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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML20236N6751998-07-0909 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 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 ML18017A0421992-12-14014 December 1992 Suppl to 921127 Part 21 Rept Re High Air Concentration in Reactor Bldg Making Area Uninhabitable for Retrieving Air Filters,Per NUREG-0737,Item II.F.1.Util Current Position Re Fuel Pool Cooling Issues Contrary to Reg Guide 1.3 ML18026A2481992-11-27027 November 1992 Part 21 Rept Re Substantial Safety Hazard in Design of Facility for Loss of Normal Spent Fuel Pool Cooling ML19325C9521989-09-29029 September 1989 Part 21 Rept Re Potential Common Failure of SMB-000 & SMB-00 Cam Type Torque Switches Supplied Prior to 1981 & 1976. Vendor Recommends That Switch W/Fiber Spacer Be Replaced 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 ML20212E5631986-12-19019 December 1986 Part 21 Rept Re Valve Problem.Houghto 620 Lubricant Attacks & Degrades Aluminum in Valves.Valves Have Been or Being Rebuilt ML20215G5351986-10-10010 October 1986 Part 21 Rept Re Vendor Tests of air-operated Diaphragm Valves Revealing Natural Frequencies Less than Required Values of 33 Hz.Initially Reported on 841227.No Adverse Effects Noted During Testing ML20203F6471986-07-23023 July 1986 Part 21 Rept Re Morrison-Knudsen Undersized Welds at Plant. Initially Reported on 860630.Study Concluded That Welds Not Cause for Failure of Plant.Welds Will Be Repaired by Vendor 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 ML20197H1991986-05-0909 May 1986 Part 21 Rept Re Hilti Fastening Sys Anchor Bolts Failing to Meet Average Ultimate Tensile Loads.Initially Reported on 860509.Design Review & Resolutions of Installed Items Underway ML20154K3611986-03-0505 March 1986 Part 21 Rept Re Possible Wiring Defect in Fabricated Primer Chamber Assemblies for Standby Liquid Control Valves. Initially Reported on 860214.Listed Corrective Actions Will Be Completed by 860328 ML20140A5281985-12-19019 December 1985 Part 21 Rept Forwarding Ltr Sent to Customers Re Check Valves Missing Lock Welds on Hinge Supports or Hinge Support Capscrews,Per 851121 Request.List of Customers Receiving Ltr Also Encl ML20138F5631985-12-0505 December 1985 Part 21 Rept Re Failure to Perform Calculations for Two 6-inch Insp Nozzles.Purchaser Notified Not to Place Vessels Into Svc.Design Spec & Rept Will Be Revised to Include Insp Openings ML20134A9511985-10-0808 October 1985 Part 21 Rept Re Defect in Valve Stems Bearing Heat Number 3876.Entire Stem/Disc Assembly Will Be Replaced Upon Request.Replacement Stem Assembly Will Be Supplied Under Unique Part Number 106626-10 ML20134B0031985-09-26026 September 1985 Part 21 Rept Re Cracked Stem Assembly Detected in 3/4-inch Yarway Welbond Valve at non-nuclear Facility.Investigation Revealed Leakage Caused by Void in Bar Stock.Valves Sold to Nuclear Facilities Contained Stems.Review Continuing ML20137G1121985-08-22022 August 1985 Part 21 Rept Re Separation of Piston from Connecting Rod on Cooper-Bessemer Reciprocating Div Ksv Engine.Initially Reported on 850304.Engine Returned,Rebuilt & Inspected.No Future Problems Foreseen ML20108B5611985-03-0404 March 1985 Part 21 Rept Re Defective Engine Used for Driving Standby Power Generator at Facility.Caused by Loosened Attachments Separating Piston from Rod.Engine Will Be Repaired Prior to Installation PLA-2355, Revised Final Deficiency