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Category:Letter
MONTHYEARIR 05000458/20230402024-01-18018 January 2024 95001 Supplemental Inspection Supplemental Report 05000458/2023040 and Follow-Up Assessment Letter RBG-48271, Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk2024-01-12012 January 2024 Supplement to License Amendment Request to Adopt Risk Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times RITSTF Initiative 4b and Application to Adopt 10 CFR 50.69, Risk ML24012A1962024-01-12012 January 2024 Response to 2nd Round Request for Additional Information Concerning Relief Request Number EN-RR-22-001 Proposed Alternative to Use ASME Code Case N-752, Risk-Informed Categorization and ML24011A1742024-01-11011 January 2024 Security Baseline Inspection Report (Cover Letter) ML23349A1672023-12-21021 December 2023 Request for Withholding Information from Public Disclosure ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology Slides and Affidavit for Pre-Submittal Meeting ML23340A1592023-12-13013 December 2023 Entergy Operations, Inc. - Entergy Fleet Project Manager Assignment ML23352A0292023-12-13013 December 2023 Entergy - 2024 Nuclear Energy Liability Evidence of Financial Protection IR 05000458/20230102023-12-12012 December 2023 Biennial Problem Identification and Resolution Inspection Report 05000458/2023010 RBG-48267, Reply to a Notice of Violation, NRC Inspection Report 05000458/20230032023-12-0707 December 2023 Reply to a Notice of Violation, NRC Inspection Report 05000458/2023003 ML23333A1362023-11-29029 November 2023 Supplement to Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23325A1432023-11-21021 November 2023 Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation ML23310A0322023-11-13013 November 2023 Integrated Inspection Report 05000458/2023003 IR 05000458/20230032023-11-13013 November 2023 Integrated Inspection Report 05000458/2023003 ML23311A2082023-11-0909 November 2023 Reassignment of U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch IV ML23311A4322023-11-0909 November 2023 Notification of NRC Supplemental Inspection (95001) and Request for Information RBG-48264, Core Operating Limits Report (COLR) - Cycle 23, Revision 12023-11-0606 November 2023 Core Operating Limits Report (COLR) - Cycle 23, Revision 1 RBG-48260, Notification of Readiness for Supplemental Inspection2023-10-12012 October 2023 Notification of Readiness for Supplemental Inspection ML23278A2402023-10-0606 October 2023 Regulatory Audit Plan in Support of License Amendment Requests to Revise TSs to Adopt Risk-Informed Completion Times and Implement the Provisions of 10 CFR 50.69 RBG-48258, Notification of Readiness for Supplemental Inspection2023-10-0505 October 2023 Notification of Readiness for Supplemental Inspection RBG-48259, Revision to Reply to Notice of Violation; EA-23-0552023-10-0303 October 2023 Revision to Reply to Notice of Violation; EA-23-055 ML23270B9932023-09-29029 September 2023 Request to Update ASME Boiler & Pressure Vessel Code Relief Request SE with NRC-Approved Revision of Bwrip Guidelines (GG-ISI-020 & RBS-ISI-019) (EPID L-2022-LLR-0090) - Non-Proprietary ML23269A1242023-09-27027 September 2023 Request for Withholding Information from Public Disclosure IR 05000458/20234012023-09-26026 September 2023 Cyber Security Inspection Report 05000458/2023401 IR 05000458/20230012023-09-21021 September 2023 NRC Inspection Report 05000458/2023001, Disputed Non-Cited Violation Rescinded RBG-48254, Report of Changes and Errors to 10CFR50.462023-09-21021 September 2023 Report of Changes and Errors to 10CFR50.46 IR 05000458/20234032023-09-21021 September 2023 NRC Security Inspection Report 05000458/2023403 (Cover Letter) RBG-48249, Reply to a Notice of Violation, EA-23-0712023-09-14014 September 2023 Reply to a Notice of Violation, EA-23-071 RBG-48253, Submittal of Owner'S Activity Report Form for Cycle 222023-09-12012 September 2023 Submittal of Owner'S Activity Report Form for Cycle 22 IR 05000458/20230122023-09-0101 September 2023 Comprehensive Engineering Team Inspection Report 05000458/2023012 IR 05000458/20230052023-08-21021 August 2023 Updated Inspection Plan for River Bend Station (Report 05000458/2023005) - Mid Cycle Letter RBG-48247, Reply to Notice of Violation; EA-23-0552023-08-21021 August 2023 Reply to Notice of Violation; EA-23-055 IR 05000458/20230922023-08-15015 August 2023 Final Significance Determination of a White Finding, Notice of Violation, and Follow-Up Assessment Letter; NRC Inspection Report 05000458/2023092 IR 05000458/20230022023-08-0909 August 2023 