Duke Energy Carolinas, LLC; McGuire Nuclear Station, Units 1 and 2; Independent Spent Fuel Storage Installation, 51083-51086 [2020-18151]

Download as PDF Federal Register / Vol. 85, No. 161 / Wednesday, August 19, 2020 / Notices Day 25 30 40 60 A A+3 A + 28 A + 53 A + 60 >A + 60 Event/activity If NRC staff finds no ‘‘need’’ or no likelihood of standing, the deadline for petitioner/requestor to file a motion seeking a ruling to reverse the NRC staff’s denial of access; NRC staff files copy of access determination with the presiding officer (or Chief Administrative Judge or other designated officer, as appropriate). If NRC staff finds ‘‘need’’ for SUNSI, the deadline for any party to the proceeding whose interest independent of the proceeding would be harmed by the release of the information to file a motion seeking a ruling to reverse the NRC staff’s grant of access. Deadline for NRC staff reply to motions to reverse NRC staff determination(s). (Receipt +30) If NRC staff finds standing and need for SUNSI, deadline for NRC staff to complete information processing and file motion for Protective Order and draft Non-Disclosure Affidavit. Deadline for submitting petition for intervention containing: (i) Demonstration of standing; and (ii) all contentions whose formulation does not require access to SUNSI (+25 Answers to petition for intervention; +7 petitioner/requestor reply). If access granted: Issuance of presiding officer or other designated officer decision on motion for protective order for access to sensitive information (including schedule for providing access and submission of contentions) or decision reversing a final adverse determination by the NRC staff. Deadline for filing executed Non-Disclosure Affidavits. Access provided to SUNSI consistent with decision issuing the protective order. Deadline for submission of contentions whose development depends upon access to SUNSI. However, if more than 25 days remain between the petitioner’s receipt of (or access to) the information and the deadline for filing all other contentions (as established in the notice of opportunity to request a hearing and petition for leave to intervene), the petitioner may file its SUNSI contentions by that later deadline. (Contention receipt +25) Answers to contentions whose development depends upon access to SUNSI. (Answer receipt +7) Petitioner/Intervenor reply to answers. Decision on contention admission. [FR Doc. 2020–18086 Filed 8–18–20; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. 72–1031, 50–369, and 50–370; NRC–2020–0044] Duke Energy Carolinas, LLC; McGuire Nuclear Station, Units 1 and 2; Independent Spent Fuel Storage Installation Nuclear Regulatory Commission. ACTION: Exemption; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption to Duke Energy Carolinas, LLC (Duke Energy) which would permit Duke Energy to maintain MAGNASTOR® Cask 0FCTKN045 at its McGuire Nuclear Station independent spent fuel storage installation (ISFSI) in a storage condition where the helium density is above the range specified in Certificate of Compliance (CoC) No. 1031, Amendment No. 7, Technical Specification (TS) 3.1.1. DATES: The exemption became effective on August 19, 2020. ADDRESSES: Please refer to Docket ID NRC–2020–0044 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 Website: Go to https://www.regulations.gov and search for Docket ID NRC–2020–0044. Address questions about NRC docket IDs in jbell on DSKJLSW7X2PROD with NOTICES SUMMARY: VerDate Sep<11>2014 51083 16:34 Aug 18, 2020 Jkt 250001 Regulations.gov to Jennifer BorgesRoman; telephone: 301–287–9127; email: Jennifer.Borges@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain publiclyavailable 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 NRC’s Public Document Room reference staff at 1–800–397–4209, 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. FOR FURTHER INFORMATION CONTACT: YenJu Chen, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555; telephone: 301–415–1018; email: Yen-Ju.Chen@nrc.gov. SUPPLEMENTARY INFORMATION: I. Background Duke Energy is the holder of Renewed Facility Operating Licenses No. NPF–9 and NPF–17, which authorize operation of the McGuire Nuclear Plant, Units 1 and 2, in Huntersville, North Carolina, pursuant to part 50 of title 10 of the Code of Federal Regulations (10 CFR), ‘‘Domestic Licensing of Production and Utilization Facilities.’’ Consistent with 10 CFR part 72, subpart K, ‘‘General License for Storage PO 00000 Frm 00077 Fmt 4703 Sfmt 4703 of Spent Fuel at Power Reactor Sites,’’ a general license is issued for the storage of spent fuel in an ISFSI at power reactor sites to persons authorized to possess or operate nuclear power reactors under 10 CFR part 50. Duke Energy is authorized to operate nuclear power reactors under 10 CFR part 50 and holds a 10 CFR part 72 general license for storage of spent fuel at the McGuire Nuclear Station ISFSI. Under the terms of the general license, Duke Energy stores spent fuel at its ISFSI using the NAC MAGNASTOR® System in accordance with CoC No. 1031, Amendment No. 7. II. Request/Action By a letter dated September 12, 2019 (ADAMS Accession No. ML19270E395), and supplemented on February 3, 2020 (ADAMS Accession No. ML20052D934), and June 15, 2020 (ADAMS Accession No. ML20178A548), Duke Energy requested an exemption from the requirements of 10 CFR 72.212(b)(3), 72.212(b)(5)(i), and 72.212(b)(11) that require Duke Energy to comply with the terms, conditions, and specifications of the CoC No. 1031, Amendment No. 7 (ADAMS Accession No. ML17013A481). If approved, Duke Energy’s exemption request would accordingly allow Duke Energy to maintain MAGNASTOR® Cask 0FCTKN045 in a storage condition where the helium density is above the range specified in CoC No. 1031, Amendment No. 7, TS 3.1.1. On June 4, 2018, then-recently loaded MAGNASTOR® Cask 0FCTKN045 was transported to the McGuire Nuclear Station ISFSI storage pad area. Subsequently, Duke Energy reviewed technical details of the completed E:\FR\FM\19AUN1.SGM 19AUN1 51084 Federal Register / Vol. 85, No. 161 / Wednesday, August 19, 2020 / Notices loading procedure and noticed that during the helium backfill process, the two helium mass flow meters for MAGNASTOR® Cask 0FCTKN045 measured significantly different volumes. Further review revealed the cask helium density within MAGNASTOR® Cask 0FCTKN045 exceeded the helium density range specified in CoC No. 1031, Amendment No. 7, TS 3.1.1, Table A3–1, prior to the transport operations. In addition, the TS 3.1.1 corresponding ‘‘Required Actions and Completion Times’’ were not performed prior to transport operations, as specified. Duke Energy