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| {{#Wiki_filter:Edwin I. Hatch Nuclear Plant Edwin I. Hatch Nuclear Plant NRC Region II Status Meeting NRC Region II Status Meeting August 15, 2007 August 15, 2007Dennis Madison -Hatch Vice PresidentSteve Douglas -Plant Manager Southern Nuclear Operating Company Agenda*Introduction | | {{#Wiki_filter:Edwin I. Hatch Nuclear Plant NRC Region II Status Meeting August 15, 2007 Dennis Madison - Hatch Vice President Steve Douglas - Plant Manager Southern Nuclear Operating Company Enclosure 2 |
| *Hatch Project Overview | | |
| -Plant Performance | | Agenda |
| -Site Vice President Reorganization | | * Introduction |
| *Topical Updates | | * Hatch Project Overview |
| *Major Projects | | - Plant Performance |
| -Major Projects Underway | | - Site Vice President Reorganization |
| -Recently Completed Projects | | * Topical Updates |
| *Open Discussion Plant Performance August 7, 2007 Unit 2 Reactor Trip*I&C technician inadvertently tripped an overcurrentrelay on the normal incoming feeder breaker for "D"4160 VAC bus during calibration*Loss of this bus resulted in a loss of 2 condensate pumps and 2 booster pumps, as well as a recirc runback *Plant scrammed on low reactor water level *All systems responded as designed; no actuation of HPCI or RCIC *Bus re-energized about 1.5 minutes from alternate source*Breakdown in risk assessment process Forced Loss Rate -HatchForced Loss Rate0.01.02.03.04.05.06.07.0 8.09.010.011.012.0Jan06Feb06Mar06Apr06May06Jun06Jul06Aug06Sep06Oct06Nov06Dec06Jan07Feb07Mar07Apr07May07Jun07Cycle Based Averages (18 or 24 Months)PercentINPO 100% Performance LevelUnit 1 - Monthly Cycle AvgUnit 2 - Monthly Cycle AvgYear End Goal LevelAction Level Industrial Safety -HatchIndustrial Safety Accident Rate - Plant Value0.00.20.40.60.81.01.21.41.61.82.0Jan06Feb06Mar06Apr06May06Jun06Jul06Aug06Sep06Oct06Nov06Dec06Jan07Feb07Mar07Apr07May07Jun07Cycle Based Averages (18 or 24 Months)Industrial Safety Accident Rate per 200,000 Hours WorkedINPO 100% Performance LevelIndustrial Safety Accident Rate (Cycle Based)Action Level NRC Performance Indicators -HatchNRC PI - Safety System Functional FailuresWhite > 6Green 6 0 1 2 3 4 5 6 7 8Safety System Functional FailuresJan-06Feb-06Mar-06Apr-06May-06Jun-06Jul-06Aug-06Sep-06Oct-06Nov-06Dec-06Jan-07Feb-07Mar-07Apr-07May-07Jun-0712 Month Rolling SumWhite > 6Green 6Unit 1 DataUnit 2 DataAction LevelNote: Yellow/Red No Threshold Unit 1 HPCI Unit 1 RCIC Unit 2 HPCI Unit 2 RCIC NRC Performance Indicators -HatchNRC PI - Mitigating System Performance Index, Emergency AC Power SystemGreen 1.0E-06White > 1.0E-06 OR PLE = YesYellow > 1.0E-05Red > 1.0E-041.0E-071.0E-061.0E-051.0E-041.0E-03Mitigating System Performance Index (MSPI) ValueJan-06Feb-06Mar-06Apr-06May-06Jun-06Jul-06Aug-06Sep-06Oct-06Nov-06Dec-06Jan-07Feb-07Mar-07Apr-07May-07Jun-07Rolling 36 Month ValuesGreen 1.0E-06White > 1.0E-06 OR PLE = YesYellow > 1.0E-05Red > 1.0E-04Unit 1 DataUnit 2 DataAction Level Emergency Diesel Generator NRC Performance Indicators -HatchNRC PI - Mitigating System Performance Index, High Pressure Injection SystemGreen 1.0E-06White > 1.0E-06 OR PLE = YesYellow > 1.0E-05Red > 1.0E-041.0E-071.0E-061.0E-051.0E-041.0E-03Mitigating System Performance Index (MSPI) ValueJan-06Feb-06Mar-06Apr-06May-06Jun-06Jul-06Aug-06Sep-06Oct-06Nov-06Dec-06Jan-07Feb-07Mar-07Apr-07May-07Jun-07Rolling 36 Month ValuesGreen 1.0E-06White > 1.0E-06 OR PLE = YesYellow > 1.0E-05Red > 1.0E-04Unit 1 DataUnit 2 DataAction Level Site Vice President Reorganization J. B. BEASLEY, JR. | | * Major Projects |
| Chairman,President & Chief Executive OfficerK. S. KING CFO & Vice PresidentCorporate Services M. M. CASTONGeneral Counsel, VP External Affairs & Corporate SecretaryW. L. BARGERON Plant ManagerJ. D. WILLIAMSSite Support ManagerW. D. DRINKARDQuality Assurance ManagerM. J. AJLUNISite Support Manager*SCS EmployeeSite Vice President Reorganization -January 2007 0407R. A. BELL*Human Res. Sr. VPSouthern CompanyD. R. MADISONVice President -HatchJ. R. JOHNSONVice President -FarleyT. E. TYNANVice President -VogtleT. L. YOUNGBLOODSite Support ManagerC. R. DEDRICKSON Plant Manager S. M. DOUGLAS Plant ManagerS. A. MITCHELLAsst. Corp. Sec./Exec. Asst. to Pres./Asst. Treas.P. R. BIZJAKSafety & Health ManagerC. D. COLLINSSupply Chain General ManagerVACANT *H. R. Director J. G. WOLFEComptroller & | | - Major Projects Underway |
| TreasurerJ. T. GASSERExecutive Vice President
| | - Recently Completed Projects |
| & Chief Nuclear OfficerA. F. THORNHILLManaging Atty. & Compliance ManagerC. H. PHILLIPSPublic Affairs ManagerJ. M. GODFREYEnvironmental Affairs ManagerW. H. LEEEmergency Planning SupervisorJ. A. MILLERSenior Vice PresidentNuclear DevelopmentD. P. BURFORDNuclear Fleet Security and Emergency Preparedness ManagerVogtle 3&4 BellefonteD. H. JONESEngineeringVice President W. L. BURMEISTERPlant Support ManagerA. HARRISEngineering Services ManagerG. K. McELROYEngineering Admin.
| | * Open Discussion Enclosure 2 |
| Services ManagerJ. B. PAPPASConfiguration Management ManagerB. E. HUNT Nuclear Fuels Manager B. J. GEORGE Nuclear Licensing ManagerW. B. THIGPENSecurity Supervisor/Access Authorization P. A. HURSTCorporate Concerns SupervisorL. M. STINSONFleet Operations SupportVice President Fleet Operations Support (proposed)Fleet Ops VPFleetOperations ManagerFleet Maintenance / WC ManagerFleet Outage Manager AssistantFleet Chem/ HP Manager Fleet Security &EP ManagerFleet Training & PI ManagerOperationsStaffMaintenance/ | | |
| WC StaffOutage StaffHP Staff ***ChemStaff *SecuritySupervisor EPSupervisorSecurity StaffEP Staff NFSCoordinatorAdmin AsstAdmin Asst *TrainingSupervisor *Instructors /Staff * / **PI Staff CAPCO* Transfer from Engineering** Transfer from Supply Chain*** Transfer from Environmental Site Engineering (proposed)
| | Plant Performance Enclosure 2 |
| Site VPPlant Mgr.Engineering Mgr. ***
| | |
| Site Suppt. Mgr.Design Engineering SupportModifications PMMS*Mech& Civil Design*Elec/I & C Design Nuc. Systems Programs BOP Systems Elec./I & C Admin. Asst Performance Improvement Principal Engineer -Licensing **
| | August 7, 2007 Unit 2 Reactor Trip |
| Equipment ReliabilityNew or Modified Org.
