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Category:DEFICIENCY REPORTS (PER 10CFR50.55E & PART 21)
MONTHYEARML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML17309A6211997-09-29029 September 1997 Part 21 Rept Re Final Disposition of Masterflow 713 & Embeco 636 Grout Nonconformance Reported by Master Builders,Inc. Licensee Continuing to Monitor shelf-life of Masterflow 713 & Embeco 636 Grouts Produced at Rancho Cucamonga ML20140G4481997-05-0101 May 1997 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby Diesel Generator Sys.Recommends That Springs Be Inspected on Periodic Basis,Such as During Refueling Outages ML20133E8001997-01-0808 January 1997 Deficiency Rept Re Nonconformance Related to Masterflow 713 Grout,Which Master Builders,Inc Has Supplied as Nuclear SR Product to 18 Npps.Cause Unknown.Requests That Listed Info Be Provided to Gain Insight as to Scope & Possible Cause ML20134H3361996-11-0505 November 1996 Part 21 Rept Re Defective Inner Thrust Bearing 1801461-01 Used in PSA 35 Mechanical Shock Arrestor Used as Restraint on Piping Sys for Nuclear Generating Plant.Lot of Defective Parts Located & Isolated to Three Customers ML20115D2001996-07-0909 July 1996 Part 21 Rept Re Mfg Defect of Enterprise DSR-4 & DSRV-4 Edgs,Originally Mfg by Calcon Corp.Amot Control Corp Purchased Calcon Product Line & Maintains Design & Production.Valves Returned to Cooper Energy Svcs on 960131 ML20117G4641996-05-14014 May 1996 Part 21 Rept Re Cooper Bessemer Reciprocating Products,Div of Cooper Cameron Corp,Issued Ltr to Define Utils/Plants Containing Similar Equipment as Supplied on Cooper Bessemer Ksv & Enterprise Dsr EDGs ML18038A8971994-09-0707 September 1994 Part 21 Rept Re Defect in Latching Mechanism of Potter & Brumfield Relay on C&D High Voltage Shut Down Alarm Assembly Printed Circuit Boards.Pull Test on Relay Reset Button Incorporated Into Receiving Insp Procedures ML20059H7721994-01-17017 January 1994 Part 21 Rept Re Virginia Power Notifying Fairbands Morse Via Failure Analysis Rept NESML-Q-058 of Defective Air Start Distributor cam,16104412 ML20059F2631994-01-0707 January 1994 Part 21 Rept Re Air Start Distributor Cam Mfg by Fairbanks Morse.Mfg Suggests That Site Referenced in Encl App I Inspect Air Start Distributor Cam as Soon as Practical ML20058K3841993-12-0909 December 1993 Part 21 Rept Re Potential Defect in Component of Dsrv & Dsr Enterprise Standby DG Sys,Regarding Potential Problem W/ Subcover Assembled Atop Power Head ML20127H2301993-01-15015 January 1993 Part 21 Rept Re Potential Defeat in Component of Dsrv & Dsr Enterprise Standby DG Sys.Starting Air Distributor Housing Assemblies Installed as Replacement Parts at Listed Sites ML20126J5961992-12-31031 December 1992 Part 21 Rept Re Potential Loss of RHR Cooling During Nozzle Dam Removal.Nozzle Dams May Create Trapped Air Column Behind Cold Leg Nozzle Dam.Mod to Nozzle Dams Currently Underway. Ltrs to Affected Utils Encl ML20126B0421992-12-17017 December 1992 Final Part 21 Rept Re Potential Problem W/Steel Cylinder Heads.Initially Reported on 921125.Caused by Inadequate Cast Wall Thickness at 3/4-inch-10 Bolt Hole.Stud at Location Indicated on Encl Sketch Should Be Removed ML20127D1491992-09-0404 September 1992 Part 21 Rept Re Defect in Component of DSRV-16-4 Enterprise Standby DG Sys Jacket Water Pump Shaft.Caused by Incorrect Tapers Machined on Shaft Due to Vendor Mismatching.All Affected Shafts Recalled & Quality Insp Plans Changed ML17289A6971992-06-26026 June 1992 Amend 1 to Part 21 Rept 158 Re gear-wear Induced Failures in engine-driven Jacket Water Pump in DSRV-16-4 Standby DG Sys. Initially Reported on 911029.Grand Gulf Station Observed Wear Characteristics in as Little as 500 Operating Hours ML20094L1271992-03-13013 March 1992 Amend 1 to Part 21 Rept 159 Re Potential Defect in Power Cylinder Liner.Initially Reported on 920115.Caused by Liner/ Block Fit & Localized Matl Microstructure.All Drawings & Specs Revised to Address Matl Design Requirements ML20087D3191992-01-14014 January 1992 Potential Part 21 Rept Re Problems W/Elmwood/Fasco Contactor Carriers Breaking in Contactor Model 30-FO-30. Caused by Distortion/Shrinkage of Molded Phenolic Contactor