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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20207M9231999-03-12012 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 ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc 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 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 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 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 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 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 ML20057G1511993-10-0707 October 1993 Part 21 Rept Re Westronics Model 2100C Series Recorders. Informs That Over Several Tests,Observed That Recorder Would Reset During Peak Acceleration & Door Being Forced Off Recorder.Small Retaining Clips Added to Bottom of Door ML20035G8191993-03-31031 March 1993 Potential Part 21 Rept Re Possible Defect in Stainless Steel Cajon Pipe Fitting Supplied by Crucible Specialty Metals. Establishment of Cause & Corrective Has Been Initiated by Supplier 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 ML13316A0821991-11-15015 November 1991 Part 21 Rept Re Incorrect transmitter-to-bracket Mounting Socket Cap Screws.Cap Screws May Fail Under Seismic Dynamic Tensile & Shear Loads.Ltr Sent to Customers Encl. Weed Instrument Co Notified on 911108 ML20043A6091990-04-27027 April 1990 Part 21 Rept Re Defective Axial Cracks in Pump Shaft in Region Immediately Above Impeller & in Reactor Recirculation Pumps.Probably Caused by Crack Growth as Thermal Fatigue. Technical Advisory Bulletin Will Be Sent to Each Util 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 ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves ML20206H7211988-11-21021 November 1988 Part 21 Rept Re Defect in Design of Component Mfg by Cooper Energy Svcs.Initially Reported on 881115.Util Became Aware of Problem on 881103.Div I Emergency Diesel Generator Declared Inoperable & Valve Reclassified ML20207N4641988-10-12012 October 1988 Part 21 Rept Re Potential Problem W/Emd 20-645E4,Type 999 Excitation Sys Circuit Breaker & Wiring.Potential for Field Circuit Breaker to Trip Due to Combined Air Temps & Field Current Exists at All Plants W/Model 999 Sys ML20153B2811988-02-22022 February 1988 Part 21 Rept Re Defect in Operation of Gas Monitors Using Fixed Filters.Initially Reported on 880212.Caused by Error in Software for Monitors.Vendor Testing Mod to Software & in Interim Recommends Changing Filters Every 48 H ML20211P7211987-02-23023 February 1987 Part 21 Rept Re Rockbestos Coaxial Cable Used in Sorrento Electronics Digital & Analog high-range Radiation Monitor. Insulation Resistance at High Temp Not High Enough for Ion Chamber & Associated Electronics to Operate Properly ML20210F8671987-02-0202 February 1987 Part 21 Rept Re Use of Improperly Designed S&W Electrical Manhole Duct Seals.Initially Reported on 870123.Manhole Covers Redesigned by S&W to Prevent Flooding of Manhole. Covers Installed Prior to Initial Criticality ML20209H1981987-01-31031 January 1987 Amended Final Deficiency Rept Re Inadequate Flow Rate for Hydrogen Recombiners Supplied by Rockwell.Blower Impeller Orientation for Both Trains Corrected & Tested. Cause of Improper Installation Will Be Submitted by 870213 ML20212Q8861987-01-26026 January 1987 Part 21 Rept Re Improper Seating of GE-supplied Agastat GP Series Relays.Defect Attributed to Inadequate Original Installation,Workers Coming in Contact W/Installed Relays or Both.Corrective Actions Listed ML20207J2641986-11-21021 November 1986 Interim Deficiency Rept (55(e)-86-22) Re Insufficient Flow Rate for Hydrogen Recombiners.Initially Reported on 861015. Extensive Trouble Shooting During Preoperational Testing Program Underway.Final Rept Will Be Submitted by 861205 ML20215M7371986-10-23023 October 1986 Final Deficiency Rept (55(e)-86-21) Re Inadvertent Closure of Automatic Fire Suppression Control Valve.Initially Reported on 860918.Drawing Fsk 23-6c Revised to Change Isolation Valve 2DFR-V128 to Open Position ML20197B3611986-10-21021 October 1986 Final Deficiency Rept (55(e)-86-18) Re Cracked Latching Roller Found on One MSIV & Problems W/Closure Time of Msivs. Initially Reported on 860806 & 15,respectively.MSIVs Capable of Performing Required Design Functions ML20197B0361986-10-20020 