ML23093A103
| ML23093A103 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 08/01/2023 |
| From: | Bo Pham Plant Licensing Branch II |
| To: | Brown R Southern Nuclear Operating Co |
| References | |
| EPID L-2022-LLE-0020 | |
| Download: ML23093A103 (1) | |
Text
NUCLEAR REGULATORY COMMISSION Docket No. 50-425 Southern Nuclear Operating Company Vogtle Electric Generating Plant, Unit 2 Exemption I. Background.
Southern Nuclear Operating Company (SNC, the licensee) is the holder of Facility Operating License No. NPF-81, for the Vogtle Electric Generating Plant (Vogtle),
Unit 2. The license provides, among other things, that the license is subject to all rules, regulations, and orders of the Commission now or hereafter in effect.
The Vogtle, Unit 2, consists of a pressurized-water reactor located at the licensees site in Burke County, Georgia.
II. Request/Action.
By letter dated June 30, 2022 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML22181B156), as supplemented by letters dated September 13, 2022 (ML22256A198), January 20, 2023 (ML23020A148), and May 5, 2023 (ML23125A269), SNC requested an exemption to Title 10 of the Code of Federal Regulations (10 CFR), part 50, Section 50.46, Acceptance criteria for emergency core cooling systems for light-water nuclear power reactors, for Vogtle, Unit 2.
Specifically, SNC requested an exemption from 10 CFR 50.46 to allow the use of AXIOM fuel rod cladding material in lead test assemblies (LTAs) 7ST1, 7ST2, 7ST3, and 7ST4 for up to two cycles of operation at Vogtle, Unit 2.
The regulation at 10 CFR 50.46(a)(1)(i) requires that, Each boiling or pressurized light-water nuclear power reactor fueled with uranium oxide pellets within cylindrical zircaloy or ZIRLO cladding must be provided with an emergency core cooling system (ECCS) that must be designed so that its calculated cooling performance following postulated loss-of-coolant accidents conforms to the criteria set forth in paragraph (b) of this section. The regulations make no provisions for use of fuel rods clad in a material other than zircaloy or ZIRLO.
III. Discussion.
Pursuant to 10 CFR 50.12, the NRC may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR part 50, including 10 CFR 50.46, when: (1) the exemptions are authorized by law, will not present an undue risk to the public health or safety, and are consistent with the common defense and security; and (2) when special circumstances are present. Under 10 CFR 50.12(a)(2), special circumstances include, among other things, when application of the specific regulation in the particular circumstances would not serve, or is not necessary to achieve, the underlying purpose of the rule.
A. The Exemption is Authorized by Law.
In accordance with 10 CFR 50.12, the NRC may grant an exemption from the requirements of 10 CFR part 50 if the exemption is authorized by law. The exemption 2
requested in this instance is authorized by law, because no other prohibition of law exists to preclude the activities which would be authorized by the exemption.
This exemption would allow the licensee to insert four LTAs containing AXIOM fuel rod cladding that is neither Zircaloy nor ZIRLO, which are the cladding materials contemplated by 10 CFR 50.46(a)(1)(i). Selection of a specific cladding material in 10 CFR 50.46 was at the discretion of the Commission consistent with its statutory authority. No statute required the NRC to adopt this specification. As stated above, 10 CFR 50.12 allows the Commission to grant exemptions from the requirements of 10 CFR part 50. The NRC staff has determined that granting of an exemption from 10 CFR 50.46 related to AXIOM fuel rod cladding, which is neither Zircaloy nor ZIRLO, will not result in a violation of the Atomic Energy Act of 1954, as amended, or the Commission's regulations. Therefore, the exemption is authorized by law.
B. The Exemption Presents no Undue Risk to Public Health and Safety.
SNC stated the following in its letter dated June 30, 2022:
The Vogtle reactors each contain 193 fuel assemblies. Each assembly consists of a matrix of 264 Zircaloy, ZIRLOTM[], or Optimized ZIRLO[TM]
clad fuel rods with an initial composition of natural or slightly enriched uranium dioxide (UO2) as fuel material, not to exceed 5 wt% [weight-percent] enrichment. The proposed change is to load four LTAs with advanced ATF [accident-tolerant fuel] features, including ADOPT fuel [2],
AXIOM cladding [3], chromium coating, and four rods per LTA with up to 6 wt% enrichment, in limiting core locations for up to two cycles of operation.
This exemption will not present an undue risk to public health and safety.
Reload evaluations ensure that acceptance criteria are met for the insertion of LTAs with fuel rods clad with AXIOM material. Due to similarities in the composition of the AXIOM alloy and the Optimized ZIRLO and standard ZIRLO alloys, fuel assemblies using AXIOM fuel rod cladding are evaluated using plant-specific models to address the changes in the cladding material properties. The LOCA [loss-of-coolant accident] safety analyses for VEGP [Vogtle Electric Generating Plant] are supported by the applicable site-specific Technical Specifications (TS).