conducted an investigation in accordance with the TS Required Action B.1 and completed an analysis as part of the corrective actions per TS Required Action B.2. Duke Energy concluded, for all MAGNASTOR® modes of operation, that Cask 0FCTKN045 is in a safe configuration for continued operation. Duke Energy’s analysis concluded that the final helium density for MAGNASTOR® Cask 0FCTKN045 is outside the allowed range of 0.694– 0.802 grams/liter specified in CoC No. 1031, Amendment No. 7, TS LCO 3.1.1, Table A3–1, ‘‘Helium Mass Per Unit Volume for MAGNASTOR [transportable storage canister] (TSC),’’ and it constitutes a nonconformance with the terms, conditions, and specifications of MAGNASTOR® System CoC No. 1031, Amendment No. 7. The NRC staff has addressed the inspection and enforcement aspects of this nonconformance separately from this exemption request. jbell on DSKJLSW7X2PROD with NOTICES III. Discussion Pursuant to 10 CFR 72.7, the Commission may, upon application by any interested person or upon its own initiative, grant such exemptions from the requirements of the regulations of 10 CFR part 72 as it determines are authorized by law and will not endanger life or property or the common defense and security and are otherwise in the public interest. Authorized by Law This exemption would allow Duke Energy to maintain MAGNASTOR® Cask 0FCTKN045 at its McGuire Nuclear Station ISFSI in a storage condition where the helium density is above the range specified in CoC No. 1031, Amendment No. 7, TS 3.1.1. The provisions in 10 CFR part 72 from which Duke Energy is requesting exemption require the licensee to comply with the terms, conditions, and specifications of the CoC for the approved cask model it uses. Section VerDate Sep<11>2014 16:34 Aug 18, 2020 Jkt 250001 72.7 allows the NRC to grant exemptions from the requirements of 10 CFR part 72. Issuance of this exemption is consistent with the Atomic Energy Act of 1954, as amended, and is not otherwise inconsistent with NRC’s regulations or other applicable laws. Therefore, the exemption is authorized by law. Will Not Endanger Life or Property or the Common Defense and Security This exemption would allow Duke Energy to maintain MAGNASTOR® Cask 0FCTKN045 at the McGuire Nuclear Station ISFSI in a storage condition where the helium density is above the range specified in CoC No. 1031, Amendment No. 7, TS 3.1.1. The requested exemption is not related to any aspect of the physical security or defense of the McGuire Nuclear Station ISFSI, therefore granting the exemption would not result in any potential impacts to common defense and security. As detailed in the safety evaluation below, the NRC staff has determined that under the requested exemption, the storage system will continue to meet the safety requirements of 10 CFR part 72 and the offsite dose limits of 10 CFR part 20 and, therefore, will not endanger life or property. Safety Evaluation The MAGNASTOR® System has been approved for storage of spent fuel under the conditions of CoC No. 1031. The cask under consideration for exemption (0FCTKN045) was loaded under CoC No. 1031, Amendment No. 7. The requested exemption does not change the fundamental design, components, contents, or safety features of the storage system. The NRC staff has evaluated the potential safety impacts of granting the exemption, as applicable, in the areas of structural integrity, thermal performance, and confinement capability. The evaluation and resulting conclusions are presented below. Structural Review for the Requested Exemption: The TSC contained in the NAC MAGNASTOR® is required by the MAGNASTOR® TS to be within a specific helium density range of 0.694– 0.802 grams/liter while maintaining internal pressures within evaluated pressure limits for normal, off-normal, and accident conditions. The internal pressure limits of the TSC with a helium density range of 0.694–0.802 grams/liter are provided in the MAGNASTOR® Final Safety Analysis Report (FSAR), Revision 6 (ADAMS Accession No. ML20196L776) as 110 psig, 130 psig, and 250 psig for normal, off-normal, and accident conditions, respectively. PO 00000 Frm 00078 Fmt 4703 Sfmt 4703 In June 2018, Duke Energy found that the TSC contained in the MAGNASTOR® Cask 0FCTKN045 is filled with a helium density up to 1.082 grams/liter, which is higher than the helium density specified in the TS. As a result, Duke Energy recalculated the internal pressures of the TSC due to the helium density of 1.082 grams/liter using the same method described in the MAGNASTOR® FSAR, Revision 6. The new internal pressures of the TSC were found to be 142.1 psig, 158 psig, and 265 psig for normal, off-normal, and accident conditions, respectively. Using these new internal pressures, Duke Energy calculated new component stress intensities at the most critical cross section (where it has the lowest reported factor of safety) in the TSC to demonstrate the adequacy of the TSC’s structural design under normal, offnormal, and accident conditions. Duke Energy used the results of the ANSYS finite element (FE) structural analysis and a linear superposition of hand calculations to calculate component stresses in the TSC. The ANSYS FE analysis and its results were previously reviewed and accepted by the staff, and they are provided in the MAGNASTOR® FSAR, Revision 6. Based on the calculated stresses at the critical location of the TSC from the previous ANSYS FE analysis, the new stresses at the same critical location of the TSC were recalculated by: (i) Adding the induced stresses due to the increased pressures from the helium density increase, and (ii) subtracting the reduced stresses due to the decreased weight of the TSC. For the second factor regarding the stress reduction from the weight of the TSC, Duke Energy stated that the actual weight of the TSC is 77,000 lbs, while the weight of the TSC in the MAGNASTOR® FSAR, Revision 6 that was used as a bounding weight in the previous ANSYS FE analysis was 90,000 lbs. The staff reviewed the methodology used to calculate the revised stresses of the TSC and finds it acceptable because the superposition method is an acceptable approach in engineering practice and the revised calculations considered the actual weight and helium density. Using the methodology described above, Duke Energy calculated component stresses and stress intensities at the critical location of the TSC and provided the factor of safety, which is a ratio of the allowable stress intensity with respect to the actual stress intensity, for normal, off-normal, and accident conditions. The staff reviewed Duke Energy’s analysis and stress calculation and finds that the