Carrier.Replacement Contactors Installed ML17223A5941990-03-0909 March 1990 Errata to 900126 Part 21 Rept Re Anchor/Darling Actuators Incorporating Use of Teldyne-Republic four-way Valves.Lists Plants Inadvertently Left Out in Original Rept ML20005G6831990-01-0505 January 1990 Part 21 Rept Re Installation Instructions for Grommet Use Range for Patel Conduit Seal P/N 841206.Conduit Seals in Environ Qualification Applications Inspected for Proper Wire Use Range & Grommets Replaced ML20248E0121989-09-13013 September 1989 Supplemental Part 21 Rept Re Potential Problem W/Six Specific Engine Control Devices in Air Start,Lube Oil, Jacket Water & Crankcase Sys.Initially Reported on 890429. California Controls Co Will Redesign Valve Seating ML20246K7401989-04-26026 April 1989 Part 21 Rept Re Incorrectly Stamped Name Plates on Certain Asco Nuclear Qualified Valves.Vendor Will Contact Each Affected Facility & Furnish Correctly Stamped Plates & in Near Future Discontinue Sale of Rebuild Kits for Valves ML20247P7991989-04-0404 April 1989 Part 21 Rept Re Atmospheric Dump Valves.Cause of Failure Speculative But Result of Piston Ring That Failed to Seal. Resolution to Problem Requires Increasing Pilot Valve Capacity & Reworking of Plug to Enlarge Pilot Flow Area ML20206M4401988-11-21021 November 1988 Deficiency Rept Re Misapplication of Raychem Criteria in Selection of Some Matl Used in Electrical Cable Field Splice Kits.Initially Reported on 880920.Investigation Is in Process.Final Rept Will Be Submitted by 881222 ML20205C9291988-10-18018 October 1988 Part 21 & Deficiency Rept Re Valves Installed Opposite to Direction of Flow,Per 10CFR21 & 50.55 Requirements.Item Being Tracked by MTS EAI B-5115 & Scheduled for Completion 881030 ML20205D6651988-10-18018 October 1988 Part 21 & Deficiency Rept Re Penetration Seals Found Not to Be Watertight.Initially Reported on 880609.Water Leakage Tests Performed on Unit Upper Cable Spreading Room Seals. All Floor Penetration Seal Assemblies Repaired ML20207P0451988-10-0505 October 1988 Part 21 Rept 146 Re Defect in Left Intercooler Inlet Adapter on Standby Diesel Engine Generator.Recommends Utils Inspect Left Intake Manifold Drain as Part of Operating Plan.Addl Info Expected by 881015 ML20155D6471988-09-28028 September 1988 Deficiency Rept Re Valves Installed Opposite to Direction of Flow.Initially Reported on 880629.Final Rept Delayed Until 881020 ML20207J7361988-09-20020 September 1988 Interim Deficiency Rept Re Misapplication of Vendor Criteria in Selection of Some Matl Used in Electrical Cable Field Splice Kits.Initially Reported on 880601.Final Rept Expected Prior to 881123 ML20153E2271988-09-0101 September 1988 Part 21 & Deficiency Rept Re ESF Filtration Unit Bolts. Initially Reported on 880628.Contractor Conducted Training Session for Personnel to Stress Importance of Clarifying Incomplete Drawing Info & Requirements of Bolting Procedure ML20151V1901988-08-16016 August 1988 Deficiency Rept Re non-water Tight Penetration Seals.Test Rig Constructed to Simulate Typical Upper Cable Spreading Room Configuration & Sealants Verified to Provide Waterproof Seal.Next Rept Will Be Submitted by 881020 ML20196L4811988-07-0707 July 1988 Part 21 & Deficiency Rept Re Valves Installed Opposite to Direction of Flow.Initially Reported on 880601.Investigation in Progress to Determine Full Scope of Condition.Final Rept Will Be Submitted by 881001 ML20151A7781988-07-0606 July 1988 Deficiency Rept Re nonwater-tight Penetration Seals. Initially Reported on 880609.Investigation Incomplete.Next Rept Expected by 880818 ML20196C2971988-06-28028 June 1988 Deficiency Rept Re ESF Filtration Bolts.Initially Reported on 880601.Investigation of Root Cause of Condition Ongoing. Final Rept Will Be Submitted by 880901 ML20195D8541988-06-16016 June 1988 Part 21 Rept Re Potentially Reportable Condition Associated W/Dresser Model 7440W Check Valves Supplied W/Flow Direction Arrow Stamped Opposite to Valve Flow.Investigation Being Conducted.Evaluation of Bechtel Western Power Co Ltr Encl ML20154J4101988-05-12012 May 1988 Addendum 1 to Supplemental Part 21 Rept 145 Re Potential Problem w/F-573-156 Pressure Sensor/Lube Oil Trip.Initially Reported