Integrated Inspection Report 05000458/2023002 ML23208A2112023-07-27027 July 2023 Entergy Operations Inc., Application to Revise Technical Specifications to Adopt TSTF-205, Revision of Channel Calibration, Channel Functional Test, and Related Definitions ML23195A0692023-07-24024 July 2023 2023 River Bend Station Notification of Biennial Problem Identification and Resolution Inspection and Request for Information IR 05000458/20230912023-07-20020 July 2023 Final Significance Determination of a White Finding, Notice of Violation, and Follow-Up Assessment Letter; NRC Inspection Report 05000458/2023091 ML23207A0762023-07-14014 July 2023 EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06 ML23195A0222023-07-11011 July 2023 4-2022-012 Letter - OI Closure to Licensee IR 05000458/20234042023-07-11011 July 2023 NRC Security Inspection Report 05000458/2023404 (Cover Letter Only) IR 05000458/20230902023-06-26026 June 2023 NRC Inspection Report 05000458/2023090 and Preliminary White Finding ML23159A2302023-06-0808 June 2023 Response to Request for Additional Information Concerning Request to Update ASME Code Relief Request Safety Evaluations with NRC-Approved Revision of BWRVIP Guidelines (GG-ISI-020, and RBS-ISI-019) ML23159A0052023-06-0505 June 2023 56557-EN 56557 - Paragon - Redlined RBG-48226, Core Operating Limits Report (COLR) - Cycle 23, Revision 02023-05-31031 May 2023 Core Operating Limits Report (COLR) - Cycle 23, Revision 0 RBG-48237, Response to NRC Integrated Inspection Report 05000458/20230012023-05-25025 May 2023 Response to NRC Integrated Inspection Report 05000458/2023001 ML23130A2732023-05-10010 May 2023 and Waterford 3 Steam Electric Station - Response to Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23117A2172023-05-0101 May 2023 Safety Evaluation for Quality Assurance Program Manual Reduction in Commitment ML23116A2352023-05-0101 May 2023 Integrated Inspection Report 05000458/2023001 RBG-48220, Submittal of 2022 Annual Radioactive Effluent Release Report2023-04-25025 April 2023 Submittal of 2022 Annual Radioactive Effluent Release Report 2024-01-18
[Table view] 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
Proprietary Notice Enclosure 1 of this letter contains proprietary information . Upon the removal of Enclosure 1, the balance of the letter may be considered non-proprietary .
-r Global Nuclear Fuel Global Nuclear Fuel - Americas, LLC Kimberly O'Connor Castle Hoyne Rood GNF Customer Project Manager Wi lm ington. NC 28401 KGO-ENO-LDl 120 September 13, 2018 Mr. Don Lomax cc: Brian Holman Entergy Operations, Inc. Frank Philpott 1340 Echelon Parkway Kristin Bennett Jackson, MS 39213 Chris Kmiec
Subject:
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
Reference:
- 1. Entergy Nuclear Operations, Inc. Fixe d Services Agreement No. 10134078 for the Supply of Fuel and Fuel Related Work to RBS with Global Nuclear Fuel, as amended
("Fuel Contract"),
- 2. Entergy Nuclear Operations, Inc. Contract Order 10495761.
Dear Mr. Lomax,
This letter transmits a revised version of the Global Nuclear Fuel - Americas, LLC (GNF-A) presentation on the River Bend Station spent fuel pool criticality analysis of Boraflex storage racks with NETCO-SNAP-IN rack inserts that was presented during the August 23 , 2018 pre-submittal meeting with NRC staff.
The revised version reflects the identification of specific information that is proprietary to GNF-A.
Please note that Enclosure 1 contains information which is considered proprietary by GNF-A and should be protected in accordance with the provisions for such information pursuant to the Entergy/General Electric Company proprietary agreement. In support of Entergy's use of the enclosed information with the NRC, the affidavit contained in Enclosure 2 identifies that the information contained in Enclosure 1 has been handled and classified as proprietary to GNF-A. GNF-A hereby requests that Entergy requ est that the NRC withhold the information contained in Enclosure 1 from public disclosure in accordance with the provisions of 10 CFR 2.390 and 9.17. GNF-A requests that any transmittal of this proprietary information to the NRC be accompanied by the enclosed affidavit and proprietary notice. In order to maintain the appli cability of the affidavit and to meet the requirements of 10 CFR 2.390, the transmittal to the NRC should :
- 1) Faithfully reproduce the proprietary information,
- 2) Preserve the proprietary annotations, and
- 3) Include the words similar to "GNF Proprietary Information" at the top of first page and each page containing the proprietary information.
