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| available electronically for public inspection in the NRC Public Document Room or from the publicly available records component of the NRC's document system, ADAMS. ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html. | | available electronically for public inspection in the NRC Public Document Room or from the publicly available records component of the NRC's document system, ADAMS. ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html. |
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| If you have any questions, please contact me at ( | | If you have any questions, please contact me at (301) 415-6802, or Yen-Ju Chen of my staff, at (301) 415-1018. |
| 301) 415-6802, or Yen-Ju Chen of my staff, at (301) 415-1018. | |
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| Sincerely, | | Sincerely, /RA/ Meraj Rahimi, Acting Chief Spent Fuel Licensing Branch Division of Spent Fuel Management |
| /RA/ Meraj Rahimi, Acting Chief Spent Fuel Licensing Branch Division of Spent Fuel Management | |
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| Office of Nuclear Material Safety | | Office of Nuclear Material Safety |
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MONTHYEARBVY 16-030, Exemption Request from Certain Requirements of 1 O CFR 72.212 and 10 CFR 72.2142016-11-0909 November 2016 Exemption Request from Certain Requirements of 1 O CFR 72.212 and 10 CFR 72.214 Project stage: Other BVY 17-041, Supplement to Exemption Request from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 to Support the Dry Fuel Loading Campaign2017-12-0707 December 2017 Supplement to Exemption Request from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 to Support the Dry Fuel Loading Campaign Project stage: Supplement ML17249A1572018-01-11011 January 2018, 16 January 2018 Package: Vermont Yankee Nuclear Power Station ISFSI Environmental Assessment and Finding of No Significant Impact Related to Issuance of Exemption to Allow a New Loading Pattern and Loading Fuel Cooled for at Least 2 Years Project stage: Request ML17249A1592018-01-16016 January 2018 Letter to C. C. Chappell Vermont Yankee Nuclear Power Station ISFSI Environmental Assessment and Finding of No Significant Impact Related to Issuance of Exemption to Allow a New Loading Pattern and Loading Fuel Cooled for at Least 2 Years Project stage: Approval ML17298A1352018-02-0202 February 2018 Safety Evaluation Report (Letter to C. C. Chappell Vermont Yankee Nuclear Power Station Independent Spent Fuel Storage Installation, Issuance of Exemption (CAC No.: 001028, Docket Nos. 50-271, 72-59, and 72-1014; EPID L-2017-LLE-0005) Project stage: Approval ML17298A1332018-02-0202 February 2018 Package: Vermont Yankee Nuclear Power Station Independent Spent Fuel Storage Installation, Issuance of Exemption (CAC No.: 001028, Docket Nos. 50-271, 72-59, and 72-1014; EPID L-2017-LLE-0005) Project stage: Request ML17298A1342018-02-0202 February 2018 Letter to C. C. Chappell Vermont Yankee Nuclear Power Station Independent Spent Fuel Storage Installation, Issuance of Exemption (CAC No.: 001028, Docket Nos. 50-271, 72-59, and 72-1014; EPID L-2017-LLE-0005) Project stage: Approval 2018-01-11
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Category:Letter
MONTHYEARML24309A2872024-11-0404 November 2024 International, HI-STORM 100 Amendment 19 Responses to Requests for Additional Information BVY 24-028, Pre-Notice of Disbursement from Decommissioning Trust2024-10-31031 October 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-027, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-10-30030 October 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G AEP-NRC-2024-80, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2024-10-15015 October 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask ML24274A3032024-10-0909 October 2024 Amendment 19 to Certificate of Compliance 1014 for Hi-Storm 100 Multi-Purpose Canister Storage System Request for Additional Information ML24240A1182024-10-0808 October 2024 0 Issuance Letter Amendment 18 to Renewed Certificate of Compliance No. 1014 for the HI-STORM 100 Cask System SVP-24-059, Correction to Registration of Use of Casks to Store Spent Fuel2024-10-0404 October 2024 Correction to Registration of Use of Casks to Store Spent Fuel BVY 24-026, Pre-Notice of Disbursement from Decommissioning Trust2024-10-0202 October 2024 Pre-Notice of Disbursement from Decommissioning Trust AEP-NRC-2024-79, Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask2024-09-26026 September 2024 Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask ML24263A2062024-09-19019 September 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for LaSalle County Station - Holtec MPC-68MCBS ML24240A1692024-09-18018 September 2024 Cy 2023 Summary of Decommissioning Trust Fund Status NL-24-0351, – ISFSI - Registration of Spent Fuel Cask Use2024-09-13013 September 2024 – ISFSI - Registration of Spent Fuel Cask Use ML24222A8592024-08-0909 August 2024 International - HI-STORM 100 Multipurpose Canister Storage System Amendment 19 Request ML24221A2702024-08-0808 August 2024 Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-62, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-08-0707 August 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask SVP-24-048, Registration of Use of Casks to Store Spent Fuel2024-07-31031 July 2024 Registration of Use of Casks to Store Spent Fuel BVY 24-024, Pre-Notice of Disbursement from Decommissioning Trust2024-07-30030 July 2024 Pre-Notice of Disbursement from Decommissioning Trust ML24178A4312024-07-29029 July 2024 Issuance of Certificate of Compliance No. 1014, Amendment No. 16 for the HI-STORM 100 Cask System, Cover Letter AEP-NRC-2024-56, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-07-0808 