ML24220A246
| ML24220A246 | |
| Person / Time | |
|---|---|
| Site: | Hatch, 07200036  |
| Issue date: | 10/08/2024 |
| From: | Christian Jacobs Storage and Transportation Licensing Branch |
| To: | Southern Nuclear Operating Co |
| Shared Package | |
| ML24220A245 | List: |
| References | |
| NRC-2024-0147, 89 FR 82645 | |
| Download: ML24220A246 (1) | |
Text
[7590- 01-P]
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 72-36, 50 -321, and 50- 366; NRC-2024- 0147]
Southern Nuclear Operating Compa ny;
Edwin I. Hatch Nuclear Plant Units 1 and 2;
Independent Spent Fuel Storage Installation;
Environmental Assessment and Finding of No Significant Impact
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice; issuance.
SUMMARY
- The U.S. Nuclear Regulatory Commission (NRC) is issuing an
environmental assessment (EA) and a finding of no significant impact (FONSI) for an
exemption request submitted by Southern Nuclear Operating Company (SNC) that
would permit Edwin I. Hatch Nuclear Plant (Hatch) Units 1 and 2, to maintain and load
68M multi-purpose canisters (MPC) with continuous basket shims (CBS) in the HI-
STORM 100 Cask System at its Hatch Units 1 and 2 independent spent fuel storage
installation (ISFSI) in a storage condition where the terms, conditions, and specifications
in the Certificate of Compliance (CoC) No. 1014, Amendment No. 11 are not met.
DATES: The EA and FONSI referenced in this document are available on October 11,
2024.
ADDRESSES: Please refer to Docket ID NRC-2024- 0147 when contacting the NRC
about the availability of information regarding this document. You may obtain publicly
available information related to this document using any of the following methods:
- Federal Rulemaking Webs ite: Go to https://www.regulations.gov and
search for Docket ID NRC-2024- 0147. Address questions about D ocket IDs in
Regulations.gov to Stacy Schumann; telephone: 301-415- 0624; email:
Stacy.Schumann@nrc.gov. For technical questions, contact the individual listed in the
For Further Information Contact section of this document.
- NRCs Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly available documents online in the ADAMS Public
Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the
search, select Begin Web-based ADAMS Search. For problems with ADAMS, please
contact the NRCs Public Document Room (PDR) reference staff at 1-800-397-4209, at
301-415-4737, or by email to PDR. Resource@nrc.gov. For the convenience of the
reader, instructions about obtaining materials referenced in this document are provided
in the Availability of Documents section.
- NRCs PDR: The PDR, where you may examine and order copies of publicly
available documents, is open by appointment. To make an appointment to visit the PDR,
please send an email to PDR.Resource@nrc.gov or call 1-800-397-4209 or 301-415-
4737, between 8 a.m. and 4 p.m. eastern time (ET), Monday through Friday, except
Federal holidays.
FOR FURTHER INFORMATION CONTACT: Heath Stroud, Office of Nuclear Material
Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001; telephone: 301-287-3664; email: Heath.Stroud@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is reviewing an exemption request from SNC, dated June 25, 2024,
and supplemented on July 26, 2024. SNC is requesting an exemption, pursuant to
section 72.7 of title 10 of the Code of Federal Regulations (10 CFR), Specific
exemptions, in paragraphs 72.212(a)(2), 72.212(b)(3), 72.212(b)(5)(i), 72.212(b)(11),
and 72.214 that require SNC to comply with the terms, conditions, and specifications of
2 the CoC No. 1014, Amendment No. 11. If approved, the exemption would allow SNC to
maintain three loaded and to load five new MPC-68M -CBS in the HI-STORM 100 Cask
System at the Hatch ISFSI in a storage condition where the terms, conditions, and
specifications in the CoC No. 1014, Amendment No. 11, are not met.
II. Environmental Assessment
=
Background===
Hatch is 32 kilometers (20 miles) east of Vidalia, Georgia. The plant is located on
the southwest side of the Altamaha River. Unit 1 began operating in 1975 and Unit 2
began operating in 1979. SNC has been storing spent fuel in the Hatch ISFSI under a
general license as authorized by 10 CFR p art 72, subpart K, General License for
Storage of Spent Fuel at Power Reactor Sites. SNC currently uses the HI-STORM 100
Cask System under CoC No. 1014, Amendment No. 11 for dry storage of spent nuclear
fuel in a specific MPC (i.e., MPC-68M) at the Hatch ISFSI.
