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Category:Meeting Briefing Package/Handouts
MONTHYEARML24016A2372024-01-17017 January 2024 NEI Environmental Reviews Slides Public Meeting 1-17-24 ML24008A0442024-01-0909 January 2024 NEI - Slides for NRC Workshop 1 on Revision to RG 1.183 R1 - Final - ML24008A044 ML23342A0262023-12-14014 December 2023 December 14, 2023, Presentation on NEI 23-01 Operator Cold Licensing Training Plan for Advanced Nuclear Reactors ML23347A1782023-12-13013 December 2023 12-14 NEI EPRI Presentation NRC Public Meeting 16-03 R1 ML23303A1922023-10-30030 October 2023 NEI Slides for SLR Public Meeting - Oct 31 2023 ML23324A2392023-10-24024 October 2023 S1P6 - Hilary Lane - NRC AMT Workshop - Oct. 2023 ML23258A1992023-09-20020 September 2023 NEI 99-02 Draft Rev. 8 Update for Sept 2023 ROP Public Meeting ML23242A0782023-08-30030 August 2023 Hbu Workshop IV Industry Presentation: Drive to Deploy ATF with Increased Enrichment and Higher Burnup ML23230A0142023-08-22022 August 2023 Industry Slide Presentation for 8-22-23 Meeting on ARCAP-TICAP and DG-1404 Guidance Documents ML23191A0632023-07-0707 July 2023 NEI Cybersecurity Presentation for July 2023 ROP Public Meeting ML23191A0662023-07-0707 July 2023 NEI 99-02 Draft Rev. 8 Update for July 2023 ROP Public Meeting ML23160A1512023-06-15015 June 2023 25 - Industry - Industry Perspectives on ASME III and XI Pre-Service Inspection ML23160A1422023-06-15015 June 2023 20 - Industry - Industry Perspective on Performance Monitoring ML23116A1892023-05-31031 May 2023 Industry Observations of NRC Licensing Program (NEI Slides May 2023) ML23136A5912023-05-18018 May 2023 NEI Safety Culture Presentation for May 2023 ROP Public Meeting ML23125A3192023-05-0909 May 2023 NEI Presentation for May 9, 2023, Public Meeting on NEI 22-05, Revision a ML23115A0302023-04-27027 April 2023 NEI Perspective on Performance Monitoring in Use of Probabilistic Fracture Mechanics for Optimizing Inspections of Non-RPV Pressure Vessels, April 27, 2023 ML23088A0822023-03-30030 March 2023 NEI Presentation - March 30, 2023 PRA Configuration Control Public Meeting ML23082A0572023-03-28028 March 2023 Proposal to Establish Alternate Requirements for Components Commensurate with Safety and Risk ML23079A2642023-03-23023 March 2023 General Visual Examination of Containment Surfaces Covered by Insulation - March 23, 2023 Public Meeting Slides from NEI ML23210A0042023-03-15015 March 2023 Destination: Termination, NRC Regulatory Information Conference ML23045A2892023-03-14014 March 2023 RIC 2023 - 03/14/2023 to 03/16/2023 Regulatory Information Conference (Ric).Operational and Safety Benefits of Risk Informed Applications ML23061A0292023-03-0202 March 2023 NEI Presentation - Advanced Reactor Digital I&C Licensing Workshop 1 ML23013A0782023-01-13013 January 2023 PI&R Inspection Discussion for January 2023 ROP Public Meeting ML23041A4342022-12-15015 December 2022 NEI Presentation for December 15, 2022 Industry Spent Fuel Activities Prioritization Meeting ML22291A4442022-10-11011 October 2022 NEI 22-01 License Termination Plan Process Presentation at October 11 2022 Meeting on NUREG-1757 Vol. 2 ML22266A2632022-09-28028 September 2022 Session 2 - Advanced Reactor Developers Perspectives on Codes and Standards ML22250A7122022-09-21021 September 2022 NEI 22-03 Presentation Slides for NRC Public Meeting (Sept. 21, 2022) ML22235A7032022-08-24024 August 2022 NEI Presentation for Aug 26, 2022 Public Meeting - Source Terms and Radiological Consequence Analyses ML22194A0682022-07-18018 July 2022 NEI Presentation for NEI 22-02 Rsi Response ML22174A2822022-06-22022 June 2022 NEI Presentation for Public Meeting with NMMSS Users Community to Discuss Foreign Obligation Reporting Requirements for Low Enriched Uranium ML22172A1352022-06-21021 June 2022 NEI Presentation for Public Meeting Industry Perspectives on Rulemaking for Greater than 5 Percent Enrichment ML22143A8542022-05-20020 May 2022 Nuclear Energy Institue (NEI) Presentation Slides to ACRS Subcommittee on CCF Secy Paper, May 20, 2022 ML22136A1162022-05-11011 May 2022 Presentation 5 - Utilizing the Nuclear Energy Institute (NEI) 07-07 Industry Groundwater Protection Initiative as a Foundation for Addressing Subsurface Site Assessments ML22088A0342022-03-29029 March 2022 Public Meeting Presentation by NEI Regarding Part 53 Rulemaking: Selected Topics ML22077A4012022-03-23023 March 2022 NEI INL Presentation March 23, 2022, NRC Workshop Isv Hfe Issue ML22070B1212022-03-16016 March 2022 Industry Perspective on IEEE Std -1819 ML22140A3612022-03-10010 March 2022 mccullumr- hv-th29 ML22060A0022022-03-0101 March 2022 Dt Public Meeting - 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Adversary Timeline Methodology (Final- 6.24.21) - Updated ML21173A2862021-06-21021 June 2021 NEI 20-07 Systematic Approach to CCF NRC 2024-01-09