Reload cores are required to be operated in accordance with the 3
operating limits specified in the TS. Thus, the granting of this exemption request will not pose an undue risk to public health and safety.1 Based upon the limited number of AXIOM clad fuel rods, the safeguards in place which would detect anomalous behavior, the use of NRC-approved models to ensure that all design criteria remain satisfied, and the requirement to operate the Vogtle, Unit 2, core within TS limits, the NRC staff finds the four LTAs acceptable for Vogtle, Unit 2. In conclusion, the NRC staff finds that the requested exemption does not result in any undue risk to the public health and safety, because NRC staff concluded that the existing LOCA evaluation models analysis of records for Vogtle are representative of the LTAs, and the presence of the LTAs will have a negligible impact on the co-resident fuel, and 10 CFR 50.46 acceptance criteria continue to be met. Further information can be found in the NRC staff safety evaluation (ML23093A028).
C. The Exemption is Consistent with the Common Defense and Security.
The proposed exemption would allow the use of four LTAs with a variant cladding material. This change to the plant core configuration has no impact on security issues.
Special nuclear material in the LTAs will continue to be handled and controlled in accordance with applicable regulations. Therefore, the common defense and security is not impacted by this exemption.
D. Special Circumstances Special circumstances, in accordance with 10 CFR 50.12(a)(2)(ii), are present whenever application of the regulation in the particular circumstances would not serve 1
Although this quoted material states that the LTAs would be placed in limiting core locations, SNCs May 5, 2023, supplement, states that the LTAs will not be placed in core regions that have been shown to be limiting with respect to the control rod ejection analysis.
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the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule. The underlying purpose of 10 CFR 50.46 is to establish acceptance criteria for ECCS performance. In the safety evaluation (SE) contained in (ML23093A028) for the license amendment request, the NRC staff evaluated for Vogtle, Unit 2, four LTAs that demonstrated the acceptability of the AXIOM cladding under LOCA conditions. The unique features of the LTAs were evaluated for effects on the LOCA analyses. The results showed that the LTAs would not adversely affect ECCS performance. Therefore, the NRC staff concludes that application of the limitation to zircaloy and ZIRLO in 10 CFR 50.46 in this particular circumstance is not necessary for the licensee to achieve the underlying purpose of the rule.
E. Environmental Considerations With respect to its impact on the quality of the human environment, the NRC has determined that the issuance of the exemption discussed herein meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). The NRC staffs determination that all of the criteria for this categorical exclusion are met is as follows:
The regulation 10 CFR 51.22(c)(9) states:
Issuance of an amendment to a permit or license for a reactor under part 50 or part 52 of this chapter that changes a requirement or issuance of an exemption from a requirement, with respect to installation or use of a facility component located within the restricted area, as defined in part 20 of this chapter; or the issuance of an amendment to a permit or license for a reactor under part 50 or part 52 of this chapter that changes an inspection or a surveillance requirement; provided that: (i) The amendment or exemption involves no significant hazards consideration; (ii) There is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite; and (iii) There is no significant increase in individual or cumulative occupational radiation exposure.
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Staff Analysis: The exemption is from requirements with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR part 20. The criteria for determining whether an action involves a significant hazards consideration are found in 10 CFR 50.92. The proposed action involves installed four LTAs. As stated in the evaluation in ML23093A028, the Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, published in the Federal Register on November 8, 2022 (87 FR 67508),
and there has been no public comment on such finding.
The proposed action involves installing four LTAs, and as the NRC staff evaluated under the SE contained in ML23093A028, this action does not involve any significant change in the types or significant increase in the amounts of any effluents that may be released offsite.
The proposed action involves installing four LTAs, and as the NRC staff evaluated under the SE contained in ML23093A028, this action does not involve any significant increase in individual or cumulative occupational exposure.
Based on the above, the NRC staff concludes that the proposed exemption meets the eligibility criteria for the categorical exclusion set forth in 10 CFR 51.22(c)(9).
Therefore, in accordance with 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the NRCs issuance of this exemption.
IV. Conclusions.
Accordingly, the NRC has determined that, pursuant to 10 CFR 50.12, the exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security. Also, special 6
circumstances, pursuant to 10 CFR 50.12(a)(2)(ii), are present. Therefore, the NRC hereby grants SNC an exemption from the requirements of 10 CFR 50.46 to allow the use of AXIOM fuel rod cladding material in LTAs, 7ST1, 7ST2, 7ST3, and 7ST4, for up to two cycles of operation at Vogtle, Unit 2.
Dated at Rockville, Maryland, this 1st day of August, 2023 For the Nuclear Regulatory Commission.
Digitally signed by Bo M.
Pham Bo M. Pham Date: 2023.08.01 16:12:09 -04'00' Bo M. Pham, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
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