Description of the Proposed Action
The CoC is the NRC-approved design for each dry cask storage system. The
proposed action would exempt the applicant from the requirements of
10 CFR 72.212(a)(2), 72.212(b)(3), 72.212(b)(5)(i), 72.212(b)(11), and 72.214 only as
these requirements pertain to the use of the MPC-68M -CBS in the HI-STORM 100 Cask
System. The exemption would allow SNC to maintain three loaded and to load five new
MPC-68M -CBS in the HI-STORM 100 Cask System at the Hatch ISFSI, despite the
MPC-68M -CBS in the HI-STORM 100 Cask System not being in compliance with the
terms, conditions, and specifications in the CoC No. 1014, Amendment No. 11.
The HI-STORM 100 Cask System CoC provides the requirements, conditions,
and operating limits necessary for use of the system to store spent fuel. Holtec
International (Holtec), the designer and manufacturer of the HI-STORM 100 Cask
3 System, developed a variant of the design with CBS for the MPC-68M, known as MPC-
68M-CBS. Holtec originally implemented the CBS variant design under the provisions of
10 CFR 72.48, which allows licensees to make changes to cask designs without a CoC
amendment under certain conditions (listed in 10 CFR 72.48(c)). After evaluating the
specific changes to the cask designs, the NRC determined that Holtec erred when it
implemented the CBS variant design under 10 CFR 72.48, as this was not the type of
change allowed without a CoC amendment. For this reason, the NRC issued three
Severity Level IV violations to Holtec. However, SNC had previously loaded three MPC-
68M-CBS in the HI-STORM 100 Cask System and plans to load five MPC-68M-CBS in
the HI-STORM 100 Cask System beginning in April 2025. This exemption considers the
storage of the three already loaded systems and the planned loading of the five
canisters with the CBS variant basket design.
Need for the Proposed Action
SNC requested this exemption because SNC is currently out of compliance with
NRC requirements, resulting from the previous loading of spent fuel into a storage
system with the CBS variant basket design. This exemption would allow three already
loaded MPC-68M-CBS in the HI-STORM 100 Cask System to remain in storage at the
Hatch ISFSI. The exemption would also allow SNC to load five new MPC-68M-CBS in
HI-STORM 100 Cask System at the Hatch ISFSI for the future loading campaign
scheduled to begin in April 2025.
Approval of the exemption request would allow SNC to effectively manage the
spent fuel pool margin and capacity to enable refueling and offloading fuel from the
reactor. It would also allow SNC to effectively manage the availability of the specialized
resources and equipment needed to support competing fuel loading and operational
activities at Hatch.
4 Environmental Impacts of the Proposed Action
This EA evaluates the potential environmental impacts of granting an exemption
from the terms, conditions, and specifications in CoC No. 1014, Amendment No. 11. The
exemption would allow three already loaded MPC-68M-CBS in the HI-STORM 100 Cask
System to remain loaded at the Hatch ISFSI. The exemption would also allow five new
MPC-68M-CBS to be loaded in the HI-STORM 100 Cask System in loading campaigns
and maintained in storage at the Hatch ISFSI.
The potential environmental impacts of storing spent nuclear fuel in NRC-
approved storage systems have been documented in previous assessments. On
July 18, 1990 (55 FR 29181), the NRC amended 10 CFR part 72 to provide for the
storage of spent fuel under a general license in cask designs approved by the NRC. The
EA for the 1990 final rule analyzed the potential environmental impacts of using NRC-
approved storage casks. The EA for the HI-STORM 100 Cask System, CoC No. 1014,
Amendment No. 11, published in 2018 tiers off of the EA issued for the July 18, 1990,
final rule (83 FR 63794). Tiering off earlier EAs is a standard process encouraged by
the regulations implementing the National Environmental Policy Act of 1969 (NEPA) that
entails the use of impact analyses of previous EAs to bound the impacts of a proposed
action where appropriate. The Holtec HI-STORM 100 Cask System is designed to
mitigate the effects of design basis accidents that could occur during storage.
Considering the specific design requirements for the accident conditions, the design of
the cask would prevent loss of containment, shielding, and criticality control. If there is
no loss of containment, shielding, or criticality control, the environmental impacts would
not be significant.
The exemptions requested by SNC at the Hatch site as they relate to CoC No.
1014, Amendment No. 11, for the HI-STORM 100 Cask System are limited to the use of
5 the CBS variant basket design only for the three previously loaded canisters and
planned loading of five canisters utilizing the CBS variant basket design. The staff has
determined that this change in the basket will not result in either radiological or non-
radiological environmental impacts that significantly differ from the environmental
impacts evaluated in the environmental assessment supporting the issuance of CoC
No. 1014, Amendment No. 1 1. If the exemption is granted, there will be no significant
change in the types or amounts of any effluents released, no significant increase in
individual or cumulative public or occupational radiation exposure, and no significant
increase in the potential for or consequences from radiological accidents. Accordingly,
the Commission concludes that there would be no significant environmental impacts
associated with the proposed action.