Rept Re RHR Throttling Valves. Initially Reported on 820316.Reversal of Valve Disks & Valves No Longer Considered Necessary1984-12-10010 December 1984 Revised Final Deficiency Rept Re RHR Throttling Valves. Initially Reported on 820316.Reversal of Valve Disks & Valves No Longer Considered Necessary PLA-2230, Final Deficiency Rept Re Electrical Separation Inside Multiple Div Junction & Pull Boxes.Initially Reported on 830721.Drawings Revised to Clarify &/Or Define Sparation Requirements for Use W/Junction & Pull Boxes1984-06-28028 June 1984 Final Deficiency Rept Re Electrical Separation Inside Multiple Div Junction & Pull Boxes.Initially Reported on 830721.Drawings Revised to Clarify &/Or Define Sparation Requirements for Use W/Junction & Pull Boxes PLA-2118, Final Part 21/deficiency Rept Re Clamps on CRD Insert/ Withdrawal Lines.Initially Reported on 831209.Outer Pedestal Modified Due to Lack of Sufficient Axial Restraint Capacity of Inner Pedestal Support1984-06-18018 June 1984 Final Part 21/deficiency Rept Re Clamps on CRD Insert/ Withdrawal Lines.Initially Reported on 831209.Outer Pedestal Modified Due to Lack of Sufficient Axial Restraint Capacity of Inner Pedestal Support PLA-2215, Final Deficiency Rept Re Base Metal Cracking & Bending of Angle Fittings Mfg by Unistrut,Powerstrut & B-Line Used on Class IE Electrical Raceways & Category 1 HVAC Supports. Initially Reported on 840206.Spec Revised1984-06-0101 June 1984 Final Deficiency Rept Re Base Metal Cracking & Bending of Angle Fittings Mfg by Unistrut,Powerstrut & B-Line Used on Class IE Electrical Raceways & Category 1 HVAC Supports. Initially Reported on 840206.Spec Revised PLA-2189, Final Part 21 Rept Re GE Reactor Mode Switch.Initially Reported on 830407.Mode Switch Design Modified,Per Franklin Inst Research Lab Recommendations1984-05-21021 May 1984 Final Part 21 Rept Re GE Reactor Mode Switch.Initially Reported on 830407.Mode Switch Design Modified,Per Franklin Inst Research Lab Recommendations ML20084C2851984-04-19019 April 1984 Final Deficiency Rept Re Waterhammer Loading of Scram Discharge Vol (SDV) Vent & Drain Lines After Opening SDV Vent & Drain Valves on Scram Reset.Initially Reported on 830628.Vent Line Supports Will Be Modified Prior to 841231 PLA-2180, Final Part 21/deficiency Rept Re Improper Relief Valve Settings,Design Pressures & Temps.Initially Reported on 831118.Calculations Performed Assure Lines Adequate for Intended Svc1984-04-19019 April 1984 Final Part 21/deficiency Rept Re Improper Relief Valve Settings,Design Pressures & Temps.Initially Reported on 831118.Calculations Performed Assure Lines Adequate for Intended Svc PLA-2166, Part 21 Rept Re Failure of Crosby IMF-2 Solenoids Supplied by Ge.Initially Reported on 840403.Licensee & GE Jointly Developed Test Procedures to Bench Test Spares & Solenoids on Both Units.Testing Complete on Unit 11984-04-0909 April 1984 Part 21 Rept Re Failure of Crosby IMF-2 Solenoids Supplied by Ge.Initially Reported on 840403.Licensee & GE Jointly Developed Test Procedures to Bench Test Spares & Solenoids on Both Units.Testing Complete on Unit 1 PLA-2137, Revised Final Deficiency Rept Re Fraying of Hydrogen Recombiner Cables.Initially Reported on 830728.Fraying Caused by Handling Process for Shipment,Installation & Testing.Cables Repaired1984-03-23023 March 1984 Revised Final Deficiency Rept Re Fraying of Hydrogen Recombiner Cables.Initially Reported on 830728.Fraying Caused by Handling Process for