ML22130A131
| ML22130A131 | |
| Person / Time | |
|---|---|
| Issue date: | 05/17/2022 |
| From: | Rowley J NRC/NMSS/DFM/FFLB |
| To: | |
| J ROWLEY NRC/NMSS/DFM/FFLB 3014154053 | |
| Shared Package | |
| ML22130A130 | List: |
| References | |
| Download: ML22130A131 (54) | |
Text
Fuel Facility Stakeholders Meeting May 17, 2022
Public Meeting With Nuclear Energy Institute and Members from the Nuclear Fuel Facility Industry
Jonathan Row ley, Project Manager Division of Fuel Management Office of Nuclear Material Safety and Safeguards Email: Jonathan.Rowley@nrc.gov Phone: 301-415-4053
1 Meeting Category and Public Participation
This is an Observation Meeting. This is a meeting in which attendees will have an opportunity to observe the NRC performing its regulatory function or discussing regulatory issues. Attendees will have an opportunity to ask questions of the NRC staff or make comments about the issues discussed following the business portion of the meeting; however, the NRC is not actively soliciting comments towards regulatory decisions at this meeting.
2 Agenda - May 17, 2022
Topic Ti m e Speakers
Introduction (Purpose, Rules for Meeting) 9:30 AM Jonathan Rowley, Project ManagerDivision of Fuel Management (DFM)
Shana Helton, Director Division of Fuel Management Office of Nuclear Material Safety and Safeguards Opening Remarks 9:35 AM(NMSS)
U.S. Nuclear Regulatory Commission
Janet Schlueter Nuclear Energy Institute (NEI)
Status of Action Items from October 2021 Meeting 9:40 AM Jonathan Rowley, Project Manager, DFM
Integrated Schedule and Supplement Updates 9:45 AM Jonathan Rowley, Project Manager, DFM
Industry Priorities 10:25 AM NEI/Industry
Break 10:50 AM
Fuel Facility Oversight
- Introduction and Region II Priorities Anthony Masters, Director DFFI, Region II
- Status of Early Implementation of Smarter 11:00 AM Inspection Program Leira Cuadrado, Senior Project Manager, COVID-19 Public Health Emergency Oversight Division of Materials Safety, Security, State, and Activities Assessment Tribal Programs
3 Agenda - May 17, 2022 (cont.)
Topic Ti m e Speakers
Hybrid Inspection = Pros and Cons 11:25 AM NEI/Industry
Public Q & A 11:55 AM
Lunch Break 12:00 PM
Discussion on Various Regulatory Initiatives: 1:30 PM Dylannne Duvigneaud, Fuel Cycle Operations
- NRC Position on Safety Margin and Engineer, DFM Forthcoming NRC Letter Aida Rivera, Executive Technical Assistant,
- Transformation Survey Office Executive Director of Operations
Implementation of the IAEA Additional 1:50 PM Santiago Aguilar, International Safeguards Protocol in the U.S. Analyst DFM
Break 2:30 PM
Be Risk Smart Framework 2:40 PM Mirabelle Shoemaker, International Safeguards Analyst, DFM
Tracking of Enriched Uranium 3:10 PM Mirabelle Shoemaker, International Safeguards Analyst, DFM
Public Q & A 3:45 AM
Recap of Action Items for the Day 3:50 PM Jonathan Rowley, DFMJanet Schlueter, NEI
Closing Remarks and Adjourn 3:55 PM Shana Helton, DFMJanet Schlueter, NEI
4 Opening Remarks
Shana Helton, Director Division of Fuel Management Office of Nuclear Material Safety and Safeguards
Janet Schlueter, Senior Director Fuel and Radiation Safety Nuclear Energy Institute
5 Action Items - October 2021 Stakeholders Meeting
Action Item 1 Action Item 2 Action Item 3 The NRC and NEI/Industry shall exchange any The NRC staff was requested to place the corrected NEI/Industry suggested that integrated schedule of meeting presentation materials at least one week integrated schedule of regulatory activities chart on regulatory activities chart include the draft interim staff prior to the scheduled meeting date. the NRC public W eb site for the fuel facility guidance (ISG) on security for facilities possessing NRC Staff ResolutionAction Items from October 2021 Fuel stakeholders meeting. Category II special nuclear material.
