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Category:Meeting Briefing Package/Handouts
MONTHYEARML23348A3572023-12-14014 December 2023
Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting
ML22231B1762022-09-0707 September 2022
Pre-Submittal Meeting - 10 CFR 50.69 and TSTF-505 License Amendment Requests (EPID L-2022-LRM-0065) (Slides)
ML21314A0642021-11-10010 November 2021
Pre-submittal Presentation: River Bend Nuclear Station, Unit 1 Relief Request to Adopt Performance Based Testing for Pressure Isolation Valves (Pivs); November 10, 2021
ML21309A0622021-11-0909 November 2021
NRC Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting
ML21312A0342021-11-0909 November 2021
Combined Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting
ML21266A1122021-08-16016 August 2021
August 16 Predecisional Enforcement Conference Redacted License Slide - September 22, 2021
ML21200A1792021-07-31031 July 2021
Scale/Melcor Non-LWR Source Term Demonstration Project - High Temperature Gas-Cooled Reactor
ML21013A0022021-01-25025 January 2021
Public Meeting Slides - River Bend Waste LAR Pre-Sub 1-25-2021
ML20269A3452020-09-28028 September 2020
Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides
ML20262H2662020-09-22022 September 2020
Pre-Submittal Meeting - Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Offsite Exercise Requirements Due to COVID-19 Pandemic
ML19346C9042019-12-17017 December 2019
Pre-Submittal Meeting - Proposed License Amendment Request - Incorporate Tornado Missile Risk Evaluator (TMRE) Into the River Bend Licensing Basis December 17, 2019
ML18275A2722018-09-13013 September 2018
Enclosure 2 - River Bend Station Spent Fuel Pool Criticality Analysis of Boraflex Storage Racks with NETCO-SNAP-IN Rack Inserts
ML18283B9402018-09-13013 September 2018
Revised Proprietary Identification for Gnf Pre-Submittal Meeting Presentation on River Bend Station Spent Fuel Pool Criticality Analysis of Boraflex Storage Racks with NETCO-SNAP-IN Rack Inserts
ML18228A7432018-08-23023 August 2018
Pre-Submittal Meeting Proposed License Amendment Request Spent Fuel Pool Neutron Absorber Inserts and Criticality Safety Analysis
ML18107A7642018-04-17017 April 2018
Additional Topic for the April 18, 2018 Public Telephone Conference with Entergy on River Bend Station, Unit 1 License Renewal Application
ML18107A3342018-04-10010 April 2018
Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides
ML18099A2362018-04-0909 April 2018
Topics for the April 10, 2018 Public Call with Entergy on River Bend Station, Unit 1 License Renewal Application
ML17283A3102017-10-12012 October 2017
10/12/2017, Meeting Slide Regarding NRC Pre-application Meeting River Bend Station Spent Fuel Pool Inserts and Criticality Safety Analysis
ML17293A5032017-09-12012 September 2017
License Renewal Application Review Public Scoping Meeting 9-19-2017
ML17142A3552017-05-25025 May 2017
05/25/2017 River Bend Station (RBS) License Renewal Application (LRA) NRC Presentation
ML17074A3522017-03-29029 March 2017
3/29/2017, Entergy Presentation for River Bend Station Pre-submittal Meeting for Control Building Air Conditioning New Technical Specification License Amendment
ML16119A3422016-04-28028 April 2016
Summary of Regulatory Conference to Discuss Safety Significance of River Bend Station Control Building Chilled Water System Apparent Violation
ML16092A0342016-04-0101 April 2016
Evaluation of RBS Remote Shutdown Panel Rooms
ML16092A0292016-04-0101 April 2016
Technical Paper on Loss of AC Bus Initiator for RBS
ML16092A0362016-04-0101 April 2016
Calc Control Sheet Attachment 22 ENTR-078-CALC-003, Rev 4 Page 216 of 219
ML16092A0322016-04-0101 April 2016
PRA Change Summary for Reg Conf Letter 3-22 Final
ML16092A0302016-04-0101 April 2016
Response to NRC Concern with Temperature Effects on Safety-Related Electronics in Main Control Room