results of the stress calculation show E:\FR\FM\19AUN1.SGM 19AUN1 jbell on DSKJLSW7X2PROD with NOTICES Federal Register / Vol. 85, No. 161 / Wednesday, August 19, 2020 / Notices that all calculated factors of safety are greater than 1.0, which meets the design criteria for the TSC specified in the MAGNASTOR® FSAR, Revision 6. Revision 6 uses the design criteria required by the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel Code (B&PV) Division I, Section III, Subsection NB. Thus, the staff determines that Duke Energy’s stress calculation and its results are acceptable. The staff concludes that, with the helium density higher than that specified in the TS, the design of the TSC continues to meet the design criteria of the ASME B&PV Code, as specified in the MAGNASTOR® FSAR, Revision 6. The TSC is designed to accommodate the combined loads (i.e., dead weight, internal pressure, handling load, and impacts from natural phenomena) in normal, off-normal, and accident conditions with an adequate margin of safety. The total stresses at the critical location of the TSC under the combined loads during normal, offnormal, accident conditions are acceptable and are found to be within the limits in the ASME B&PV Code, as specified in the MAGNASTOR® FSAR Revision 6. Therefore, the staff finds that the MAGNASTOR® Cask 0FCTKN045 continues to maintain its structural integrity and meet the structural requirements of 10 CFR part 72 and the offsite dose limits of 10 CFR part 20. Confinement Review for the Requested Exemption: According to the MAGNASTOR® System FSAR Revision 5 (ADAMS Accession No. ML17132A265), the confinement boundary includes a lid welded consistent with Interim Staff Guidance18, ‘‘The Design and Testing of Lid Welds on Austenitic Stainless Steel Canisters as the Confinement Boundary for Spent Fuel Storage’’ (ADAMS Accession No. ML082750469). The remaining confinement boundary is tested to a ‘‘leaktight’’ criteria per the American National Standard Institute N14.5 standard. Duke Energy stated in its exemption request that the increased helium pressure within the TSC was used to compute updated factors of safety due to revised stress intensities. The calculations were updated for the most critical cross sections for the bounding load cases of each of the four service levels evaluated in the design basis MAGNASTOR® TSC structural evaluation. The service levels are taken from the ASME B&PV Code, and correspond to different conditions of operation. Duke Energy stated that the updated factors of safety for Service Level A, Service Level B, Service Level VerDate Sep<11>2014 16:34 Aug 18, 2020 Jkt 250001 C, and Service Level D conditions were greater than one. Therefore, Duke Energy determined that MAGNASTOR® Cask 0FCTKN045 is safe because it continues to meet the structural criteria used to evaluate the MAGNASTOR® system. The NRC staff reviewed the exemption request and concludes that the cask confinement performance is not affected by the increased helium pressure because, according to Duke Energy’s analysis and the staff’s structural evaluation, the integrity of the TSC is maintained and, therefore, there would be no release from the canister. The NRC staff finds that the confinement function of MAGNASTOR® Cask 0FCTKN045, loaded under CoC No. 1031, Amendment No. 7, addressed in the exemption request remains in compliance with 10 CFR 72.236(d) and (l) and the offsite dose limits of 10 CFR part 20. Thermal Review for the Requested Exemption: According to Duke Energy’s analysis in the exemption request, the higher helium density (1.082 g/L) and pressure of MAGNASTOR® Cask 0FCTKN045 have a positive effect on the thermal performance of the verticaloriented TSC confining the spent fuel. In addition, in the February 2020 submittal (ADAMS Accession No. ML20052D934), Duke Energy noted that MAGNASTOR® Cask 0FCTKN045 has a decay heat load of less than 30 kW which is less than the design basis heat load for the MAGNASTOR® system of 35.5 kW. Duke Energy analyzed a MAGNASTOR® canister with a 30 kW heat load and helium density of 1.082 g/L. The results were a 575 °F maximum fuel temperature, which is less than the design basis temperature (718 °F) found in Table 4.4–3 of the MAGNASTOR® System FSAR, Revision 7 (ADAMS Accession No. ML15265A419). The staff concludes that the positive effects of the higher pressure and the lower heat load in the canister would reduce the actual temperatures and increase the margin between the actual temperatures and the design temperatures. The NRC staff reviewed the exemption request and concludes that the cask thermal performance is not affected by the higher helium density because it would not adversely affect thermal performance and, according to Duke Energy’s analysis and the staff’s structural evaluation, the integrity of the TSC is maintained. The integrity of the primary confinement boundary ensures that the spent fuel is stored in an inert environment and with unaffected heat transfer characteristics that keep peak PO 00000 Frm 00079 Fmt 4703 Sfmt 4703 51085 cladding temperatures below allowable limits. The NRC staff finds that the thermal function of MAGNASTOR® Cask 0FCTKN045, loaded under CoC No. 1031, Amendment No. 7, addressed in the exemption request remains in compliance with 10 CFR 72.236 (b) and (f) and the offsite dose limits of 10 CFR part 20. Otherwise in the Public Interest The proposed exemption is to maintain MAGNASTOR® Cask 0FCTKN045 at McGuire Nuclear Station ISFSI in the storage condition where the helium density is above the range specified in CoC No. 1031, Amendment No. 7, TS 3.1.1. The NRC staff notes that in this condition there will be no operations involving the opening of the storage canister, which confines the spent nuclear fuel, and there will be no operations involving the opening of the MAGNASTOR® cask. In considering whether granting the exemption is in the public interest, the NRC staff also considered the alternative of not granting the exemption. If the exemption were not granted, in order to comply with the CoC, Duke Energy would have to unload MAGNASTOR® Cask 0FCTKN045 to restore compliance with helium density in the TS. This would subject onsite 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. Approving the requested exemption reduces the opportunity for a release of radioactive material compared to the alternative to the proposed action, while continuing to provide reasonable assurance of public health and safety. Therefore, the staff concludes that approving the exemption is in the public interest. Environmental Consideration The NRC staff also considered whether there would be any significant