| | * I&C technician inadvertently tripped an overcurrent relay on the normal incoming feeder breaker for D 4160 VAC bus during calibration |
| *EFIN *Design Chg. (Corp) *Mech/Civil (Corp) | | * Loss of this bus resulted in a loss of 2 condensate pumps and 2 booster pumps, as well as a recirc runback |
| *Elec/I &C (Corp)**Dotted line reporting to Corporate Licensing *** Dotted line reporting to Chief Engineer Topical Updates SNM Update*Procedure revisions implemented to upgrade SNM accountability practices for in-core detectors following conclusion of SNM retrieval activities last year*Initial results indicated that 4 in-core detectors were not at the location specified*All 4 detectors were subseque ntly located and accounted for*Fuel pool legacy cleanup scheduled 3 rd/4 th quarter 2007 Tritium Sampling*Update on tritium graphs (T12, NW10, N008A)*Mactec Status -Phase 2 Report (2007)-Complete hydrology study (determine need)*Unit 2 CST pipe Replacement Update Tritium SamplingSAMPLE WELL T121.00E+031.00E+041.00E+051.00E+06 1.00E+07 F e b-0 3 M a y-0 3 A u g-03 Nov-03Mar-04 J un-04 S e p-0 4 J an-05 A pr-05Jul-05Oct-05Feb-06May-0 6 A u g-0 6 D e c-06 M ar-07Jun-07H3 pCi / LT12 Tritium SamplingTritium Outfall Sample (Subsurface drain N008A) 1.00E+031.00E+041.00E+0505/01/0 6 0 7/01/0 609/01/0 6 1 1/01/0 601/01/0 703/01/0 7 05/0 1/0 707/01/0 7H3 pCi / L1Y22N008A Tritium SamplingSAMPLE WELL (NW10)1.00E+043.00E+045.00E+047.00E+049.00E+041.10E+051.30E+051.50E+051.70E+0510/9/200611/9/200612/9/20061/9/20072/9/20073/9/20074/9/20075/9/20076/9/20077/9/20078/9/2007H3 pCi/ LNW10 1A RHR Pump Vibration*Vibration observed on 1A RHR pump only during two pump flow in Division 1 (Pumps A & C)*Occurs only in loop flow range of 4000 -6000 gpm*Cause of vibration has not been determined*Conceptual design being developed to increase natural frequency of the loop Alternative Source Term*Full scope AST analysis submitted to NRC 8/29/2006*Addresses control room inleakage concerns of Generic Letter 2003-01*Control room inleakage testing showed good results, well within interim licensing basis limits*Approval of AST submittal required by 5/31/2010*Significant interdisciplinary review at NRR is in progress*Planned and potential modifications to support AST are scheduled to complete by spring 2010 Staffing*Pipeline Replenishment-Strategies for hiring entry level workers and engineers-License classes*8 candidates to finish this December*10 SRO candidates started June 2007*16 candidates to start March 2008 | | * Plant scrammed on low reactor water level |
| *16 candidates to start March 2009
| | * All systems responded as designed; no actuation of HPCI or RCIC |
| *Average class size of 16-All other initial programs up and running (Chemistry, HP, Maintenance, etc.)
| | * Bus re-energized about 1.5 minutes from alternate source |
| Steam Chase Grating Analyses*Tool boxes were staged over grated vent openings between Reactor Building steam pipe chase and torus room*Hinged vent covers were strapped to vent grating on Unit 2*Tool boxes were removed from grating on both units and strap was removed on Unit 2 Tool Box Steam Chase Grating Analyses*Unit 1 limiting parameter is differential pressure on wall between torus room and ECCS pump rooms*Unit 1 analysis demonstrated that as-found vent paths provided adequate opening to meet differential pressure limits*Unit 2 limiting parameter is differential pressure on wall between torus room and reactor building ground level floor*Unit 2 analysis is at the preliminary results stage (not checked)*Preliminary results indicate that correcting for mass flow conservatisms will result in differential pressures within the analyzed limits TSC HVAC Availability*Event represents good incorporation of corrective actions from 2005 TSC white finding*EP and work planning personnel discussed work activity during planning phase*Work was placed on hold when first phase took longer than expected so issue could be discussed with NRC Region II personnel*Region II provided timely feedback regarding SNC's planned course of action Planned Major Projects Unit 1 Main Transformer Replacement*Unit 1 Main transformer replacement (2008)-Asset management/Life Cycle management-Replaces leased Alabama Power transformer with permanent transformer-Spare transformer delivered earl y 2008 for infant mortality issue-New transformer good to end of plant life Shroud Tie Rod Upper Restraints*Unit 1 Shroud tie rod upper restraint replacement (2008)*Unit 2 Shroud tie rod upper restraint replacement (2009)-Equipment reliability/safety-Replaces upper supports with larger components to remove susceptibility to IGSCC-Restores to BWRVIP criteria for repaired shrouds
| | * Breakdown in risk assessment process Enclosure 2 |
| -Eliminates need to re-inspect shroud horizontal welds-Licensing submittal for Unit 1 has been issued Condenser Bypass SpargerReplacement*Unit 1 and Unit 2 Condenser bypass spargerreplacements (Unit 1 in 2008. Unit 2 in 2009)-Replaces degraded bypass spargers-Spargerscurrently limit Operations use of bypass (i.e., length of time in Hot shutdown)
| | |
| Adjustable Speed Drives*Adjustable speed drives (Unit 1 in 2010 and Unit 2 in 2011)-Asset management/Life Cycle management-Replaces the Recirculation M-G se ts with Variable Frequency drives-Eliminates Recirculation flow step changes from fluid coupling positioner-Does not eliminate step changes from Bi-stable flow-Equipment reliability Feedwater SpargerEnd Pins*Feedwater spargerend pin replacement (Unit 1 in 2008, no Unit 2 installation)*Remote tooling will allow the installation of the Feedwater SpargerEnd Pins simultaneously with other work activities on the refueling floor Completed Major Projects Mark VI Turbine Controls*Unit 1 and Unit 2 Mark VI Turbine Controls-Completed on both units-Asset management/Life Cycle management-Installs triple redundant digital controls
| | Forced Loss Rate - Hatch Forced Loss Rate 12.0 11.0 10.0 9.0 8.0 7.0 Percent 6.0 5.0 4.0 3.0 2.0 1.0 0.0 Jan06 Feb06 M ar06 A pr06 M ay06 Jun06 Jul06 A ug06 Sep06 Oct06 No v06 Dec06 Jan07 Feb07 M ar07 A pr07 M ay07 Jun07 Cycle Based Averages (18 or 24 Months) |
| -Replaces obsolete Mark I control system Unit 2 Generator Exciter Controls*Unit 2 Generator Exciter Controls -Completed on Unit 2 -Unit 1 to complete in 2008)-Asset management/Life Cycle management-Replaces obsolete exciter with EX 2100 alterex Condenser Bellows Replacement*Unit 1 and Unit 2 Condenser Bellows Replacement-Completed on both units-Equipment reliability -Industry OE-Replaced bellows that were beyond design life Unit 1 Drywell Cooler Replacement*Unit 1 Drywell Cooler Replacement-Equipment reliability-2005 shutdown due to drywell leakage and containment integrity issue (leak from drywell into cooler) -Replaced all 16 Drywell cooler coils Open Discussion}} | | INPO 100% Performance Level Unit 1 - Monthly Cycle Avg Unit 2 - Monthly Cycle Avg Year End Goal Level Action Level Enclosure 2 |
| | |
| | Industrial Safety - Hatch Industrial Safety Accident Rate - Plant Value Industrial Safety Accident Rate per 2.0 1.8 1.6 1.4 1.2 1.0 200,000 Hours Worked 0.8 0.6 0.4 0.2 0.0 Jan06 Feb06 M ar06 A pr06 M ay06 Jun06 Jul06 A ug06 Sep06 Oct06 No v06 Dec06 Jan07 Feb07 M ar07 A pr07 M ay07 Jun07 Cycle Based Averages (18 or 24 Months) |
| | INPO 100% Performance Level Industrial Safety Accident Rate (Cycle Based) |
| | Action Level Enclosure 2 |
| | |
| | NRC Performance Indicators - Hatch NRC PI - Safety System Functional Failures 0 |
| | 1 Safety System Functional Failures 2 |
| | 3 Green 6 4 |
| | 5 6 |
| | 7 White > 6 8 |
| | Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 Oct-06 Nov-06 Dec-06 Jan-07 Feb-07 Mar-07 Apr-07 May-07 Jun-07 12 Month Rolling Sum Note: Yellow/Red No Threshold White > 6 Green 6 Unit 1 Data Unit 2 Data Action Level Enclosure 2 |
| | |
| | Unit 1 HPCI Enclosure 2 |
| | |
| | Unit 1 RCIC Enclosure 2 |
| | |
| | Unit 2 HPCI Enclosure 2 |
| | |
| | Unit 2 RCIC Enclosure 2 |
| | |
| | NRC Performance Indicators - Hatch NRC PI - Mitigating System Performance Index, Emergency AC Power System 1.0E-07 Green 1.0E-06 Mitigating System Performance Index 1.0E-06 White > 1.0E-06 OR PLE = Yes 1.0E-05 (MSPI) Value Yellow > 1.0E-05 1.0E-04 Red > 1.0E-04 1.0E-03 Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 Oct-06 Nov-06 Dec-06 Jan-07 Feb-07 Mar-07 Apr-07 May-07 Jun-07 Rolling 36 Month Values Green 1.0E-06 White > 1.0E-06 OR PLE = Yes Yellow > 1.0E-05 Red > 1.0E-04 Unit 1 Data Unit 2 Data Action Level Enclosure 2 |
| | |
| | Emergency Diesel Generator Enclosure 2 |
| | |
| | NRC Performance Indicators - Hatch NRC PI - Mitigating System Performance Index, High Pressure Injection System 1.0E-07 Green 1.0E-06 Mitigating System Performance Index 1.0E-06 White > 1.0E-06 OR PLE = Yes 1.0E-05 (MSPI) Value Yellow > 1.0E-05 1.0E-04 Red > 1.0E-04 1.0E-03 Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 Oct-06 Nov-06 Dec-06 Jan-07 Feb-07 Mar-07 Apr-07 May-07 Jun-07 Rolling 36 Month Values Green 1.0E-06 White > 1.0E-06 OR PLE = Yes Yellow > 1.0E-05 Red > 1.0E-04 Unit 1 Data Unit 2 Data Action Level Enclosure 2 |
| | |
| | Site Vice President Reorganization Enclosure 2 |
| | |
| | Site Vice President Reorganization - January 2007 J. B. BEASLEY, JR. |
| | Chairman, President & Chief Executive Officer S. A. MITCHELL Asst. Corp. Sec./Exec. |
| | Asst. to Pres./Asst. Treas. |
| | K. S. KING D. H. JONES M. M. CASTON J. T. GASSER R. A. BELL* J. A. MILLER CFO & Vice President Engineering General Counsel, Executive Vice President Human Res. Sr. VP Senior Vice President VP External Affairs & |
| | Corporate Services Vice President Corporate Secretary & Chief Nuclear Officer Southern Company Nuclear Development J. G. WOLFE B. J. GEORGE A. F. THORNHILL W. D. DRINKARD Vogtle 3&4 Comptroller & Managing Atty. & Quality Assurance L. M. STINSON Nuclear Licensing Treasurer Manager Compliance Manager Manager Fleet Operations Support Bellefonte Vice President C. D. COLLINS B. E. HUNT C. H. PHILLIPS Supply Chain Nuclear Fuels Public Affairs Manager General Manager Manager P. R. BIZJAK J. M. GODFREY D. P. BURFORD W. L. Nuclear Fleet Security Safety & Health BURMEISTER Environmental Affairs Manager Manager and Emergency Plant Support Preparedness Manager Manager VACANT |
| | * P. A. HURST H. R. Director A. HARRIS Corporate Concerns W. B. THIGPEN W. H. LEE Engineering Supervisor Security Emergency Planning Services Manager Supervisor/Access Supervisor Authorization G. K. McELROY Engineering Admin. |
| | Services Manager J. R. JOHNSON T. E. TYNAN D. R. MADISON J. B. PAPPAS Vice President - Farley Vice President - Vogtle Vice President - Hatch Configuration Management Manager W. L. BARGERON T. L. YOUNGBLOOD S. M. DOUGLAS M. J. AJLUNI Plant Manager Site Support Plant Manager Site Support Manager Manager C. R. DEDRICKSON J. D. WILLIAMS Plant Manager Site Support Manager 0407 |
| | *SCS Employee Enclosure 2 |
| | |
| | Fleet Operations Support (proposed) |
| | Fleet Ops VP Assistant Fleet Fleet Fleet Outage Fleet Chem / Fleet Security & Fleet Training & |
| | Operations Maintenance / |
| | Manager HP Manager EP Manager PI Manager Manager WC Manager Operations Maintenance/ NFS Outage Staff HP Staff *** Admin Asst Admin Asst |
| | * CAPCO Staff WC Staff Coordinator Security EP Training Chem Staff |
| | * PI Staff Supervisor Supervisor Supervisor * |
| | * Transfer from Engineering |
| | ** Transfer from Supply Chain |
| | *** Transfer from Environmental Security Staff EP Staff Instructors / |
| | Staff * / ** |
| | Enclosure 2 |
| | |
| | Site Engineering (proposed) |
| | New or Modified Org. |
| | Site VP Plant Mgr. Engineering Mgr. *** Site Suppt. Mgr. |
| | *** Dotted line reporting to Chief Performance Admin. Asst Engineer Improvement |
| | *EFIN |
| | *Design Chg. (Corp) |
| | *Mech/Civil (Corp) Principal Engineer - |
| | *Elec/I &C (Corp) |
| | Design Engineering Support Licensing ** |
| | **Dotted line Modifications PMMS Nuc. Systems Programs reporting to Corporate Licensing |
| | *Mech & Civil BOP Systems Elec./I & C Design |
| | *Elec/I & C Equipment Reliability Design Enclosure 2 |
| | |
| | Topical Updates Enclosure 2 |
| | |
| | SNM Update |
| | * Procedure revisions implemented to upgrade SNM accountability practices for in-core detectors following conclusion of SNM retrieval activities last year |
| | * Initial results indicated that 4 in-core detectors were not at the location specified |
| | * All 4 detectors were subsequently located and accounted for |
| | * Fuel pool legacy cleanup scheduled 3rd/4th quarter 2007 Enclosure 2 |
| | |
| | Tritium Sampling |
| | * Update on tritium graphs (T12, NW10, N008A) |
| | * Mactec Status |
| | - Phase 2 Report (2007) |
| | - Complete hydrology study (determine need) |
| | * Unit 2 CST pipe Replacement Update Enclosure 2 |
| | |
| | H3 pCi / L Fe b-03 1.00E+03 1.00E+04 1.00E+05 1.00E+06 1.00E+07 M |
| | ay |
| | -0 3 |
| | Au g-0 3 No v-03 M |
| | ar |
| | -0 4 |
| | Ju n-04 Se p-Tritium Sampling 04 Ja n-05 Ap r- 0 T12 5 Ju SAMPLE WELL T12 l- 0 5 |
| | O ct |
| | -0 5 |
| | Fe b-06 M |
| | ay |
| | -0 6 |
| | Au g-0 6 De c-06 M |
| | ar |
| | -0 7 |
| | Ju n-07 |
| | |
| | Tritium Sampling Tritium Outfall Sample (Subsurface drain N008A) 1.00E+05 H3 pCi / L 1.00E+04 1.00E+03 |
| | /0 6 /0 6 /0 6 /0 6 /0 7 /0 7 /0 7 /0 7 |
| | /0 1 /0 1 /0 1 /0 1 /0 1 /0 1 /0 1 /0 1 05 07 09 11 01 03 05 07 1Y22N008A Enclosure 2 |
| | |
| | Tritium Sampling SAMPLE WELL (NW10) 1.70E+05 1.50E+05 1.30E+05 H3 pCi/ L 1.10E+05 9.00E+04 7.00E+04 5.00E+04 3.00E+04 1.00E+04 10/9/2006 11/9/2006 12/9/2006 1/9/2007 2/9/2007 3/9/2007 4/9/2007 5/9/2007 6/9/2007 7/9/2007 8/9/2007 NW10 Enclosure 2 |
| | |
| | 1A RHR Pump Vibration |
| | * Vibration observed on 1A RHR pump only during two pump flow in Division 1 (Pumps A & C) |
| | * Occurs only in loop flow range of 4000 - 6000 gpm |
| | * Cause of vibration has not been determined |
| | * Conceptual design being developed to increase natural frequency of the loop Enclosure 2 |
| | |
| | Alternative Source Term |
| | * Full scope AST analysis submitted to NRC 8/29/2006 |
| | * Addresses control room inleakage concerns of Generic Letter 2003-01 |
| | * Control room inleakage testing showed good results, well within interim licensing basis limits |
| | * Approval of AST submittal required by 5/31/2010 |
| | * Significant interdisciplinary review at NRR is in progress |
| | * Planned and potential modifications to support AST are scheduled to complete by spring 2010 Enclosure 2 |
| | |
| | Staffing |
| | * Pipeline Replenishment |
| | - Strategies for hiring entry level workers and engineers |
| | - License classes |
| | * 8 candidates to finish this December |
| | * 10 SRO candidates started June 2007 |
| | * 16 candidates to start March 2008 |
| | * 16 candidates to start March 2009 |
| | * Average class size of 16 |
| | - All other initial programs up and running (Chemistry, HP, Maintenance, etc.) |
| | Enclosure 2 |
| | |
| | Steam Chase Grating Analyses |
| | * Tool boxes were staged over grated vent openings between Reactor Building steam pipe chase and torus room |
| | * Hinged vent covers were strapped to vent grating on Unit 2 |
| | * Tool boxes were removed from grating on both units and strap was removed on Unit 2 Enclosure 2 |
| | |
| | Tool Box Enclosure 2 |
| | |
| | Steam Chase Grating Analyses |
| | * Unit 1 limiting parameter is differential pressure on wall between torus room and ECCS pump rooms |