Division of Fuel Management (DFM) developed new NRC Staff Resolution NRC Staff Resolution guidance for planning and conducting the bi -annual The website was updated on November 16, 2021. The Office of Nuclear Security and Incident Response Fuel Facility Stakeholders Meeting. The guidance Facility Stakeholders Public Meeting(NSIR) concluded that the working draft of the ISG did not will assure that information will be ready to provide warrant being on the integrated schedule chart. The NEI at least 7 days prior to the meetings. document is not associated with a public rulemaking and the document is not publicly available. The document is official use only and has a need-to-know aspect, given the site specific, case-by-case nature of the interaction with applicants/licensees and the site-specific nature of the supplemental security measures.
Action Item 4 Action Item 5 Action Item 6 The NRC staff is to inquire how the industry was The NRC staff will consider NEI/Industry suggestion The NRC will work to make as many licensing division able to obtain two different versions of draft of having a public meeting by the end of 2021 to instructions publicly available as possible.
NUREG-2159. discuss the tracking of higher enriched material.NRC Staff Resolution NRC Staff Resolution NRC Staff ResolutionJonathan Row ley The following four division instructions (DIs) should be Additional discussion with NEI determined that the A public meeting on tracking of higher enriched available by September 2022 after NRC staff has been trained and has implemented the DIs for a couple months:
industry was reviewing the 2018 version of the draft material was held on December 14, 2021; meeting Project ManagerLicensing Overview (LIC-FM-1), Acceptance Reviews NUREG. The staff confirmed that the ADAMS notice (ML21335A329), presentation (LIC-FM-2), Requests for Additional Information (LIC-FM-accession number was linked to the 2021 version (ML21344A149 ). 3), Safety Evaluation Reports (LIC-FM-4).
and industry is working with the current version.
Action Item 7 Division of Fuel Management The NRC and NEI/Industry will work to have the dates for the 2022 Fuel Facility Stakeholders Public Office of Nuclear Material Safety and Safeguards Meetings (Spring and Fall) set by the end of January 2022 to help assist all parties with planning and preparation.
NRC Staff Resolution The Spring 2022 meeting date was set on December 28, 2021, for May 17 and 18, 2022.
6 Integrated Schedule Chart and Supplement Updates
Jonathan Rowley Project Manager Division of Fuel Management Office of Nuclear Material Safety and Safeguards
7 Integrated Schedule Chart Updates
2021 2022 2023 Com m ents Regulatory Ac tiv ity Rev is ed
The Com m is s ion approved integrating Inte grate d Low-Le v e l Radioactiv e Waste Disposal Rule making the greater-than-Clas s C was te and (SECY-20-0098) 5/6/2022 Part 61 low-level radioac tive was te Irene W u/Cardelia Maupin/Priya Yadav dis pos al rulem aking ac tivities and to is s ue a new propos ed rule.
The Com m is s ion dis approved dis c ontinuation of rulem aking. Per Part 73 - Enhanced Security of SNM (SECY-19-0095) Com m is s ion direc tion, the s taff is Mars hall Kohen/Irene W u 5/6/2022 *preparing a notation vote paper c ontaining options. Notation vote paper s c heduled to go to Com m is s ion by end of Septem ber 2022.
Part 73 - Enhance d We apons Rule making January 2022, the Com m is s ion is s ued (SECY-18-0058) 5/6/2022 SRM-SECY-18-0058 approving the final Martha Barillas /Phil Broc hm an rule. Final rule expec ted to be publis hed by end of Septem ber 2022.
Part 73-Cybe r Se curity Rule making (SECY-17-0099) 5/6/2022 Awaiting Com m is s ion direc tion.
Irene W u/Jam es Downs
De commissioning Financial Assurance for Se ale d and The regulatory bas is was publis hed for Unse ale d Radioactiv e M ate rial (PRM 66; NRC-2017-0159) - 5/6/2022 a 60-day public c om m ent period on (SECY-19-0125) April 28, 2022.
Greg Trus s ell/Cardelia Maupin
Propose d Rule making - Alte rnativ e s to the Use of Cre dit The propos ed rule pac kage was Ratings (RIN 3150-AJ92) (SECY-16-0009, SECY-20-0056) 5/6/2022 s ubm itted to the Com m is s ion on April Greg Trus s ell 28, 2022.
Part 51 - Rule making Plan - T ransforming the NRC Rulem aking denied by Com m is s ion in Env ironme ntal Re v ie w Proce ss (SECY-21-0001) 5/6/2022 April 2022.