October 1986 Final Deficiency Rept (55(e)-86-20) Re MSIV Leakage Rates. Initially Reported on 860909.Actions Being Taken to Restore Valves to Acceptable Condition & Reduce Wearing Stress to Acceptable Level NMP2L0896, Interim Deficiency Rept 50.55(e)-86-20 Re Excessive Leakage of Msiv.Initially Reported on 860909.Meeting Scheduled for 861015 in Bethesda,Md to Discuss Rept1986-10-0808 October 1986 Interim Deficiency Rept 50.55(e)-86-20 Re Excessive Leakage of Msiv.Initially Reported on 860909.Meeting Scheduled for 861015 in Bethesda,Md to Discuss Rept ML20214T3921986-09-12012 September 1986 Interim Deficiency Rept (55(e)86-00-19) Re Failure of MSIV 2MSS*HYV7B to Unlatch & Close within 3-5 as Required by Design.Initially Reported on 860815.Matter Under Investigation.Final Rept Will Be Submitted by 861020 ML20214T3171986-09-11011 September 1986 Interim Deficiency Rept 86-00-18 Re Cracked Latch Roller Bearing on MSIV 2MSS*HYV7A.Initially Reported on 860808. Problem Under Investigation.Final Rept Will Be Submitted by 861020 ML20214M3181986-09-0404 September 1986 Potential Part 21 Rept Re Contromatics Actuator W/Jackscrew/ Handwheel Emergency Override Operator.Jackscrew/Handwheel Should Be Used for Emergency Manual Operation Only.Encl Ltr Also Sent to Listed Utils/Ae Firms ML20203M0311986-08-20020 August 1986 Final Deficiency Rept (55(e)86-17) Re Cracks in Contact Levers for MSIV Limit Switches (Namco EA180).Initially Reported on 860717.Visual Insp of Contact Levers Performed & Cracked Parts Replaced ML20215M5271986-08-0808 August 1986 Final Deficiency Rept Re Problem W/Response Time of Moderate Energy Line Cracking Temp Sensing Devices.Initially Reported on 860708.W/o Encl ML20211F7071986-08-0303 August 1986 Final Deficiency Rept (55(e)-86-14) Re Control Cable Length Verification.Initially Reported on 860703.Design Changes Issued to Correct Circuits Where Unacceptable Conditions Occurred to Reduce Circuit Resistance of Cables ML20207G9531986-07-14014 July 1986 Corrected Part 21 Rept Re Cracks in Plastic Contact Lever Assembly EA188-30007 in Series EA180 Limit Switches. Replacement of Contact Lever Arms in All Category I safety-related Limit Switches Proposed.Tests Initiated ML20203D2131986-07-14014 July 1986 Part 21 Rept Re Cracks in Plastic Contact Lever Assembly EA188-30007 Found in 14 EA180 Limit Switches During S&W Insp.Replacement of Contact Lever Arms in All Category I safety-related Limit Switches Proposed.Tests Initiated ML20209G0781986-07-14014 July 1986 Part 21 Rept Re Possible Defect in Namco Contact Lever Assembly Part EA188-30007 for Series EA180 Limit Switches. Program Will Be Initiated to Determine If Cracks Caused Switch Failure ML20215M5391986-07-10010 July 1986 Final Deficiency Rept (55(e)-86-11) Re Category I Components in non-Category I Stair Tower.Initially Reported on 860610. Stair Tower Will Be Braced to Resist Seismic Forces Prior to Fuel Load ML20215M7321986-07-0303 July 1986 Final Deficiency Rept (55(e)-86-12) Re Problem W/Air Start Valve Seat Inserts for Div I & II Emergency Diesel Generators.Initially Reported on 860619.Inserts Replaced.Air Start Distributors for Diesels Readjusted ML20204J0581986-07-0101 July 1986 Final Deficiency Rept (55(e)-86-07) Re Excessive Vibrations in Low Pressure Fuel Oil Supply Lines of Div I & II Standby Diesel Generators.Initially Reported on 860508.Damaged Fuel Lines Replaced ML20206S0841986-06-30030 June 1986 Part 21 Rept Re Possible Cut Wires in Wire Harness of Bbc Brown Boveri K600/K800 Circuit Breakers.Initially Reported on 860509.Safety Implications Listed.Gear Guard Designed to Prevent Cut Wires ML20212D2651986-06-27027 June 1986 Forwards Final Deficiency Rept Re Cracks in Delivery Valve Holders for Div I & II Emergency Diesel Generators.Initially Reported on 860528.W/o Encl ML20211K5571986-06-20020 June 1986 Part 21 Rept Re Inadequate Thread Engagement on Motor Hold Down Bolts for Plant Svc Water Sys Pump/Motor,Per NRC .No Further Action Necessary.Customer Initiated Change in Bolt Length ML20215M5421986-06-16016 June 1986 Final Deficiency Rept (55(e)-86-09) Re Borg Warner electro- Hydraulic Actuator Oil Leak on Dc Motor.Initially Reported on 860516.Valves Returned to Mfg & Rebuilt to Include New Seals & Qualified Pao Hydraulic Fluid ML20215M5351986-06-10010 June 1986 Final