environmental impacts associated with the exemption. For this proposed action, the NRC staff performed an environmental assessment pursuant to 10 CFR 51.30. The environmental assessment concluded that the proposed action would not significantly impact the quality of the human environment. The NRC staff concluded that the proposed action would not result in any changes in the types or amounts of any radiological or non-radiological effluents that may be released offsite, and there is no significant increase in occupational or public radiation exposure because of the proposed E:\FR\FM\19AUN1.SGM 19AUN1 51086 Federal Register / Vol. 85, No. 161 / Wednesday, August 19, 2020 / Notices action. The Environmental Assessment and the Finding of No Significant Impact was published on July 22, 2020 (85 FR 44329). IV. Availability of Documents The documents identified in the following table are available to interested persons through one or more of the following methods, as indicated. Document ADAMS accession No. Duke Energy Carolinas, LLC (Duke Energy), McGuire Nuclear Station, Units 1 and 2, Independent Spent Fuel Storage Installation (ISFSI), Exemption Request for NAC MAGNASTOR® Cask Loaded to Incorrect Helium Backfill Density, dated September 12, 2019. Duke Energy Carolinas, LLC (Duke Energy), McGuire Nuclear Station, Response to NRG Request for Additional Information (RAI) Regarding NAC MAGNASTOR® Cask Loaded to Incorrect Helium Backfill Density, dated February 3, 2020. Duke Energy Carolinas, LLC (Duke Energy), McGuire Nuclear Station, Response to NRC Request for Additional Information (RAI) Regarding NAC MAGNASTOR® Cask Loaded to Incorrect Helium Backfill Density, dated June 5, 2020. NAC International, MAGNASTOR® Cask System, Certificate of Compliance No. 1031, Amendment No. 7 .. Final Safety Analysis Report, Revision 6 for MAGNASTOR® Cask System .................................................... Final Safety Analysis Report, Revision 5 for MAGNASTOR® Cask System .................................................... Interim Staff Guidance, ISG–18, Revision 1, ‘‘The Design and Testing of Lid Welds on Austenitic Stainless Steel Canisters as the Confinement Boundary for Spent Fuel Storage’’. Final Safety Analysis Report, Revision 7 for MAGNASTOR® Cask System .................................................... The NRC may post materials related to this document, including public comments, on the Federal rulemaking website at https://www.regulations.gov under Docket ID NRC–2020–0044. The Federal rulemaking website allows you to receive alerts when changes or additions occur in a docket folder. To subscribe: (1) Navigate to the docket folder (NRC–2020–0044); (2) click the ‘‘Sign up for Email Alerts’’ link; and (3) enter your email address and select how frequently you would like to receive emails (daily, weekly, or monthly). V. Conclusion Based on the above considerations, the NRC has determined that, pursuant to 10 CFR 72.7, the exemption is authorized by law, will not endanger life or property or the common defense and security, and is otherwise in the public interest. Therefore, the NRC grants Duke Energy an exemption from the requirements of 10 CFR 72.212(b)(3), 72.212(b)(5)(i), and 72.212(b)(11) with respect to the ongoing storage of MAGNASTOR® Cask 0FCTKN045. This exemption is effective upon issuance. Dated: August 14, 2020. For the Nuclear Regulatory Commission. John B. McKirgan, Chief, Storage and Transportation Branch, Division of Fuel Management, Office of Nuclear Material Safety, and Safeguards. [FR Doc. 2020–18151 Filed 8–18–20; 8:45 am] jbell on DSKJLSW7X2PROD with NOTICES BILLING CODE 7590–01–P PEACE CORPS Information Collection Request; Submission for OMB Review AGENCY: Peace Corps. VerDate Sep<11>2014 16:34 Aug 18, 2020 Jkt 250001 60-Day notice and request for comments. ACTION: The Peace Corps will be submitting the following information collection request to the Office of Management and Budget (OMB) for review and approval. The purpose of this notice is to allow 60 days for public comment in the Federal Register preceding submission to OMB. We are conducting this process in accordance with the Paperwork Reduction Act of 1995. SUMMARY: Submit comments on or before October 19, 2020. ADDRESSES: Comments should be addressed to Virginia Burke, FOIA/ Privacy Act Officer. Virginia Burke can be contacted by email at pcfr@ peacecorps.gov. Email comments must be made in text and not in attachments. FOR FURTHER INFORMATION CONTACT: Virginia Burke at the Peace Corps address above. SUPPLEMENTARY INFORMATION: Title: Onboarding Portal for Peace Corps Volunteer Applicants. OMB Control Number: 0420–0563. Type of Request: Revision. Affected Public: Individuals. Form Number: PC–2174. Respondents Obligation to Reply: Voluntary. Respondents: Individuals. Burden to the Public: Estimated burden (hours) of the collection of information: a. Number of respondents: 5000. b. Frequency of response: one time. c. Completion time: 60 minutes. d. Annual burden hours: 5000 hours. General Description of Collection: The Peace Corps uses the Onboarding Portal to collect essential administrative DATES: PO 00000 Frm 00080 Fmt 4703 Sfmt 9990 ML19270E395. ML20052D934. ML20178A548. ML17013A481. ML20196L776. ML17132A265. ML082750469. ML15265A419. information from invitees for use during Peace Corps Volunteer service, including such information as first, middle and last name, birthdate, Social Security number, primary contact information, designated emergency contact names an contact information, legal history updates, direct deposit information associated with a bank account, student loan history, and life insurance designations. The information is used by the Peace Corps to establish specific services for invitees for the purposes of supporting the Peace Corps Volunteer during service. Request for Comment: Peace Corps invites comments on whether the proposed collections of information are necessary for proper performance of the functions of the Peace Corps, including whether the information will have practical use; the accuracy of the agency’s estimate of the burden of the proposed collection of information, including the validity of the information to be collected; and, ways to minimize the burden of the collection of information on those who are to respond, including through the use of automated collection techniques, when appropriate, and other forms of information technology. This notice is issued in Washington, DC, on August 14, 2020. Virginia Burke, FOIA/Privacy Act Officer, Management. [FR Doc. 2020–18146 Filed 8–18–20; 8:45 am] BILLING CODE 6051–01–P E:\FR\FM\19AUN1.SGM 19AUN1

