Interim Rept & Suppl on Termination Cabinet - Termination Modules Damaged Conductor Insulation. Describes Damage to Insulation on 200 Conductors in Termination Modules in Cabinet 1TC621 & 11 Cables.Correction Scheduled for 790215ML18031A074 |
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Susquehanna |
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01/04/1979 |
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PENNSYLVANIA POWER & LIGHT CO. |
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ML18031A073 |
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MCAR-1-29, NUDOCS 7901230194 |
Download: ML18031A074 (7) |
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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
[Table view] |
Text
QUALITYASSURANCE PROGRAM MAlEMENT coRREOTIUE AGTICN REPo~ti 4 '>E 09 87 8 9 MCAR-0 REPORWNO.
JOB NO. 8856 Q No. 30.0 DATE '
.DESCRIPTION (Including rejerencet):
NCR 3030 was issued 9-28-78 to identify damaged insulation an conductors installed in termination Itcdules located in texmination cabinet 1'IC621. Thirty-nine termination Itcdules were inspected for cut, stripped or damaged insulation on module conductors and thirty-three modules were found with damaged ccnductors. An average of four to five conductors were determined to be damaged in each terminal Itcdule connector The terttunation cabinets are supplied by GE under. the+-1 NSSS contract. 'nspected.
o RECOMMENDED ACTION (Optional)
- 1. Construction to perform an investigation to determine the extent of damaged conductor insulation in termination mxiules not inspected to date.
- 2. Construction to document nonconfornences identified during investigation requested in One above.
- 3. Project Engineering to advise QP regazding reportability for this deficiency under 10 CFR 50.55e by 10-6-78.
REFERRED TO X ENGINEERING Q CONSTRUCTION Q QA MANAGEMENT Q Q PROCUREMENT ISSUED B Date Zf-~Z Project QA Engineer II REPORTABLE DEF ICIENCY NOTIFIED CLIENT Date r
Q YES P snags ate III CAUSE CORRECTIVE ACTION TAKEN See attached interim report and interim report supplement.
- PP&L notified NRC per PLA-301 AUTHORIZED BY Date DISTRISVTIQN Dlv. QA Msnsger Mpr. of QA-TPQ FORMAL REPORT TO CLIENT Drv. Procursmsnt Mar, Protect Msnsgsr III section II Appiiet I Date Contructlon Msnsgcr engineering Msnsger Proiecs Engineer PEOI.Supt./PEDI. COnSt.Mgr,Or Proi.Procurement Mgr.
chl ~ I const. Qc Engineer or oc supervisor or CORRECTIVE ACTION IMPLEMENTED Procurement Suppher Qusllty Mgr. snd Div. Supplier Quslltv Mgr.
Qa Supervisor Client OPQ aA Mgr.
I.APD aa Mgr. VERIFIED BY Ptoj ~
.I QA Engineer Date trots .Ihe ln specs provided snd attach relerenre document.
SFP 21 130. Rev I 10/7tt 7BDM3 QI Vg
t
~
.OFc zl 7a 097546 MCAR 1-29 INTER3ld REPORT TERMINATION CABINET - TERMINATION MODULES DAMAGED CONDUCTOR INSULATION SUSQUEHANNA STEAM ELECTRIC STATION UNJTS 1 Ci 2 Prepared by:
Wecked by:
Approved by:
- Prospect Engineer
- Engineering Ma'nager SECHTEL POMEH COHPOHATION San I'rancisco, Uaiifor nia December 19, 1975 (P5-20/1)
s CsC 21 'P2 O.g gg4 g ATTACHMENT INTERIM REPORT MCAR 1-29 Descri tion NCR 3030 was issued 9/2'/75 to identiQ damaged insulation on conductors installed in termination moduLes located in termination cabinet 1TCb21.
Thirty nine termination modules were inspected for cut, stripped or damaged insulation on module conductors and thirty-three modules were found with damaged conductors.. Subsequently NCR 3030 was revised to identify approxi-mately 200 damaged T-MODS. An average of four to five conductors were de-termined to be damaged in each terminaL moduLe connector inspected. The termination cabinets are supplied by GE unaer the M-1 NSSS contract.
Cause The cause of the damage is attributed to the manual insertion and extrac-tion of terminated pins on connector sheLLs.
Anai sis of the Safet Im lications The system design was reviewed and the following was concluded for the worst condition. The deficiency which invoLves damaged insulation of PGCC T-MODS if'ndetected or uncorrected could permit shorting or introduction of external voltage sources into safety related circuits which couLd prevent the circuits from performing the designed safety function. Since the occurrence of da-maged insulation is a random thing and could occur in any and alL safety re-lated circuits the possibility of a coarnon mode failure exists. The simul-taneous degradation and loss of safety-related circuits couLd resuLt in a safety hazard to the operation of the plant.
Project Engineering has determined the PGCC T-MODS def'iciency to be reportable under IOCFR 50.55(e).
Corrective Action GE San Jose is preparing a repair procedure for the T-MODS. The first 32 are in the process of being totally reworked. %he remaining U5 will be shipped to GE San Jose for repair/rework per the above procedure upon com-pLetion of' report by GE on the same subject.
Conclusion Upon completion of the repair/rework and re-test of the T-MODS per GE pro-
'cedures and criteria, the aef'iciency wiLL have been corrected and the po-tential safety hazard will have been eliminated. GE forecasts completion of this effort by February 15, 1979.