July 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask BVY 24-023, Pre-Notice of Disbursement from Decommissioning Trust2024-07-0202 July 2024 Pre-Notice of Disbursement from Decommissioning Trust IR 05000271/20240012024-06-28028 June 2024 NRC Inspection Report No. 05000271/2024001, Northstar Nuclear Decommissioning Company, LLC, Vermont Yankee Nuclear Power Station, Vernon, Vermont NL-24-0199, Request for Specific Exemption2024-06-25025 June 2024 Request for Specific Exemption SVP-24-040, Registration of Use of Casks to Store Spent Fuel2024-06-25025 June 2024 Registration of Use of Casks to Store Spent Fuel NL-24-0243, Registration of Spent Fuel Cask Use2024-06-18018 June 2024 Registration of Spent Fuel Cask Use ML24151A6482024-06-0303 June 2024 Changes in Reactor Decommissioning Branch Project Management Assignments for Some Decommissioning Facilities BVY 24-022, Pre-Notice of Disbursement from Decommissioning Trust2024-05-30030 May 2024 Pre-Notice of Disbursement from Decommissioning Trust ML24183A2752024-05-30030 May 2024 Registration of Use of Casks to Store Spent Fuel SVPLTR 24-0019, Registration of Use of Casks to Store Spent Fuel2024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel ML24145A0432024-05-23023 May 2024 Registration of Use of Casks to Store Spent Fuel 10 CFR 72.212 ML24143A0752024-05-22022 May 2024 Re. Ginna Nuclear Power Plant and Independent Spent Fuel Storage Installation (ISFSI) Registration for Use of General License ISFSI Casks BVY 24-020, Biennial Update of Quality Assurance Program Manual2024-05-22022 May 2024 Biennial Update of Quality Assurance Program Manual NL-24-0197, Registration of Spent Fuel Cask Use2024-05-20020 May 2024 Registration of Spent Fuel Cask Use ML24135A3212024-05-14014 May 2024 Annual Radioactive Effluent Release Report, January 1 Through December 31, 2023 BVY 24-019, 2023 Radiological Environmental Operating Report2024-05-0909 May 2024 2023 Radiological Environmental Operating Report BVY 24-017, Pre-Notice of Disbursement from Decommissioning Trust2024-05-0606 May 2024 Pre-Notice of Disbursement from Decommissioning Trust BVY 24-018, 2023 Radiological Effluent Release Report2024-05-0505 May 2024 2023 Radiological Effluent Release Report CP-202400153, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2024-04-29029 April 2024 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters SVP-24-028, Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report2024-04-26026 April 2024 Independent Spent Fuel Storage Installation Annual Radioactive Effluent Release Report ML24109A2072024-04-18018 April 2024 International - Submittal of HI-STORM Final Safety Analysis Report Update BVY 24-016, 2023 Individual Monitoring NRC Form 5 Report2024-04-18018 April 2024 2023 Individual Monitoring NRC Form 5 Report BYRON 2024-0021, Registration of Use of Cask to Store Spent Fuel2024-04-11011 April 2024 Registration of Use of Cask to Store Spent Fuel BVY 24-014, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-04-0101 April 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-015, Pre-Notice of Disbursement from Decommissioning Trust2024-04-0101 April 2024 Pre-Notice of Disbursement from Decommissioning Trust BYRON 2024-0019, Registration of Use of Cask to Store Spent Fuel2024-03-28028 March 2024 Registration of Use of Cask to Store Spent Fuel RS-24-020, Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS2024-03-15015 March 2024 Request for Exemption from Certain Requirements of 10 CFR 72.212 and 10 CFR 72.214 for Quad Cities Nuclear Power Station - Holtec MPC-68MCBS BVY 24-012, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-03-14014 March 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-011, Report of Investigation Pursuant to 10 CFR 20, Appendix G2024-03-0606 March 2024 Report of Investigation Pursuant to 10 CFR 20, Appendix G BVY 24-010, Pre-Notice of Disbursement from Decommissioning Trust2024-03-0505 March 2024 Pre-Notice of Disbursement from Decommissioning Trust ML24053A2572024-03-0101 March 2024 Withdrawal of Requested Licensing Action for a License Amendment Submitted for Approval of the License Termination Plan LR-N24-0022, Spent Fuel Cask Registration2024-02-29029 February 2024 Spent Fuel Cask Registration 2024-09-26
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Text
February 2, 2018
Mr. Coley C. Chappell Manager, Design and Programs Entergy Nuclear Operations, Inc. Vermont Yankee 320 Governor Hunt Road
Vernon, VT 05354
SUBJECT:
VERMONT YANKEE NUCLEAR POWER STATION INDEPENDENT SPENT FUEL STORAGE INSTALLATION, ISSUANCE OF EXEMPTION (CAC NO. 001028; DOCKET NOS.: 50-271, 72-59, and 72-1014; EPID: L-2017-LLE-0005)
Dear Mr. Chappell:
This is in response to your letter dated May 16, 2017 1 (BVY 17-006), and supplemented on September 7, 2017 2 and December 7, 2017 3, requesting an exemption under Title 10 of the Code of Federal Regulations (10 CFR) 72.7 to use the new regionalized quarter-symmetric head load (QSHL) pattern, load fuel that has been cooled for at least 2 years, and establish a per-cell maximum average burnup limit at 65,000 megawatt days per metric ton of uranium (MWD/MTU) for using HI-STORM 100 multipurpose canister (MPC)-68M at the Vermont Yankee Nuclear Power Station (VYNPS). Specifically, you requested an exemption from the requirements of 10 CFR 72.212(a)(2), 10 CFR 72.212(b)(3), 10 CFR 72.212(b)(5)(i), 10 CFR 72.214, and the portion of 10 CFR 72.212(b)(11), which require storage of spent nuclear fuel under a general license in dry storage casks approved under the provisions of 10 CFR Part 72, and compliance with the terms and conditions set forth in the certificate of compliance (CoC) for each dry storage spent fuel cask used by an independent spent fuel storage installation (ISFSI) general licensee.
