|
---|
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
r
-PP&L Pennsylv:nin Pow r & Light Comp:ny Two North Ninth Street
- Allentown, PA 18101 e 215 / T105151 August 19, 1983 Dr. Thcmas Marley Regional Administrator, Region I U.S. Nuclear Regulatory Ccmmission 631 Park Avenue King of Prussia, PA 19406 SUSQUEHANNA STFAM ELETRIC STATICN REPORP OF A DEFICIENCY INVOLVING MISPFTJANEOUS DEBRIS IN CONTROL RG) DRIVE (CRD) GUIDE 'IUBES ER 100508 FILE 821-10 PIA-1803
Dear Dr. Murley:
This letter serves to provide the Ccmnission with a report on miscellaneous debris in several Unit #2 CRD guide tubes.
This deficiency was originally reported by telephone to Mr. E. C. McCabe of NBC Region I on July 22, 1983 by Mr. J. Saranga of PP&L.
The attachment to this letter contains the results of PP&L's investigation into the subject deficiency. Based upon the infonnation provided in the attachttent, PP&L considers this deficiency not to be a reportable condition under the provisions of 10CFR50.55(e) or 10CFR21.
We trust the Ccmnission will find this report satisfactory.
Very truly yours, N. W. Curtis Vice President-Engineering & Construction-Nuclear MHC:po Attachment 8309070193 830819
['o.,1 PDR ADOCK 05000388 '
S PM -
ff
August 19,'1983 2 PIA-1803 ER 100508 FILE 821-10 Copy to:
Mr. Richard C. DeYoung (15)
Director-Office of Inspection & Enforcenent '
U.S. Nuclear Regulatory Cantnission Washington, D.C. 20555-Mr. G. Mcdonald, Director Office of Managenent Information & Program Control U.S. Nuclear Regulatory Cminission Washington, D.C. 20555 Mr. Gary Rhoads U.S. Nuclear Regulatory Cminission P.O. Box 52 shickshinny, PA 18655 Records Center Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Suite 1500 Atlanta, GE 30339
n g r ,- .
3 Attachment to PIA-1803
> Page~ l of'3
, FDEL REPORP SUBJICT:
~ ~
l Miscellaneous debris in several-Unit 2 control rod ~ drive' (CRD) guideItubes. -
DESCRIPTIW:
During final installation of' reactor internals, foreign material was found to be present in a-CRD guide tube / blade assembly. As a result, an inspection of all 185 guide tubes was performed. It was discovered that 19 of the 185 guide-tubes had debris in then. All the debris was located in the guide tubes on
. top of the velocity limiter section of the CRD blade. The debris consisted of grinding wheels (only found in 3 tubes) and such degradable matariala as-cloth, paper, string, and wood splinters.
CAUSE:
In an atteipt to determine how the debris got into the guide tubes, investigations into the source of the grinding wheels and the time period of possible debris introduction to the guide tubes were conducted. The results of. the investigation-into the grinding wheels source revealed that wheels of the type found have not been purchased for use at SSES by any group performing work at.SSES. Therefore, it is concluded the source of the grinding wheels is
' indeterminable.
The investigation into de+amining the time period of possible introduction of the debris into the tubes resulted in the conclusion that the debris was most likely intrMvwl after the blades were installed into the guide tubes (as all the debris found in the tubes was found on tcp of the velocity limiter section of the control blades). Blade installation took 16 days (5/6/83 to 5/22/83).
This installation activity included checking the guide tubes for debris prior to installation of the blades. Upon installation of the blades and at the conclusion of each work shift, the staging racks which were located on elevation 818 of the reactor building were covered with Visqueen. The racks were covered with Visqueen and sat on Elevation 818 until guide tube installation activities cmmenced 7/16/83 (cmpleted on 7/18/83). During this installation activity, the debris was accidentally discovered. Therefore, the debris was probably intr M v wl to the guide tubes after blade installation and before guide tube installation.
SAFETY IMPLICATINS:
Iwo types of debris were found - degradable materials and grinding wheels.
Based upon the nature of the degradable materials (described previously in Description), it is determined that they are not capable of adversely affecting the safe operation of the CRD assemblies, or cause damage to the reactor core.
U . .
2 Attactment- to PIA-1803
.Page 2 of 3=
1he grinding wheels, however, could potentially restrict the movment of the
~
control rods, thereby possibly affecting the. safe operation of the CRD aa==hlies. Failure of the control rods to insert during a scram poses a -
concern fran the standpoint of assuring sufficient shutdown reactivity to maintain reactor subcriticality following scrm. Analyses, therefore, were performed to assess core shutdown margin ===Mng that all three control rods
~
- are stuck in their fully withdrawn position. The calculations indicate that no degradation of core shutdown margin would result and the Technical.
Specification requirments (Tech. Spec. 3/4.1.1) would easily be' met. This is expected since the three affected control rods are radially dispersed in the core, thus resulting in relatively low reactivity _ worths.
The possibility that the debris could cause a control rod to han= stuck during withdrawal was also considered. Assuming that a control rod han = s stuck and the control rod drive becmes decoupled, the control red could at a
-later optimtun nrnent drop'out of the core. The wisiiequences of this -
postulated event is a design basis for SSES Unit #2 and the analysis for it is presented in Susquehanna SES FEAR section 15.4.9, Control Rod Drop Accident Analysis.
The possibility of all .three CRD bladaa getting stuck and dropping out of the core simultaneously was not considered as numerous systm (Rod Sequence Control System and Rod Worth Minimizer) and operator failures are needed for this to occur.
If it is postulated that the grinding wheel debris exits the CRD tubes into the reactor vesml, their effects on the fuel would also be of concern.
However, assuning the debris could make its way to the lower plenum region, passage through the lower tie plate would be inprobable due to the size of the grinding wheels steel ccuponents. Therefore, any damage 'to the fuel rods would be unlikely. Furthermore, due to the small size of the~ metal debris,
- any flow blockage which may occur would be minimal and have an insignificant effect on fuel rod performance.
-In light of the above, the miscellaneous debris found in the CED guide tubes, would not, if they had gone undetected, have affected the safe operation of SSES Unit #2.
CORRECPIVE ACTICNS:
As previously discussed a 100% inspection was performed (on 7/19/83) upon identification of the debris in the tubes. This inspection was performed with the aid of flashlights, binoculars and a camera with a zoom lens (no pictures were taken). The inspection results were documented on General Electric Special Process Control Sheet (SPCS) number 219S-1, Rev. O. All debris was removed by using an aluminum pole with approved nuclear grade tape. No damage was incurred by the presence of the foreign material.
.. +
p .e. . .
,e
,.e
- .c
. - - - +
.m -
a-
N j ,
~
.Kttachment~to PIA-1803 t ,
. ' Page 3'of 3c
.r- .
, , g
. k - h, Upon coupletion of the 100% inspection of 7/19/83,':a third security guan!'was posted at the reactor vessel. 'Ihis guard's duties were and are to monitor all N:-
activities performed in and'around the reactor vessel during periods when - ; ,
physical work is being acomplished in the vessel. ,
a
\
e,w" s
s 6
\
v
- 9. a*
as e
av W
u 4
s m l
- , . - - - - . - , . . . . ... - _ - . - ,