Further, 10 CFR 2.390 requires that the proprietary information be incorporated, as for as possible into a
KGO-ENO-LDl-18-120 September 13, 2018 separate paper. Therefore, Enclosure 1 contains the proprietary information, and the non-proprietary information is provided in Enclosure 2.
Based on past discussions with the NRC, GNF-A has been encouraged to request its customers to provide a paragraph similar to the following paragraph in the customer letters transmitting proprietary information to the NRC in order to clearly indicate the proprietary nature of the information and to document the source of the proprietary information as indicated in the GNF-A affidavit.
"The enclosed documents contain proprietary information as defined by 10 CFR 2.390. GNF-A. as the owner of the proprietary information, has executed the enclosed affidavit, which identifies that the enclosed proprietary information has been handled and classified as proprietary, is customarily held in confidence, and has been withheld from public disclosure. The proprietary information was provided to Entergy in a GNF-A transmittal that is referenced by the affidavit. The proprietary information has been faithfully reproduced in the enclosed such that the affidavit remains applicable. GNF-A hereby requests that the enclosed proprietary information be withheld from public disclosure in accordance with the provisions of 10 CFR 2.390 and 9.17. Information that is not considered proprietary is provided in a separate enclosure."
Please contact me if you have any questions.
Sincerely,
~O/~
Kimberly O'Connor GNF-A Customer Project Manager
Enclosures:
- 1. River Bend Station Spent Fuel Pool Criticality Analysis of Boraflex Storage Racks with NETCO-SNAP-IN Rack Inserts, GNF Proprietary Information - Non -Public
- 2. River Bend Station Spent Fuel Pool Criticality Analysis of Boraflex Storage Racks with NETCO-SNAP-IN Rack Inserts, Non -Proprietary Information
- 3. GNF-A Affidavit for Enclosure 1 004N9640 R1
ENCLOSURE 2 KGO-ENO-LDl 120 River Bend Station Spent Fuel Pool Criticality Analysis of Boraflex Storage Racks with NETCO-SNAP-IN Rack Inserts Non-Proprietary Information IMPORTANT NOTICE This is a non-proprietary version of Enclosure 1. from which the proprietary information has been removed. Portions of the enclosure that have been removed are indicated by an open and closed bracket as shown here (( n.
Non-Proprietary Information Global Nuclear Fuel River Bend Station Spent Fuel Pool Criticality Analysis of Boraflex Storage Racks with NETCO-SNAP-IN Rack Inserts GNii=
Global Nuclear Fuel
Non-Proprietary Information Regulatory Requirements 10 CFR 50.68 (b) (4)
"The k-effective of the spent fuel storage racks loaded with fuel of the maximum fuel assembly reactivity must not exceed 0.95, at a 95 percent probability, 95 percent confidence level, if flooded with unborated water."
KmaX (95/95) ~ 0.95 General Design Criterion 62, Appendix A to 10 CFR 50 "Criticality in the fuel storage and handling system shall be prevented by physical systems or processes, preferably by use of geometrically safe configurations."
GN;:
Global Nuclear Fuel 2
Non-Proprietary Information Methodology Overview
- Consistent with NEI 12-16 Revision 3, "Guidance for Performing Criticality Analyses of Fuel Storage at Light-Water Reactor Power Plants."
- Peak reactivity analysis with most limiting (bounding) lattice in every rack cell location.
- No credit for the Boraflex neutron absorber (modeled as water).
- B-10 areal density used for rack insert analysis (0.0115 g 8-10/cm2) is 10%
less than the certified minimum areal density (0.0129 g B-10/cm2).
- Quantification of credible normal and abnormal conditions with consideration of biases, rack/fuel tolerances and computational uncertainties.
- Covers current and future (GNF3) fuel product lines at River Bend Station.
GNii=
Global Nuclear Fuel 3
Non-Proprietary Information Analysis Uncertainty Quantification k maX (95/95) == I1kNominal + I1k Bias + I1kTolerance + 11k Uncertainty The contribution from the biases are:
I n
lJ.k Bias = lJ.k Bi i=l The contribution from the tolerances are:
I n
lJ.kTolerance = I lJ.kfi i=l The contribution from the uncertainties are:
I n
lJ.kuncertainty I lJ.k~i i=l GNr Global Nuclear Fuel 4
Non-Proprietary Information Computer Code Calculations TGBLA06 a MCNP-OSP b
- NRC-approved lattice physics code
- Monte Carlo N-Particle code used for in (NEDE-30130-P-A). rack reactivity (keff) calculations.