Entergy plans to use Holtec's HI-STORM 100 cask system under CoC No. 1014, Amendment No. 10 for dry storage of spent nuclear fuel in MPC-68M canisters at VYNPS ISFSI. CoC No. 1014, Amendment No. 10, Appendix B, Figure 2.1-4 provides a regionalized loading pattern for MPC-68M; Section 2.4.3 and Table 2.4-4 identify that fuel must be cooled for at least 3 years before loading into storage canisters; and Appendix B, Section 2.4.3 provides an equation to calculate maximum allowable fuel assembly average burnup based on fuel decay heat, enrichment, and cooling time (for 3 years and longer). Entergy requested an exemption to allow
the use of the new QSHL pattern described in Figure 2.4-1 in BVY 17-006 Attachment 1; the QSHL pattern allows VYNPS to load hotter fuel from its final operating cycle with cooler fuel, as well as damaged fuel or fuel debris, in an optimized manner. The exemption would also allow VYNPS to load fuel cooled for at least 2 years into the MPC-68M as described in BVY 17-006 , Appendix B, Table 2.1-1,Section VI; this change would allow VYNPS to load fuel
1 Agency-wide Documents Access and Management System (ADAMS) Accession Number No. ML17142A354.
2 ADAMS Accession No. ML17255A236.
3 ADAMS Accession No. ML17346A685.
assemblies from its final operating cycle, which has minimum cooling times ranging from 2.83 to 2.99 years as of October 2017. In addition, VYNPS would be allowed to use a per-cell maximum average burnup limit at 65,000 MWD/MTU as described in BVY 17-006 Attachment 3, Appendix B, Table 2.1-1,Section VI.
The NRC staff reviewed Entergy's exemption request for the VYNPS ISFSI, and the details of the review are included in the enclosed safety evaluation report. Based upon the staff's evaluation, 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 is granting Entergy an exemption from the requirements in 10 CFR 72.212(a)(2), 10 CFR 72.212(b)(3), 10 CFR 72.212(b)(5)(i),
10 CFR 72.214, and the portion of 10 CFR 72.212(b)(11) that requires compliance with terms, conditions, and specifications of the CoC. This exemption allows VYNPS to use the new QSHL pattern, to load fuel that has been cooled for at least 2 years, and to establish a per-cell maximum average burnup limit at 65,000 MWD/MTU for using a MPC-68M canister.
In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter will be
available electronically for public inspection in the NRC Public Document Room or from the publicly available records component of the NRC's document system, ADAMS. ADAMS is accessible from the NRC Website at http://www.nrc.gov/reading-rm/adams.html.
If you have any questions, please contact me at (301) 415-6802, or Yen-Ju Chen of my staff, at (301) 415-1018.
Sincerely, /RA/ Meraj Rahimi, Acting Chief Spent Fuel Licensing Branch Division of Spent Fuel Management
Office of Nuclear Material Safety
and Safeguards
CAC NO. 001028 DOCKET NOS.: 50-271, 72-59, and 72-1014 EPID: L-2017-LLE-0005
Enclosure:
Safety Evaluation Report
SUBJECT:
VERMONT YANKEE NUCLEAR POWER STATION INDEPENDENT SPENT FUEL STORAGE INSTALLATION, ISSUANCE OF EXEMPTION (CAC NO.
001028; DOCKET NOS.: 50-271, 72-59, and 72-1014; EPID: L-2017-LLE-0005), DOCUMENT DATE: FEBRUARY 2, 2018
DISTRIBUTION: SFM R/F RPowell, RI MLayton, SFM /NMSS JParrott, RDB/NMSS Close out CAC No. 001028/ EPID: L-2017-LLE-0005 Package: ML17298A133; Ltr: ML17298A134; Enclosure (SER): ML17298A135 OFC NMSS NMSS NMSS NAME YChen WWheatley MRahimi DATE 10/25/2017 2/1/2018 2/2/2018 OFFICIAL RECORD COPY