ML21217A302: Difference between revisions
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{{#Wiki_filter:}} | {{#Wiki_filter:NRC Perspective on BWRVIP-100 Nonconservatism Michael L. Benson, Ching Ng, and David Rudland Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Industry/NRC Materials Programs Technical Information Exchange August 10, 2021 | ||
History of Core Shroud Cracking | |||
* Relatively severe cracking discovered in the 1990s | |||
* NRC issued Generic Letter 94-03 | |||
* NRC published NUREG-1544 | |||
- Available via websearch | |||
- Summary of the cracking experience | |||
- Summary of industry response, included inspection and repair activities Industry/NRC Materials Programs Technical Information Exchange 2 | |||
Aging Management of Core Shroud | |||
* BWRVIP-76, Revision 1-A | |||
- proprietary | |||
* BWRVIP-100, Revision 1-A | |||
- proprietary | |||
* Inspection and flaw evaluation guidelines for the core shroud | |||
* ASME Code, Section XI inspection requirements for Core Support Structures | |||
* Generic Aging Lessons Learned reports for license renewal and subsequent license renewal Industry/NRC Materials Programs Technical Information Exchange 3 | |||
BWRVIP-100 Nonconservatism | |||
* Affects toughness and fluence threshold assumptions | |||
* Actual toughness could be lower than currently assumed in licensee calculations | |||
* Failure mode could transition from ductile to brittle earlier in life than previously assumed in licensee calculations | |||
* Licensee inspection frequencies for the core shroud could be too long Industry/NRC Materials Programs Technical Information Exchange 4 | |||
Staff Flaw Evaluation | |||
* Conservative assumptions | |||
- Shroud wall thickness | |||
- Crack size (through-wall and 360° surface flaw) | |||
- Loading conditions (i.e., accident conditions) | |||
* Staff calculations indicate that the shroud can tolerate a relatively severe flaw Industry/NRC Materials Programs Technical Information Exchange 5 | |||
Risk-Informed Decision Making | |||
* NRRs LIC-504 process for dispositioning emergent safety concerns | |||
* Applies key principles of risk-informed decision-making | |||
* Staff weighs options for NRC management consideration | |||
- Immediate action | |||
- Longer-term action | |||
- No action | |||
* The staff does not recommend immediate action Industry/NRC Materials Programs Technical Information Exchange 6 | |||
Conclusions | |||
* Licensees should update their inspection programs to account for the new information | |||
* LIC-504 document describes complete NRC risk-informed evaluation of the significance | |||
- Flaw analysis and risk analysis | |||
- Currently under internal review | |||
- May be made public in the future | |||
* NRC is currently assessing options for appropriate oversight of industry actions on this matter Industry/NRC Materials Programs Technical Information Exchange 7}} |
Latest revision as of 17:59, 18 January 2022
ML21217A302 | |
Person / Time | |
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Issue date: | 08/09/2021 |
From: | Michael Benson, Ching Ng, David Rudland NRC/NRR/DNRL |
To: | |
Hiser A | |
Shared Package | |
ML21217A247 | List: |
References | |
Download: ML21217A302 (7) | |
Text
NRC Perspective on BWRVIP-100 Nonconservatism Michael L. Benson, Ching Ng, and David Rudland Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Industry/NRC Materials Programs Technical Information Exchange August 10, 2021
History of Core Shroud Cracking
- Relatively severe cracking discovered in the 1990s
- NRC issued Generic Letter 94-03
- NRC published NUREG-1544
- Available via websearch
- Summary of the cracking experience
- Summary of industry response, included inspection and repair activities Industry/NRC Materials Programs Technical Information Exchange 2
Aging Management of Core Shroud
- BWRVIP-76, Revision 1-A
- proprietary
- BWRVIP-100, Revision 1-A
- proprietary
- Inspection and flaw evaluation guidelines for the core shroud
- ASME Code,Section XI inspection requirements for Core Support Structures
- Generic Aging Lessons Learned reports for license renewal and subsequent license renewal Industry/NRC Materials Programs Technical Information Exchange 3
BWRVIP-100 Nonconservatism
- Affects toughness and fluence threshold assumptions
- Actual toughness could be lower than currently assumed in licensee calculations
- Failure mode could transition from ductile to brittle earlier in life than previously assumed in licensee calculations
- Licensee inspection frequencies for the core shroud could be too long Industry/NRC Materials Programs Technical Information Exchange 4
Staff Flaw Evaluation
- Conservative assumptions
- Shroud wall thickness
- Crack size (through-wall and 360° surface flaw)
- Loading conditions (i.e., accident conditions)
- Staff calculations indicate that the shroud can tolerate a relatively severe flaw Industry/NRC Materials Programs Technical Information Exchange 5
Risk-Informed Decision Making
- Applies key principles of risk-informed decision-making
- Staff weighs options for NRC management consideration
- Immediate action
- Longer-term action
- No action
- The staff does not recommend immediate action Industry/NRC Materials Programs Technical Information Exchange 6
Conclusions
- Licensees should update their inspection programs to account for the new information
- LIC-504 document describes complete NRC risk-informed evaluation of the significance
- Flaw analysis and risk analysis
- Currently under internal review
- May be made public in the future
- NRC is currently assessing options for appropriate oversight of industry actions on this matter Industry/NRC Materials Programs Technical Information Exchange 7