ML21312A545: Difference between revisions

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{{#Wiki_filter:November 17, 2021 MEMORANDUM TO:                  Brian W. Smith, Director Division of New and Renewed Licenses Office of Nuclear Reactor Regulation FROM:                          Angela R. Buford, Chief /RA/
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Vessels and Internals Branch Division of New and Renewed Licenses Office of Nuclear Reactor Regulation
 
==SUBJECT:==
TECHNICAL ASSESSMENT OF NONCONSERVATIVE FRACTURE TOUGHNESS IN BOILING WATER REACTOR VESSEL AND INTERNALS PROJECT TOPICAL REPORT, BWRVIP-100, REVISION 1-A In accordance with the Office of Nuclear Reactor Regulation (NRR) Instruction LIC-504, Revision 5, Integrated Risk-Informed Decision-Making Process for Emergent Issues, dated March 4, 2020, the staff of the U.S. Nuclear Regulatory Commission (NRC) has performed a risk-informed evaluation of the potential safety significance of a fracture toughness nonconservatism in BWRVIP-100, Revision 1-A.
On February 17, 2021, during an information exchange meeting between NRC management and industry materials issues program leadership, the NRC was made aware of a potential nonconservatism in Boiling-Water Reactor Vessel and Internals Project (BWRVIP) guidance on fracture toughness values for evaluation of irradiated stainless steel reactor internals components. This guidance is contained in Electric Power Research Institute (EPRI) report BWRVIP-100, Revision 1-A and describes recommendations for fracture toughness and evaluation of flaws in a boiling water reactor core shroud.
EPRI subsequently determined that, although BWRVIP-100, Revision 1-A was not prepared under EPRIs Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants, nuclear quality assurance (NQA) program, the report had been incorporated into another EPRI product (BWRVIP-235) that was prepared under EPRIs NQA program. As such, a 10 CFR Part 21, Reporting of Defects and Noncompliance, Transfer of Information Notice was sent to EPRI members on February 19, 2021 (modified on March 19, 2021). EPRI transmitted a copy of this notice (BWRVIP-2021-030) to the NRC on March 22, 2021 (Agencywide Documents Access and Management System ML21084A164).
CONTACT: Michael Benson, NRR/DNRL 301-415-2425
 
B. Smith                                            As a result of the initial investigation, EPRI recommended the following to its members:
: 1. The BWRVIP-235 software should not be used going forward to evaluate flaws in the weld region of reactor internals where the accumulated fluence is greater than 5E20 n/cm2 (E>1MeV).
: 2. Recipients should evaluate their use of these EPRI products to determine if any flaw evaluations could be impacted, possibly resulting in either a reduction in structural margins or changes in inspection frequencies, specifically those components having an accumulated fluence in the range of 5E20 n/cm2 to 3E21 n/cm2.
: 3. If BWRVIP-100, Revision 1-A was implemented without the use of BWRVIP-235, the specific requirements associated with the 10 CFR Part 21 Transfer of Information may not be applicable. However, the potential nonconservatism of BWRVIP-100, Revision 1-A would still need to be evaluated.
The enclosure to this memorandum summarizes the NRC staffs analysis of the safety implication of the nonconservative fracture toughness values in BWRVIP-100, Revision 1-A.
The NRC staff assessment concludes that the safety significance of the nonconservative fracture toughness in BWRVIP-100, Revision 1-A is low for U.S. plants.
The options considered by staff include the following:
: 1. Issue Shut Down Orders  This option requires shut down of some or all operating reactors, through a regulatory process such as an order, until inspections, analyses and mitigation are conducted to provide reasonable assurance that the calculated risk levels are acceptable.
: 2. Leverage NRC Inspection Programs  EPRI has initiated communications with impacted licensees, describing the potential nonconservatism and how licensees may need to adjust their plant-specific programs. This option leverages existing Regional inspection programs to target licensee corrective actions to address the BWRVIP-100, Revision 1-A nonconservatism.
: 3. Take no Action  In this option, the agency takes no action or programmatic approach to verify licensee corrective actions.
Option 1 is not justified in light of the low risk associated with the BWRVIP-100, Revision 1-A nonconservatism. While failure of the core shroud might impact safe shutdown capability, the low loads on the shroud during normal operation make core shroud failure a highly unlikely event. Therefore, the staff judges that immediate regulatory action is unwarranted.
While Option 3 has the least impact on NRC and industry resources, it also provides no independent oversight of plant-specific programs. The NRC would be entirely relying on the interactions with EPRI and the limited information available to staff, without observing actual licensee corrective actions and drawing independent conclusions about their efficacy.
Therefore, the staff does not recommend Option 3.
Option 2 provides appropriate oversight of licensee corrective actions without negatively impacting NRC and industry resources. Focused inspection activities within the Reactor Oversight Process (or some similar process) will provide information to the staff about plant-
 
B. Smith                                        specific reactor vessel internal inspection programs and will serve as an independent check on licensee activities related to the BWRVIP-100, Revision 1-A nonconservatism.
Therefore, given the risk determination, and the uncertainty associated with the plant-specific action, the NRC staff recommends Option 2.
 
==Enclosure:==
 
Technical Assessment of Nonconservative Fracture Toughness In BWRVIP-100, Revision 1-A
 
MEMO: ML21312A545 ENCLOSURE: ML21312A545                    *via e-mail            NRR-106 OFFICE    NRR/DNRL/NVIB: PM NRR/DNRL/NRLB: LA      NRR/DNRL/NVIB: BC NAME      MBenson          SGreen                  ABuford DATE      11/08/2021        11/09/2021              11/10/2021 OFFICE    NRR/DNRL          NRR/DRA/APHB            NRR/DRA/APHB NAME      DRudland          CNg                    AZoulis DATE      11/10/2021        11/12/2021              11/15/2021 OFFICE    NRR/DRA          NRR/DNRL/NVIB: BC NAME      SWeerakkody      ABuford DATE      11/16/2021        11/17/2021}}

Revision as of 16:18, 16 January 2022

Technical Assessment of Non-conservative Fracture Toughness in Boiling Water Reactor Vessel and Internals Project Topical Report, BWRVIP-100, Revision 1-A
ML21312A545
Person / Time
Issue date: 11/17/2021
From: Angela Buford
NRC/NRR/DNRL/NVIB
To: Beverly Smith
NRC/NRR/DNRL
Benson M
Shared Package
ML21312A543 List:
References
Download: ML21312A545 (4)
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