ML25199A022

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NRC Slides - Hybrid Workshop to Support Comprehensive Review of Radiation Safety Cornerstones in Reactor Oversight Process - ML25199A022
ML25199A022
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Issue date: 07/18/2025
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Office of Nuclear Reactor Regulation
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Hybrid Workshop to Support Comprehensive Review of Radiation Safety Cornerstones in Reactor Oversight Process July 18, 2025 ADAMS Accession No. ML25199A022 https://www.nrc.gov/pmns/mtg?do=details&Code=20250885

Announcements/Introductions 2

Please identify yourself each time before speaking throughout the meeting.

Meeting Agenda 3

NRC Opening Remarks Meena Khanna, Director (Acting) Division of Risk Assessment Office of Nuclear Reactor Regulation 4

5 Reactor Oversight Process (ROP)

Why Oversight?

Atomic Energy Act Industry and NRC and have roles in ensuring safety

- Operate safely

- Independently conclude Inspections help confirm that U.S.

nuclear power plants are meeting their responsibilities 6

https://www.nrc.gov/docs/ML0606/ML060690104.pdf Independently conclude

7 Assessment Letters: https://www.nrc.gov/reactors/operating/oversight/listofasmrpt.html

Assessment of Plant Performance 8

Assessment of Plant Performance 9

Radiation Safety Inspection Procedures 10 IP 71124.01 Radiological Hazard Assessment and Exposure Controls IP 71124.03 In-Plant Airborne Radioactivity Control and Mitigation IP 71124.04 Occupational Dose Assessment IP 71124.05 Radiation Monitoring Instrumentation IP 71124.06 Radioactive Gaseous and Liquid Effluent Treatment IP 71124.07 Radiological Environmental Monitoring Program IP 71124.08 Radioactive Solid Waste Processing and Radioactive Material Handling, Storage, and Transportation

Developing Inspectable Areas 11

12 Cornerstone objective Attributes Areas to Measure Inspectable Areas

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Occupation Radiation Safety Objective, Attributes and Areas to Measure 14

15 Cornerstone objective Attributes Areas to Measure Inspectable Areas

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Public Radiation Safety Objective, Attributes and Areas to Measure 17

Public Radiation Safety PI 18

Occupational Radiation Safety PI 19

20 Regulatory Experience NUREG-0713, Vol 44 NUREG/CR-2907, Vol 27 NUREG-0713: https://www.nrc.gov/docs/ML2430/ML24303A136.pdf NUREG/CR-2907: https://www.nrc.gov/docs/ML2413/ML24134A119.pdf Occupational and Public Dose

SECY-025-0045 21 https://www.nrc.gov/docs/ML2512/ML25127A212

Selected ROP Revision Items Revise guidance on inspecting to minimum samples instead of nominal samples.

Gives guidance on when it may be appropriate to expect above minimum samples based on risk or licensee performance. SRI or Team Inspection lead makes the decision, Branch Chief (BC) if single person inspection. BC still approves going above max samples (and informs DD). IMC 2515 App A and IMC 0308 Attachment 2 will be issued before 1 July.

Expand the VLSSIR language in all ROP guidance documents including Inspection Manual Chapter (IMC) 0612 to cover all potential compliance issues verses only licensing basis issues. IMC 0612 and IMC 0612 Appendix B were issued on 5/27/2025 (in effect now).

Dual path ROP and TE violations are eliminated for Green and SLIV issues. IMC 0612 Appendix B issued on 5/27/2025 (in effect now).

Entrance and Exit meetings are reduced. Entrance meetings optional (coordinate with licensee) and minimal in time. Exit meetings - Can (and will most likely be) remote meetings. Exit can be Team lead with Licensing Manager, especially if no findings. IMC 2515 revision will be issued before 1 July.

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For Workshop Discussion What performance-related information is available to licensees that can be used by the NRC to risk-inform its inspection effort? Is this information standardized across the industry? If not standardized, is there support for doing so? Would the staff have the ability to document this information in an inspection report to justify modulating inspection effort?

What approaches that do not involve inspection are available to verify performance indicator information?

The staff is considering shifting some inspection effort to remote-based inspection if it can conclude that licensee performance can be adequately evaluated using this approach. Given preexisting knowledge of the IP 71124 inspection procedures, what would be the licensees resource impact of shifting some of the inspection effort to remote?

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For Workshop Discussion

  • Recognizing that radioactive effluents and environmental monitoring are areas of low radiological safety significance, but important areas of the NRCs regulatory framework, what changes could the staff consider to right-size oversight in this area?
  • Radiation protection programs are best assessed during periods of high radiological risk significance; however, at these times, licensee personnel resources are most strained. What are some approaches that the NRC and licensees could adopt to ensure risk-informed, performance-based inspection can continue during these periods, while minimizing impact on licensee resources.

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Thank you!

25 NRC concluded that overall performance at your facility preserved public health and safety

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Break 27

Public Comment 28

Contacts David Garmon david.garmon@nrc.gov 301-415-3512 Bill Rautzen william.rautzen@nrc.gov 301-415-7206 https://www.nrc.gov/pmns/mtg?do=details&Code=20250885 How did we do?

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