999 SER Accepting Licensee 180-day Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves RBG-45091, Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for River Bend Station, Unit 1.With U-603245, Monthly Operating Rept for Jul 1999 for CPS Unit 1.With1999-07-31031 July 1999 Monthly Operating Rept for Jul 1999 for CPS Unit 1.With ML20211A6921999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Grand Gulf Nuclear Station,Unit 1.With PY-CEI-NRR-2424, Monthly Operating Rept for July 1999 for Perry Npp.With1999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Perry Npp.With ML20210J3851999-07-28028 July 1999 Pnpp - Unit 1 ISI Summary Rept Results for Outage 7 (1999) First Period,Second Interval ML20211C9621999-07-26026 July 1999 ISI Summary Rept ML20209J1961999-07-12012 July 1999 Special Rept 99-001:on 990528,smoke Detectors Failed to Alarm During Performance of Routine Channel Functional Testing.Applicable TRM Interim Compensatory Measure of Establishing Roving Hourly Fire Patrol Was Implemented U-603232, Special Rept:On 990531 Lpms Was Declared Inoperable Due to Receipt of High Vibration & Loose Parts Alarm Which Did Not Clear.Lpms Was Restored to Operable Status on 990707 After Alignment & Tension on Recorder Tape Drive Was Adjusted1999-07-0909 July 1999 Special Rept:On 990531 Lpms Was Declared Inoperable Due to Receipt of High Vibration & Loose Parts Alarm Which Did Not Clear.Lpms Was Restored to Operable Status on 990707 After Alignment & Tension on Recorder Tape Drive Was Adjusted ML20210C6391999-07-0202 July 1999 Rev 2 to River Bend Station,Cycle 9 Colr ML20196K4981999-07-0101 July 1999 Safety Evaluation Authorizing PRR-E12-01,PRR-E21-01, PRR-P75-01,PRR-P81-01,VRR-B21-01,VRR-B21-02,VRR-E38-01 & VRR-E51-01.Concludes That Alternatives Proposed by EOI Acceptable ML20209G0691999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Grand Gulf Nuclear Station,Unit 1.With PY-CEI-NRR-2416, Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Perry Nuclear Power Plant,Unit 1.With RBG-45055, Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for River Bend Station, Unit 1.With U-603233, Monthly Operating Rept for June 1999 for Clinton Power Station,Unit 1.With1999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Clinton Power Station,Unit 1.With ML20196J8031999-06-24024 June 1999 Rev 1 to Rbs,Cycle 9 Colr ML20196A1951999-06-17017 June 1999 Instrument Drift Analysis ML20207G2741999-06-0707 June 1999 Safety Evaluation Concluding That Firstenergy Flaw Evaluation Meets Rules of ASME Code & That IGSCC & Thermal Fatigue Crack Growth Need Not Be Considered in Application ML20196A1161999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Grand Gulf Nuclear Station.With PY-CEI-NRR-2409, Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Perry Nuclear Power Plant,Unit 1.With RBG-45028, Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for River Bend Station, Unit 1.With U-603222, Monthly Operating Rept for May 1999 for Clinton Power Station.With1999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Clinton Power Station.With PY-CEI-NRR-2393, Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored1999-05-12012 May 1999 Special Rept Update:On 990327 Refueling Outage 7 Began & Troubleshooting Efforts Began.Troubleshooting of Affected Calbe Confirmed Fault in Drywell Section of Cable.Determined That Installation of Newer Technology Should Be Explored ML20210K8391999-05-11011 May 1999 British Energy Annual Rept & Accounts 1998-99 ML20206H1231999-05-0505 May 1999 Illinois Power Co CPS Main CR Simulator Certification Rept ML20206G6451999-05-0303 May 1999 Safety Evaluation Authorizing Requests for Relief IR-032 to IR-035 & IR-037 to IR-040 Re Implementation of Subsections IWE & Iwl of ASME