(P5-20/2)
MCAR 1-29 INTERIM REPORT SUPPLANT ON TERMINATION CABINET - TERYiINATION MODULES DAMAGED CONDUCTOR INSULATION SUSQUEHANNA STEAM ELECTRIC STATION UNITS 1 h 2 Prepared by:
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Checked by:
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- Project Engineer '
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- Engineering Manager
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BECHTEL PO>lER CORPORATION San Francisco, California Decanber 29, 1978 (P5-21/1)
SUPPLEMENT TO INTERIM REPORT ON MCAR 1-29 Description of Related Cable Problems Subsequent.to the issue of MCAR 1-29 and during the investigation relative to the termination modules located in termination cabinet 1TC621, additional problems were identified.
In letter BCLPC-5105, dated October 3, 1978, SFHO Document Control No. 094517, the Field Construction Manager, Mr. S. Schoenenberger informed PP&L, that on PGCC/ACR, during implenentation of General Electric's FDDR-KR1-521, Rev. 0 (Generic Cable Retrofit) rework, it was noted that numerous insulation damages (cuts, nicks and shield solder connections, etc.) were found.
Due to the high percentage of damaged cable, the quality of all terminations is rendered indeterminate.
Below is a list of those cables which were found damaged:
- 1) 7442/C94A-408 7) 4113/C94A-744
- 2) 7442/C94A-410 8) 4113/C94A-714
- 3) 7442/C94A-412 9) 4119/C94A-736
- 4) 7442/C94A-409 10) 4128/C94A-806
- 5) 7119/C94A-715 11) 41.12/C94A-733
- 6) 4111/C94A-822 In letter BCLPC-5106, dated October 3, 1978, SFHO Document Control No. 094517, the Field Construction Manager, Mr. S. Schoenenberger, also informed PP&L, that on the PGCC/ACR, during implementation of General Electric's FDDR-KR1-521, Rev. 0, (Generic Cable Retrofit) rework, was noted that. one cable'.4108/C94A-712 was found to have four (4) con-it ductors pulled out of its pin connectors. The quality of this cable is rendered indeterminate.
The above noted letters, plus BCLPC-5104, dated October 3, 1978 - basically describing the same problem given in the MCAR description were forwarded to Project Engineering by IOM QK-4056, dated October 17, 1978, SFHO Document Control No. 094517, from the Field Construction Manager. The IOM was provided as an assist in determining possible reportability of cable deficiencies found in the Power Generation Control Complex/Advanced Control Room,(PGCC/ACR).
An updated status on T-MOD inspection was provided in TWX CME-2044, dated 10/30/78, to J. R. Schmiedel from S. Schoenenberger. A copy is attached. This 7ÃX provides additional detail on Bechtel inspection results of the T-MODs in Unit 1.
Nonconfomance Report (NCR) 3231 was generated to document the additional items/problems within the PGCC/ACR complex. General Electric (GE) is in the process of preparing an FDI which is to detail a complete inspection plan (F5-21/2)
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"7> ~097844 SUPPLEMENT TO INTERIM REPORT ON MCAR 1-29 PAGE TN'O and an approved repai'r procedure (reference IOM Document Control No. 097038 to H. Lilligh from C. Turnbow copy attached). For types of problems found see pages 3, 4, 5, and 6 of the attached NCR 3231.
The Pennsylvania Power and Light Company (PP&L) issued a letter to Project Engineering, dated November 10, 1978, SFHO Document Control No. 096038, stating their requirements for resolving the PGCC T-MOD problems. A copy is attached. Project Engineering responded to PP&L with a letter BLP-10055, dated November 21, 1978, Document Control No. 096266, providing a Bechtel inspection program as requested by PP&L. A copy is attached.
Cause The cause of problems associated with the PGCC/ACR, according to GE is established as related to inadequate fabrication technique.
Analysis of Safety Implications The system design was reviewed and the following was concluded for the worst condition. The deficiency which involves damaged PGCC/ACR cable connectors if undetected or uncorrected could permit shor ting or introduction of external voltage sour ces into safety related circuits which could prevent the circuits from performing the designed safety function. Since the occurrence of damaged cable connectors is a random thing and could occur in any and all safety-related circuits, the possibility of a common mode failure exists. The simultaneous degradation and loss of safety-related circuits could result in a safety hazard to the operation of the'lant.
Project Engineering has determined the PGCC/ACR deficiency to be reportable under 10CFR 50.',55(e).
Corrective Actions Corrective actions in the form of Inspection programs by Bechtel and GE are identified in correspondence indicated in the'above description and in PP&L letter to Project Engineering, PLB-9354, dated December 14, 1978, SFHO Document Control No. 097413. A copy is attached.
Corrective actions to-date have been basically the initiation of the in-spection program and repair-rework procedures. It is currently anticipated that repair or rework of all deficient Unit 1 PGCC/ACR cables are scheduled for completion by February 15, 1979.
(P5-21/3)
SUPPLEMB1T'TO INTERlM REPORT ON SCAR 1-29 PAGE THREE Corrective actions to prevent recurrences of like problems in the futur e including Unit 2 facilities are indicated by GE to be:
- 1) Appropriate training of personnel involved,
- 2) Revision of fabrication techniques,
- 3) Increased/revised inspection activities,
- 4) Assess all Unit 2 PGCC/ACR to assur e against similar problems.
Conclusions Upon completion of the repair /rework and re-test of the PGCC/ACR items per GE procedures and crite. ia, the deficiencies will be corrected and the potential safety hazard will be eliminated. GE forecasts completion of repair/rework effort by February 15, 1979. Additional GE fabrication personnel training, inspection and revised fabrication techniques should preclude recurrence of similar problems in the future.