Shipment,Installation & Testing.Cables Repaired PLA-2140, Second Interim Deficiency Rept Re Base Metal Cracking in Angle Fittings.Initially Reported on 840206.Angle Fittings Added to Defective Device List & Conduit Installation Spec Revised.Also Reportable Per 10CFR211984-03-22022 March 1984 Second Interim Deficiency Rept Re Base Metal Cracking in Angle Fittings.Initially Reported on 840206.Angle Fittings Added to Defective Device List & Conduit Installation Spec Revised.Also Reportable Per 10CFR21 PLA-2074, Third Interim Deficiency Rept Re Electrical Separation Inside Multiple Division Junction & Pull Box.Initially Reported on 830721.Design Basis Criteria & Barrier Configuration Established.Also Reported Per Part 211984-03-20020 March 1984 Third Interim Deficiency Rept Re Electrical Separation Inside Multiple Division Junction & Pull Box.Initially Reported on 830721.Design Basis Criteria & Barrier Configuration Established.Also Reported Per Part 21 PLA-2120, Interim Part 21/deficiency Rept Re Base Metal Cracking in Fittings Used on Class IE Electrical Raceways & HVAC Supports.Initially Reported on 840206.Final Rept Expected Prior to Initial Criticality1984-03-0707 March 1984 Interim Part 21/deficiency Rept Re Base Metal Cracking in Fittings Used on Class IE Electrical Raceways & HVAC Supports.Initially Reported on 840206.Final Rept Expected Prior to Initial Criticality PLA-2103, Final Deficiency Rept Re Cavitation of Jet Pumps Due to Induction Heating Stress Improvement Cooling.Initially Reported on 831206.No Erosion Found.Also Reportable Per Part 21.Item Not Reportable Per 10CFR50.55(e)1984-03-0606 March 1984 Final Deficiency Rept Re Cavitation of Jet Pumps Due to Induction Heating Stress Improvement Cooling.Initially Reported on 831206.No Erosion Found.Also Reportable Per Part 21.Item Not Reportable Per 10CFR50.55(e) PLA-2075, Second Interim Deficiency Rept Re Improper Relief Valve Setting,Design Pressures & Design Temp within Several Sys. Initially Reported on 831118.Spec M-199 Revised & Code Data Repts Amended.Also Reported Per Part 211984-03-0202 March 1984 Second Interim Deficiency Rept Re Improper Relief Valve Setting,Design Pressures & Design Temp within Several Sys. Initially Reported on 831118.Spec M-199 Revised & Code Data Repts Amended.Also Reported Per Part 21 PLA-2089, Final Deficiency & Part 21 Repts Re Safety Parameter Display Sys Technology Energy Corp Model 156 Isolators.Initially Reported on 840106.Non-IE Power Supply Will Be Provided for Isolator Prior to End of First Refueling1984-02-27027 February 1984 Final Deficiency & Part 21 Repts Re Safety Parameter Display Sys Technology Energy Corp Model 156 Isolators.Initially Reported on 840106.Non-IE Power Supply Will Be Provided for Isolator Prior to End of First Refueling PLA-2062, Final Deficiency Rept Re Bechtel Failure to Accomplish Design Verification of safety-related Power & Control Cables.Caused by Failure to Complete Required Cable Length Verification.Deficiency Not Reportable Per 10CFR50.55(e)1984-02-13013 February 1984 Final Deficiency Rept Re Bechtel Failure to Accomplish Design Verification of safety-related Power & Control Cables.Caused by Failure to Complete Required Cable Length Verification.Deficiency Not Reportable Per 10CFR50.55(e) PLA-2073, Final Part 21 Rept Re Hydrogen Catalyst Used in Comsip Custom Line Model K-IV Containment Gas Monitoring Panels. Initially Reported on 840113.Comsip Redesigned Catalyst Will Be Installed1984-02-13013 