Agencies

[Federal Register Volume 85, Number 161 (Wednesday, August 19, 2020)]
[Notices]
[Pages 51083-51086]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2020-18151]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 72-1031, 50-369, and 50-370; NRC-2020-0044]


Duke Energy Carolinas, LLC; McGuire Nuclear Station, Units 1 and 
2; Independent Spent Fuel Storage Installation

AGENCY: Nuclear Regulatory Commission.

ACTION: Exemption; issuance.

-----------------------------------------------------------------------

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an 
exemption to Duke Energy Carolinas, LLC (Duke Energy) which would 
permit Duke Energy to maintain MAGNASTOR[supreg] Cask 0FCTKN045 at its 
McGuire Nuclear Station independent spent fuel storage installation 
(ISFSI) in a storage condition where the helium density is above the 
range specified in Certificate of Compliance (CoC) No. 1031, Amendment 
No. 7, Technical Specification (TS) 3.1.1.

DATES: The exemption became effective on August 19, 2020.

ADDRESSES: Please refer to Docket ID NRC-2020-0044 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 Website: Go to https://www.regulations.gov and search for Docket ID NRC-2020-0044. Address 
questions about NRC docket IDs in Regulations.gov to Jennifer Borges-
Roman; telephone: 301-287-9127; email: [email protected]. For 
technical questions, contact the individual listed in the FOR FURTHER 
INFORMATION CONTACT section of this document.
     NRC's 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 NRC's Public 
Document Room reference staff at 1-800-397-4209, 301-415-4737, or by 
email to [email protected]. For the convenience of the reader, 
instructions about obtaining materials referenced in this document are 
provided in the ``Availability of Documents'' section.

FOR FURTHER INFORMATION CONTACT: Yen-Ju Chen, Office of Nuclear 
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555; telephone: 301-415-1018; email: [email protected].

SUPPLEMENTARY INFORMATION:

I. Background

    Duke Energy is the holder of Renewed Facility Operating Licenses 
No. NPF-9 and NPF-17, which authorize operation of the McGuire Nuclear 
Plant, Units 1 and 2, in Huntersville, North Carolina, pursuant to part 
50 of title 10 of the Code of Federal Regulations (10 CFR), ``Domestic 
Licensing of Production and Utilization Facilities.''
    Consistent with 10 CFR part 72, subpart K, ``General License for 
Storage of Spent Fuel at Power Reactor Sites,'' a general license is 
issued for the storage of spent fuel in an ISFSI at power reactor sites 
to persons authorized to possess or operate nuclear power reactors 
under 10 CFR part 50. Duke Energy is authorized to operate nuclear 
power reactors under 10 CFR part 50 and holds a 10 CFR part 72 general 
license for storage of spent fuel at the McGuire Nuclear Station ISFSI. 
Under the terms of the general license, Duke Energy stores spent fuel 
at its ISFSI using the NAC MAGNASTOR[supreg] System in accordance with 
CoC No. 1031, Amendment No. 7.

II. Request/Action

    By a letter dated September 12, 2019 (ADAMS Accession No. 
ML19270E395), and supplemented on February 3, 2020 (ADAMS Accession No. 
ML20052D934), and June 15, 2020 (ADAMS Accession No. ML20178A548), Duke 
Energy requested an exemption from the requirements of 10 CFR 
72.212(b)(3), 72.212(b)(5)(i), and 72.212(b)(11) that require Duke 
Energy to comply with the terms, conditions, and specifications of the 
CoC No. 1031, Amendment No. 7 (ADAMS Accession No. ML17013A481). If 
approved, Duke Energy's exemption request would accordingly allow Duke 
Energy to maintain MAGNASTOR[supreg] Cask 0FCTKN045 in a storage 
condition where the helium density is above the range specified in CoC 
No. 1031, Amendment No. 7, TS 3.1.1.
    On June 4, 2018, then-recently loaded MAGNASTOR[supreg] Cask 
0FCTKN045 was transported to the McGuire Nuclear Station ISFSI storage 
pad area. Subsequently, Duke Energy reviewed technical details of the 
completed