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24016A2372024-01-17017 January 2024 NEI Environmental Reviews Slides Public Meeting 1-17-24 ML24010A0202024-01-11011 January 2024 Public Meeting on SLR Efficiencies - NEI Presentation ML24008A0442024-01-0909 January 2024 NEI - Slides for NRC Workshop 1 on Revision to RG 1.183 R1 - Final - ML24008A044 ML23342A0262023-12-14014 December 2023 December 14, 2023, Presentation on NEI 23-01 Operator Cold Licensing Training Plan for Advanced Nuclear Reactors ML23347A1782023-12-13013 December 2023 12-14 NEI EPRI Presentation NRC Public Meeting 16-03 R1 ML23303A1922023-10-30030 October 2023 NEI Slides for SLR Public Meeting - Oct 31 2023 ML23324A2392023-10-24024 October 2023 S1P6 - Hilary Lane - NRC AMT Workshop - Oct. 2023 ML23261C3792023-09-27027 September 2023 NEI 22-04 Pre-Submittal Meeting with NRC - September 27, 2023 ML23258A1992023-09-20020 September 2023 NEI 99-02 Draft Rev. 8 Update for Sept 2023 ROP Public Meeting ML23242A0782023-08-30030 August 2023 Hbu Workshop IV Industry Presentation: Drive to Deploy ATF with Increased Enrichment and Higher Burnup ML23242A1662023-08-30030 August 2023 the Future of Nuclear Power: 2023 Baseline Survey (Slides) ML23230A0142023-08-22022 August 2023 Industry Slide Presentation for 8-22-23 Meeting on ARCAP-TICAP and DG-1404 Guidance Documents ML23228A0042023-08-18018 August 2023 NEI Slides for Public Meeting to Discuss Possible Efficiencies on the Subsequent License Renewal Review - August 18, 2023 ML23191A0162023-07-11011 July 2023 NEI Comments on Risk-Informed Process for Evaluation (RIPE) DORL TSG - 7/11/23 Public Meeting Slides from NEI ML23191A0632023-07-0707 July 2023 NEI Cybersecurity Presentation for July 2023 ROP Public Meeting ML23191A0662023-07-0707 July 2023 NEI 99-02 Draft Rev. 8 Update for July 2023 ROP Public Meeting ML23160A1512023-06-15015 June 2023 25 - Industry - Industry Perspectives on ASME III and XI Pre-Service Inspection ML23160A1422023-06-15015 June 2023 20 - Industry - Industry Perspective on Performance Monitoring ML23116A1892023-05-31031 May 2023 Industry Observations of NRC Licensing Program (NEI Slides May 2023) ML23136A5912023-05-18018 May 2023 NEI Safety Culture Presentation for May 2023 ROP Public Meeting ML23125A3192023-05-0909 May 2023 NEI Presentation for May 9, 2023, Public Meeting on NEI 22-05, Revision a ML23117A3712023-05-0202 May 2023 NEI Lessons Learned Meeting Slides, May 2, 2023 ML23115A0302023-04-27027 April 2023 NEI Perspective on Performance Monitoring in Use of Probabilistic Fracture Mechanics for Optimizing Inspections of Non-RPV Pressure Vessels, April 27, 2023 ML23088A0822023-03-30030 March 2023 NEI Presentation - 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November 2022 - Final Presentation to NRC ML22318A3032022-11-16016 November 2022 NEI-22-01 License Termination Process Pre-Submittal Meeting November 16, 2022 (Presentation) ML22291A4442022-10-11011 October 2022 NEI 22-01 License Termination Plan Process Presentation at October 11 2022 Meeting on NUREG-1757 Vol. 2 ML22250A7122022-09-21021 September 2022 NEI 22-03 Presentation Slides for NRC Public Meeting (Sept. 21, 2022) ML22235A7032022-08-24024 August 2022 NEI Presentation for Aug 26, 2022 Public Meeting - Source Terms and Radiological Consequence Analyses ML22216A1152022-08-0404 August 2022 August 4, 2022 Rislr Public Meeting Presentation by Nuclear Energy Institute ML22194A0682022-07-18018 July 2022 NEI Presentation for NEI 22-02 Rsi Response ML22174A2822022-06-22022 June 2022 NEI Presentation for Public Meeting with NMMSS Users Community to Discuss Foreign Obligation Reporting Requirements for Low Enriched Uranium ML22172A1352022-06-21021 June 2022 NEI Presentation for Public Meeting Industry Perspectives on Rulemaking for Greater than 5 Percent Enrichment ML22152A0942022-06-0202 June 2022 NEI Slides - 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Text
Regulatory Issue Resolution Protocol (RIRP) for Graded Approach to Dry Spent Fuel Storage Licensing NRC Meeting Brian Gutherman for the Nuclear Energy Institute Rockville, MD
Basis for RIRP I-16-01
- Both NRC and industry recognize that there is a need to improve the efficiency of the licensing process for dry storage of spent nuclear fuel (SNF) under 10 CFR Part 72.
- The process continues to consume an inordinate amount of both NRC and industry resources.