Section XI for Containment Insp ML20206Q4831999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Grand Gulf Nuclear Station Unit 1.With ML20206J1201999-04-30030 April 1999 Redacted ME-98-001-00, Pressure Locking & Thermal Binding Test Program on Two Gate Valves with Limitorque Actuators PY-CEI-NRR-2399, Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Perry Nuclear Power Plant,Unit 1.With U-603210, Monthly Operating Rept for Apr 1999 for Cps,Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Cps,Unit 1.With U-603204, Final Part 21 Rept 21-99-003 Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier Trentec for Westinghouse Breaker 1AP05EH.Issue Determined Not Reportable Per 10CFR211999-04-30030 April 1999 Final Part 21 Rept 21-99-003 Re Deficiency in Commercial Grade Dedication Process Used by Circuit Breaker Refurbishment Supplier Trentec for Westinghouse Breaker 1AP05EH.Issue Determined Not Reportable Per 10CFR21 RBG-45016, Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With1999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for River Bend Station, Unit 1.With ML20206E2261999-04-29029 April 1999 Safety Evaluation Concluding That Proposed Alternatives Will Result in Acceptable Level of Quality & Safety.Authorizes Use of Code Case N-504 for Weld Overlay Repair of FW Nozzle Weld at Pnpp & Use of Table IWB-3514 ML20206D7911999-04-23023 April 1999 Rev 6 to PDB-F0001, COLR for Pnpp Unit 1 Cycle 8,Reload 7 ML20206A2111999-04-21021 April 1999 Safety Evaluation Authorizing Pump Relief Request PRR-001 & Valve Relief Request VRR-001 & Denying Valve Relief Request VRR-002 1999-09-09
[Table view] |
Text
'
GENER AL h ELECTRIC NUCLEAR POWER SYSTEMS DIVISION l GENERAL ELECTRIC COMPANY,175 CURTNER AVE., SAN JOSE, CALIFORNIA 95125 CAC 103-81 MC 682, (408) 925-5040 MFN 200-81 November 16, 1981 b
U.S. Nuclear Regulatory Commission {* af*VlY 7
~~
Office of Inspection and Enforcement -
Washington, DC 20555 t N u.
O\/2 3 ;g
- s. ,% % g ';e,
[ Coimss$p Attention: Richard C. DeYoung, Director A @
e,..
Gentlemen: (',g /
SUBJECT:
REPORTABLE CONDITION - TRANSMITTER AND TRIP UNITS FOR REACTOR VESSEL WATER LEVEL SCRAMS
Reference:
Letter, Glenn G. Sherwood (GE) to Victor Stello, Jr. ,
same subject, August 19, 1981, MFN-154-81 This is to advise the NRC of a change in the information about a report-able defect submitted in the referenced letter per 10CFR Part 21. The
) report of the subject defect erroneously included River Bend (Gulf States Utilities) as being one of the affected plants. In fact, there has been no similarly defective equipment offerei to this utility, and River Bend should not have been included in this report.
Field Disposition Instructions are scheduled to be issued by General Electric for correction of this condition as follows:
Clinton - 11/25/81 Perry 1 a 2 - 2/5/82, 3/5/82 TVA (Hartsville) - 6/25/81 Grand Gulf 1 & 2 - 8/28/81 (done), 5/14/82 Very truly yours, u
f, HUkU nnG.Sherwood, Manager /
, Nuclear Safety and Licensing Operation y",o" a;7 GC3:sem/4B wo 88O Attachment b cc: Mr. B. H. Grier, NRC Region I EI$ Mr. J. P. O'Reilly, NRC Region II 7pli
$$ Mr. J. G. Keppler, NRC Region III
- Mr. U. Potapovs, NRC Region IV "E
- Mr. J. F. McAllister, General Electric 4' \
C# Mr. L. S. Gifford, General Flectric
l pO W E EA R NU N ggsgO si S \
}r,p 5* \.E { } b te gt ac'\ D k pOGM\
cos -
- g A'J E s,
, or.
i 73 C -Mb C
n ct .b Cnu,e.t .- 86B7' o031 g
3 ES a 1
5, 19 , ' '
( '3 O
M gsiO CCC nt
_. tO 1 "niofC,;e
, f
, R24"'3 3r 2 g, MGC pggE- g6 S 0 e of c 3r ' Qif E q;p OM g (C Offgch'"qto
. n , 9t ste\30, c5 yiCtOf _qi; G *suo T q 3s gta nd 91T1GM ' E SU 1GC?l 3t 09 r
,a e si ;w, ,pte,, e Ga0 t ,- RE90 ,z'iE3E 3 w' e ysola(,3qef',,qaMO{3t , s LP B
se:Ett .na #c of ^ l."*cr .