ML16092A0372016-04-0101 April 2016
Potential Greater than Green (a)(4) Violation
ML12275A5492012-10-0101 October 2012
Summary of Meeting with Entergy Operations, Inc., to Discuss the Performance of the Subject Facilities, Recent Organizational Changes, and Current Regulatory Issues
ML1117906392011-06-28028 June 2011
Summary of Meeting with Entergy Operations Inc
ML1117901522011-05-20020 May 2011
Summary of Annual Performance Assessment Meeting for River Bend Station
ML1029403512010-10-19019 October 2010
10/182010 Summary of Public Meeting with Entergy Operations to Discuss Initiatives to Improve Plant Reliability
ML0935201272009-12-18018 December 2009
Nrc/Entergy Operations, Inc., Management Meeting
ML0920907732009-07-28028 July 2009
July 28, 2009 Meeting Slides from Entergy Operations(River Bend Station) to Discuss Ri ISI
ML0812801922008-05-0606 May 2008
04-29-2008 River Bend End-of-Cycle Meeting Summary
ML0712005272007-04-30030 April 2007
Nrc/Entergy Operations, Inc. Management Meeting to Discuss the Performance of Arkansas Nuclear One, Cooper, Grand Gulf, River Bend and Waterford, Unit 3
ML0712005252007-04-30030 April 2007
Summary of Annual Performance Assessment Meeting for River Bend Station
ML0514501982005-05-25025 May 2005
Summary of Annual Performance Assessment Meeting for River Bend Station
ML0510304092005-04-13013 April 2005
Summary of Meeting with Entergy Operations, Inc. River Bend Station Performance and Improvement Initiatives
ML0328101732003-09-25025 September 2003
Entergy Operations, Inc.'S Presentation for Management Meeting Held on 09/25/2003. See ML032801514 for Cover Letter and Attendance List
ML0323705292003-08-22022 August 2003
Summary of Nrc/Entergy Operations, Inc. Management Meeting
ML0229700492002-10-0808 October 2002
Handouts of Meeting with Entergy Operations, Inc., Re Alternative Souce Term License Amendment Application
ML0208107562002-03-19019 March 2002
Operator Licensing Workshop Meeting Summary
2023-12-14
[Table view]
Category:Slides and Viewgraphs
MONTHYEARML23348A3572023-12-14014 December 2023
Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting
ML22231B1762022-09-0707 September 2022
Pre-Submittal Meeting - 10 CFR 50.69 and TSTF-505 License Amendment Requests (EPID L-2022-LRM-0065) (Slides)
ML22164A8012022-06-13013 June 2022
Entergy Fleet (GGNS, RBS, and WF-3) - Code Case N-752 RR 6-14-22 Pre-Submittal Public Meeting Presentation Slides
ML21319A2452021-11-15015 November 2021
Natrium Energy Island Decoupling Strategy - 11-17-2021
ML21314A0642021-11-10010 November 2021
Pre-submittal Presentation: River Bend Nuclear Station, Unit 1 Relief Request to Adopt Performance Based Testing for Pressure Isolation Valves (Pivs); November 10, 2021
ML21306A3162021-11-0909 November 2021
Digital IC Presentation 11/09/2021
ML21309A0622021-11-0909 November 2021
NRC Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting
ML21312A0342021-11-0909 November 2021
Combined Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting
ML21266A1122021-08-16016 August 2021
August 16 Predecisional Enforcement Conference Redacted License Slide - September 22, 2021
ML21200A1792021-07-31031 July 2021
Scale/Melcor Non-LWR Source Term Demonstration Project - High Temperature Gas-Cooled Reactor
ML21013A0022021-01-25025 January 2021
Public Meeting Slides - River Bend Waste LAR Pre-Sub 1-25-2021
ML20269A3452020-09-28028 September 2020
Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides
ML20262H2662020-09-22022 September 2020
Pre-Submittal Meeting - Request for One-Time Exemption from 10 CFR 50, Appendix E Biennial Emergency Preparedness Evaluated Offsite Exercise Requirements Due to COVID-19 Pandemic
ML19346C9042019-12-17017 December 2019