[[Page 51084]]

loading procedure and noticed that during the helium backfill process, 
the two helium mass flow meters for MAGNASTOR[supreg] Cask 0FCTKN045 
measured significantly different volumes. Further review revealed the 
cask helium density within MAGNASTOR[supreg] Cask 0FCTKN045 exceeded 
the helium density range specified in CoC No. 1031, Amendment No. 7, TS 
3.1.1, Table A3-1, prior to the transport operations. In addition, the 
TS 3.1.1 corresponding ``Required Actions and Completion Times'' were 
not performed prior to transport operations, as specified.
    Duke Energy conducted an investigation in accordance with the TS 
Required Action B.1 and completed an analysis as part of the corrective 
actions per TS Required Action B.2. Duke Energy concluded, for all 
MAGNASTOR[supreg] modes of operation, that Cask 0FCTKN045 is in a safe 
configuration for continued operation. Duke Energy's analysis concluded 
that the final helium density for MAGNASTOR[supreg] Cask 0FCTKN045 is 
outside the allowed range of 0.694-0.802 grams/liter specified in CoC 
No. 1031, Amendment No. 7, TS LCO 3.1.1, Table A3-1, ``Helium Mass Per 
Unit Volume for MAGNASTOR [transportable storage canister] (TSC),'' and 
it constitutes a nonconformance with the terms, conditions, and 
specifications of MAGNASTOR[supreg] System CoC No. 1031, Amendment No. 
7. The NRC staff has addressed the inspection and enforcement aspects 
of this nonconformance separately from this exemption request.

III. Discussion

    Pursuant to 10 CFR 72.7, the Commission may, upon application by 
any interested person or upon its own initiative, grant such exemptions 
from the requirements of the regulations of 10 CFR part 72 as it 
determines are authorized by law and will not endanger life or property 
or the common defense and security and are otherwise in the public 
interest.

Authorized by Law

    This exemption would allow Duke Energy to maintain 
MAGNASTOR[supreg] Cask 0FCTKN045 at its McGuire Nuclear Station ISFSI 
in a storage condition where the helium density is above the range 
specified in CoC No. 1031, Amendment No. 7, TS 3.1.1. The provisions in 
10 CFR part 72 from which Duke Energy is requesting exemption require 
the licensee to comply with the terms, conditions, and specifications 
of the CoC for the approved cask model it uses. Section 72.7 allows the 
NRC to grant exemptions from the requirements of 10 CFR part 72. 
Issuance of this exemption is consistent with the Atomic Energy Act of 
1954, as amended, and is not otherwise inconsistent with NRC's 
regulations or other applicable laws. Therefore, the exemption is 
authorized by law.

Will Not Endanger Life or Property or the Common Defense and Security

    This exemption would allow Duke Energy to maintain 
MAGNASTOR[supreg] Cask 0FCTKN045 at the McGuire Nuclear Station ISFSI 
in a storage condition where the helium density is above the range 
specified in CoC No. 1031, Amendment No. 7, TS 3.1.1. The requested 
exemption is not related to any aspect of the physical security or 
defense of the McGuire Nuclear Station ISFSI, therefore granting the 
exemption would not result in any potential impacts to common defense 
and security. As detailed in the safety evaluation below, the NRC staff 
has determined that under the requested exemption, the storage system 
will continue to meet the safety requirements of 10 CFR part 72 and the 
offsite dose limits of 10 CFR part 20 and, therefore, will not endanger 
life or property.

Safety Evaluation

    The MAGNASTOR[supreg] System has been approved for storage of spent 
fuel under the conditions of CoC No. 1031. The cask under consideration 
for exemption (0FCTKN045) was loaded under CoC No. 1031, Amendment No. 
7. The requested exemption does not change the fundamental design, 
components, contents, or safety features of the storage system. The NRC 
staff has evaluated the potential safety impacts of granting the 
exemption, as applicable, in the areas of structural integrity, thermal 
performance, and confinement capability. The evaluation and resulting 
conclusions are presented below.
    Structural Review for the Requested Exemption: The TSC contained in 
the NAC MAGNASTOR[supreg] is required by the MAGNASTOR[supreg] TS to be 
within a specific helium density range of 0.694-0.802 grams/liter while 
maintaining internal pressures within evaluated pressure limits for 
normal, off-normal, and accident conditions. The internal pressure 
limits of the TSC with a helium density range of 0.694-0.802 grams/
liter are provided in the MAGNASTOR[supreg] Final Safety Analysis 
Report (FSAR), Revision 6 (ADAMS Accession No. ML20196L776) as 110 
psig, 130 psig, and 250 psig for normal, off-normal, and accident 
conditions, respectively.
    In June 2018, Duke Energy found that the TSC contained in the 
MAGNASTOR[supreg] Cask 0FCTKN045 is filled with a helium density up to 
1.082 grams/liter, which is higher than the helium density specified in 
the TS. As a result, Duke Energy recalculated the internal pressures of 
the TSC due to the helium density of 1.082 grams/liter using the same 
method described in the MAGNASTOR[supreg] FSAR, Revision 6. The new 
internal pressures of the TSC were found to be 142.1 psig, 158 psig, 
and 265 psig for normal, off-normal, and accident conditions, 
respectively. Using these new internal pressures, Duke Energy 
calculated new component stress intensities at the most critical cross 
section (where it has the lowest reported factor of safety) in the TSC 
to demonstrate the adequacy of the TSC's structural design under 
normal, off-normal, and accident conditions.
    Duke Energy used the results of the ANSYS finite element (FE) 
structural analysis and a linear superposition of hand calculations to 
calculate component stresses in the TSC. The ANSYS FE analysis and its 
results were previously reviewed and accepted by the staff, and they 
are provided in the MAGNASTOR[supreg] FSAR, Revision 6. Based on the 
calculated stresses at the critical location of the TSC from the 
previous ANSYS FE analysis, the new stresses at the same critical 
location of the TSC were recalculated by: (i) Adding the induced 
stresses due to the increased pressures from the helium density 
increase, and (ii) subtracting the reduced stresses due to the 
decreased weight of the TSC. For the second factor regarding the stress 
reduction from the weight of the TSC, Duke Energy stated that the 
actual weight of the TSC is 77,000 lbs, while the weight of the TSC in 
the MAGNASTOR[supreg] FSAR, Revision 6 that was used as a bounding 
weight in the previous ANSYS FE analysis was 90,000 lbs. The staff 
reviewed the methodology used to calculate the revised stresses of the 
TSC and finds it acceptable because the superposition method is an 
acceptable approach in engineering practice and the revised 
calculations considered the actual weight and helium density.
    Using the methodology described above, Duke Energy calculated 
component stresses and stress intensities at the critical location of 
the TSC and provided the factor of safety, which is a ratio of the 
allowable stress intensity with respect to the actual stress intensity, 
for normal, off-normal, and accident conditions. The staff reviewed 
Duke Energy's analysis and stress calculation and finds that the 
results of the stress calculation show