| | * Unit 1 analysis demonstrated that as-found vent paths provided adequate opening to meet differential pressure limits |
| | * Unit 2 limiting parameter is differential pressure on wall between torus room and reactor building ground level floor |
| | * Unit 2 analysis is at the preliminary results stage (not checked) |
| | * Preliminary results indicate that correcting for mass flow conservatisms will result in differential pressures within the analyzed limits Enclosure 2 |
| | |
| | TSC HVAC Availability |
| | * Event represents good incorporation of corrective actions from 2005 TSC white finding |
| | * EP and work planning personnel discussed work activity during planning phase |
| | * Work was placed on hold when first phase took longer than expected so issue could be discussed with NRC Region II personnel |
| | * Region II provided timely feedback regarding SNCs planned course of action Enclosure 2 |
| | |
| | Planned Major Projects Enclosure 2 |
| | |
| | Unit 1 Main Transformer Replacement |
| | * Unit 1 Main transformer replacement (2008) |
| | - Asset management/Life Cycle management |
| | - Replaces leased Alabama Power transformer with permanent transformer |
| | - Spare transformer delivered early 2008 for infant mortality issue |
| | - New transformer good to end of plant life Enclosure 2 |
| | |
| | Shroud Tie Rod Upper Restraints |
| | * Unit 1 Shroud tie rod upper restraint replacement (2008) |
| | * Unit 2 Shroud tie rod upper restraint replacement (2009) |
| | - Equipment reliability/safety |
| | - Replaces upper supports with larger components to remove susceptibility to IGSCC |
| | - Restores to BWRVIP criteria for repaired shrouds |
| | - Eliminates need to re-inspect shroud horizontal welds |
| | - Licensing submittal for Unit 1 has been issued Enclosure 2 |
| | |
| | Condenser Bypass Sparger Replacement |
| | * Unit 1 and Unit 2 Condenser bypass sparger replacements (Unit 1 in 2008. Unit 2 in 2009) |
| | - Replaces degraded bypass spargers |
| | - Spargers currently limit Operations use of bypass (i.e., length of time in Hot shutdown) |
| | Enclosure 2 |
| | |
| | Adjustable Speed Drives |
| | * Adjustable speed drives (Unit 1 in 2010 and Unit 2 in 2011) |
| | - Asset management/Life Cycle management |
| | - Replaces the Recirculation M-G sets with Variable Frequency drives |
| | - Eliminates Recirculation flow step changes from fluid coupling positioner |
| | - Does not eliminate step changes from Bi-stable flow |
| | - Equipment reliability Enclosure 2 |
| | |
| | Feedwater Sparger End Pins |
| | * Feedwater sparger end pin replacement (Unit 1 in 2008, no Unit 2 installation) |
| | * Remote tooling will allow the installation of the Feedwater Sparger End Pins simultaneously with other work activities on the refueling floor Enclosure 2 |
| | |
| | Completed Major Projects Enclosure 2 |
| | |
| | Mark VI Turbine Controls |
| | * Unit 1 and Unit 2 Mark VI Turbine Controls |
| | - Completed on both units |
| | - Asset management/Life Cycle management |
| | - Installs triple redundant digital controls |
| | - Replaces obsolete Mark I control system Enclosure 2 |
| | |
| | Unit 2 Generator Exciter Controls |
| | * Unit 2 Generator Exciter Controls |
| | - Completed on Unit 2 - Unit 1 to complete in 2008) |
| | - Asset management/Life Cycle management |
| | - Replaces obsolete exciter with EX 2100 alterex Enclosure 2 |
| | |
| | Condenser Bellows Replacement |
| | * Unit 1 and Unit 2 Condenser Bellows Replacement |
| | - Completed on both units |
| | - Equipment reliability - Industry OE |
| | - Replaced bellows that were beyond design life Enclosure 2 |
| | |
| | Unit 1 Drywell Cooler Replacement |
| | * Unit 1 Drywell Cooler Replacement |
| | - Equipment reliability |
| | - 2005 shutdown due to drywell leakage and containment integrity issue (leak from drywell into cooler) |
| | - Replaced all 16 Drywell cooler coils Enclosure 2 |
| | |
| | Open Discussion Enclosure 2}} |
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Category:Meeting Agenda
MONTHYEARML24317A0292024-11-13013 November 2024 November 13, 2024 Hatch Pre-Submittal Public Meeting Slides (NRC Staff Presentation) ML24313A1052024-11-13013 November 2024 November 13, 2024, Hatch Pre-Submittal Public Meeting Slides (Southern Co.) PMNS20241317, Notice of Public, pre-submittal Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss a Future License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch)2024-10-16016 October 2024 Notice of Public, pre-submittal Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss a Future License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch) ML24263A0822024-09-19019 September 2024 SLR Pre-Application Meeting - NRC Presentation Slides PMNS20241127, Pre-Submittal Meeting for License Renewal Application for Edwin I. Hatch Nuclear Plant, Units 1 & 2 Environmental2024-09-19019 September 2024 Pre-Submittal Meeting for License Renewal Application for Edwin I. Hatch Nuclear Plant, Units 1 & 2 Environmental PMNS20240906, Southern Nuclear Operating Company (SNC) Fleet Physical Barrier Exemptions2024-07-11011 July 2024 Southern Nuclear Operating Company (SNC) Fleet Physical Barrier Exemptions PMNS20240691, Southern Nuclear Operating Company (SNC) Fleet Physical Barrier Exemptions2024-05-21021 May 2024 Southern Nuclear Operating Company (SNC) Fleet Physical Barrier Exemptions PMNS20240479, Annual Assessment Meeting2024-04-0505 April 2024 Annual Assessment Meeting PMNS20231395, Notice of Public Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss Submitted License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch)2023-12-21021 December 2023 Notice of Public Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss Submitted License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch) PMNS20231383, Pre-submittal Meeting with Southern Nuclear Operating Company, Inc. (SNC) Regarding the Proposed Transition of the Vogtle Electric Generating Plant, Units 3 and 4 Ndqam Into the SNC Fleet QATR2023-12-11011 December 2023 Pre-submittal Meeting with Southern Nuclear Operating Company, Inc. (SNC) Regarding the Proposed Transition of the Vogtle Electric Generating Plant, Units 3 and 4 Ndqam Into the SNC Fleet QATR PMNS20231347, Notice of Public, pre-submittal Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss a Proposed Fleet License Amendment Request (LAR) for Farley, Hatch, and Vogtle2023-11-29029 November 2023 Notice of Public, pre-submittal Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss a Proposed Fleet License Amendment Request (LAR) for Farley, Hatch, and Vogtle PMNS20231273, Notice of Public Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss Submitted License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch)2023-11-0808 November 2023 Notice of Public Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss Submitted License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch) PMNS20231198, Closed Meeting - Security-Related - SNC Fleet Physical Barriers Exemptions.The Basis for the Closed Meeting Is the Discussion of Official Use Only - Security-Related Information2023-10-25025 October 2023 Closed Meeting - Security-Related - SNC Fleet Physical Barriers Exemptions.The Basis for the Closed Meeting Is the Discussion of Official Use Only - Security-Related Information PMNS20230831, Notice of Public, pre-submittal Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss a Future License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch)2023-07-13013 July 2023 Notice of Public, pre-submittal Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss a Future License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch) PMNS20230486, Notice