- The level of detail in ISFSI licenses and cask CoCs is not commensurate with dry cask storage risk
- NRC and industry are applying the dry storage regulatory issue resolution protocol (RIRP) to provide risk appropriate criteria for determining the content of ISFSI licenses and CoCs
Used Fuel Storage and Transportation Regulatory Issue Resolution Protocol Number: I-16-01 Improving the efficiency of the regulatory framework for dry storage of used nuclear fuel
- NRC and industry interact in public meetings and letters
- Establish a structured process for determining what information should be in ISFSI licenses or CoCs, including Tech.
Specs.
- Implement one or more pilot CoC amendments using preliminary CoC format, content and selection criteria agreed to between NRC and industry
- Utilize lessons learned from pilot(s) to finalize CoC format, content and selection criteria
- NEI develops guidance for NRC submittal and endorsement in the Standard Review Plans for licenses and cask CoCs
The Efficiency Improvement
- Industry has developed criteria for ISFSI license and CoC content
- Based on those proposed in 2012 petition for rulemaking (PRM 72-7)
- Criteria based on principles from the power reactor Improved Technical Specification NRC Policy Statement of 1993
- ITS has been a significant factor in improving operating reactor safety and efficiency since
- Places change control for ISFSI and cask designs in the correct domain, based on safety significance
- Important premise is that information in the ISFSI or cask FSAR is part of the licensing basis and must be complied with (i.e., the FSAR is an enforceable document)
Actions To Date
- Public Meeting Kick-Off for RIRP issue resolution-8/8/2016
- Public Meeting to discuss proposed format, content and selection criteria for the graded approach and pilot-10/28/2016
- NRC/Industry Public Workshop to discuss preliminary license/CoC format, content and selection criteria for the graded approach for dry cask storage pilot-11/21/2016
- NEI letter to NRC clarifying the RIRP approach -
1/12/17
Proposed Pilot CoC Amendment
- Review each existing CoC condition and TS requirement against the PRM format and content
- Any yes determination is tentatively retained in the CoC/TS
- Could be re-located within the CoC or TS based on format for information in the document
- Confirm the above conclusion for each retained or re-located condition or TS using risk insights:
- No significant increase in the probability or consequences of an accident previously evaluated
- No possibility of a new or different kind of accident being created compared to those previously evaluated
- No significant reduction in margin of safety
Proposed CoC Format CoC Body - Certified Design Technology Design Features CoC Appendix A - Inspections, Tests, and Evaluations CoC Appendix B - Technical Specifications Section 1 - Definitions, Use and Application Section 2 - Approved Contents Section 3 - Limiting Conditions for Operation (LCOs) and Surveillance Requirements (SRs)
Section 4 - Administrative Controls
Certified Design
- Replaces information in the body of the CoC
- Concise description of dry storage system
- Those that would have a significant effect on safety if modified, such as some materials of construction or geometric arrangement
- CoC holder has compliance responsibility
Inspections, Tests and Evaluations
- When performed and the acceptance criteria are met, a cask will operate in conformance with the certified design and fulfill its required safety functions
- Compliance demonstrated by CoC holder or general licensee as specified in the ITE
Technical Specifications
- Section 1: Definitions, Use and Application
- Section 2: Approved Contents
- Parameters that if modified would have a significant effect on safety
- Selection Criteria 1 through 3
- Section 3: Limiting Conditions for Operation (LCOs) and Surveillance Requirements
- Lowest functional capability or performance levels of equipment required for safe operation of the ISFSI facility and cask
- Selection Criteria 4 through 6
- Section 4: Administrative Controls
CoC Appendix B, TS Section 1
- Administrative rules on how to use the TS
- Essentially the same as the information currently in TS Section 1
CoC Appendix B, TS Section 2
- Approved Contents Selection Criteria
- Criterion 2. A characteristic or parameter for which verification is a necessary condition to provide reasonable assurance that the cask safety functions of confinement, sub-criticality, and shielding will be performed;
- Criterion 3. A characteristic or parameter that has a significant impact on public health and safety, based on risk insights and expert knowledge.