Alternative to the Proposed Action
The staff considered the no-action alternative. The no -action alternative (denial of
the exemption request) would require SNC to unload spent fuel from the MPC-68M-CBS
in the HI-STORM 100 Cask System to bring it in compliance with the CoC terms,
conditions, and specifications in the CoC No. 1014, Amendment No. 11. Unloading the
cask would subject station personnel to additional radiation exposure, generate
additional contaminated waste, increase the risk of a possible fuel handling accident,
and increase the risk of a possible heavy load handling accident. Furthermore, the
removed spent fuel would need to be placed in the spent fuel pool, where it would
remain until it could be loaded into an approved storage cask. SNC has rescheduled its
2024 loading campaign to April 2025, and further delay in the loading of this spent fuel
into other casks could affect SNCs ability to effectively manage the spent fuel pool
capacity and reactor fuel offloading. Not allowing the planned future loading campaign
could affect SNCs ability to manage pool capacity, reactor fuel offloading, and refueling.
6 It could also pose challenges to spent fuel heat removal and impact the availability of the
specialized resources and equipment needed to support competing fuel loading and
operational activities at Hatch, including spent fuel pool clean-up and refueling outages.
SNC has ordered an additional five MPC-68M canisters for the planned loading starting
in April 2025, that comply with CoC No. 1014, Amendment No. 11. However, due to
factors outside of SNCs control, delivery of the compliant canisters is not guaranteed for
the April 2025 loading.
The NRC has determined that the no-action alternative would result in undue
potential human health and safety impacts that could be avoided by proceeding with the
proposed exemption, especially given that the staff has concluded in NRCs Safety
Determination Memorandum, issued with respect to the enforcement action against
Holtec regarding these violations, that fuel can be stored safel y in the MPC-68M-CBS
canisters.
Agencies Consulted
The NRC provided the Georgia Division of Natural Resources (DNR) and
Georgia Emergency Management and Homeland Security Administration (GEMA) a
copy of this draft EA for review by an email dated August 28, 2024. On
September 25, 2024, Georgia DNR and GEMA provided its concurrence by email.
III. Finding of No Significant Impact
The environmental impacts of the proposed action have been reviewed in
accordance with the requirements in 10 CFR part 51, which implement NEPA. Based
upon the foregoing e nvironmental assessment, the NRC finds that the proposed action
of granting the exemption from the regulations in 10 CFR 72.212(a)(2), 72.212(b)(3),
72.212(b)(5)(i), 72.212(b)(11), and 72.214, which require the licensee to comply with the
terms, conditions, and specifications of the CoC, in this case limited to the past and
7 specific future loading of baskets with the CBS variant design, would not significantly
impact the quality of the human environment. Accordingly, the NRC has determined that
a FONSI is appropriate, and an environmental impact statement is not warranted.
IV. Availability of Documents
The documents identified in the following table are available to interested
persons through ADAMS, as indicated.
Document Description ADAMS Accession No. or Federal Register notice SNCs request for exemption, dated ML24177A217 June 25, 2024.
SNCs request for exemption, amended, dated ML24208A172 July 26, 2024.
Renewed Certificate of Compliance No. 1014, ML23328A045 (Package)
Amendment 11, dated June 29, 2023.
Holtec International, Inc. - Notice of Violation; The U.S. Nuclear Regulatory Commission Inspection ML24016A190 Report No. 07201014/2022-201, EA-23- 044, dated January 30, 2024.
10 CFR part 72 amendment to allow spent fuel storage in NRC-approved casks, dated 55 FR 29181 July 18, 1990.
EA for part 72 amendment to allow spent fuel storage in NRC-approved casks, dated ML051230231 March 8, 1989.
Direct final rule for List of Approved Spent Fuel Storage Casks: Holtec International HI-STORM 100 Cask System CoC No. 1014, Certificate and 83 FR 63794 Amendment Nos. 11 and 12, dated December 12, 2018.
Safety Determination of a Potential Structural Failure of the Fuel Basket During Accident Conditions for the HI-STORM 100 and HI-STORM ML24018A085 Flood/Wind Dry Cask Storage Systems, dated January 31, 2024.
NRC email to Georgia DNR and GEMA, States review of EA/FONSI for Hatch Exemption, dated ML24274A068 August 28, 2024.
8 Georgia DNR and GEMA email response, States response regarding EA/FONSI for Hatch ML24274A067 Exemption, dated September 25, 2024.
Dated: October 8, 2024.
For the Nuclear Regulatory Commission.
/RA/
Christian Jacobs, Acting Chief, Storage and Transportation Licensing Branch,
Division of Fuel Management, Office of Nuclear Material Safety and Safeguards.
9