Yanely Malavé
Harmonization of T ransportation Safe ty Re quire me nts with Coordinating public ation with Inte rnational Atomic Ene rgy Age ncy Standards (RIN 3150-AJ85; Departm ent of Trans portation, with NRC-2016-0179) - Part 71 (SECY-16-0093 and SECY-20-0102) 5/6/2022 public ation expec ted in late Spring 2022 Jam es Firth (after DO T propos ed rule is approved for public ation).
ANS 57.11 - Inte grate d Safe ty Asse ssme nt Standard The Nonreac tor Nuc lear Fac ilities Marilyn Diaz 5/6/2022 Cons ens us Com m ittee s elec ted a new W orking Group Chair.
Re gulatory Information Confe re nce 5/6/2022 Pres entations prepared for s es s ions of Jonathan Rowley fuel c yc le interes t are available online.
W orking Group Rec om m endations Smarte r Lice nsing Effort Final Report - April 30, 2020; Public Matt Bartlett 5/6/2022 Vers ion of Sm arter Lic ens ing Ac tion Mid Term - Job Aids, Long Term - Turn-over Guidanc e, SRP for GTCM, Update Plan and Projec t Status - July 10, 2020 Near Term - Develop DIs Tem plates, Training, NUREG-1520, Les s ons learned, Lic ens e review road m ap - See s upplem ent.
and Evaluate Ris k Tool
NUREG-2159 - M C&A Guidance for SNM of M ode rate Congres s ional Review Ac t review in Strate gic Significance 5/6/2022 progres s. Final is s uanc e: Augus t 2022 Suz anne Ani
Ve ry Low Safe ty Significance Issue s Guidanc e developm ent and Stephen Koenic k 5/6/2022 im provem ent c ontinues as experienc e is gained.
Parts 11, 25, and 95 - Incre ase d Acce ss Authoriz ation Fe e s 5/6/2022 Final rule is going through c onc urrenc e.
Em ily Robbins
= Final Rule /Final Guidance = Public Inte raction = ANPR De v e lopme nt = Issue Draft Guidance
= Final Re port/Closure M e mo = Pe nding Commission Action = Guidance De v e lopme nt = ANPR Issue d
= De nie d by Commission = Marks issuance of SRM = Pilot Program = Pre -rule making Activ itie s
= Re g. Basis/Draft Guidance = Propose d Rule /DG De v e lopme nt
= Imple me ntation = Non-rule making/NRC Activ itie s
- = Sche dule d M e e ting l = M arks issuance of SECY V = Site Visit A = ACRS M e e ting
88 Updates to Integrated Schedule Chart and Supplement
- Updated information
- Fuel Facility Stakeholders Meeting https://www.nrc.gov/materials/fuel -cycle -fac/regs -guides-comm.html#cumeffects
- Integrated Schedule (Chart)
ADAMS Accession Number ML Summary of changes to previously listed activities(October 2021 - April 2022)
- Integrated Schedule Supplement ADAMS Accession Number ML
9 INDUSTRY PRIORITIES
NEI/INDUSTRY
10 Introduction Region II Priorities Status of Early Implementation of Smarter Inspection Program
Anthony Masters, Director Division of Fuel Facility Inspection Region II
11 Inspection Lessons during the COVID-19 Pandemic
Office of Nuclear Material Safety and Safeguards
Presented by: Leira Cuadrado, Sr. Project Manager Division of Materials Safety, Security, State, and Tribal Programs Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Leira.Cuadrado@nrc.gov
12 Phased Approach for this Assessment
Phase B
(April 2021 - November 2021)
- Gather additional feedback Phase A internally and externally (August 2020 - April 2021)* Expanded on best practices and
- Gather initial internal feedback on challenges the implementation of inspection p ro g ra m during t h e COVI D-19
- Developed recommendations for the pandemic routine implementation of inspection p ro g ra m s
- Shared feedback, challenges, and good practices
(Report available at ADAMS Accession No. ML21158A231) 13 Feedbac k Mechanisms
- Internal survey(s) to inspection staff and program office staff
- Interviews to inspection staff and management (Branch Chiefs, Division Directors, and Regional Administrators/Office Directors)
- Public meetings to obtain external feedback in July and August 2021
- Government to Government Meeting in October 2021
14 Assessment Key Messa ges:
- On-site inspections continue to be the most effective and preferred method of inspection
- Keep the option to employ flexibilities (i.e. remote, hybrid, in-off i c e revi ews of records), when appropriate
- Specific inspection guidance is warranted for pandemic preparedness
Report is available here
15 Upcoming Activities
Each inspection program will evaluate their current guidance to identify needed revisions.