on 880429.Addl 1-1/8-inch Diameter W/Deep Counterbone in Pressure Head Added to Activate Valve ML20154A6841988-05-10010 May 1988 Deficiency Rept Re Electrical Cable Tray Separation. Initially Reported on 880414.Walkdown of All safety-related Cable Trays Conducted to Ensure Any Unacceptable Separation Distance Identified ML20153B6191988-04-29029 April 1988 Part 21 Rept Re Potential Defect in Component of Dsr or Dsrv Standby Diesel Generators Supplied to Utils.Recommends Return of Subj Components in Onsite Warehouse Storage & Suggests Surveillance of Devices Already Installed ML20151K2621988-04-14014 April 1988 Interim Deficiency & Part 21 Rept Re Control Room Essential HVAC Sys.Initially Reported on 870914.Addl Concern Noted Re Incorrect Assumption in Design Calculation.Corrective Action Beyond Calculation Review Involves Logic Mod ML20151K2371988-04-14014 April 1988 Part 21 & Deficiency Rept Re Damage to Emergency Diesel Generator Jacket Water HX During Flushing.Initially Reported on 860917.HX Repaired & Installed in Unit 2.Thermostatic Valves Being Modified ML20148R6441988-01-27027 January 1988 Part 21 & Deficiency Rept Re Protection of Containment Electrical Penetration Assemblies Fabricated by Conax Buffalo Corp.Initially Reported on 871203.LOCA Could Cause One or More of nonsafety-related Circuits to Short Circuit ML20237E9941987-12-22022 December 1987 Deficiency Rept Re Protection of Containment Electrical Penetration Assemblies (Epa).Initially Reported on 871203. Investigations in Progress.Final Rept Will Be Submitted by 880130 ML20236V2981987-11-19019 November 1987 Deficiency Rept Re Electrical Separation Criteria Specified in Const Spec X3AR01.Initially Reported on 870909.Second Test of Electrical Separation Requirements Very Positive. Final Rept Expected to Be Submitted Prior to 880301 ML20236K1431987-11-0202 November 1987 Interim Part 21 & Deficiency Rept Re Inductive Current Interruptive Capacity of Solid State Protection Sys Motor Driven Relay Contacts.Shunt Suppression Device Will Be Added to Solenoid ML20236J5371987-10-29029 October 1987 Part 21 & Deficiency Rept Re Solid State Protection Sys motor-driven Relay Contacts Inductive Current Interruptive Capacity.Initially Reported on 870110.Hardware Mods to Affected Circuits Planned Prior to Fuel Load ML20239A2111987-09-14014 September 1987 Part 21 & Deficiency Rept Re Design of Control Room Essential (CRE) HVAC Sys.Initially Reported on 870713. Backdraft Dampers Added to Unit 1 CRE HVAC Units & Will Be Added to Unit 2 Commensurate W/Const Schedule ML20237H7741987-08-12012 August 1987 Interim Deficiency Rept Re Emergency HVAC Sys in Control Room.Initially Reported on 870713.Engineering Evaluation in Progress to Determine Potential Impacts of Condition on Plant Safety.Final Rept Will Be Submitted by 870915 ML20216E4721987-05-28028 May 1987 Part 21 Rept 140 Re Potential Defect in Air Pressure Regulators Mfg by Bellofram.Dripwell Gasket May Fail Due to Mismachining of Gasket Seating Surface Causing Loss of Control Air & Starting Air Pressure 1999-04-12
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217P3791999-10-21021 October 1999 Forwards NRC Form 396 & NRC Form 398 for Renewal of Licenses SOP-20607-1 & SOP-20610-1.Without Encls ML20217N2521999-10-20020 October 1999 Provides Supplemental Info Re 990405 Containment Insp Program Requests for Relief RR-L-1 & RR-L-2,in Response to 991013 Telcon with NRC ML20217K7541999-10-15015 October 1999 Forwards Rev 1 to Unit 1,Cycle 9 & Unit 2 Cycle 7 Colrs,Iaw Requirements of TS 5.6.5.Figure 5, Axial Flux Difference Limits as Function of Percent of Rated Thermal Power for RAOC, Was Revised for Both Units ML20217G6751999-10-13013 October 1999 Requests Withholding of Proprietary Info Contained in Application for Amend to OLs to Implement Relaxations Allowed by WCAP-14333-P-A,rev 1 ML20216J9161999-10-0101 October 1999 Forwards Response to NRC 990723 RAI Re GL 95-07, Pressure Locking & Thermal Binding of SR Power-Operated Gate Valves ML20216J9041999-10-0101 October 1999 Forwards Response to RAI Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves ML20212E7481999-09-20020 September 1999 Requests Approval Per 10CFR50.55a to Use Alternative