- TGBLA solves Two-Dimensional (20)
- Uses point-wise (Le., continuous) ENDF/B-diffusion equations with diffusion VII cross-section library, and all reactions parameters corrected by transport in a given cross-section evaluation are theory to provide system considered.
multiplication factors and perform ((
burnup (depletion) calculations.
- Uses ENDF/B-V cross-section data.
- Performs coarse-mesh, broad- ))
group, diffusion theory calculations; ((
including thermal neutron scattering with hydrogen using an S(a,~) light water thermal scattering kernel.
))
a) [( b) MCNP-OSP is the GNF controlled production version of the Los Alamos National Laboratory code MCNPS.
))
GNii= Global Nuclear Fuel 5
Non-Proprietary Information Boraflex Rack Cell Model with Inserts
((
- No credit taken for 80raflex neutron absorber.
((
))
- Assumes every rack cell contains a design basis bundle with the worst rack reactivity suppression capability (i.e., highest rack efficiency) ((
))
((
))
- Stainless steel rack modeled.
- 8-10 areal density used in the rack insert model is 10% lower than the certified minimum (95/95).
)) . ((
GNr:Global Nuclear Fuel
))
6
Non-Proprietary Information Design Basis Bundle
(( . ((
)) bounds current and future fuel types at River Bend Station.
- Design basis bundle is selected to be the bundle with the worst rack reactivity suppression capability (i.e., highest rack efficiency) ((
))
- The design basis bundle is used to:
~ Define the nominal in rack keff result.
~ Used for performing all biases, manufacturing tolerances, com putationa I u ncerta i nty ca Icu lations, and all credible abnormal/accident condition calculations.
))
GN;:
Global Nuclear Fuel 7
Non-Proprietary Information Fuel Storage Conditions Analyzed Credible Normal Conditions Credible Abnormal Conditions
((
- Misloaded or mislocated fuel assembly
))
- No inserts along the rack periphery GNr Global Nuclear Fuel 8
Non-Proprietary Information Analyzed Tolerances and Biases Bundle and Rack Tolerances Fuel Depletion Bias
(( ((
))
(( ))
))
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Non-Proprietary Information Summary
- Consideration given to all credible abnormal conditions, manufacturing tolerance implications, and computational uncertainties in determining maximum in-rack eigenvalue.
- The analysis resulted in a storage rack maximum k-effective less than the 0.95 limit from 10 CFR 50.68 for normal and credible abnormal operation with tolerances and computational uncertainties taken into account.
GNi=
Global Nuclear Fuel 11
ENCLOSURE 3 KGO-ENO-LDl-18-120 Affidavit for Enclosure 1
_, . ~ I .. --'"' ............ .~
Global Nuclear Fuel- Americas AFFIDAVIT I, Lisa K. Schichlein, state as follows:
(1) I am a Senior Project Manager, NPP/Services Licensing, Regulatory Affairs, Global Nuclear Fuel - Americas, LLC (" GNF-A"), and have been delegated the fUllction of reviewing the information described in paragraph (2) which is sought to be withheld, and have been authorized to apply for its withholding.
(2) The information sought to be withheld is contained in Enclosure I of GNF letter KGO-ENO-LDI-18-120, Kimberly O' Connor (GNF) to Don Lomax (Entergy), entitled "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," dated September 13, 2018. The proprietary information in Enclosure 1, which is entitled "River Bend Station Spent Fuel Pool Criticality Analysis of Boraflex torage Racks with NETCO-SNAP-IN Rack Inserts", is identified by a dotted underline inside double square brackets. ((Ib.i~...~~;mt~n£Y...i ... Jm.. ~~w:np.l~ . ~~!.J] GNF proprietary information in figures and large objects is identified with double square brackets before and after the object. In each ca e, the superscript notation {3} refers to Paragraph (3) of this affidavit, which provides the ba is for the proprietary determination .
(3) In making this application for withholding of proprietary information of which it is the owner or licensee, GNF-A relies upon the exemption from disclosure set forth in the Freedom of Information Act ("FOIA"), 5 USC Sec. 552(b)(4), and the Trade Secrets Act, 18 USC Sec. 1905, and NRC regulations 10 CFR 9.17(a)(4), and 2.390(a)(4) for "trade secrets" (Exemption 4). The material for which exemption from disclosure is here sought also qualify under the narrower definition of "trade secret", within the meanings assigned to those terms for purposes of FOIA Exemption 4 in, respectively, Critical Mass Energy Project v. Nuclear Regulatory Commission, 975F2d871 (DC Cir. 1992), and Public Citizen Health Research Group v. FDA, 704F2d 1280 (DC Cir. 1983).