[[Page 51085]]

that all calculated factors of safety are greater than 1.0, which meets 
the design criteria for the TSC specified in the MAGNASTOR[supreg] 
FSAR, Revision 6. Revision 6 uses the design criteria required by the 
American Society of Mechanical Engineers (ASME) Boiler and Pressure 
Vessel Code (B&PV) Division I, Section III, Subsection NB. Thus, the 
staff determines that Duke Energy's stress calculation and its results 
are acceptable.
    The staff concludes that, with the helium density higher than that 
specified in the TS, the design of the TSC continues to meet the design 
criteria of the ASME B&PV Code, as specified in the MAGNASTOR[supreg] 
FSAR, Revision 6. The TSC is designed to accommodate the combined loads 
(i.e., dead weight, internal pressure, handling load, and impacts from 
natural phenomena) in normal, off-normal, and accident conditions with 
an adequate margin of safety. The total stresses at the critical 
location of the TSC under the combined loads during normal, off-normal, 
accident conditions are acceptable and are found to be within the 
limits in the ASME B&PV Code, as specified in the MAGNASTOR[supreg] 
FSAR Revision 6. Therefore, the staff finds that the MAGNASTOR[supreg] 
Cask 0FCTKN045 continues to maintain its structural integrity and meet 
the structural requirements of 10 CFR part 72 and the offsite dose 
limits of 10 CFR part 20.
    Confinement Review for the Requested Exemption: According to the 
MAGNASTOR[supreg] System FSAR Revision 5 (ADAMS Accession No. 
ML17132A265), the confinement boundary includes a lid welded consistent 
with Interim Staff Guidance-18, ``The Design and Testing of Lid Welds 
on Austenitic Stainless Steel Canisters as the Confinement Boundary for 
Spent Fuel Storage'' (ADAMS Accession No. ML082750469). The remaining 
confinement boundary is tested to a ``leaktight'' criteria per the 
American National Standard Institute N14.5 standard. Duke Energy stated 
in its exemption request that the increased helium pressure within the 
TSC was used to compute updated factors of safety due to revised stress 
intensities. The calculations were updated for the most critical cross 
sections for the bounding load cases of each of the four service levels 
evaluated in the design basis MAGNASTOR[supreg] TSC structural 
evaluation. The service levels are taken from the ASME B&PV Code, and 
correspond to different conditions of operation. Duke Energy stated 
that the updated factors of safety for Service Level A, Service Level 
B, Service Level C, and Service Level D conditions were greater than 
one. Therefore, Duke Energy determined that MAGNASTOR[supreg] Cask 
0FCTKN045 is safe because it continues to meet the structural criteria 
used to evaluate the MAGNASTOR[supreg] system.
    The NRC staff reviewed the exemption request and concludes that the 
cask confinement performance is not affected by the increased helium 
pressure because, according to Duke Energy's analysis and the staff's 
structural evaluation, the integrity of the TSC is maintained and, 
therefore, there would be no release from the canister.
    The NRC staff finds that the confinement function of 
MAGNASTOR[supreg] Cask 0FCTKN045, loaded under CoC No. 1031, Amendment 
No. 7, addressed in the exemption request remains in compliance with 10 
CFR 72.236(d) and (l) and the offsite dose limits of 10 CFR part 20.
    Thermal Review for the Requested Exemption: According to Duke 
Energy's analysis in the exemption request, the higher helium density 
(1.082 g/L) and pressure of MAGNASTOR[supreg] Cask 0FCTKN045 have a 
positive effect on the thermal performance of the vertical-oriented TSC 
confining the spent fuel. In addition, in the February 2020 submittal 
(ADAMS Accession No. ML20052D934), Duke Energy noted that 
MAGNASTOR[supreg] Cask 0FCTKN045 has a decay heat load of less than 30 
kW which is less than the design basis heat load for the 
MAGNASTOR[supreg] system of 35.5 kW. Duke Energy analyzed a 
MAGNASTOR[supreg] canister with a 30 kW heat load and helium density of 
1.082 g/L. The results were a 575 [deg]F maximum fuel temperature, 
which is less than the design basis temperature (718 [deg]F) found in 
Table 4.4-3 of the MAGNASTOR[supreg] System FSAR, Revision 7 (ADAMS 
Accession No. ML15265A419). The staff concludes that the positive 
effects of the higher pressure and the lower heat load in the canister 
would reduce the actual temperatures and increase the margin between 
the actual temperatures and the design temperatures.
    The NRC staff reviewed the exemption request and concludes that the 
cask thermal performance is not affected by the higher helium density 
because it would not adversely affect thermal performance and, 
according to Duke Energy's analysis and the staff's structural 
evaluation, the integrity of the TSC is maintained. The integrity of 
the primary confinement boundary ensures that the spent fuel is stored 
in an inert environment and with unaffected heat transfer 
characteristics that keep peak cladding temperatures below allowable 
limits.
    The NRC staff finds that the thermal function of MAGNASTOR[supreg] 
Cask 0FCTKN045, loaded under CoC No. 1031, Amendment No. 7, addressed 
in the exemption request remains in compliance with 10 CFR 72.236 (b) 
and (f) and the offsite dose limits of 10 CFR part 20.