of Public Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss Submitted License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch)2023-04-20020 April 2023 Notice of Public Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss Submitted License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch) PMNS20230285, Annual Assessment Meeting2023-03-22022 March 2023 Annual Assessment Meeting ML23079A2362023-03-20020 March 2023 Annual Assessment Meeting Presentation Slides PMNS20230217, Notice of Public Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss Submitted License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch)2023-03-0303 March 2023 Notice of Public Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss Submitted License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch) PMNS20220741, Notice of Public, pre-submittal Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss a Future License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch)2022-07-22022 July 2022 Notice of Public, pre-submittal Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss a Future License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch) PMNS20220607, Notice of Public, pre-submittal Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss a Future License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch)2022-06-0707 June 2022 Notice of Public, pre-submittal Meeting with Southern Nuclear Operating Company, Inc. (SNC) to Discuss a Future License Amendment Request (LAR) for the Edwin I. Hatch Nuclear Plant, Units 1 and 2 (Hatch) PMNS20220266, Annual Assessment Meeting2022-03-21021 March 2022 Annual Assessment Meeting ML22080A0192022-03-18018 March 2022 Annual Assessment Meeting Presentation PMNS20211197, Follow-Up Pre-Submittal Meeting Regarding a NFPA-805 Supplement License Amendment Request2021-09-16016 September 2021 Follow-Up Pre-Submittal Meeting Regarding a NFPA-805 Supplement License Amendment Request PMNS20211130, Follow-Up Pre-Submittal Meeting - Proposed License Amendment Request to Adopt TSTF-505 for Hatch, Units 1 and 22021-08-30030 August 2021 Follow-Up Pre-Submittal Meeting - Proposed License Amendment Request to Adopt TSTF-505 for Hatch, Units 1 and 2 PMNS20211015, Pre-Submittal Meeting with Southern Nuclear Operating Company, Inc. Planned License Amendment Request for Edwin I. Hatch Nuclear Plant, Units 1 and 22021-07-30030 July 2021 Pre-Submittal Meeting with Southern Nuclear Operating Company, Inc. Planned License Amendment Request for Edwin I. Hatch Nuclear Plant, Units 1 and 2 PMNS20210976, Pre-Submittal Meeting - Proposed Hatch TSTF-505 Lar(Provide Risk-Informed Extended Completion Times- RITSTF LAR 4b)2021-07-22022 July 2021 Pre-Submittal Meeting - Proposed Hatch TSTF-505 Lar(Provide Risk-Informed Extended Completion Times- RITSTF LAR 4b) PMNS20210429, Annual Assessment Meeting2021-04-27027 April 2021 Annual Assessment Meeting PMNS20210227, Notice of Meeting with Southern Nuclear Operating Company (SNC) Regarding a Proposed Quality Assurance (QA) Licensing Action for the SNC Fleet2021-03-25025 March 2021 Notice of Meeting with Southern Nuclear Operating Company (SNC) Regarding a Proposed Quality Assurance (QA) Licensing Action for the SNC Fleet ML20350B7092020-12-15015 December 2020 Pre-Submittal Meeting - Hatch Proposed National Fire Protection Association (NFPA)-805 Supplemental License Amendment Request PMNS20201237, Notice of Meeting with Southern Nuclear Operating Company, Inc. to Discuss Fleet Emergency Plan License Amendment Request2020-10-21021 October 2020 Notice of Meeting with Southern Nuclear Operating Company, Inc. to Discuss Fleet Emergency Plan License Amendment Request ML16071A3132016-03-14014 March 2016 Notice of Forthcoming Closed Meeting with Southern Nuclear Operating Company to Discuss the Replacement of Security Computer System at Edwin I. Hatch, Units 1 and 2 ML14076A1172014-03-17017 March 2014 Notice of Public Meeting to Discuss the NRC Reactor Oversight Process Annual Assessment for the Hatch Nuclear Station ML14066A3172014-03-0707 March 2014 20140476 Public Meeting Agenda by Rii - to Discuss the NRC Reactor Oversight Process Annual Assessment for the Hatch Nuclear Station ML13277A3822013-11-0404 November 2013 Notice of Forthcoming Meeting with Southern Nuclear on Polyethylene Pipe for Hatch Service Water Systems ML11250A1712011-09-14014 September 2011 Notice of Forthcoming Meeting with Petitioner Requesting Action Under 10 CFR 2.206 Regarding Immediate Suspension of the Operating Licenses of General Electric (GE) Mark 1 Boiling Water Reactors (Bwrs) ML11126A0962011-05-12012 May 2011 Notice of Meeting with Petitioner Requesting Action Under 10CFR2.206 Regarding Immediate Suspension of Operating Licenses of General Electric Mark 1 Boiling Water Reactors ML0810704462008-04-0909 April 2008 Annual Assessment Public Meeting, Slides ML0723505462007-08-23023 August 2007 08/15/2007 Public Meeting Summary - Enclosure 2 ML0536202702005-12-12012 December 2005 Enclosure 4 to Summary of Public Meeting with the Boiling Water Reactor Owner'S Group to Discuss 10 CFR Part 21 Report on Safety Limit 2.1.1.1 of NUREG 1433/34 ML0313206932003-05-0606 May 2003 Endangered Species Meeting with NMFS ML0300702372002-09-26026 September 2002 Sero/Nrc Meeting on Section 7 Consultations ML17037B8001978-03-17017 March 1978 Information Meeting on BWR Equipment Seismic Qualification ML17252A1551977-09-19019 September 1977 Summary of Meeting with Representatives of the Mark I Owner'S Group and GE to Discuss the Structural Acceptance Criteria for the Mark I Containment Ltp ML17252A1571977-09-14014 September 1977 Summary of Meeting Held with Representatives of the Mark I Owner'S Group to Discuss the Structural Acceptance Criteria for the Mark I Containment Long Term Program 2024-09-19
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML24313A1052024-11-13013 November 2024 November 13, 2024, Hatch Pre-Submittal Public Meeting Slides (Southern Co.) ML24317A0292024-11-13013 November 2024 November 13, 2024 Hatch Pre-Submittal Public Meeting Slides (NRC Staff Presentation) ML24295A1842024-10-16016 October 2024 SNC Slides - Hatch Public Pre-Submittal Meeting on Oct 30, 2024 - Change EDG SRs 3.8.1.2 & 3.8.1.5 Load Bands ML24278A0012024-09-19019 September 2024 SLR Environmental Pre-Application Meeting - Southern Nuclear Corporation Presentation Slides ML24263A0822024-09-19019 September 2024 SLR Pre-Application Meeting - NRC Presentation Slides ML24123A0502024-05-0202 May 2024 2023 Annual Assessment Public Meeting Summary Meeting Number 20240479 ML23361A1092024-01-0808 January 2024 SNC Slides for Public Meeting on 1-8-24 to Discuss Hatch LAR - Revise TS Table 1.1-1 (Modes) to Relax Required No. of Fully Tensioned RPV Head Closure Studs ML23361A0812024-01-0808 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR ML23079A2362023-03-20020 March 2023 Annual Assessment Meeting Presentation Slides ML22209A1872022-07-28028 July 2022 Pre-Submittal Meeting on August 1, 2022 Re Plant Hatch LAR: Relaxation of Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs (EPID L-2022-LRM-0052) (Slides) ML22167A1402022-06-22022 June 2022 Pre-Submittal Public Meeting Slides for Rewrite TS-3.7.2 License Amendment ML22080A0192022-03-18018 March 2022 Annual Assessment Meeting Presentation ML21225A0312021-08-31031 August 2021 Pre-Submittal Meeting - Request to Eliminate the Requirement for Automatic Main Steam Isolation on High Turbine Building Area Temperature ML21222A0342021-08-16016 August 2021 SNC Slides - Hatch TSTF-505 LAR - Pre-Submittal Meeting - 08-16-2021 ML20318A1032020-11-12012 November 2020 SNC ERO Staffing LAR RAI Responses ML20217L4312020-08-13013 