Similar Documents at Hatch |
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Category:Meeting Agenda
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Notice of Meeting with Southern Nuclear Operating Company (SNC) Regarding a Proposed Quality Assurance (QA) Licensing Action for the SNC Fleet
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Notice of Meeting with Southern Nuclear Operating Company, Inc. to Discuss Fleet Emergency Plan License Amendment Request
ML16071A3132016-03-14014 March 2016
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Notice of Public Meeting to Discuss the NRC Reactor Oversight Process Annual Assessment for the Hatch Nuclear Station
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Notice of Forthcoming Meeting with Southern Nuclear on Polyethylene Pipe for Hatch Service Water Systems
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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)
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Notice of Meeting with Petitioner Requesting Action Under 10CFR2.206 Regarding Immediate Suspension of Operating Licenses of General Electric Mark 1 Boiling Water Reactors
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Annual Assessment Public Meeting, Slides
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08/15/2007 Public Meeting Summary - Enclosure 2
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Endangered Species Meeting with NMFS
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Sero/Nrc Meeting on Section 7 Consultations
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Information Meeting on BWR Equipment Seismic Qualification
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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
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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
2023-07-13
[Table view]
Category:Meeting Briefing Package/Handouts
MONTHYEARML23361A0812024-01-0808 January 2024
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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
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Annual Assessment
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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
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May 21, 2018 Slides for Public Teleconference Regarding Changes to Hatch, Farley, and Vogtle TS 5.2.2.g
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Summary of Public Meeting - Hatch Nuclear Plant Docket Nos. 50-321, 50-366
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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
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April 22, 2015, Meeting with Southern Nuclear Company, Slide Presentation
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Southern Nuclear Operating Company Seismic Reevaluation - GMRS NTTF 2.1 Presentation Slides
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NRC Presentation Slides for Public Meeting with Southern on Seismic Reevaluation (GMRS)
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
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NRC Comments on Draft Integrated Plans, Hatch
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Draft Submittal Order EA-12-049 - February 2013 FLEX Integrated Plan- Hatch
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Summary of with Southern Nuclear Operating Co., Inc., to Discuss the Annual Assessment of Edwin I. Hatch for 2011
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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
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September 29, 2010 Summary O Public Meeting with Farley to Discuss Corrective Actions Associated with Two White Regulatory Performance Public Meeting Summary
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Summary of Public Meeting to Discuss the Annual Assessment of Edwin I. Hatch for the Period of January 1, 2009 Through December 31, 2009
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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
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Annual Assessment Public Meeting, Slides
ML0810704522008-04-0909 April 2008
Annual Assessment Public Meeting of Attendee List
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08/15/2007 Public Meeting Summary - Enclosure 2
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05/2007 Generation Planning Overview.
ML0715902092007-05-31031 May 2007
Enclosure 7 - Definitions: SSE (Safe Shutdown Earthquake) & OBE (Operating Basis Earthquake)
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Meeting Summary Handouts, Enclosure 2 (Tac Nos. MD2934 and MD2935)
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Slides for Annual Assessment Meeting Cy 2005
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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
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Hatch, Units 1 & 2, Enclosure, Meeting Summary, Generic Letter 2003-01
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List of Meeting Attendees for the Annual Assessment Meeting Cy 2004, Edwin I. Hatch Nuclear Plant - NRC Region II, Vidalia, Ga, April 13, 2005
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,Kewaunee & Hatch Meeting Handout Re Planned License Amendment Requests Using Alternate Source Term
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Praire Island Meeting Handout Re Planned License Amendment Requests Using Alternate Source Term
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Examiner - Vendor Matrix with Phone Number
ML0327206112003-09-22022 September 2003
Exam Process
ML0309900642003-04-0909 April 2003
Annual Assessment Meeting - Hatch Nuclear Power Plant
2024-01-08
[Table view]
Category:Slides and Viewgraphs
MONTHYEARML23361A0812024-01-0808 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
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08/15/2007 Public Meeting Summary - Enclosure 2
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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
ML0610704022006-04-12012 April 2006
Edwin I. Hatch Annual Assessment Meeting Cy 2005- Slides
ML0611505512006-04-12012 April 2006
Slides for Annual Assessment Meeting Cy 2005
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
ML0333003292003-11-19019 November 2003
Summary of Meeting Held on November 3, 2003, Between NOAA Fisheries, U.S.Corps of Engineers, and U.S. Nuclear Regulatory Commission to Discuss Section 7 Consultations Under the Endangered Species Act
ML0332202492003-11-0303 November 2003
NRC Usace, NOAA Fisheries Meeting, November 3, 2003, Southeast Regional Office, NOAA Fisheries (Encl.2)
ML0403502122003-08-13013 August 2003
DRS Open Items Status
2024-01-08
[Table view] |
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