CoC Appendix B, TS Section 3
- Criterion 1. Installed instrumentation that is used to detect, and indicate a significant abnormal degradation of the cask confinement boundary;
- Criterion 2. An initial condition of a design basis accident that either assumes the failure of or presents a challenge to the integrity of a fission product barrier;
- Criterion 3. A structure, system, or component that has a significant impact on public health and safety, based on risk insights and expert knowledge.
CoC Appendix B, Section 4
- High level description of required programs
- Includes essential elements of the programs are required to assure safe ISFSI operation
- Details included in implementing procedures
CoC 1004 Example 1
- Condition 3 is a description of the NUHOMS and currently occupies a page and a half.
- The condition would be retained as the description of the storage technology in the Certified Design section of the CoC
- The page and a half would be condensed to a succinct description of the system and the authorized component models
CoC 1004 Example 1 Similar lists of HSM and TC models would be included
CoC 1004, Example 2
- Condition 4 currently states: Notification of fabrication schedules shall be made in accordance with the requirements of 10 CFR 72.232(d).
- Condition 4 would be eliminated from the CoC and not relocated because it simply cites a regulation that stands alone
CoC 1004, Example 3
- Condition 8 specifies the elements of pre-operational testing and dry run training exercises before first use by each licensee
- TS 5.2.2 contains specific elements of the training program
- These requirements would be re-located from the CoC to the FSAR
- A training program is required to comply with §72.190 and the general QA requirement to ensure personnel are qualified
- The specifics of classroom and dry run training are adequately controlled by the licensees training program and subject to NRC inspection
- Training requirements relocated to the FSAR do not increase the frequency of and accident, create a new accident of decrease the DSS safety margin
CoC 1004, Example 4
- LCO 3.1.1 specified that helium shall be used for DSC drainage and specifies a drying pressure/hold time
- This LCO would be retained as-is in its entirety
- Risk insights and expert knowledge tell us that dryness and a helium environment inside the DSC are important to protect the cladding against gross rupture
- Meets LCO selection criterion 3
- A DSC not adequately dried or use of air for draining may introduce a new accident and/or reduce the margin of safety
CoC 1004, Example 5
- Design Feature 4.3.3.3 specifies a maximum ambient temperature
- This limit would be retained but re-defined as an LCO and relocated to CoC Appendix B, Section 3
- Meets LCO selection criterion 2 as an initial condition for an accident (blocked vent).
CoC 1004, Example 6
- TS 5.2.4 specifies numerous requirements for the licensees radiation protection program
- TS 5.2.4 would be significantly condensed to reflect only the key elements of the radiation protection program in Administrative Controls section of TS
- Details of compliance with 10 CFR 20, 72.104, and ALARA would be removed as requirements already specified in the rules themselves
Future Actions
- Industry issues letter to NRC confirming todays graded approach to the pilot exercise - April 2017
- Industry submit a pilot CoC amendment application to NRC implementing the proposed format and content-June 2017
- NRC complete safety review of pilot CoC amendment application- January 2018
- Public meeting to discuss lessons learned from the pilot -
February 2018
- NRC complete rulemaking to make CoC amendment effective-June 2018
- Industry develop guidance reflecting the pilot and submit for NRC endorsement as part of standard review plan
Conclusions
- Economic challenges and resource constraints demand a more efficient approach to dry cask licensing
- Based on years of experience, and what is known about the relatively low risks of dry cask storage - there is a significant opportunity to attain a more efficient process
- Industry and NRC are committed to working together to achieve this goal
Questions?