August 2020 Edwin I Hatch, Units 1 and 2; and Vogtle Electric Plant, Units 1, 2, 3, and 4 - Meeting Slides a License Amendment Request for the Emergency Plan (EPID Nos L-2020-LLA-0150 and L-2020-LLA-051 ML20156A0012020-06-0404 June 2020 Slides - SNC Slides - Pre-Submittal Meeting on June 10, 2020 - Hatch EDG AOT Extension ML20101K6582020-04-10010 April 2020 Annual Assessment ML19025A0242019-01-25025 January 2019 SNC License Amendment Request for Proposed Changes to Emergency Response Organization Staffing and Augmentation ML18234A4712018-08-23023 August 2018 NRC-Pre Submittal Meeting TSTF-51 for Hatch and TSTF-51 and -471 for Farley - August 23, 2018 ML18136A8902018-05-16016 May 2018 May 21, 2018 Slides for Public Teleconference Regarding Changes to Hatch, Farley, and Vogtle TS 5.2.2.g ML18124A0052018-05-0404 May 2018 Summary of Public Meeting - Hatch Nuclear Plant Docket Nos. 50-321, 50-366 ML18066A0302018-03-0101 March 2018 Slides for March 1, 2018 Public Meeting ML17009A3832017-01-0909 January 2017 Degraded Voltage Pre-Submittal Public Meeting Slides ML16174A0272016-06-21021 June 2016 Revised NRC-SNC Hatch NFPA 805 Extension 06212016 ML16169A0612016-06-20020 June 2016 SNC Slides for 6-21-16 Public Meeting on Hatch NFPA 805 Extension ML15191A4872015-07-13013 July 2015 Unit 2: Plant Service Water Piping Replacement Using High Density Polyethylene (Hdpe) Piping Nrc/Snc Meeting July 13, 2015 ML15106A2042015-04-22022 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Slide Presentation ML14177A0862014-06-26026 June 2014 NRC Presentation Slides for Public Meeting with Southern on Seismic Reevaluation (GMRS) ML14176B2392014-06-26026 June 2014 Southern Nuclear Operating Company Seismic Reevaluation - GMRS NTTF 2.1 Presentation Slides ML14115A4102014-04-25025 April 2014 Summary of Public Meeting to Discuss Annual Assessment of Edwin I. Hatch Nuclear Plant, Units 1 and 2, in Vidalia, Georgia ML13112A2552013-04-22022 April 2013 Summary of Public Meeting to Discuss the Annual Assessment of Edwin I. Hatch Nuclear Plant with the Public for the Period of January 1, 2012, - December 31, 2012 ML13025A3012013-01-29029 January 2013 NRC Comments on Draft Integrated Plans, Hatch ML13015A2682012-12-17017 December 2012 Draft Submittal Order EA-12-049 - February 2013 FLEX Integrated Plan- Hatch ML12115A2572012-04-24024 April 2012 Summary of with Southern Nuclear Operating Co., Inc., to Discuss the Annual Assessment of Edwin I. Hatch for 2011 ML1111900612011-04-28028 April 2011 Summary of Public Meeting with Southern Nuclear Operating Company, Inc., to Discuss the Nrc'S Reactor Oversight Process and the Nrc'S Annual Assessment of Plant Safety Performance at Hatch for the Period of 01/01/210 - 12/31/2010 ML11090A0912011-04-0505 April 2011 Plant Hatch Fire Risk Monitoring ML1028105222010-10-0808 October 2010 September 29, 2010 Summary O Public Meeting with Farley to Discuss Corrective Actions Associated with Two White Regulatory Performance Public Meeting Summary ML1011304442010-04-23023 April 2010 Summary of Public Meeting to Discuss the Annual Assessment of Edwin I. Hatch for the Period of January 1, 2009 Through December 31, 2009 ML0910607322009-04-16016 April 2009 Summary of Meeting with Southern Nuclear Operating Co, Inc., to Provide Opportunities to Discuss Annual Assessment of Edwin I. Hatch for the Period of 01/01/2008 - 12/31/08 ML1019404512008-08-20020 August 2008 RA Drop-In Briefing Sheet - Hatch, Dated August 20, 2008 ML0810704462008-04-0909 April 2008 Annual Assessment Public Meeting, Slides ML0810704522008-04-0909 April 2008 Annual Assessment Public Meeting of Attendee List ML0723505462007-08-23023 August 2007 08/15/2007 Public Meeting Summary - Enclosure 2 ML0715902092007-05-31031 May 2007 Enclosure 7 - Definitions: SSE (Safe Shutdown Earthquake) & OBE (Operating Basis Earthquake) ML0717004662007-05-31031 May 2007 05/2007 Generation Planning Overview. ML0632800652006-11-14014 November 2006 Meeting Summary Handouts, Enclosure 2 (Tac Nos. MD2934 and MD2935) ML0611505512006-04-12012 April 2006 Slides for Annual Assessment Meeting Cy 2005 ML0536202702005-12-12012 December 2005 Enclosure 4 to Summary of Public Meeting with the Boiling Water Reactor Owner'S Group to Discuss 10 CFR Part 21 Report on Safety Limit 2.1.1.1 of NUREG 1433/34 ML0534700922005-11-29029 November 2005 Hatch, Units 1 & 2, Enclosure, Meeting Summary, Generic Letter 2003-01 2024-09-19
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24317A0292024-11-13013 November 2024 November 13, 2024 Hatch Pre-Submittal Public Meeting Slides (NRC Staff Presentation) ML24313A1052024-11-13013 November 2024 November 13, 2024, Hatch Pre-Submittal Public Meeting Slides (Southern Co.) ML24295A1842024-10-16016 October 2024 SNC Slides - Hatch Public Pre-Submittal Meeting on Oct 30, 2024 - Change EDG SRs 3.8.1.2 & 3.8.1.5 Load Bands ML24278A0012024-09-19019 September 2024 SLR Environmental Pre-Application Meeting - Southern Nuclear Corporation Presentation Slides ML24263A0822024-09-19019 September 2024 SLR Pre-Application Meeting - NRC Presentation Slides ML24123A0502024-05-0202 May 2024 2023 Annual Assessment Public Meeting Summary Meeting Number 20240479 ML23361A0812024-01-0808 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR ML23361A1092024-01-0808 January 2024 SNC Slides for Public Meeting on 1-8-24 to Discuss Hatch LAR - Revise TS Table 1.1-1 (Modes) to Relax Required No. of Fully Tensioned RPV Head Closure Studs ML23206A0412023-08-0202 August 2023 SNC Slides - Public Pre-Submittal Meeting on Aug 02, 2023 - Request for 45-Day Limited Extension of Risk Informed Completion Time (RICT) Program Backstop for TS 3.7.1 & 3.7.2 ML23088A2362023-03-28028 March 2023 SNC Presentation - Public Meeting - 03-28-2023 - Page from ML22231B055 ML23079A2362023-03-20020 March 2023 Annual Assessment Meeting Presentation Slides ML22209A1872022-07-28028 July 2022 Pre-Submittal Meeting on August 1, 2022 Re Plant Hatch LAR: Relaxation of Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs (EPID L-2022-LRM-0052) (Slides) ML22167A1402022-06-22022 June 2022 Pre-Submittal Public Meeting Slides for Rewrite TS-3.7.2 License Amendment ML22080A0192022-03-18018 March 2022 Annual Assessment Meeting Presentation ML21271A2022021-10-0505 October 2021 Pre-Submittal Meeting on October 5, 2021 - Hatch NFPA 805 Supplement LAR (SNC Slides) ML21225A0312021-08-31031 August 2021 Pre-Submittal Meeting - Request to Eliminate the Requirement for Automatic Main Steam Isolation on High Turbine Building Area Temperature ML21222A0342021-08-16016 August 2021 SNC Slides - Hatch TSTF-505 LAR - Pre-Submittal Meeting - 08-16-2021 ML21083A2872021-03-24024 March 2021 Pre-Submittal Meeting - Quality Assurance Topical Report Revision to Allow Application of Remote Assessment Techniques During Exigent Conditions ML21021A2462021-01-21021 January 2021 Slides - SNC Slides - Pre-Submittal Meeting on January 26, 2021 - Hatch NFPA-805 LAR ML20318A1032020-11-12012 November 2020 SNC ERO Staffing LAR RAI Responses ML20156A0012020-06-0404 June 2020 Slides - SNC Slides - Pre-Submittal Meeting on June 10, 2020 - Hatch EDG AOT Extension ML20101K6582020-04-10010 April 2020 Annual Assessment ML19123A3542019-05-0202 May 2019 Public Meeting Summary - Hatch Nuclear Plant, Docket Nos. 50-321 and 50-366 ML19025A0242019-01-25025 January 2019 SNC License Amendment Request for Proposed Changes to Emergency Response Organization Staffing and Augmentation ML18124A0052018-05-0404 May 2018 Summary of Public Meeting - Hatch Nuclear Plant Docket Nos. 50-321, 50-366 ML18066A0302018-03-0101 March 2018 Slides for March 1, 2018 Public Meeting ML17324A3462017-11-15015 November 2017 Meeting Slides for 11/15/2017, Public Meeting