February 1984 Final Part 21 Rept Re Hydrogen Catalyst Used in Comsip Custom Line Model K-IV Containment Gas Monitoring Panels. Initially Reported on 840113.Comsip Redesigned Catalyst Will Be Installed PLA-2063, Interim Part 21 Rept Re Safety Parameter Display Sys Model 156 Isolators Mfg by Technology for Energy Corp (Tec). Initially Reported on 840106.All Tec Isolators Reviewed for Corrective Actions1984-02-0606 February 1984 Interim Part 21 Rept Re Safety Parameter Display Sys Model 156 Isolators Mfg by Technology for Energy Corp (Tec). Initially Reported on 840106.All Tec Isolators Reviewed for Corrective Actions PLA-2045, Followup Deficiency Rept Re Mod of RHR Globe Valves F017A & FO17B to Enable Valves in Shutdown Cooling Mode to Perform W/O Adverse Cavitation & Vibration at Low Flow Rates.Initially Reported on 811112.Valves Replaced1984-01-25025 January 1984 Followup Deficiency Rept Re Mod of RHR Globe Valves F017A & FO17B to Enable Valves in Shutdown Cooling Mode to Perform W/O Adverse Cavitation & Vibration at Low Flow Rates.Initially Reported on 811112.Valves Replaced PLA-2033, Interim Deficiency Rept Re Clamps on Control Rod Drive Insert/Withdraw Lines Not Providing Axial Restraint. Initially Reported on 831209.Design Mod to Pedestal Support Initiated.Also Reportable Per Part 211984-01-12012 January 1984 Interim Deficiency Rept Re Clamps on Control Rod Drive Insert/Withdraw Lines Not Providing Axial Restraint. Initially Reported on 831209.Design Mod to Pedestal Support Initiated.Also Reportable Per Part 21 PLA-2026, Interim Deficiency Rept Re GE Reactor Mode Switch.Proposed Redesign of Mode Switch by GE Rejected,Based on Results of Testing Conducted at Franklin Inst Research Lab.Alternate Switch Ordered Through Electroswitch.Final Rept by Apr 19841984-01-12012 January 1984 Interim Deficiency Rept Re GE Reactor Mode Switch.Proposed Redesign of Mode Switch by GE Rejected,Based on Results of Testing Conducted at Franklin Inst Research Lab.Alternate Switch Ordered Through Electroswitch.Final Rept by Apr 1984 PLA-2009, Final Deficiency Rept Re Standby Gas Treatment Sys (SGTS) Performance Not as Described in Fsar.Fsar Change Prepared to Indicate SGTS May Be Required to Maintain Secondary Containment Integrity1984-01-0909 January 1984 Final Deficiency Rept Re Standby Gas Treatment Sys (SGTS) Performance Not as Described in Fsar.Fsar Change Prepared to Indicate SGTS May Be Required to Maintain Secondary Containment Integrity PLA-1990, Final Deficiency Rept Re Isolation of Nitrogen Makeup Sys. Permanent Mod Consists of Rerouting Drywell & Wetwell Nitrogen Makeup Lines to Spare Penetrations.Divisionalized Isolation Valves Will Be Installed1983-12-30030 December 1983 Final Deficiency Rept Re Isolation of Nitrogen Makeup Sys. Permanent Mod Consists of Rerouting Drywell & Wetwell Nitrogen Makeup Lines to Spare Penetrations.Divisionalized Isolation Valves Will Be Installed PLA-1946, Interim Deficiency Rept Re Bechtel Failure to Accomplish Design Verification of safety-related Power & Control Cables.Bechtel Completed & Documented Required Cable Length Verification & Calculations1983-12-30030 December 1983 Interim Deficiency Rept Re Bechtel Failure to Accomplish Design Verification of safety-related Power & Control Cables.Bechtel Completed & Documented Required Cable Length Verification & Calculations PLA-1991, Final Deficiency Rept Re Cracks in Pacific Scientific PSA-1 & PSA-3 Snubber Capstan Springs.Caused by