Pre-Submittal Meeting - Proposed License Amendment Request - Incorporate Tornado Missile Risk Evaluator (TMRE) Into the River Bend Licensing Basis December 17, 2019
ML18283B9402018-09-13013 September 2018
Revised Proprietary Identification for Gnf Pre-Submittal Meeting Presentation on River Bend Station Spent Fuel Pool Criticality Analysis of Boraflex Storage Racks with NETCO-SNAP-IN Rack Inserts
ML18275A2722018-09-13013 September 2018
Enclosure 2 - River Bend Station Spent Fuel Pool Criticality Analysis of Boraflex Storage Racks with NETCO-SNAP-IN Rack Inserts
ML18228A7432018-08-23023 August 2018
Pre-Submittal Meeting Proposed License Amendment Request Spent Fuel Pool Neutron Absorber Inserts and Criticality Safety Analysis
ML18107A3342018-04-10010 April 2018
Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides
ML18075A1232018-03-20020 March 2018
Entergy Nuclear Operations - March 20, 2018, Presentation Slides for Surveillance Frequency Control Program, UFSAR Change Considerations
ML17283A3102017-10-12012 October 2017
10/12/2017, Meeting Slide Regarding NRC Pre-application Meeting River Bend Station Spent Fuel Pool Inserts and Criticality Safety Analysis
ML17293A5032017-09-12012 September 2017
License Renewal Application Review Public Scoping Meeting 9-19-2017
ML17249A2502017-09-0606 September 2017
Updated Entergy Handout for River Bend and NRC Public Conference Call on September 11, 2017, to Discuss Technical Specification Task Force Traveler 542
ML17187A0462017-08-0202 August 2017
License Renewal Pre- Application Coordination Meeting 1 River Bend Nuclear Generating Station Unit 1 - Summary of Meeting Held on April 25, 2017
ML17187A0272017-08-0202 August 2017
License Renewal Application, NRC Presentation Summary of Meeting Held on May 25, 2017
ML17142A3552017-05-25025 May 2017
05/25/2017 River Bend Station (RBS) License Renewal Application (LRA) NRC Presentation
ML17074A3522017-03-29029 March 2017
3/29/2017, Entergy Presentation for River Bend Station Pre-submittal Meeting for Control Building Air Conditioning New Technical Specification License Amendment
ML16119A3422016-04-28028 April 2016
Summary of Regulatory Conference to Discuss Safety Significance of River Bend Station Control Building Chilled Water System Apparent Violation
ML12275A5492012-10-0101 October 2012
Summary of Meeting with Entergy Operations, Inc., to Discuss the Performance of the Subject Facilities, Recent Organizational Changes, and Current Regulatory Issues
ML1134706402011-12-13013 December 2011
Predecisional Enforcement Conference Summary NRC Investigation Report 4-2010-064
ML1117901522011-05-20020 May 2011
Summary of Annual Performance Assessment Meeting for River Bend Station
ML1032601252010-11-19019 November 2010
Presentation Slides for the RBS Decommissioning Pec Public Meeting
ML1029403512010-10-19019 October 2010
10/182010 Summary of Public Meeting with Entergy Operations to Discuss Initiatives to Improve Plant Reliability
ML0935201272009-12-18018 December 2009
Nrc/Entergy Operations, Inc., Management Meeting
ML0920907732009-07-28028 July 2009
July 28, 2009 Meeting Slides from Entergy Operations(River Bend Station) to Discuss Ri ISI
ML0719002022007-07-0909 July 2007
Summary of Meeting with Entergy Operations, Inc., Regarding Discussion of River Bend Station Plans for Improving Human Performance and Corrective Action Program
ML0617802712006-03-0707 March 2006
RIC 2006 Presentation - T2E - Vincent Coulehan - Use of Operating Experience (Regulator/Operator/Licensee)
ML0615902322006-03-0707 March 2006
2006/03/07- - RIC 2006 Presentation - T1F - Garry G. Young - License Renewal
ML0615901582006-03-0707 March 2006
03/07/2006 - RIC 2006 Presentation - T1E - John F. Mccann - License Renewal
ML0607204302006-03-0101 March 2006
March 1, 2006 Public Meeting Slides for Proposed Generic Letter Post-Fire Safe-Shutdown Circuit Analysis Spurious Actuations.