Deficiency Rept (55(e)-86-08) Re Failure of Elgar Class 1E Inverters Fuse Block Connection.Initially Reported on 860508.Vendor-recommended Mods Which Provide Proper Block to Bar Connection Will Be Completed by 860701 ML20215M7211986-06-0909 June 1986 Interim Deficiency Rept (55(e)-86-07) Re Damaged Fuel Lines in Divs I & II Diesel Generators.Initially Reported on 860508.Investigation Continuing.Final Rept Will Be Submitted by 860701 ML20211H3591986-06-0505 June 1986 Final Deficiency Rept (55(e)-86-06) Re Rosemount Loose Environ Seal Installations.Initially Reported on 860506. Loose Fittings & All Units w/90-degree Fittings Will Be Modified Prior to Fuel Load 1999-03-12
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G2161999-10-15015 October 1999 Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20216J9251999-09-30030 September 1999 Suppl to Special Rept:On 990621,11 Containment Hydrogen Monitoring Sys Chart Recorder Was Indicating Below Normal Operating Range.Caused by Excessive Wear on Valve Body & Discs of Bypass Pump.Sample Pump Replaced ML20217K4631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Nine Mile Point, Unit 1.With ML20212F7301999-09-21021 September 1999 Special Rept:On 990907,CR Operators Declared 12 Containment Hydrogen Monitoring Sys Inoperable for Planned Maint.Cause of Low Flow Condition Was Determined to Be Foreign Matl. Replaced Sample Pump Valve Discs ML20212D3611999-09-21021 September 1999 Safety Evaluation Supporting Amend 168 to License DPR-63 ML20212B9081999-09-14014 September 1999 Special Rept:On 990901, 12 Containment Hydrogen Monitoring Sys Was Declared Inoperable for Planned Maint.Caused by Planned Maint Being Performed as Corrective Action.Check Valves with O Rings Were Replaced ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 ML20212C4601999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Nine Mile Point Nuclear Station,Unit 1.With 05000220/LER-1999-005-01, :on 990801,RT During Plant Startup on IRM Spiking Was Noted.Caused by electro-magnetic Interference. Inspected,Cleaned,Burnished & Tested IRM 11 Range Switch. with1999-08-30030 August 1999
- on 990801,RT During Plant Startup on IRM Spiking Was Noted.Caused by electro-magnetic Interference. Inspected,Cleaned,Burnished & Tested IRM 11 Range Switch. with
05000220/LER-1999-004-01, :on 990723,reactor Scram Was Noted.Caused by Mechanical Pressure Regulator Suppressor Valve Failure. Cleaned Pressure Suppressor Valve & Provided Guidance for Valve Disassembly & Insp.With1999-08-23023 August 1999
- on 990723,reactor Scram Was Noted.Caused by Mechanical Pressure Regulator Suppressor Valve Failure. Cleaned Pressure Suppressor Valve & Provided Guidance for Valve Disassembly & Insp.With
ML20210U4591999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Nine Mile Point, Unit 1.With ML20210H7851999-07-29029 July 1999 Corrected SER Supporting Amend 167 to License DPR-63, Replacing Pages 4,5 & 11.New Pages Correct SE to Be Consistent with Application for Amend ML20209D0291999-07-0202 July 1999 Special Rept:On 990621,operator Identified That Number 11 Hydrogen Monitoring Sys (Hms) Chart Recorder Was Indicating Below Normal Operating Range.Cause Indeterminate.Licensee Will Complete Troubleshooting of Subject Hms by 990709 ML20210B9081999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Nine Mile Point Unit 1.With ML20196A3041999-06-17017 June 1999 Safety Evaluation Supporting Amend 167 to License DPR-63 ML20209F8811999-06-0808 June 1999 Rev 1 to NMP Unit 1 COLR for Cycle 14 ML20207G2261999-06-0707 June 1999 SER Accepting Proposed Mod to Each of Four Core Shroud Stabilizers for Implementation During Current 1999 Refueling Outage at Plant,Unit 1 ML20196E2111999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Nmp,Unit 1.With ML20207B0241999-05-18018 May 1999 Safety Evaluation of Topical Rept TR-107285, BWR Vessel & Intervals Project,Bwr Top Guide Insp & Flaw Evaluation Guidelines (BWRVIP-26), Dtd December 1996.Rept Acceptable ML20206U5351999-05-17017 May 1999 SER Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant, Units 1 & 2 ML17059C6601999-04-30030 April 1999 Safety Evaluation Accepting Licensee & Suppl ,re Alternative Repair Plan for Core Shroud Vertical Welds at Plant,Unit 1 ML20196L2301999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Nmp,Unit 1.With 05000220/LER-1999-003-01, :on 990320,noted That Plant Operated with Average Planear LHGR Exceeding TS Limits.Caused by Inadequate Interface Design Between Color Graphics Terminal & 3-D Monicore Sys.Lowered Reactor Power.With1999-04-22022 April 1999