Improper Spring Forming.Snubbers Will Be Corrected Prior to Completion of First Refueling Outage.Also Reported Per Part 211983-12-27027 December 1983 Final Deficiency Rept Re Cracks in Pacific Scientific PSA-1 & PSA-3 Snubber Capstan Springs.Caused by Improper Spring Forming.Snubbers Will Be Corrected Prior to Completion of First Refueling Outage.Also Reported Per Part 21 PLA-2000, Interim Deficiency Rept Re Electrical Sys Separation in Multiple Div Pull & Junction Boxes.One Box Identified Containing Redundant Channel C & D Circuits Insufficiently Separated by Approved Barrier1983-12-27027 December 1983 Interim Deficiency Rept Re Electrical Sys Separation in Multiple Div Pull & Junction Boxes.One Box Identified Containing Redundant Channel C & D Circuits Insufficiently Separated by Approved Barrier PLA-2006, Interim Part 21 Rept Re Improper Relief Valve Settings & Design Pressures & Temps Found in Hpci,Rcic,Rhr,Core Spray & Essential Svc Water Sys.Initially Reported on 831118. Hydrotests Performed1983-12-20020 December 1983 Interim Part 21 Rept Re Improper Relief Valve Settings & Design Pressures & Temps Found in Hpci,Rcic,Rhr,Core Spray & Essential Svc Water Sys.Initially Reported on 831118. Hydrotests Performed PLA-1987, Updated Interim Deficiency Rept Re Scram Discharge Vol Vent & Drain Valve Waterhammer.Testing & Subsequent Analysis Will Be Completed in Mar 1984.Util Will Submit Final Rept by Apr 19841983-12-14014 December 1983 Updated Interim Deficiency Rept Re Scram Discharge Vol Vent & Drain Valve Waterhammer.Testing & Subsequent Analysis Will Be Completed in Mar 1984.Util Will Submit Final Rept by Apr 1984 PLA-1967, Final Deficiency Rept Re Suppression Pool Temp Monitoring Sys (Spotmos).Initially Reported on 821015.Modified Installation Configuration Tested.Review of Test Results Will Be Completed by End of Mar 19841983-12-13013 December 1983 Final Deficiency Rept Re Suppression Pool Temp Monitoring Sys (Spotmos).Initially Reported on 821015.Modified Installation Configuration Tested.Review of Test Results Will Be Completed by End of Mar 1984 PLA-1968, Final Deficiency & Part 21 Repts Re Final Design of GE 7700 Series 250-volt Dc Control Ctrs.Plant Operating Procedures Revised to Include Methods of Clearing Obstructions as Provided by GE & Exam & Reforming of Draw Out Contacts1983-12-0505 December 1983 Final Deficiency & Part 21 Repts Re Final Design of GE 7700 Series 250-volt Dc Control Ctrs.Plant Operating Procedures Revised to Include Methods of Clearing Obstructions as Provided by GE & Exam & Reforming of Draw Out Contacts 1998-07-09
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217A9931999-09-30030 September 1999 NRC Regulatory Assessment & Oversight Pilot Program, Performance Indicator Data ML17146B1741999-08-0303 August 1999 GL 96-06 Risk Assessment for Sses. ML20206D3331999-04-27027 April 1999 SER of Individual Plant Examination of External Events Submittal on Susquehanna Steam Electric Station,Units 1 & 2. Staff Notes That Licensee IPEEE Complete with Regard to Info Requested by Suppl 4 to GL 88-20 ML20195B2381999-03-31031 March 1999 Redacted Version for 10CFR2.790 Request for Decommissioning Status Rept for Sses,Units 1 & 2 ML17164A8451998-10-31031 October 1998 SSES Unit 1 Tenth Refueling & Insp Outage ISI Outage Summary Rept. 