Method for Determining Qualified Life of Certain BOP Diaphragm Valves than That Specified in Code Case N-31.Proposed Alternative,Encl ML20212E8751999-09-20020 September 1999 Forwards Response to NRC GL 99-02, Lab Testing of Nuclear Grade Activated Charcoal. Description of Methods Used to Comply with Std Along with Most Recent Test Results Encl ML20212C2191999-09-16016 September 1999 Forwards NRC Form 536, Operator Licensing Exam Data, Which Is Current Need for NRC Operator Licensing Exams for Years 2000 Through 2003 of Plant Vogtle,Per Administrative Ltr 99-03 ML20211J5291999-08-30030 August 1999 Forwards Snoc Copyright Notice Dtd 990825,re Production of Engineering Drawings Ref in VEGP UFSAR ML20211J5251999-08-30030 August 1999 Forwards Response to NRC 990727 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions ML20211J7381999-08-27027 August 1999 Informs That Licensee Vessel Data Is Different than NRC Database Based on Listed Info,Per 990722 Request to Review Rvid ML20211E9251999-08-23023 August 1999 Forwards fitness-for-duty Performance Data for Jan-June 1999,as Required by 10CFR26.71(d).Data Reflected in Rept Covers Employees at Vogtle Electric Generating Plant ML20210L2181999-08-0202 August 1999 Forwards NRC Form 396 & Form 398 for Renewal of Listed Licenses,Iaw 10CFR55.57.Without Encl ML20210C8011999-07-21021 July 1999 Provides Response to NRC AL 99-02,which Requests That Addressees Submit Info Pertaining to Estimates of Number of Licensing Actions That Will Be Submitted for NRC Review for Upcoming Fy 2000 & 2001 ML20209H3881999-07-14014 July 1999 Forwards Revs 1 & 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Unit 1 & 2 ML20209C4041999-07-0101 July 1999 Forwards Rev 29 to VEGP Units 1 & 2 Emergency Plan.Rev 29 Incorporates Design Change Associated with Consolidation of Er Facilities Computer & Protues Computer.Justifications for Changes & Insertion Instructions Are Encl ML20196F9171999-06-21021 June 1999 Forwards Owner Rept for ISI for Vogtle Electric Generating Plant,Unit 1 Eighth Maint/Refueling Outage. Separate Submittal Will Not Be Made to NRC on SG Tubes Inspected During Subj Outage ML20212J2521999-06-21021 June 1999 Responds to NRC RAI Re Yr 2000 Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701 ML20195F8031999-06-11011 June 1999 Forwards Changes to VEGP Unit 1 Emergency Response Data Sys (ERDS) Data Point Library.Changes Were Completed on 990308 While Unit 1 Was SD for Refueling Outage 05000424/LER-1998-006, Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Exi1999-05-10010 May 1999 Forwards LER 98-006-03 Re Motor Control Ctr Breaker Buckets Not Being Seismically Qualified.Rev Is Submitted to Document Results of Seismic Testing That Demonstrated That No Condition Outside Design Basis of TS Requirements Existed ML20206D5881999-04-29029 April 1999 Forwards Rept Which Summarizes Effects of Changes & Errors in ECCS Evaluation Models on PCT for 1998,per Requirements of 10CFR50.46(a)(3)(ii).Rept Results Will Be Incorporated Into Next FSAR Update ML20206D6411999-04-29029 April 1999 Forwards Vogtle Electric Generating Plant Radiological Environ Operating Rept for 1998 & Vogtle Electric Generating Plant Units 1 & 2 1998 Annual Rept Annual Radioactive Effluent Release Rept ML20206D6951999-04-28028 April 1999 Provides Update of Plans for VEGP MOV Periodic Verification Program Re GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Movs ML20206C2241999-04-21021 April 1999 Forwards Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2.Page E2-2 Was Iandvertently Omitted from Previously Submitted Rept on 990413 ML20209A3741999-04-0505 April 1999 Submits Several Requests for Relief for Plant from Code Requirements Pursuant to 10CFR50.55a(a)(3) & (g)(5)(iii).NRC Is Respectfully Requested to Approve Requests Prior to Jan 1,2000 ML20205H3481999-03-31031 March 1999 Forwards Georgia Power Co,Oglethorpe Power Corp,Municipal Electric Authority of Ga & City of Dalton,Ga Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81 ML20205F9091999-03-29029 March 1999 Submits Rept of Number of SG Tubes Plugged During Plant Eighth Maintenance/Refueling Outage (1R8).Inservice Insps Were Completed on SGs 1 & 4 on 990315.No Tubes