Between NRC and SNC Regarding Hatch License Amendment Request - Application of TSTF-423 to Drywell Spray Function Technical Specification End State ML16174A0272016-06-21021 June 2016 Revised NRC-SNC Hatch NFPA 805 Extension 06212016 ML16169A0612016-06-20020 June 2016 SNC Slides for 6-21-16 Public Meeting on Hatch NFPA 805 Extension ML16169A0602016-06-17017 June 2016 SNC Draft Letter to NRC Regarding Hatch NFPA 805 Extension ML15191A4872015-07-13013 July 2015 Unit 2: Plant Service Water Piping Replacement Using High Density Polyethylene (Hdpe) Piping Nrc/Snc Meeting July 13, 2015 ML15106A2042015-04-22022 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Slide Presentation ML14177A0862014-06-26026 June 2014 NRC Presentation Slides for Public Meeting with Southern on Seismic Reevaluation (GMRS) ML14176B2392014-06-26026 June 2014 Southern Nuclear Operating Company Seismic Reevaluation - GMRS NTTF 2.1 Presentation Slides ML13112A2552013-04-22022 April 2013 Summary of Public Meeting to Discuss the Annual Assessment of Edwin I. Hatch Nuclear Plant with the Public for the Period of January 1, 2012, - December 31, 2012 ML12115A2572012-04-24024 April 2012 Summary of with Southern Nuclear Operating Co., Inc., to Discuss the Annual Assessment of Edwin I. Hatch for 2011 ML1111900612011-04-28028 April 2011 Summary of Public Meeting with Southern Nuclear Operating Company, Inc., to Discuss the Nrc'S Reactor Oversight Process and the Nrc'S Annual Assessment of Plant Safety Performance at Hatch for the Period of 01/01/210 - 12/31/2010 ML1011304442010-04-23023 April 2010 Summary of Public Meeting to Discuss the Annual Assessment of Edwin I. Hatch for the Period of January 1, 2009 Through December 31, 2009 ML1020105352009-10-29029 October 2009 Tritium Meeting, Southern Nuclear, Hatch ML0910607322009-04-16016 April 2009 Summary of Meeting with Southern Nuclear Operating Co, Inc., to Provide Opportunities to Discuss Annual Assessment of Edwin I. Hatch for the Period of 01/01/2008 - 12/31/08 ML0810704462008-04-0909 April 2008 Annual Assessment Public Meeting, Slides ML0723505462007-08-23023 August 2007 08/15/2007 Public Meeting Summary - Enclosure 2 ML0717004662007-05-31031 May 2007 05/2007 Generation Planning Overview. ML0632800652006-11-14014 November 2006 Meeting Summary Handouts, Enclosure 2 (Tac Nos. MD2934 and MD2935) ML0622804942006-08-0909 August 2006 Hatch Tritium Public Meeting Power Point Slide Attachment ML0611505512006-04-12012 April 2006 Slides for Annual Assessment Meeting Cy 2005 ML0610704022006-04-12012 April 2006 Edwin I. Hatch Annual Assessment Meeting Cy 2005- Slides ML0535403442005-12-12012 December 2005 Submittal of Power Point Presentation Proposed Solutions to Part 21 on Safety Limit 2.1.1.1, NUREG-1433/34 ML0511501332005-04-13013 April 2005 Annual Assessment Meeting Cy 2004, Edwin I. Hatch Nuclear Plant - NRC Region II, Vidalia, Ga, April 13, 2005 ML0410406802004-04-0606 April 2004 Meeting Presentation for Edwin I. Hatch Annual Assessment Meeting, Reactor Oversight Program - Cy 2003 2024-09-19
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Text
Edwin I. Hatch Nuclear Plant NRC Region II Status Meeting August 15, 2007 Dennis Madison - Hatch Vice President Steve Douglas - Plant Manager Southern Nuclear Operating Company Enclosure 2
Agenda
- Plant Performance
- Site Vice President Reorganization
- Major Projects Underway
- Recently Completed Projects
- Open Discussion Enclosure 2
Plant Performance Enclosure 2
August 7, 2007 Unit 2 Reactor Trip
- I&C technician inadvertently tripped an overcurrent relay on the normal incoming feeder breaker for D 4160 VAC bus during calibration
- Loss of this bus resulted in a loss of 2 condensate pumps and 2 booster pumps, as well as a recirc runback
- Plant scrammed on low reactor water level
- All systems responded as designed; no actuation of HPCI or RCIC
- Bus re-energized about 1.5 minutes from alternate source
- Breakdown in risk assessment process Enclosure 2
Forced Loss Rate - Hatch Forced Loss Rate 12.0 11.0 10.0 9.0 8.0 7.0 Percent 6.0 5.0 4.0 3.0 2.0 1.0 0.0 Jan06 Feb06 M ar06 A pr06 M ay06 Jun06 Jul06 A ug06 Sep06 Oct06 No v06 Dec06 Jan07 Feb07 M ar07 A pr07 M ay07 Jun07 Cycle Based Averages (18 or 24 Months)
INPO 100% Performance Level Unit 1 - Monthly Cycle Avg Unit 2 - Monthly Cycle Avg Year End Goal Level Action Level Enclosure 2
Industrial Safety - Hatch Industrial Safety Accident Rate - Plant Value Industrial Safety Accident Rate per 2.0 1.8 1.6 1.4 1.2 1.0 200,000 Hours Worked 0.8 0.6 0.4 0.2 0.0 Jan06 Feb06 M ar06 A pr06 M ay06 Jun06 Jul06 A ug06 Sep06 Oct06 No v06 Dec06 Jan07 Feb07 M ar07 A pr07 M ay07 Jun07 Cycle Based Averages (18 or 24 Months)
INPO 100% Performance Level Industrial Safety Accident Rate (Cycle Based)
Action Level Enclosure 2
NRC Performance Indicators - Hatch NRC PI - Safety System Functional Failures 0
1 Safety System Functional Failures 2
3 Green 6 4
5 6
7 White > 6 8
Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 Oct-06 Nov-06 Dec-06 Jan-07 Feb-07 Mar-07 Apr-07 May-07 Jun-07 12 Month Rolling Sum Note: Yellow/Red No Threshold White > 6 Green 6 Unit 1 Data Unit 2 Data Action Level Enclosure 2
Unit 1 HPCI Enclosure 2
Unit 1 RCIC Enclosure 2
Unit 2 HPCI Enclosure 2
Unit 2 RCIC Enclosure 2
NRC Performance Indicators - Hatch NRC PI - Mitigating System Performance Index, Emergency AC Power System 1.0E-07 Green 1.0E-06 Mitigating System Performance Index 1.0E-06 White > 1.0E-06 OR PLE = Yes 1.0E-05 (MSPI) Value Yellow > 1.0E-05 1.0E-04 Red > 1.0E-04 1.0E-03 Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 Oct-06 Nov-06 Dec-06 Jan-07 Feb-07 Mar-07 Apr-07 May-07 Jun-07 Rolling 36 Month Values Green 1.0E-06 White > 1.0E-06 OR PLE = Yes Yellow > 1.0E-05 Red > 1.0E-04 Unit 1 Data Unit 2 Data Action Level Enclosure 2
Emergency Diesel Generator Enclosure 2
NRC Performance Indicators - Hatch NRC PI - Mitigating System Performance Index, High Pressure Injection System 1.0E-07 Green 1.0E-06 Mitigating System Performance Index 1.0E-06 White > 1.0E-06 OR PLE = Yes 1.0E-05 (MSPI) Value Yellow > 1.0E-05 1.0E-04 Red > 1.0E-04 1.0E-03 Jan-06 Feb-06 Mar-06 Apr-06 May-06 Jun-06 Jul-06 Aug-06 Sep-06 Oct-06 Nov-06 Dec-06 Jan-07 Feb-07 Mar-07 Apr-07 May-07 Jun-07 Rolling 36 Month Values Green 1.0E-06 White > 1.0E-06 OR PLE = Yes Yellow > 1.0E-05 Red > 1.0E-04 Unit 1 Data Unit 2 Data Action Level Enclosure 2
Site Vice President Reorganization Enclosure 2
Site Vice President Reorganization - January 2007 J. B. BEASLEY, JR.
Chairman, President & Chief Executive Officer S. A. MITCHELL Asst. Corp. Sec./Exec.
Asst. to Pres./Asst. Treas.
K. S. KING D. H. JONES M. M. CASTON J. T. GASSER R. A. BELL* J. A. MILLER CFO & Vice President Engineering General Counsel, Executive Vice President Human Res. Sr. VP Senior Vice President VP External Affairs &
Corporate Services Vice President Corporate Secretary & Chief Nuclear Officer Southern Company Nuclear Development J. G. WOLFE B. J. GEORGE A. F. THORNHILL W. D. DRINKARD Vogtle 3&4 Comptroller & Managing Atty. & Quality Assurance L. M. STINSON Nuclear Licensing Treasurer Manager Compliance Manager Manager Fleet Operations Support Bellefonte Vice President C. D. COLLINS B. E. HUNT C. H. PHILLIPS Supply Chain Nuclear Fuels Public Affairs Manager General Manager Manager P. R. BIZJAK J. M. GODFREY D. P. BURFORD W. L. Nuclear Fleet Security Safety & Health BURMEISTER Environmental Affairs Manager Manager and Emergency Plant Support Preparedness Manager Manager VACANT
- P. A. HURST H. R. Director A. HARRIS Corporate Concerns W. B. THIGPEN W. H. LEE Engineering Supervisor Security Emergency Planning Services Manager Supervisor/Access Supervisor Authorization G. K. McELROY Engineering Admin.