- on 990320,noted That Plant Operated with Average Planear LHGR Exceeding TS Limits.Caused by Inadequate Interface Design Between Color Graphics Terminal & 3-D Monicore Sys.Lowered Reactor Power.With
ML17059C6031999-04-0202 April 1999 Safety Evaluation Supporting Alternative GVRR-6 Re IST of Safety & Relief Valves in Steam or Compressible Fluid Svc ML20205L0541999-04-0101 April 1999 Nonproprietary Replacement Pages to HI-91738,consisting of Section 5.0, Thermal-Hydraulic Analysis ML20205S5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for NMP Unit 1.With 05000220/LER-1999-002, :on 990217,noted That ASME Code Preservice Exams Had Not Been Performed on Emergency Condensers.Caused by Misinterpretation of ASME Code Requirements.Required Preservice Exams Were Completed on 990218.With1999-03-19019 March 1999
- on 990217,noted That ASME Code Preservice Exams Had Not Been Performed on Emergency Condensers.Caused by Misinterpretation of ASME Code Requirements.Required Preservice Exams Were Completed on 990218.With
ML17059C5951999-03-18018 March 1999 Safety Evaluation Supporting Amend 86 to License NPF-69 ML20204C8001999-03-16016 March 1999 Safety Evaluation Supporting Amend 165 to License DPR-63 05000410/LER-1999-001-01, :on 990212,NMP2 Was Outside Design Basis Due to Safe SD SW Pump Bay Unit Coolers Being Oos.Caused by Inadequate Managerial Methods.Interim ACs Were Set for Safe SD Equipment.With1999-03-15015 March 1999
- on 990212,NMP2 Was Outside Design Basis Due to Safe SD SW Pump Bay Unit Coolers Being Oos.Caused by Inadequate Managerial Methods.Interim ACs Were Set for Safe SD Equipment.With
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 ML20207G2671999-03-0101 March 1999 Special Rept:On 990315,Nine Mile Point,Unit 1 Declared Number 12 Containment Hydrogen Monitoring Sys Inoperable. Caused by Degraded Encapsulated Reed Switch within Flow Switch FS-201.2-1495.Technicians Replaced Flow Switch ML20204C9971999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Nine Mile Point,Unit 1.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced 05000220/LER-1999-001, :on 990125,noted That Plant Operated Outside Design Basis Due to Failure to Revise Satellite pre-fire Plans.Satellite Copies of pre-fire Plans Were Revised & Procedure Re pre-fire Plans Was Revised.With1999-02-24024 February 1999
- on 990125,noted That Plant Operated Outside Design Basis Due to Failure to Revise Satellite pre-fire Plans.Satellite Copies of pre-fire Plans Were Revised & Procedure Re pre-fire Plans Was Revised.With
ML17059C5701999-02-18018 February 1999 Safety Evaluation Supporting NMPC Responses to NRC Bulletin 95-002, Unexpected Clogging of Rhrp Strainer While Operating in Suppression Pool Cooling Mode ML17059C5611999-02-17017 February 1999 Safety Evaluation Approving Inservice Testing Program Relief Request GVRR-01 ML17059C5501999-01-31031 January 1999 Rev 0 to MPR-1966(NP), NMP Unit 1 Core Shroud Vertical Weld Repair Design Rept ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20206P2391998-12-31031 December 1998 Special Rept:On 981222,operators Removed non-TS Channel 12 Drywell Pressure Recorder & Associated TS Pressure Indicator from Svc.Caused by Intermittent Measuring Cable Connection in non-TS Recorder Circuitry.Replaced Cable ML20210R8441998-12-31031 December 1998 1998 Annual Rept for Energy East ML20199K9331998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20206P2421998-12-30030 December 1998 Special Rept:On 981219,number 12 Hydrogen Monitoring Sys (Hms) Was Declared Inoperable When Operators Closed Valve 201.2-601.Caused by Indeterminate Failure of Valve 201.2-71. Supplemental Rept Will Be Submitted After Valve Is Repaired ML20198M3571998-12-23023 December 1998 Special Rept:On 981210,operators Declared Number 11 Inoperable,Due to Failure of CR Chart Recorder.Caused by Inverter Board in Power Supply Circuitry of Recorder Due to Component Aging.Maint Personnel Replaced Failed Inverter ML17059C4331998-12-14014 December 1998 Safety Evaluation Concluding That Proposed Restructuring of Rg&E by Creation of Holding Company Will Not Adversely Affect Financial Qualifications of Rg&E Re Operation & Decommissioning of Nine Mile Point Unit 2 ML17059C4231998-12-11011 December 1998 SER Approving Restructuring of NMP Corp by Creation of Holding Company 05000220/LER-1998-019-01, :on 981110,ASME Section XI ISI Was Missed. Caused by Cognitive Error Involving Technical Inaccuracies. Util Will Revise Second 10-yr Interval ISI Program Plan to Incorporate Visual Exam Requirements.With1998-12-10010 December 1998