The agency will ensure consistency in the development of inspection guidance for pandemic preparedness.
NRR is undergoing a similar lessons learned effort and the offices are collaborating.
16 Hybrid Inspections Pros and Cons
Janet Schlueter, NEI
17 Public Participation
At this time, the public is afforded an opportunity to ask questions and/or provide comments on the following topics:
- Status of Action Items from October 2021 Meeting
- Integrated Schedule and Supplement Updates
- Industry Priorities
- Fuel Facility Oversight
- Hybrid Inspection - Pros and Cons
18 Status of NRC Letter on Safety Margin
DyLanne Duvigneaud Inspection and Oversight Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards
19 Status of NRC Letter on Safety Margin
- In two letters, submitted by NEI, dated July 24, 2020 (ML20211L714) and April 20, 2021 (ML21236A302 ), the industry discussed their position on safety margin and suggested edits to Inspection Manuel Chapter 0616
- By letter dated December 29, 2021 (ML21336A763), the NRC staff stated that it will perform a backfit assessment of changes to IMC 0616, as identified in NEIs July 24, 2020, letter.
- The staff is developing a response letter providing the backfit assessment outcome
- Deferred due to staffing and other priorities
- Letter and update to IMC 0616 expected by end of FY 2022
2020 Transformation Survey Update
Aida Rivera Executive Technical Assistant Office of the Executive Director for Operations
21 Implementation of the IAEA Additional Protocol in the U.S.
Santiago Aguilar Material Control and Accounting Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards
22 Background of the Additional Protocol
- The IAEA applies safeguards around the w orld pursuant to comprehensive safeguards agreements (CSA)
- United States: INFCIRC/288 or Voluntary Offer Agreement (1977)
- After the 1st Gulf War, discoveries in Iraq highlighted the limitations of traditional IAEA safeguards
- International community recognized the need for strengthened safeguards
- Model Additional Protocol (INFCIRC/540)
- Focuses on materials and activities, related to the nuclear fuel cycle, that were not previously covered by comprehensive safeguard agreements
2323 History of the U.S. Additional Protocol
- U.S. Additional Protocol
- Signed by the U.S. on June 12, 1998
- Entered into force on January 6, 2009
- Initial declaration submitted in 2009
- Tw o primary impacts of the U.S. Additional Protocol
- Broader reporting requirementsincluding additional aspects of the nuclear fuel cycle and related activities
- Includes initial declaration, annual updates, and quarterly export reports
- Complementary Access (CA) to facilities
2424 U.S. Safeguards Implementation
U.S. Nuclear Regulatory Commission
Department Department of Energy of Commerce
Department Department of Defense of State
2525 Complementary Access (CA)
- Complementary Access is an essential aspect of the IAEAs expanded authorities
- Complementary Access allow s the IAEA to:
- Verify the absence of undeclared nuclear materials and activities
- Resolve a question or inconsistency
- Access for IAEA w ith 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> advance notice
- 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> if IAEA is already onsite
- CAs are rare in the U.S.
- Only 2 CAs have been conducted in the U.S.
(2010)
- Framatome Inc., Fuel Fabrication Facility (Lynchburg, VA)
- Global Advanced Metals (Boyertown, PA)
2626 Reporting Requirements
- Annual reporting requirements (10 CFR Part 75.6)
- (2.a.i) Nuclear fuel cycle research and development
- Approximately 75% of the total number of U.S. declarations are 2.a.i. declarations
- (2.a.iii) Site declaration including description of activities
- Only relevant for facilities that are currently or have previously been selected for IAEA safeguards
- Not applicable to a vast majority of the industry
- (2.a.iv) Nuclear fuel cycle related manufacturing and assembly
- Annex I items from the U.S. Additional Protocol
- (2.a.v) Uranium and thorium mines, mills, and concentration plants
- (2.a.vi) Possession of large quantities of impure source material
- Source material that is not yet suitable for fuel fabrication or enrichment
- (2.a.x) Ten-year plan
- Input is not requested from the industry
- Quarterly reporting requirements [10 CFR Part 110.54(a)(1)]
- (2.a.ix) Exports of Annex II items
2727 Snapshot of Licensees Who Report Under the U.S. APand many more!
Additional Protocol
2828 Snapshot of Licensees Who Report Under the U.S. AP Agreement States!
Additional Protocol
2929 Quarterly Export Reports Explained (2.a.ix)
- For licensees using NRC general or specific license authorizations for exports of specified equipment and non-nuclear material as listed in Annex II of the Additional Protocol.
