ML21019A071
| ML21019A071 | |
| Person / Time | |
|---|---|
| Issue date: | 01/21/2021 |
| From: | Hector Rodriguez-Luccioni NRC/NRR/DNRL/NLRP |
| To: | |
| Rodriguez-Luccioni H | |
| References | |
| Download: ML21019A071 (7) | |
Text
Public NRC Meeting License Renewal for 100 years of Plant Operation, Technical Issues for Civil Structures and Concrete A Researchers Point of View Victor E. Saouma url; saouma@colorado.edu University of Colorado, Boulder X-Elastica, LLC Jan 21, 2021 Victor E. Saouma; Univ. of Colorado 100 Years of operation? Concrete Concerns 1/7
Table of Contents 1 A: Should the NRC develop guidance?
2 B: Technical issues 3 C: Approaches Lessons Learned by VES Recommendations 4 Background Victor E. Saouma; Univ. of Colorado 100 Years of operation? Concrete Concerns 2/7
A: Should the NRC develop guidance?
My guess is that there will be a strong push from industry (and possibly from the NRC) for such an extension.
Short answer: Yes. If the Pentagon has contingency plans to attack Canada, then the NRC should develop properly crafted contingency documents for a 100 years operation, as soon as possible.
Note:
Keep in mind that there is a time lag between scientific knowledge and engineering codes.
To the best of my knowledge no other country is making such a bold move, not even for 80 years Let us always keep in mind that those reactors were designed with 40+
year-old technology for 40 years (not 60, 80, let alone 100).
Since then much has been learned about aging, seismic, and safety. We can not ignore those developments.
Victor E. Saouma; Univ. of Colorado 100 Years of operation? Concrete Concerns 3/7
B: Technical issues 3 6 3 2.3 1: Chloride diffusion; LCF/ILRT Delayed Ettringite 8 2.6 Thermal cycles 10 2.3 2: Carbonation; Freeze/Thaw Succeptibility Succeptibility 5 2.1 Shrinkage Formation 1 2.9 Creep 2 2 3: AAR; External Sulfate 12 3 2 7 1.7 2.0 2.9 2.6 4a DEF; Fracture 4b 4b: External sulfate Attack 1 4a 1 1.4 1.6 1.9 attach; 9 5: Acid attack; 11 2.3 Chloride Diffusion Time Dependent 6: leaching; Sulfate Attack Temperature 0 0 Carbonation Acid Attack Leaching Mechanical 1 2 3 1 2 3 7: Shrinkage; ASR Knowledge Knowledge 8: Creep; 9: Thermal cycling; Confidence values High 10: Freeze and thaw; Symbol size and color is a measure of structural Chemical Physical Radiation Medium significance, relative to a maximum value of 3 11: Fracture; Low 12: Radiation.
Containment Internal Structure concrete Technical issues have been addressed (for 80 years of operations) by NUREG/CR-7153, Vol 4 Expanded Materials Degradation Assessment (EMDA)
Volume 4: Aging of Concrete and Civil Structures (2014)1 Two sites have been affected (as far as I know) by ASR:
Seabrook: Containment building North Anna: Transmission towers Biggest issues (2021) & both cause swelling AAR Containment building Radiation Reactor vessel Within a 100 years operations, likely to be many more.
1 I was a member of the panel Victor E. Saouma; Univ. of Colorado 100 Years of operation? Concrete Concerns 4/7
C: Approaches Lessons Learned by VES First, lessons learned from my personal involvement with Crystal River and Seabrook2 NRC has not regulated, but commented on documents submitted by industry Minimal technical input from regulator Absence of well known NRC experts (such as Herman Graves, Dan Naus or Abdul Sheikh)
No panel reviews What is the point in having knowledge (per previous slide) if it is not applied and we remain shackled by 40 years old design codes!
Administrative/bureaucratic considerations prevailed over best possible (and reasonable/achievable) safety.
This paradigm should be avoided in its entirety. This is now an entirely new ball game 2
This is relevant as it is indicative as to how the NRC seems to have has addressed technical challenges related to Beyond Design Basis Victor E. Saouma; Univ. of Colorado 100 Years of operation? Concrete Concerns 5/7
C: Approaches Recommendations The NRC should:
1 Safety and not $$ utmost priority 2 Science first, Engineering second 3 Develop regulation itself and not subcontract task to industry or EPRI.
4 Convene panel of experts and revisit the 2014 EMDA.
5 Fund and adopt research (laboratory tests and simulation tools) when needed, and results should be implemented in regulations 6 Convene technical panels, perform peer reviews 7 Forget original design codes for operation or aging management, enforce compliance with most recent ones, and prioritize scientific knowledge over design codes 8 Tighten Aging Management Program 9 Should be a collaborative effort between Scientists, Engineers, Regulators, &
Utility Companies.
and maintain its worldwide leadership in nuclear safety.
Victor E. Saouma; Univ. of Colorado 100 Years of operation? Concrete Concerns 6/7
Background
RILEM State-of-the-Art Reports Victor Saouma Saouma Saouma
- Hariri-Ardebili Mohammad Amin Hariri-Ardebili Numerical Modeling of AAR isting struc-s.
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lorem. Integer at tellus nulla, id venenatis lorem. Etiam ut condimentum Aging, Shaking, Diagnosis &
. codes), this felis. Morbi et tortor vitae est lobortis rhoncus. Praesent eget facilisis the first 1 lorem. In hac habitasse platea dictumst. Aliquam sagittis mauris eget massa aliquam eget auctor arcu ultrices. Sed rhoncus faucibus diam, quis porta libero dapibus quis. Sed nibh nisl, viverra eu pretium eget, and Cracking oncrete tincidunt convallis mauris. Donec tortor neque, congue et gravida a, Prognosis feugiat vitae nulla.
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From Mechanics to of AAR Affected Concrete Dams and Nuclear Structures Structures State-of-the-Art Report of the RILEM Technical Committee 259-ISR Victor E. Saouma barcode an informa business Victor E. Saouma Victor E. Saouma; Univ. of Colorado 100 Years of operation? Concrete Concerns 7/7