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 ML20217Q4891998-04-21021 April 1998 Rev 1 to Draft LDCN 2482, FSAR Chapter 13.4 & FSAR Chapter 17.2 Changes to Support ITS Implementation ML18026A4931998-03-30030 March 1998 LER 97-007-01:on 971017,entry Into TS 3.0.3 Occurred to Allow Completion of Surveillance Testing of One Channel of Rbm.Caused by Failure of Components in LPRM Output to Rbm. Submitted TS Change Request to Extend LCO Action Statement ML18026A5401998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Susquehanna Steam Electric Station.W/980313 Ltr ML18026A4891997-11-17017 November 1997 LER 97-007-00:on 971017,TS 3.0.3 Entry Voluntarily Made. Caused by Inadequate Post Maint Testing Following Earlier Work Associated W/Components.Failed Components Repaired, Replaced & Testing Completed ML18017A2921997-10-28028 October 1997 1997 Nrc/Fema Observed Exercise. ML17158C1861997-06-0505 June 1997 Proceedings of Intl Topical Meeting on Advanced Reactors Safety Vol II, on 970601-05 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 ML18026A4781997-03-28028 March 1997 Rev 1 to Application of Anfb to ATRIUM-10 for Susquehanna Reloads. 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 ML20155F7661996-07-25025 July 1996 Partially Deleted Job Number 739619-96, Investigation of E Diesel Breaker Misalignment ML20155F7491996-07-24024 July 1996 Independent Safety Evaluation Svcs Project Rept 3-96, Investigation of E Diesel Generator In-Operability Event 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 ML18026A5961996-01-0202 January 1996 LER 95-013-00:on 951119,thermally Induced Pressure Locking of HPCI Valve Occurred Under Bonnet Pressure of 3,000-7,000 Psig.Damaged HPCI Injection Valve repaired.W/960102 Ltr ML18017A0511995-11-30030 November 1995 Monthly Operating Repts for Nov 1995 for SSES Units 1 & 2. W/951215 Ltr ML20092H7641995-08-31031 August 1995 Monthly Operating Repts for Aug 1995 for Susquehanna Ses ML17158A8771995-08-15015 August 1995 Exercise Manual. ML17158A8061995-07-14014 July 1995 Books 1 & 2 of ISI Outage Summary Rept SSES Unit 1 8th Refuel Outage. ML18017A0461995-07-0707 July 1995 LER 95-008-00:on 950609,shift Average Licensed Core Thermal Power Was Exceeded.Caused by Failed Instrumentation Drift. Repaired & Recalibrated Subject Instrumentation ML17164A6631995-04-11011 April 1995 Impact of Extending T-10 AOT from 3 to 7 Days. ML17164A5871995-01-31031 January 1995 Monthly Operating Repts for Jan 1995 for Susquehanna Ses ML18026A5351994-10-31031 October 1994 SSES Unit 1 & 2 MSIV Leakage Alternate Treatment Method Seismic Evaluation. W/One Oversize Drawing ML17158A4821994-08-23023 August 1994 ISI Outage Summary Rept Unit 2 6th Refueling Outage, Books 1 & 2 of 2 ML17158A2391994-04-0505 April 1994 Books 1 & 2 of SSES Unit 1 Seventh Refueling & Insp Outage ISI Outage Summary Rept. ML18017A2701993-12-31031 December 1993 PP&L Annual Rept 1993. ML17158A2651993-12-31031 December 1993 Allegheny Electric Cooperative,Inc Annual Rept 1993. ML17158A1631993-12-0909 December 1993 Remote Indication of Spent Fuel Pool Level & Temperature. ML18026A4281993-08-16016 August 1993 PP&L Response to NRC Concerns Re Loss of Spent Fuel Pool Cooling Following Loca,Sses,Units 1 & 2. ML18026A4261993-06-0909 June 1993 LER 90-007-01:on 900705,primary Power Supply to RPS a Power Distribution Panel Lost When One Electrical Protection Assembly (EPA) Breaker Tripped.Epa Logic Cards Reviewed & RPS Power Supply Will Be redesigned.W/930609 Ltr ML17157C2441993-02-28028 February 1993 Monthly Operating Rept for Feb 1993 for Susquehanna Steam Electric Station,Units 1 & 2 ML18017A2031993-02-0101 