Were Plugged ML20205G0761999-03-26026 March 1999 Provides Results of Individual Monitoring for 1998.Encl Media Contains All Info Required by Form NRC 5.Without Encl ML20205H4051999-03-25025 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1) ML20205H3891999-03-25025 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1).Page 2 in Third Amend Power Sales Contract of Incoming Submittal Not Included ML20205A9441999-03-25025 March 1999 Forwards VEGP Unit 1 Cycle 9 Colr,Per TS 5.6.5.d ML20205H3811999-03-24024 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81,as Requested IAW 10CFR50.75(f)(1) ML20205H3621999-03-22022 March 1999 Forwards Info on Status of Decommissioning Funding for Each Reactor or Part of Reactor Owned for OLs NPF-68 & NPF-81, as Requested IAW 10CFR50.75(f)(1) ML20204G4361999-03-18018 March 1999 Forwards Summary Rept of Present Level & Source of on-site Property Damage Insurance Coverage for Vegp,Iaw Requirements of 10CFR50.54(w)(3) ML20204C0591999-03-17017 March 1999 Forwards Rev 0 to WCAP-15160, Evaluation of Pressurized Thermal Shock for Vegp,Unit 2 & Rev 0 to WCAP-15159, Analysis of Capsule X from Vegp,Unit 2 Reactor Vessel Radiation Surveillance Program ML20207K9551999-03-11011 March 1999 Forwards Response to Rai,Pertaining to Positive Alcohol Test of Licensed Operator.Encl Info Provided for NRC Use in Evaluation of Fitness for Duty Occurrence.Encl Withheld,Per 10CFR2.790(a)(6) ML20207L9721999-03-10010 March 1999 Forwards Rev 15 to EPIP 91104-C of Manual Set 6 of Vogtle Epips.Without Encl ML20207B0191999-02-25025 February 1999 Forwards Fitness for Duty Performance Data for six-month Reporting Period 980701-1231,IAW 10CFR26.71(d) 05000424/LER-1998-009, Forwards LER 98-009-00 Re Event in Which Improper Testing Method Resulted in Inadequate Surveillances on 9812291999-01-27027 January 1999 Forwards LER 98-009-00 Re Event in Which Improper Testing Method Resulted in Inadequate Surveillances on 981229 ML20199F7701999-01-13013 January 1999 Submits Revised Response to RAI Re Licensee 980713 Proposed Amend to Ts,Eliminating Periodic Response Time Testing Requirements on Selected Sensors & Protection Channels. Corrected Copy of Table,Encl ML20199F7981999-01-13013 January 1999 Forwards Corrected Pages to VEGP-2 ISI Summary Rept for Spring 1998 Maint/Refueling Outage. Change Bar in Margin of Affected Pages Denotes Changes to Rept ML20199G1381999-01-13013 January 1999 Forwards Copy of Permit Renewal Application Package for NPDES Permit Number GA0026786,per Section 3.2 of VP Environ Protection Plan 05000424/LER-1998-007, Forwards LER 98-007-00,re Inadequate Surveillances Due to Improperly Performed Response Time Testing,On 981215,IAW 10CFR50.731999-01-13013 January 1999 Forwards LER 98-007-00,re Inadequate Surveillances Due to Improperly Performed Response Time Testing,On 981215,IAW 10CFR50.73 ML20198F6131998-12-18018 December 1998 Forwards Revised Certification of Medical Exam Form for License SOP-21147.Licensee Being Treated for Hypertension. Util Requests That Individual License Be Amended to Reflect Change in Status ML20198L6631998-12-18018 December 1998 Forwards Amend 37 to Physical Security & Contingency Plan. Encl 1 Provides Description & Justification for Changes & Encl 2 Contains Actual Amend 37 Pages.Amend Withheld,Per 10CFR73.21 ML20198D9291998-12-16016 December 1998 Forwards Requested Info Re Request to Revise TSs Elimination of Periodic Pressure Sensor Response Time Tests & Elimination of Periodic Protection Channel Response Time Tests ML20198D9991998-12-16016 December 1998 Forwards Responses to 980916 RAI Re Response to GL 97-01, Degradation of Control Rod Drive Mechanism Nozzle & Other Vessel Closure Head Penetrations ML20198D8171998-12-14014 December 1998 Forwards NRC Form 396 & Form 398 for Renewal of License OP-20993.Without Encls ML20206N3051998-12-0808 December 1998 Submits RAI Re Replacement of Nuclear Instrument Sys Source & Intermediate Range Channels & post-accident Neutron Flux Monitoring Sys 1999-09-20