- This reporting requirement is also reflected in 10 CFR Part 110.54(a)(1) for Agreement State licensees.
- Most NRC licensees should report as a location using AP -13 form found on www.AP.gov. Report directly to Department of Commerce (DOC),
Bureau of Industry and Security (BIS) every quarter (forms are joint DOC/NRC forms).
- Quarterly deadlines to BIS are January 15, April 15, July 15, and October 15 of each year.
- Exporters should check if any of the items exported under Part 110.26 -
exports of components under General License - may also need to be reported under the AP (Part 110.54(c).
3030 Additional Protocol-Annex II
- Examples of equipment to be reported under 10 CFR 110.54(a)(1)
- Reactor Control Rods (Annex II, 1.4)
- Zirconium tubes (Annex II, 1.6)
- Reactor Primary Coolant Pump (Annex II, 1.7)
3131 Additional Protocol Reporting Process
- Information is sent to DOC by Jan 31st
- Can be sent via facsimile, mail, or email
- NRC receives licensees declarations from DOC and performs a review
- NRC compiles data and submits a report to DOC for inclusion in the overall U.S.
Government declaration
- U.S. declaration must sit before Congress for a 60- day review period (for annual report only)
3232 Additional Protocol Webpage
- The Department of Commerce manages a w ebpage that contains the handbooks and forms for the U.S. Additional Protocol
- Handbooks and forms are joint use for both DOC and NRC
- The majority of companies use the Report Handbook for Locations.
http://www.AP.gov
3333 Additional Protocol Webpage
3434 Questions
- Please ask questions early and often!
- NRC - Office of Nuclear Material Safety and Safeguards (NMSS);
Material Control and Accounting Branch (MCAB)
- Santiago Aguilar Santiago.Aguilar@nrc.gov
- Eduardo Sastre Eduardo.Sastre@nrc.gov
- Department of Commerce, Treaty Compliance Division, Bureau of Industry and Security, U.S. Department of Commerce
- Hung Ly Hung.Ly@bis.doc.gov
- Additional resource:
- http://www.nrc.gov/about-nrc/ip/intl -safeguards.html
3535 Mirabelle Shoemaker, International Safeguards Analyst Material Control and Accounting Branch Division of Security Operations Office of Nuclear Security and Incident Response
36 3
37 Benefits of Be riskSMART Framework
- Allows NRC to make decisions in the presence of uncertainty
- Using all available information to make a decision
- Reveals the entire toolbox for risk assessment and risk management
38 Benefits of Be riskSMART Framework (cont.)
- Facilitates early alignment on risks
- Enables the adoption of new technology
- Refines processes & allows NRC to select the best option
39 Can the NRC conduct an on-site inspection of Prairie Island Independent Spent Fuel Storage Installation (ISFSI) operations during the spent fuel loading campaign?
Additional background about the problem statement
- This evolution is performed ~2 years and was due within a year at the time the problem statement was identified.
- If the inspection were postponed, NRC would miss its only opportunity to evaluate license performance during cask loading operations (most risk significant activity at an ISFSI) prior to the inspection due date.
40 What could happen? (right/wrong)
What could go right?
- NRC conducts remote inspection or an on-site inspection adhering to CDC guidelines.
- In either case, an inspection is completed by the due date and in compliance with CDC guidelines.
What could go w rong?
- The inspection is postponed or delayed and the NRC misses the only opportunity to directly inspect dry cask operations for 2 years.
- A remote inspection may fail to identify safety issue.
- An onsite inspection greatly increases the risk of all involved personnel contracting COVID-19.
41 What could happen? (consequences)
What are the consequences?
- NRC cant complete the remote inspection and provide reasonable assurance that operations were conducted safely, potentially resulting in fuel damage, inadvertent release of radioactive material, unexpected exposure to workers/public, injury;
- NRC cannot conclude whether operations were conducted safely/within regulatory requirements through remote inspection; or,
- NRC can conclude that operations were conducted safely and no personnel contract COVID-19 through onsite inspection
42 What could happen? (likelihood)
How likely is it?