ML0532206852005-11-17017 November 2005
Nrc/Entergy Operations, Inc. Management Meeting 11/10/05
ML0514501982005-05-25025 May 2005
Summary of Annual Performance Assessment Meeting for River Bend Station
ML0510304092005-04-13013 April 2005
Summary of Meeting with Entergy Operations, Inc. River Bend Station Performance and Improvement Initiatives
ML0422602762004-08-12012 August 2004
Meeting Summary of the August 8, 2004 Public Workshop - Region IV Operator Licensing Feedback
ML0323705292003-08-22022 August 2003
Summary of Nrc/Entergy Operations, Inc. Management Meeting
ML0318902592003-07-0202 July 2003
Summary of Regulatory Conference with Entergy Operations, Inc. River Bend Station
ML0314003602003-04-17017 April 2003
Meeting Summary for Annual Performance Assessment for River Bend Station
2023-12-14
[Table view] |
Text
1 RIVER BEND STATION PRE-SUBMITTAL MEETING Proposed License Amendment Request Spent Fuel Pool Neutron Absorber Inserts And Criticality Safety Analysis August 23, 2018
2 OPENING REMARKS / AGENDA Brian Jones Licensing Engineer River Bend Station
3 Purpose
- Discuss River Bend Stations plan to install NETCOs SNAP-IN neutron absorber inserts into the spent fuel pool storage cells
- Describe the methodology for a new spent fuel pool criticality safety analysis, crediting the inserts and supporting the license amendment request
- Review the proposed license changes to credit the inserts
- Seek feedback from the NRC staff before making the submittal
4 Agenda (Non-Proprietary Session)
Introductions Brian Jones - Licensing Engineer RBS Background / Objective Don Lomax - Entergy Project Manager SNAP-IN Inserts Overview Don Lomax - Entergy Project Manager Criticality Analysis Overview Brian Holman - Entergy Corporate Fuels Chris Kmiec - Global Nuclear Fuel (GNF)
Implementation Strategy Don Lomax - Entergy Project Manager Proposed License Changes Don Lomax - Entergy Project Manager Questions All
5 INTRODUCTIONS Brian Jones Licensing Engineer River Bend Station
6 BACKGROUND / OBJECTIVE Don Lomax Project Manager Entergy Major Fleet Projects
7 Background / Objective
- Current RBS spent fuel pool criticality analysis credits Boraflex neutron absorber material
- Contracted with Curtiss-Wright Nuclear Division to design, manufacture, and install neutron absorber inserts
- Contracted with Global Nuclear Fuel-Americas to prepare new criticality analysis which removes credit for Boraflex and credits inserts
- Installation and long term monitoring of neutron absorber inserts satisfies commitments made to NRC as part of the license renewal application to remove dependence on Boraflex
8 SNAP-IN INSERTS OVERVIEW Don Lomax Project Manager Entergy Major Fleet Projects
9 NETCO-SNAP-IN Inserts
- Simple design; L-shaped (chevron), full length inserts TM
- Robust material, Rio Tinto Alcans Boralcan ; a metal matrix of aluminum alloy with nuclear grade B4C
- Similar inserts installed in BWR racks for Exelons LaSalle, Peach Bottom and Quad Cities
- Nominal B4C content = 21 vol%
- Minimum certified B10 areal density = 0.0129 g B-10/cm2
10 NETCO-SNAP-IN Inserts
- Monitoring program will be implemented:
- Complies with NEI 16-03, Rev. 0, Guidance for Monitoring of Fixed Neutron Absorbers in Spent Fuel Pools
- Includes 3 different types of test coupons installed in the spent fuel pool (general, bend, and galvanic) and examined periodically
- Inspections may include visual, dimensional, neutron attenuation, corrosion, stress relaxation, dependent on coupon type
- Includes full insert in-situ and removal inspections
- Visual for physical deformities (in-situ and removal)
- Thickness and retention force (removal only)