February 1993 Books 1 & 2 of Unit 2 Fifth Refueling & Insp Outage,Isi Outage Summary Rept. ML20044C2741993-01-31031 January 1993 Corrected Monthly Operating Rept for Jan 1993 for Susquehanna Steam Electric Station,Unit 2,consisting of Info on Unit Shutdowns & Power Reductions ML17157C3691992-12-31031 December 1992 PP&L Annual Rept 1992. ML20056C3941992-12-31031 December 1992 Allegheny Electric Cooperative,Inc Annual Rept 1992 ML18017A0421992-12-14014 December 1992 Suppl to 921127 Part 21 Rept Re High Air Concentration in Reactor Bldg Making Area Uninhabitable for Retrieving Air Filters,Per NUREG-0737,Item II.F.1.Util Current Position Re Fuel Pool Cooling Issues Contrary to Reg Guide 1.3 ML18026A2481992-11-27027 November 1992 Part 21 Rept Re Substantial Safety Hazard in Design of Facility for Loss of Normal Spent Fuel Pool Cooling ML18026A4231992-11-17017 November 1992 LER 92-016-00:on 920416,discovered That Existing Analysis for Two Spent Fuel Storage Pools Did Not Reflect Current Fuel Design & Plant Operation.Caused by Failure to Modify FSAR Analysis.Fsar Will Be revised.W/921117 Ltr ML17157C1421992-10-21021 October 1992 Engineering Assessment of Fuel Pool Cooling Piping EDR-G20020. ML17157C1411992-08-31031 August 1992 Loss of Fuel Pool Cooling Event Evaluation. ML17157C1401992-08-31031 August 1992 Review of Fuel Pool Cooling During Postulated Off-Normal & Accident Events SSES Units 1 & 2. ML20082C4941992-08-14014 August 1992 Evaluation of Unit 1 & Unit 2 Derating of Power Cables in Raceways Wrapped W/Thermo-Lag Matl ML17157C1381992-07-27027 July 1992 Safety Consequences of Boiling Spent Fuel Pool at Susquehanna Steam Electric Station. ML17157B9331992-07-24024 July 1992 Sixth Refueling & Insp Outage Inservice Insp Outage Summary Rept, Books 1 & 2 ML20097D4681991-12-31031 December 1991 Pennsylvania Power & Light Company,1991 Annual Rept ML18017A0391991-07-26026 July 1991 LER 91-010-00:on 910628,RWCU Isolated on Two Occassions Due to Actuations of Steam Leak Detection Instrumentation. Caused by Design Deficiency & Elevated Ambient Penetration Room Temps.Temp Modules replaced.W/910726 Ltr 1999-09-30
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p,559 '
@ Pennsylvania Pow r & Light Company Two North Ninth Street
- 215 / 770L5151 Norrnan W. Curtis Vice President-Engineering & Construction-Nuclear 215 / 770-5381 August 5, 1981 p u)
A 6 /
Mr. Boyce H. Grier s t !*I b b Director, Region I g i U. S. Nuclear Regulahry Commission f~ - )
631 Park Avenue '
l pjG 1 O gg y King of Prussia, PA 19406 3 gagap
/\ '
N SUSQUEHANNA STEAM ELECTRIC STATION #p, INTERIM REPORT OF A DEFICIENCY INVOLVING INADEQUATE M THROAT THICKNESS ON SMALL PIPE SOCKET WELDS ERs 100450/100508 FILES 821-10/900-10 l PLA-894 l
Dear Mr. Grier:
This letter serves to provide the Commission with an interim report of a l deficiency involving socket welds on small pipe. The welds were discovered I to have inadequate throat thickness. The deficiency was originally reported by telephone to Mr. L. Narrow of NRC Region I by Mr. A. Sabol of -PP&L on ;
July 17, 1981. During that conversation, Mr. Narrow was advised that the condition was considered reportable under the provisions of 10 CFR 50.55(e). j l
The deficiency involves welding performed by a single welder on small pipe in safety and non safety related systems at SSES. The attachment to this letter contains a description of the deficiency, its cause, safety impact and the corrective action taken.