e
,f lc't is\"s't@nT3s cet*'#
4,J ;' c e . .1q O'l c. W * ** (t 3C ' ','3COnditso
., to 3
', oftTb ' 1931 gts. pe 3y t'De p' p' ini 5 m,3 to u4 [,3st Tr5? 0th' s 3nd jiOC 36 gT 3 3j{aCge 3(a08statgist gpat 3to fe9o' Ss 00 g
.q t0 m3qn . g be prcGT3 s t 3ci*g,o
- the 5.. 1B,'3931-y[r,ef '
s 3ctT , , et ] p^ s W
,3JB T ' Ti eS
'J AuQ "
,u ,, u ofrPC b zg ~, ggy s e C
w -e 399 C m 1- 340 g7 e
DE ^
' ~ it O t gT g .
' '^, c530 "'
we f2gaf
._ a33 toe-@
5 0 ~p Tev_.
4
-'~cneoM EL '
7,'qctC 5
3p \ 32yu,$ r,3 C
e 3 w 3 ) ,-
9029 g T\ --
E T-8 C5
Gef C.' 30 Y 7qcO 2 ' -rOO deiE[l, ad Cc f,c Q'J q, O
-nee yye "of 'ee q u.
,.W w 0
QGC3 d te90 '- 2 ts, t t'3YI f [-
~,
(QW
!M E @ f d. '3u. ,
,M(r Dg go od, 1 L Q3nY) tgc. y ; *q 3 3 gTarn"[sti et'l O' R2\T T'] ,
,A'", c T e 3 c
,f 3. 7J G' t 3'('('G\igru, gGs- C5' g j l
,#qi c a' 'g'r
- t. -
L- ~
l7 .
, ont #C o n kcctrK
't h
'fIj G EN ER AL th ELECTRIC NUCLEAR POWER SYSTEMS DIVISION CAC-77-81 GENERAL ELECTRIC COMPANY.175 CUPTNER AVE., SAN JOSE, CALIFORNIA 9512s MC 682, (408) 925-5040 MFN-154-81 I August 19, 1981 U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Washington, DC 20555 Attention: Victor Stello, Jr. , Director Gentlemen:
SUBJECT:
REPORTABLE CONDITION - TRANSMITTER AND TRIP UNITS FOR REACTOR VESSEL WATER LEVEL SCRAMS This is to advise the NRC of a reportable defect per 10CFR Part 21 as reported to your office by C. A. Cameron, Manager, Safety Evaluation Programs on August 19, 1981. This defect is in the Reactor Vessel Water Level Transmitters and Trip units. Attached is the report of the defect as it applies to the affected plants. The condition was determined to be reportable on August 18, 1981.
General Electric will inform the utilities that are affected by the defect and will advise them of the corrective action to be taken. The scheduled corrective action completion dates have not yet been established.
Once the corrective actions have been scheduled, the schedules will be reported to the NRC.
Very truly yours, c
Glenn G. Sherwood, Manager Nuclear Safety & Licensing Operation GGS:csc: rf/148-F A'ttachment cc: Mr. R. T. Carlson, NRC ilegion I Mr. J. P. O'Reilly, NRC Region II Mr. U. Potapovs, NRC Region IV Mr. J. G. Keppler, NRC Region III Mr. J. F. McAllister, General Electric Mr. L. S. Gifford, General Electric Mr. V. Stello, NRC (2 extra copies) g-t$9i$57an
i ~
j,
/:
TRANStilTTERS AND TRIP UNITS FOR REACTOR VESSEL WATER LEVEL SCRAM I. DESCRIPTION OF THE CONDITION It has been determined that incorrect reactor vessel water level transmitters and trip units have been provided to
- several BWR/6 projects. Wide range transmitters have been installed instead of narrow range transmitters, as are required for the design. Several master trip units are also the wrong instruments. The plants affected by these deviations are:
Clinton Perry TVA(Hartsville)
River Bend Grand Gulf II. SAFETY If1PLICATIONS Wide range transmitters cannot be adjusted to the required range and thus cannot provide the intended and required safety function. This defect is reportable per 10CFR21 because safety related components had been shipped to the sites prior to the discovery of the defect. No operating domestic plants are affected by this defect.
III. CORRECTIVE ACTIONS Narrow range transmitters are required with compatible trip units. All incorrect transmitters and trip units will be replaced.
.. - . _-