- on 981110,ASME Section XI ISI Was Missed. Caused by Cognitive Error Involving Technical Inaccuracies. Util Will Revise Second 10-yr Interval ISI Program Plan to Incorporate Visual Exam Requirements.With
ML17059C3941998-12-0303 December 1998 Safety Evaluation Supporting Amend 84 to License NPF-69 ML20198D9361998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Nine Mile Point,Unit 1.With ML17059C3821998-11-25025 November 1998 Safety Evaluation Supporting Amend 164 to License DPR-63 1999-09-30
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2 M V NIAGARA RUMOHAWK NIAGARA MOHAWK POWER CORPORATION /300 ERIE BOULEVARD V'EST. SYRACUSE, N Y.13202/ TELEPHONE (315) 474-1511 o-December 19, 1983 (7821)
Mr. R. W. Starostecki, Director U.S. Nuclear Regulatory Commission Region I Division of Project and Resident Programs 631 Park Avenue King of Prussia, PA 19406 Re: Nine Mile Point Unit 2 Docket No. 50-410-
Dear Mr. Starostecki:
Enclosed is a final report in accordance with 10CFR50.55(e) for the problem concerning ITT Grinnell radiographs for welds of T-quenchers and pipes with wall thickness equal to or greater than 1/2 in. Mr. H. Kister of your staff was informed, via telecon, of the condition concerning T-quencher walds on January 19, 1983, and the condition concerning other pipe welds on May 23, 1983.
Very truly yours, MW C.V.ManNn Vice President Nuclear Engineering & Licensing CVM/TL:ja Enclosure xc: Director of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555 Mr. R. Gramm, Resident Inspector 1
B401130342 831219 gonApocKoscoog
f t
NIAGARA M0 HAWK POWER CORPORATION NINE MILE POINT UNIT 2 DOCKET N0. 50-410 of Final Report for a Problem Concerning the ITT Grinnell Weld Radiographs of T-Quenchers and Piping
.. 1 Equal to or Greater than 1/2 Inch Description-of the Problem A review of ITT Grinnell Corporation shop weld radiographs of T-quencher, Mark No. 2SVV*DIFF127, indicated that there was an attempt to artificially enhance a radiograph for weld F.
This weld is ASME Code Class 3.
This item has been identified in Stone & Webster Engineering Corporation Nonconformance and Disposition Report No. 4262.
As a result of this finding, additional weld radiographs of other T-quenchers and piping with wall thickness equal to or greater than 1/2 inch were reviewed both at the jobsite and at ITT Grinnell's shop at Kernersville, North
~~-
Carolina. As a result, a total of 53 weld radiographs (including radiographs for weld F identified above) w re found to have enhancements.
Analysis of Safety Implications Out of the 53 welds found to have enhancements, 37 were reradiographed and found to be acceptable. Ten welds were not reradiographed because they had been eliminated (i.e., no longer exist) due to other reasons (e.g., spool cancellation due to design change, etc.). The remaining six enhanced weld radiographs were for the weld material buildup at the service water system
~'
pipe end preparations prior to the welds being completed in the field.
It was not possible to reradiograph the weld material buildup only, due to the subsequently mace field weld. Additionally, the ASME Code requires, as a minimum, only magnetic particle testing for these weids. Magnetic particle e
testing for the weld material buildup was also initially performed at ITT Grinnell's shop at Kernersville, and it provided satisfactory results.
However, the e welds were identified on ITT Grinnell Nonconformance and Disposition Report Nos. IG529 through IG533 and IG536.
The field welds were cut out and the remaining shop weld material buildups were found to be acceptable after radiographic testing.
We therefore believe that if this problem were to have remained uncorrected, it would not have adversely affected plant safety.
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