11 CRITICALITY ANALYSIS OVERVIEW Brian Holman Entergy Corporate Fuels Engineering Chris Kmiec Global Nuclear Fuel (GNF)
12 Criticality Analysis Overview
- Consistent with most current NRC and industry guidance
- DSS-ISG-2010-01, Rev. 0, Staff Guidance Regarding the Nuclear Criticality Safety Analysis for Spent Fuel Pools
- NEI 12-16, Rev. 3, Guidance for Performing Criticality Analyses of Fuel Storage at Light-Water Reactor Power Plants
- No credit for Boraflex neutron absorber; only credit for inserts
- Main codes were TGBLA-06 and MCNP-05P
- Standard BWR cold, in-core k peak reactivity methodology
- No axial blankets credited
- Established maximum in-core k so that kmax < 0.95 for normal and credible accident conditions
13 Criticality Analysis Overview
- Addressed current fuel type (GNF2), future fuel product (GNF3),
and all legacy fuel
- Uniform pool loading - all fuel storage locations loaded with an insert and the bundle with the highest rack efficiency
- Misload of fuel outside the rack was evaluated
- Missing insert evaluated to address removal during fuel movement and during periodic removal for inspection
- More detail to be provided in proprietary session
14 IMPLEMENTATION STRATEGY Don Lomax Project manager Entergy Major Fleet Projects
15 Implementation Strategy
- Inserts installed through 10 CFR 50.59 process but not credited until license amendment request approval from NRC
- Installation scheduled June - October 2019
- License amendment request submission end of 3rd quarter 2018
- Request 12 month review from NRC
16 PROPOSED LICENSE CHANGES PROPOSED LICENSE CHANGES Don Lomax Project Manager Entergy Major Fleet Projects
17 Proposed License Changes
- Add new item to specify maximum fuel enrichment and k-infinity (to bring in alignment with Standard Technical Specifications)
- Add new item to state that neutron absorbing inserts are installed
- Add new section to describe the Spent Fuel Storage Rack Neutron Absorber Monitoring Program that will be implemented in accordance with NEI-16-03, Guidance for Monitoring of Fixed Neutron Absorbers in Spent Fuel Pools
18 Proposed License Changes (Draft) 4.3.1 Criticality 4.3.1.1 The spent fuel storage racks are designed and shall be maintained with:
- a. Fuel assemblies having a maximum k-infinity of 1.28 in the normal reactor core configuration at cold conditions and a maximum average U-235 enrichment of 4.9 weight percent;
- b. keff 0.95 if fully flooded with unborated water, which includes an allowance for uncertainties as described in Section 9.1 of the USAR;
- c. A nominal fuel assembly center to center storage spacing of 7 inches within rows and 12.25 inches between rows in the low density storage racks in the upper containment pool; and
- d. A nominal fuel assembly center to center storage spacing of 6.28 inches within a rack and 8.5 inches between cell centers of adjacent racks, with a neutron poison material insert within the storage cells, in the high density storage racks in the spent fuel storage facility in the Fuel Building.
19 Proposed License Changes (Draft) 5.5.15 Spent Fuel Storage Rack Neutron Absorber Monitoring Program This program provides controls for monitoring the condition of the neutron absorber used in the spent fuel pool storage racks to verify the Boron-10 areal density is consistent with the assumptions in the spent fuel poo criticality analysis. The program shall be in accordance with NEI 16-03-A, Guidance for Monitoring of Fixed Neutron Absorbers in Spent Fuel Pools, Revision 0, May 2017.
20 QUESTIONS
21 CLOSING COMMENTS Brian Jones Licensing Engineer River Bend Station
22 END OF PUBLIC (NON-PROPRIETARY) MEETING