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217K4591999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20217K8041999-09-30030 September 1999 Rev 1 to Vegp,Unit 2 Cycle 7 Colr ML20217K7741999-09-30030 September 1999 Rev 1 to Vegp,Unit 1 Cycle 9 Colr ML20216E5061999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Vegp,Units 1 & 2. with ML20210P9841999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20209H1211999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20196F9711999-05-31031 May 1999 Owner Rept for ISI for Vogtle Electric Generating Plant, Unit 1 Eighth Maint/Refueling Outage ML20195G1731999-05-31031 May 1999 Monthly Operating Repts for May 1999 for VEGP Units 1 & 2. with ML20206N2141999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20206A6561999-04-21021 April 1999 Safety Evaluation Authorizing Licensee Re Rev 9 to First 10-year ISI Interval Program Plan & Associated Requests for Relief (RR) 65 from ASME Boiler & Pressure Vessel Code ML18016A9011999-04-12012 April 1999 Part 21 Rept Re Defect in Component of DSRV-16-4,Enterprise DG Sys.Caused by Potential Problem with Connecting Rod Assemblies Built Since 1986,that Have Been Converted to Use Prestressed Fasteners.Affected Rods Should Be Inspected ML20206C2291999-03-31031 March 1999 Revised Monthly Operating Repts for Mar 1999 for Vogtle Electric Generating Plant,Units 1 & 2 ML20205Q8081999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Vegp,Units 1 & 2. with ML20205A9581999-03-31031 March 1999 Rev 0 to VEGP Unit 1 Cycle 9 Colr ML20207K6051999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20209H3951999-02-15015 February 1999 Rev 2 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2 ML20209H4091999-02-15015 February 1999 Rev 1 to ISI Program Second 10-Year Interval Vogtle Electric Generating Plant Units 1 & 2 ML20202H9851999-01-29029 January 1999 Safety Evaluation Accepting Rev 8 to First 10-year Interval Inservice Insp Program & Associated Requests for Relief for Vogtle Electric Generating Plant,Unit 1 ML20199F8041999-01-13013 January 1999 Corrected Pages to VEGP-2 ISI Summary Rept for Spring 1998 Maint/Refueling Outage ML20199E7561998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20198S1781998-12-31031 December 1998 SER Re Second 10-year Interval Inservice Insp Program Plan & Associated Requests for Relief for Southern Nuclear Operating Co,Inc Units 1 & 2 ML20196E5221998-12-0101 December 1998 Rev 8 to ISI-P-014, ISI Program for VEGP-2 ML20198B8571998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Vogtle Electric Generating Plant,Units 1 & 2.With ML20195H2131998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Vogtle Electric Generating Station,Units 1 & 2.With ML20154L5681998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Vegp,Units 1 & 2 ML20151W3681998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Vogtle Electric Generating Plant Units 1 & 2.With ML20154L5721998-08-31031 August 1998 Corrected Page from MOR for Aug 1998 for Vegp,Unit 2 ML20237D2051998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Vogtle Electric Generating Plant Units 1 & 2 ML20236V3121998-07-29029 July 1998 Final Part 21 Rept Re Enterprise DSR-4 & DSRV-4 Edgs.Short Term Instability Was Found During post-installation Testing & Setup as Part of Design mod/post-work Testing Process. Different Methods Were Developed to Correct Problem ML20236P6991998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20236Q3051998-06-30030 June 1998 Owner'S Rept for ISI for Sixth Maint/Refueling Outage of Vogtle Electric Generating Plant,Unit 2 ML20249A3911998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Vogtle Electric Generating Plant ML20248A1671998-05-22022 May 1998 Interim Part 21 Re Enterprise DSR-4 & DSRV-4 Emergency diesel.Post-installation Testing Revealed,High Em/Rfi Levels Affected New Controllers,Whereas Original Controllers Were unaffected.Follow-up Will Be Provided No Later than 980731 ML20249A3931998-04-30030 April 1998 Revised MOR for Apr 1998 for Vogtle Electric Generating Plant Unit 1 ML20247F3841998-04-30030 April 1998 Monthly Operating Repts for Apr 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20154Q9721998-04-20020 April 1998 10CFR50.59(B) Rept of Facility Changes,Tests & Experiments for Vogtle Electric Generating Plant,Units 1 & 2 ML20217H7181998-04-0101 April 1998 Corrected Page 5 to 980324 SER Re Relief