Otherwise in the Public Interest

    The proposed exemption is to maintain MAGNASTOR[supreg] Cask 
0FCTKN045 at McGuire Nuclear Station ISFSI in the storage condition 
where the helium density is above the range specified in CoC No. 1031, 
Amendment No. 7, TS 3.1.1. The NRC staff notes that in this condition 
there will be no operations involving the opening of the storage 
canister, which confines the spent nuclear fuel, and there will be no 
operations involving the opening of the MAGNASTOR[supreg] cask.
    In considering whether granting the exemption is in the public 
interest, the NRC staff also considered the alternative of not granting 
the exemption. If the exemption were not granted, in order to comply 
with the CoC, Duke Energy would have to unload MAGNASTOR[supreg] Cask 
0FCTKN045 to restore compliance with helium density in the TS. This 
would subject onsite 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.
    Approving the requested exemption reduces the opportunity for a 
release of radioactive material compared to the alternative to the 
proposed action, while continuing to provide reasonable assurance of 
public health and safety. Therefore, the staff concludes that approving 
the exemption is in the public interest.

Environmental Consideration

    The NRC staff also considered whether there would be any 
significant environmental impacts associated with the exemption. For 
this proposed action, the NRC staff performed an environmental 
assessment pursuant to 10 CFR 51.30. The environmental assessment 
concluded that the proposed action would not significantly impact the 
quality of the human environment. The NRC staff concluded that the 
proposed action would not result in any changes in the types or amounts 
of any radiological or non-radiological effluents that may be released 
offsite, and there is no significant increase in occupational or public 
radiation exposure because of the proposed

[[Page 51086]]

action. The Environmental Assessment and the Finding of No Significant 
Impact was published on July 22, 2020 (85 FR 44329).

IV. Availability of Documents

    The documents identified in the following table are available to 
interested persons through one or more of the following methods, as 
indicated.

------------------------------------------------------------------------
                  Document                       ADAMS accession No.
------------------------------------------------------------------------
Duke Energy Carolinas, LLC (Duke Energy),    ML19270E395.
 McGuire Nuclear Station, Units 1 and 2,
 Independent Spent Fuel Storage
 Installation (ISFSI), Exemption Request
 for NAC MAGNASTOR[supreg] Cask Loaded to
 Incorrect Helium Backfill Density, dated
 September 12, 2019.
Duke Energy Carolinas, LLC (Duke Energy),    ML20052D934.
 McGuire Nuclear Station, Response to NRG
 Request for Additional Information (RAI)
 Regarding NAC MAGNASTOR[supreg] Cask
 Loaded to Incorrect Helium Backfill
 Density, dated February 3, 2020.
Duke Energy Carolinas, LLC (Duke Energy),    ML20178A548.
 McGuire Nuclear Station, Response to NRC
 Request for Additional Information (RAI)
 Regarding NAC MAGNASTOR[supreg] Cask
 Loaded to Incorrect Helium Backfill
 Density, dated June 5, 2020.
NAC International, MAGNASTOR[supreg] Cask    ML17013A481.
 System, Certificate of Compliance No.
 1031, Amendment No. 7.
Final Safety Analysis Report, Revision 6     ML20196L776.
 for MAGNASTOR[supreg] Cask System.
Final Safety Analysis Report, Revision 5     ML17132A265.
 for MAGNASTOR[supreg] Cask System.
Interim Staff Guidance, ISG-18, Revision 1,  ML082750469.
 ``The Design and Testing of Lid Welds on
 Austenitic Stainless Steel Canisters as
 the Confinement Boundary for Spent Fuel
 Storage''.
Final Safety Analysis Report, Revision 7     ML15265A419.
 for MAGNASTOR[supreg] Cask System.
------------------------------------------------------------------------

    The NRC may post materials related to this document, including 
public comments, on the Federal rulemaking website at https://www.regulations.gov under Docket ID NRC-2020-0044. The Federal 
rulemaking website allows you to receive alerts when changes or 
additions occur in a docket folder. To subscribe: (1) Navigate to the 
docket folder (NRC-2020-0044); (2) click the ``Sign up for Email 
Alerts'' link; and (3) enter your email address and select how 
frequently you would like to receive emails (daily, weekly, or 
monthly).

V. Conclusion

    Based on the above considerations, the NRC has determined that, 
pursuant to 10 CFR 72.7, the exemption is authorized by law, will not 
endanger life or property or the common defense and security, and is 
otherwise in the public interest. Therefore, the NRC grants Duke Energy 
an exemption from the requirements of 10 CFR 72.212(b)(3), 
72.212(b)(5)(i), and 72.212(b)(11) with respect to the ongoing storage 
of MAGNASTOR[supreg] Cask 0FCTKN045.
    This exemption is effective upon issuance.

    Dated: August 14, 2020.

    For the Nuclear Regulatory Commission.
John B. McKirgan,
Chief, Storage and Transportation Branch, Division of Fuel Management, 
Office of Nuclear Material Safety, and Safeguards.
[FR Doc. 2020-18151 Filed 8-18-20; 8:45 am]
BILLING CODE 7590-01-P
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