(4) orne examples of categories of information which fit into the definition of proprietary information are:
- a. Information that discloses a proce , method, or apparatus, including supporting data and analyses, where prevention of its u e by GNF-A's competitors without license from GNF -A constitutes a competitive economic advantage over other companies;
- b. Information which, if used by a competitor, would reduce his expenditure of resources or improve his competitive position in the design, manufacture, shipment, installation, assurance of quality , or licensing of a similar product; KGO-ENO-LDl-18-120 Affidavit Page 1 of3
- c. Information which reveals aspects of past, present, or future GNF-A customer-funded development plans and programs, resulting in potential products to GNF-A;
- d. Information which discloses patentable subject matter for which it may be desirable to obtain patent protection.
The information sought to be withheld is considered to be proprietary for the reasons set forth in paragraphs (4)a. and (4)b. above.
(5) To address 10 CFR 2.390 (b) (4), the information sought to be withheld is being submitted to NRC in confidence. The information is of a sort customarily held in confidence by GNF-A, and is in fact so held . The information sought to be withheld has, to the best of my knowledge and belief, consistently been held in confidence by GNF-A, no public disclosure has been made, and it is not available in public sources. All disclosures to third parties including any required tran mittals to NRC, have been made, or must be made, pursuant to regulatory provisions or proprietary agreements which provide for maintenance of the information in confidence. Its initial designation as proprietary information, and the subsequent steps taken to prevent its unauthorized disclosure, are as set forth in paragraphs (6) and (7) following.
(6) Initial approval of proprietary treatment of a document is made by the manager of the originating component, the person most likely to be acquainted with the value and sensitivity of the information in relation to industry knowledge, or subject to the terms under which it was licensed to GNF-A .
(7) The procedure for approval of external release of such a document typically requires review by the staff manager, project manager, principal scientist or other equivalent authority, by the manager of the cognizant marketing function (or his delegate), and by the Legal Operation, for technical content, competitive effect, and determination of the accuracy of the proprietary designation. Di closures outside GNF-A are limited to regulatory bodies, customers, and potential customer , and their agents, suppliers, and licensees, and others with a legitimate need for the information, and then only in accordance with appropriate regulatory provisions or proprietary agreements.
(8) The information identified in paragraph (2), above, is classified as proprietary because it contains detail s of GNF-A ' s criticality analysis methodology . The development of this methodology, along with the testing, development and approval was achieved at a significant cost to GNF-A or its licensor.
The development of the criticality analysis methodology along with the interpretation and application of the analytical results is derived from the extensive experience database that constitutes a major GNF-A asset.
KGO-ENO-LDl-18-120 Affidavit Page 2 of3
(9) Public disclosure of the information sought to be withheld is likely to cause substantial harm to GNF-A's competitive position and foreclose or reduce the avai lability of profit-making opportunities. The information is part of GNF-A's comprehensive BWR safety and technology base, and its commercial value extends beyond the original development cost.
The value of the technology base goes beyond the extensive physical database and analytical methodology and includes development of the expertise to determine and apply the appropriate evaluation process. In addition, the technology base includes the value derived from providing analyses done with NRC-approved methods.
The research, development, engineering, analytical , and NRC review costs comprise a substantial investment of time and money by GNF-A.
The precise value of the expertise to devise an evaluation process and apply the correct analytical methodology is difficult to quantify , but it clearly is substantial.
GNF-A's competitive advantage will be lost if its competitors are able to u e the results of the GNF-A experience to normalize or verify their own process or if they are able to claim an equivalent understanding by demonstrating that they can arrive at the same or similar conclusions.
The value of this information to GNF-A would be lost if the information were disclosed to the public. Making sLlch information available to competitors without their having been required to undertake a similar expenditure of resources would unfairly provide competitors with a windfall, and deprive GNF-A of the opportunity to exercise its competitive advantage to seek an adequate return on its large investment in developing and obtaining these very valuable analytical tools.
I declare under penalty of perjury that the foregoing is true and correct.
Executed on this lIth day of September 2018 .
Lisa K. chichlein Sen ior Project Manager, NPP/Services Licensing Regulatory Affairs Global Nuclear Fuel - Americas, LLC 3901 Castle Hayne Road Wilmington, NC 28401 Lisa.Schichlein@ge.com KGO-ENO-LDl-18-120 Affidavit Page 3 of3