Requests Associated W/Second 10-year Interval Insp program.RR-21 in Error in That Component,Suction Damper Inadvertently Omitted. Corrected Page 7 of Technical Ltr Rept Also Encl ML20216D6141998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20217Q1301998-03-31031 March 1998 Rev 0 to Vepc Unit 2 Cycle 7,COLR ML20217B8831998-03-24024 March 1998 SER Accepting Relief Request RR-5,RR-19,RR-20,RR-21,RR-23 & RR-24 for Second 10-yr Interval ISI Program Plan ML20216E2421998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20203H9551998-02-23023 February 1998 SER Denying Quality Assurance Program Description Change for Vogtle Electric Generating Plant,Units 1 & 2 ML20203E4831998-02-11011 February 1998 Rev 1 to Vogtle Electric Generating Plant,Units 1 & 2 Second Ten-Yr Interval Pump Inservice Test Program ML20198T1211998-01-31031 January 1998 Owners Rept for Inservice Inspection for Seventh Maintenance/Refueling Outage ML20202G5441998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Vogtle Electric Generating Plant,Units 1 & 2 ML20199E5431998-01-31031 January 1998 Rev 3 to WCAP-14720, Vogtle Units 1 & 2 Spent Fuel Rack Criticality Analysis W/Credit for Soluble Boron ML20198L6471997-12-31031 December 1997 Monthly Operating Repts for Dec 1997 for Vogtle Electric Generating Plant,Units 1 & 2 ML20203C2811997-12-0909 December 1997 Safety Evaluation Authorizing Request for Relief of Second 10 Yr Interval Inservice Insp Program ML20202B7881997-12-0101 December 1997 Rev 8 to ISI-P-006, ISI Program for Gpc Vogtle Electric Generating Plant Unit 1 ML20203H0601997-11-30030 November 1997 Monthly Operating Repts for Nov 1997 for Vegp,Units 1 & 2 1999-09-30
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. Georgia Ftwer Company.
Post Office Box 282 Waynesboro, Georgia 30030 Telephone 404 554 9961, Extension 3413 404 724 8114, Extension 3413 m
r.o.me. Georgia Power Vice President vogtie project September 14, 1987 """"*'"*"*""
United States Nuclear Regulatory Commission File: X7BG03-M139 Document Control Desk Log: GN-1396 Washington, D. C. 20555
Reference:
Vogtle Electric Generating Plant - Unit 2; 50-425 Control Room Essential HVAC Letter GN-1391, dated August 12, 1987 l' In previous correspondence, Georgia Power Company notified the NRC of a potentially reportable condition associated with the design of the Control Room Essential HVAC System. Georgia Power Company has' completed its deportability evaluation and has. determined that a reportable condition as defined by the . reporting requirements of 10CFR Parts 21 and 50.55(e) does_ e&ist. Based upon NRC guidance in NUREG-0302, Revision 1, and other NRC correspondence, Georgia Power requirements Company is reportinge).
of 10CFR50.55 (this Acondition summary pursuant to the reporting of our evaluation is attached. This condition has been reported for Unit 1 in LER 50-424/1987-044.
The broadness review to determine if this or a similar situation exists on other systems is not yet complete. If any other systems are found with this condition, then a supplemental report will be submitted providing this information.
This correspondence contains no proprietary information and may l
be placed in the NRC Public Document Room.
, ,h.h / n P. D. Rice CWH/PDR/wkl xc: USNRC - Region 11 Suite 2900 101 Marietta Street, NW Atlanta, GA 30323 H. G. Baker D. R. Altman L. T. Gucwa .
J. P. O'Reilly J. A. Bailey C. W. Hayes l R. E. Conway G. Bockhold R. W. McManus l R. H. Pinson C. E. Belflower Sr. Resident (NRC) l E. D. Groover J. F. D'Amico C. C. Garrett (OPC) i C. T. Moore D. Feig (GANE) J. E. Joiner (TSLA) J G. A. McCarley NORMS j (g
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EVALUATION OF A POTENTIALLY REPORTABLE CONDITION' CONTROL ROOM ESSENTIAL HVAC j ..
/ i Initial Report: On July 13, 1987, Mr. R. E. Folker, Project Quality Assurance Engineer, notified Mr. E. F. Christnot of the ' USNRC Region 11 and Mr. H. H. Livermore, Senior Resident inspector, of a potentially reportable condition associated with the Control ,.
Room Essential HVAC System. In subsequent correspondence with 1' the NRC, Georgia Power Company indicated that a final report on. >
this_ issue would be submitted by September 15, 1987.