- That NRC conducts inspection remotely to meet at least minimum sampling-LIKELY;
- That a significant safety issue missed during a remote inspection-UNLIKELY, two previous dry cask campaigns using same vendor were successful;
- That no personnel contract COVID-19-UNLIKELY, given the increasing infection rate; and
43 What can I manage?
What can NRC do?
- Discuss remote inspection capability and experience with peers/other regions.
- Discuss opportunity to do a follow-on onsite portion of the inspection when conditions improve under PHE.
- Assess capabilities/limitations using cameras for remote inspection.
- Assess close -contact risks encountered during inspection to reduce chances of contracting COVID-19.
- Review changes to PI dry cask storage program to weigh the risk of the changes resulting in a potential safety issue.
44 What actions will I take?
What w ill NRC do?
- NRC decides to conduct a remote inspection with onsite follow-up because:
- NRC confirmed the ability to: remotely monitor ISFSI operations using a camera system; relay real-time (2 second delay) camera observations to the licensee; review other videotaped footage; and conduct daily discussions with the licensee.
- When the PHE conditions allow, NRC will be able to conduct onsite inspection of material and radiological conditions.
- Considerations that led to this action included that:
- The site had no findings of significance during last ISFSI inspection in 2018;
- The site had no process changes since previous ISFSI campaigns; and
- Onsite inspection addresses public perception of risk and lack of NRC oversight.
45 What happened when I acted?
What were the results of NRCs decision to conduct a remote inspection?
- As a result of NRCs decision to conduct a remote inspection with onsite inspection follow-up, the Biennial Prairie Island ISFSI Cask Loading Campaign Inspection was conducted in a timely manner.
- Conducting a remote inspection yielded a secondary benefit where multiple simultaneously occurring activities could be observed for longer periods of time, with reduced exposure to the inspector.
46 How can I teach others?
Follow ing the inspection:
- Staff planned to share lessons learned from the remote inspection with other inspectors;
- Staff suggested using public meetings to discuss use of remoted inspections in NRC oversight during the Covid-19 Public Health Emergency; and,
- The example was highlighted as a success story during the 2022 RIC Session for Be riskSMART: Real Examples and Real Impacts.
47 Tracking of Enriched Uranium:
NRC update on the industrys request related to tracking foreign obligations of uranium enriched <10%
Mirabelle Shoemaker, International Safeguards Analyst Material Control and Accounting Branch Division of Security Operations Office of Nuclear Security and Incident Response
48 Engagement with Industry on Reporting Foreign Obligations on LEU enriched <10%
- Industry has requested that the NRC expand the definition of E1 material to less than 10%, to match the special nuclear material description of Cat III material.
- Under this change, licensees would be able to manage foreign obligations on uranium up to 10% enrichment without the need for prior approval, in the same manner as they currently manage obligations on uranium up to 5% enrichment.
49 Engagement with Industry on Reporting Foreign Obligations on LEU enriched <10% (cont.)
- NRC conferred with Interagency Partners and presented a solution at public meeting in December 2021. The Interagency proposed that fuel facilities submit a one-time request for prior approval of obligation reassignment for their licensed blending operations.
- NRC and the interagency will consider each request as received and will have the ability to grant prior approval for obligation reassignments between E1 and E2 material.
50 Continued Pathway to Resolution
- Following the December 2021 public meeting, NRC continued dialogue with POCs at fuel facilities responsible for NMMSS reporting.
- NRC also conferred with NMMSS to identify potential impacts to other licensees.
- A public meeting is scheduled for June 22, 11am ET - 2pm, to provide details about reporting E1 material.
5151 Public Participation
At this time, the public is afforded an opportunity to ask questions and/or provide comments on the following topics:
- Safety Margin Letter
- Transformation Survey Status
- Operational Event program
- Filing System for Additional Protocol
- VLSSIR
- Be riskSmart
- Tracking of Enriched Uranium
52 Recap of Action Items - Day 1
Jonathan Row ley, Project Manager Division of Fuel Management Office of Nuclear Material Safety and Safeguards
53 Closing Remarks - Day 1
Shana Helton, Director Division of Fuel Management Office of Nuclear Material Safety and Safeguards
Janet Schlueter, Senior Director Fuel and Radiation Safety Nuclear Energy Institute
54