ML19214A203
| ML19214A203 | |
| Person / Time | |
|---|---|
| Issue date: | 08/06/2019 |
| From: | Andrew Proffitt, Jennifer Whitman Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| Download: ML19214A203 (6) | |
Text
NRC Public Meeting:
Draft Interim Staff Guidance for Chromium-Coated Cladding Andrew Proffitt, NRR Josh Whitman, NRR August 6, 2019
Background
- September 2018: NRCs Accident Tolerant Fuel (ATF) Project Plan issued (ML18261A414)
- October 2018: Electric Power Research Institute (EPRI) Coated Cladding Gap Analysis
- November 2018: Nuclear Energy Institute In-Reactor Screening Review
- January 2019: Initial report on degradation and failure mechanisms of Cr-coated cladding issued
- April 2019: Expert panel convened to conducted phenomena identification and ranking table (PIRT)
- June 2019: Final PIRT report on degradation and failure mechanisms of Cr-coated cladding issued (ML19172A154) 2
ISG Development Timeline
- July 18, 2019: Initial public draft issued
- August 06, 2019: Public meeting to solicit stakeholder feedback
- September 17, 2019: ACRS Subcommittee briefing
- September 30, 2019: Issue in Federal Register for public comment
- Early December 2019: Public meeting on comment resolution
- Late December 2019: Final issuance of ISG 3
ISG will incorporate PIRT findings into regulatory infrastructure
- ISG does not: General Design Criterion 10 -
- include new requirements Reactor design. The reactor
- create new rules or core and associated coolant, regulations control, and protection
- require specific testing or systems shall be designed analyses with appropriate margin to assure that specified
- ISG does: acceptable fuel design limits
- provide guidance to staff, are not exceeded during any informed by the PIRT, on condition of normal important areas for review operation, including the
- provide information to effects of anticipated vendors and licensees of what is expected operational occurrences.
4
Standard Review Plan (SRP)
Chapter 4 - Reactor
- Fuel properties
- Refers to Appendix B, taken from the PIRT
- All properties listed should be addressed in submittal
- Specified acceptable fuel design limits (SAFDLs)
- Refers to Appendix C, taken from the PIRT
- Existing SAFDLs may need to be amended
- New failure mechanisms listed
- Should be addressed by submittal
- Many may be covered by existing SAFDLs
- New SAFDLs may be needed
- Nuclear and thermal hydraulic design requirements exist in Sections 4.3 and 4.4 5
SRP Chapter 15 - Transient and Accident Analysis
- Changes to material properties and thermal mechanical behavior should be incorporated
- Impact on each anticipated operational occurrence (AOO) and postulated accident should be addressed
- Impacts of changes to existing SAFDLs should be addressed 6