Background Information: The control building control room essential (CRE) HVAC system consists of two redundant and physically separated 100 percent capacity HVAC units ' for each . side of the control room, I' or four for the combined - Unit 1 and Unit 2 control room. Each I
of the two redundant HVAC' units belongs to a different safety train. However, portions of the outside air ' intake ductwork 'and the control room supply and return ductwork are common to each of the HVAC units. This system is . shown ' schematically in ~ FSAR Figure 9.4.1-2.
To protect against high airborne radioactivity inside the control room, following receipt of a safety injection signal or a control room outside air intake high radiation signal, the control room HVAC is automatically transferred from the normal units to the CRE units in the emergency mode of operation. The associated dampers for the essential units are automatically opened and the The essential unitst normal units are automatically isolated.
are designed to be capable of:
- 1) removing the sensible and latent heat loads from the contr61 room,
- 2) recirculating the air within the control room. through engineered -
l safety feature filters to provide continuous purification I
capability, and l
- 3) pressurizing the control room to 1/8 inch water gauge (w.g. ) ,
pressure relative to the adjacent areas to minimize unfiltered g inleakage (Technical Specification 3/4.7.6).
On July 2, 1987, Plant Engineering identified a design problem related to the adequacy- of the- CRE HVAC system analysis for operatior in the emergency mode. Either loss of power to an operating train of' CRE HVAC, or a . failure of the emergency , fan, while operating in the emergency mode, could change the ' amount of outside air available to pressurize the control room. This is because the dampers fail in the "as-is"' position, and there were no back-draft dampers installed. This failure . mode allows additional flow paths through the common ductwork and failed unit's ductwork potentially reducing the amount of outside air brought
, in through the operating unit. The effect of reducing the outside, l air flow would be to potentially reduce the control room pressure' .,..
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I below the design (1/8 inch w.g. positive)' value. There is also a flowpath which could increase the amount of outside air available to pressurize the control room. Bechtel WestMn Power Corporation is the architect / engineer for this system. },
Engineering Evaluation: An accurate analysis of the volume of 1 air which would be transmitted by the various flowpaths through the failed HVAC ductwork would be difficult to perform without test data. However, in lieu of a test, GPC decided to develop hardware modifications to eliminate the potential for changes in the amount of outside air available to pre:suMz,e Ve control room. Accordingly, no analytical conclusion can, be drawn regarding the effect on outside air flow resulting from the failure of en operating CRE HVAC train. ]
The root cause of this condition was determined to be the f ailure to perform an adequate failure modes and effects analysis (FMEA) of operation in the emergency mcde.
L Insufficient data exists to perform a calculation . to determine )
if a reduction in outside air makeup flow would dave ,occured. l Consequently, the ' effect of this potential reduction of control room pressurization on the amount of air inleakage to the control room and increased dose to the operators in the event of an accident cannot be adequately determined. Therefore, this condition is I considered repcrtable under 10CFR50.55(e) and 10CFR21.
Broadness Review: An inadequate FMEA on this system for its emergency mode of operation prevented this condition from being
( detected during design. A review of all other safety-related HVAC FEMA's will be conducted to determine if the same or a similar situation exists. This review is currently scheduled to be complete by the end of 1987. If this review finds any other systems with l
this condition, then a supplemental report will be submitted.
1 Evaluation of Quality Assurance Program Breakdown- At present, I the reported condition is isolated to one safety-related HVAC system. Therefore, it is not currently indicative of a significant breakdown in . , the Bechtel Quality Assurance Progra. If the broadness review discussed above finds any other defects, then another evaluation for a breakdown in the Quality Assurance Program will be conducted.
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Conclusion:
Base'd on the results of the above analysis,. it cannot l
be determined if the required 1/8 inch w.g positive , pressure could have been maintained in - the control room after a' CRE HVAC train failure. The pressure differential limit is a technical specification requirement, and is used in the design basis'1 for meeting General Design Criteria 19 contained in Appendix'A to 10CFR50. Therefore, GPC has concluded that a reportable condition I
as defined by the criteria of 10CFR50.55(e) and 10CFR21 does exist.
Based on the guidance in NUREG-0302, Revision 1, 'concedning duplicate reporting of an event, Georgia Power is reporting this event per the criteria of 10CFR50.55(e).
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k,,o i Corrective Action: To correct this condition, backdraft dampers have been added to the Unit 1 CRE HVAC units as described in LER 50-424/1987-044 and will be added to the Unit 2 outside_ air makeup branch and control room return air branch of each of the control building control room essential HVAC units. This work will be completed commensurate with the Unit 2 construction schedule.
Figure I below provides an illustration of the corrective action which will be.taken on Unit 2 to resolve this concern.
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