Services Manager J. R. JOHNSON T. E. TYNAN D. R. MADISON J. B. PAPPAS Vice President - Farley Vice President - Vogtle Vice President - Hatch Configuration Management Manager W. L. BARGERON T. L. YOUNGBLOOD S. M. DOUGLAS M. J. AJLUNI Plant Manager Site Support Plant Manager Site Support Manager Manager C. R. DEDRICKSON J. D. WILLIAMS Plant Manager Site Support Manager 0407
Fleet Operations Support (proposed)
Fleet Ops VP Assistant Fleet Fleet Fleet Outage Fleet Chem / Fleet Security & Fleet Training &
Operations Maintenance /
Manager HP Manager EP Manager PI Manager Manager WC Manager Operations Maintenance/ NFS Outage Staff HP Staff *** Admin Asst Admin Asst
- CAPCO Staff WC Staff Coordinator Security EP Training Chem Staff
- PI Staff Supervisor Supervisor Supervisor *
- Transfer from Engineering
- Transfer from Supply Chain
- Transfer from Environmental Security Staff EP Staff Instructors /
Staff * / **
Enclosure 2
Site Engineering (proposed)
New or Modified Org.
Site VP Plant Mgr. Engineering Mgr. *** Site Suppt. Mgr.
- Dotted line reporting to Chief Performance Admin. Asst Engineer Improvement
- Mech/Civil (Corp) Principal Engineer -
Design Engineering Support Licensing **
- Dotted line Modifications PMMS Nuc. Systems Programs reporting to Corporate Licensing
- Mech & Civil BOP Systems Elec./I & C Design
- Elec/I & C Equipment Reliability Design Enclosure 2
Topical Updates Enclosure 2
SNM Update
- Procedure revisions implemented to upgrade SNM accountability practices for in-core detectors following conclusion of SNM retrieval activities last year
- Initial results indicated that 4 in-core detectors were not at the location specified
- All 4 detectors were subsequently located and accounted for
- Fuel pool legacy cleanup scheduled 3rd/4th quarter 2007 Enclosure 2
Tritium Sampling
- Update on tritium graphs (T12, NW10, N008A)
- Phase 2 Report (2007)
- Complete hydrology study (determine need)
- Unit 2 CST pipe Replacement Update Enclosure 2
H3 pCi / L Fe b-03 1.00E+03 1.00E+04 1.00E+05 1.00E+06 1.00E+07 M
ay
-0 3
Au g-0 3 No v-03 M
ar
-0 4
Ju n-04 Se p-Tritium Sampling 04 Ja n-05 Ap r- 0 T12 5 Ju SAMPLE WELL T12 l- 0 5
O ct
-0 5
Fe b-06 M
ay
-0 6
Au g-0 6 De c-06 M
ar
-0 7
Ju n-07
Tritium Sampling Tritium Outfall Sample (Subsurface drain N008A) 1.00E+05 H3 pCi / L 1.00E+04 1.00E+03
/0 6 /0 6 /0 6 /0 6 /0 7 /0 7 /0 7 /0 7
/0 1 /0 1 /0 1 /0 1 /0 1 /0 1 /0 1 /0 1 05 07 09 11 01 03 05 07 1Y22N008A Enclosure 2
Tritium Sampling SAMPLE WELL (NW10) 1.70E+05 1.50E+05 1.30E+05 H3 pCi/ L 1.10E+05 9.00E+04 7.00E+04 5.00E+04 3.00E+04 1.00E+04 10/9/2006 11/9/2006 12/9/2006 1/9/2007 2/9/2007 3/9/2007 4/9/2007 5/9/2007 6/9/2007 7/9/2007 8/9/2007 NW10 Enclosure 2
1A RHR Pump Vibration
- Vibration observed on 1A RHR pump only during two pump flow in Division 1 (Pumps A & C)
- Occurs only in loop flow range of 4000 - 6000 gpm
- Cause of vibration has not been determined
- Conceptual design being developed to increase natural frequency of the loop Enclosure 2
Alternative Source Term
- Full scope AST analysis submitted to NRC 8/29/2006
- Control room inleakage testing showed good results, well within interim licensing basis limits
- Approval of AST submittal required by 5/31/2010
- Significant interdisciplinary review at NRR is in progress
- Planned and potential modifications to support AST are scheduled to complete by spring 2010 Enclosure 2
Staffing
- Strategies for hiring entry level workers and engineers
- License classes
- 8 candidates to finish this December
- 10 SRO candidates started June 2007
- 16 candidates to start March 2008
- 16 candidates to start March 2009
- All other initial programs up and running (Chemistry, HP, Maintenance, etc.)
Enclosure 2
Steam Chase Grating Analyses
- Tool boxes were staged over grated vent openings between Reactor Building steam pipe chase and torus room
- Hinged vent covers were strapped to vent grating on Unit 2
- Tool boxes were removed from grating on both units and strap was removed on Unit 2 Enclosure 2
Tool Box Enclosure 2
Steam Chase Grating Analyses
- Unit 1 limiting parameter is differential pressure on wall between torus room and ECCS pump rooms
- Unit 1 analysis demonstrated that as-found vent paths provided adequate opening to meet differential pressure limits
- Unit 2 limiting parameter is differential pressure on wall between torus room and reactor building ground level floor
- Unit 2 analysis is at the preliminary results stage (not checked)
- Preliminary results indicate that correcting for mass flow conservatisms will result in differential pressures within the analyzed limits Enclosure 2
TSC HVAC Availability
- Event represents good incorporation of corrective actions from 2005 TSC white finding
- EP and work planning personnel discussed work activity during planning phase
- Work was placed on hold when first phase took longer than expected so issue could be discussed with NRC Region II personnel
- Region II provided timely feedback regarding SNCs planned course of action Enclosure 2
Planned Major Projects Enclosure 2
Unit 1 Main Transformer Replacement
- Asset management/Life Cycle management
- Replaces leased Alabama Power transformer with permanent transformer
- Spare transformer delivered early 2008 for infant mortality issue
- New transformer good to end of plant life Enclosure 2
Shroud Tie Rod Upper Restraints
- Unit 1 Shroud tie rod upper restraint replacement (2008)
- Unit 2 Shroud tie rod upper restraint replacement (2009)
- Equipment reliability/safety
- Replaces upper supports with larger components to remove susceptibility to IGSCC
- Restores to BWRVIP criteria for repaired shrouds
- Eliminates need to re-inspect shroud horizontal welds
- Licensing submittal for Unit 1 has been issued Enclosure 2
Condenser Bypass Sparger Replacement
- Unit 1 and Unit 2 Condenser bypass sparger replacements (Unit 1 in 2008. Unit 2 in 2009)
- Replaces degraded bypass spargers
- Spargers currently limit Operations use of bypass (i.e., length of time in Hot shutdown)
Enclosure 2
Adjustable Speed Drives
- Adjustable speed drives (Unit 1 in 2010 and Unit 2 in 2011)
- Asset management/Life Cycle management
- Replaces the Recirculation M-G sets with Variable Frequency drives
- Eliminates Recirculation flow step changes from fluid coupling positioner
- Does not eliminate step changes from Bi-stable flow
- Equipment reliability Enclosure 2
Feedwater Sparger End Pins
- Feedwater sparger end pin replacement (Unit 1 in 2008, no Unit 2 installation)
- Remote tooling will allow the installation of the Feedwater Sparger End Pins simultaneously with other work activities on the refueling floor Enclosure 2
Completed Major Projects Enclosure 2
Mark VI Turbine Controls
- Unit 1 and Unit 2 Mark VI Turbine Controls
- Completed on both units
- Asset management/Life Cycle management
- Installs triple redundant digital controls
- Replaces obsolete Mark I control system Enclosure 2
Unit 2 Generator Exciter Controls
- Completed on Unit 2 - Unit 1 to complete in 2008)
- Asset management/Life Cycle management
- Replaces obsolete exciter with EX 2100 alterex Enclosure 2
Condenser Bellows Replacement
- Unit 1 and Unit 2 Condenser Bellows Replacement
- Completed on both units
- Equipment reliability - Industry OE
- Replaced bellows that were beyond design life Enclosure 2
Unit 1 Drywell Cooler Replacement
- Unit 1 Drywell Cooler Replacement
- Equipment reliability
- 2005 shutdown due to drywell leakage and containment integrity issue (leak from drywell into cooler)
- Replaced all 16 Drywell cooler coils Enclosure 2
Open Discussion Enclosure 2