Since the details of this report provide information relevant to the reporting requirements of 10 CFR 21, this correspondence i* considered to also discharge any formal responsibility PP&L may have in cc s :ance thereto.
We expect to issue a final report on the deficiency in September,1981. We trust the Commission will find this information acceptable.
Very truly yours, N. W. Curtis Vice President-Engineering & Construction-Nuclear PLW:sab j Attachment 8108140423 810805 G ofb PDR ADOCK 05000307 i
PDR L _ ___ _S A
+
4L '. .
Mr. Boyce H. Grier August 5, 1981 cc Mr. Victor Stello (15)
Director-Office of Inspection & Enforcement U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. G. Mcdonald, Director (1)
Office of Management Information & Program Control U. S. Nuclear Regulatory Commission Washington, D.C. 20555 Mr. Gary Rhoads U. S. Nuclear Regulatory Commission P.O. Box 52 Shickshinny, PA 18655
.a
4 *
! Attachment to PLA-894 1
i' ' SUBJECT I Several socket welds on "Q" systems were discovered to have inadequate throat
, thickness.
i DESCRIPTION OF PROBLEM During piping system revision, three socket welds made by the Gas Tungsten Arc ;
7 Welding (GTAW) process were discovered which exhibited less than complete
- penetration to the root of the weld.
t l This condition was documented on Bechtel NCR 6963 dated 12/30/80 based on ,
the lack of complitte penetration te the root of three socket welds in the .
Instrument Gas System line SP-CC-201-1.
] I
) CAUSE OF THE DEFICIENCY l An extensive investigation designed to establish the extent of this deficiency
- revealed that these and all subsequantly identified deficient welds were made
- by a single welder. .
d 4
The welder performing these welds apparently lacked sufficient experience with the i- GTAW process to detect that penetrat; ion to the root of the weld was not being achieved. The performance qualification test (groove test qualifying for .!
1 fillets) administered to this welder did not reveal the technique deficiencies.
ANALYSIS OF SAFETY IMPLICATION i
Socket welds are used extensively throughout safety related piping systems of two inch diameter and under. Specific systemsdierein this deficiency was
,' discovered included Emergency Service Water, High Pressure Core Injection, ;
Residual Heat Removal and Core Spray. Insufficient throat thickness can be the cause of piping system failure. Failure of one or more of these welds could possibly affect the ability to safely shutdown the plant. .Therefore, this
! nonconformance is considered a significant deficiency in construction and is.
thus reportable under 10 CFR 50.55(e). ,
i CORREC'I VE ACTION g
In order to determine the extent of the deficiency, a sampling of two hundred l l
and eight additional socket welds was taken. The sampledwelds had been made' by I
' J fferent welders utilizing GTAW and Shielded Metal Arc Welding (SMAW) on both carbon steel and austenitic stainless steel materials. These welds were i examined by radiographic techniques to ascertain the degree of penetration (or.
i lack of) to the root of the weld, any material uniqueness,. welders involve 4 and' '
proc 6ss dependency. The results of this investigation' revealed that the abject l- deficiency was u.ique to one welder and one process (GTAW).
i An ultrasonic procedure for thickness measurement was developed.to verify the-existing throat thickness.
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- i All ASME Section III, Class 1, 2 and 3 socket welds made by the subject welder using the GTAW process were identified. These welds were examined to determine the actual throat thickness. In excess of six hundred welds were measured using the engineering approved ultrasonic technique and twelve were found to be below the minimum acceptance criteria (ASME Section III, NB4427-1). These welds will be either removed and replaced or, built up to the required throat thickness.
They will be examined in accordance with the original fabrication and installation code as well as subjected to throat thickness ultrasonic measurement to verify this dimension.
The welder has received additional instruction and training in the use of the GTAW process on this weld configuration. Destructive testing of sample welds made after this period of retraining have verified this welder's ability to achieve penetration to the root of the weld.
A further description of corrective action taken will be included in our final report.
FINAL REPORT The final report will be issued in September, 1981.
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