ML25085A255
| ML25085A255 | |
| Person / Time | |
|---|---|
| Site: | North Anna  (SNM-2507) |
| Issue date: | 03/26/2025 |
| From: | Hilbert L Virginia Electric & Power Co (VEPCO) |
| To: | Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| 25-090 | |
| Download: ML25085A255 (1) | |
Text
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 March 26, 2025 Attention: Document Control Desk Director, Division of Spent Fuel Management Office of Nuclear Material Safety and Safeguards United States Nuclear Regulatory Commission Washington, D. C. 20555-0001 Serial No.25-090 NAPS/RAP Docket Nos. 72-16 72-56 License No. SNM-2507 VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)
NORTH ANNA POWER STATION INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
SUMMARY
OF FACILITY CHANGES, TESTS AND EXPERIMENTS Pursuant to 10 CFR 72.48(d)(2), a report containing a brief description of any changes, tests, and experiments, including a summary of the evaluation of each, must be submitted to the NRC, at intervals not to exceed 24 months. Attachment 1 provides a summary description of Facility Changes, Tests and Experiments identified in 10 CFR 72.48 Evaluations performed for the North Anna Power Station ISFSI during 2024.
If you have any questions, please contact Marcus A. Hofmann at (540) 894-2100.
Very truly yours,
~~)-
Lisa Hilbert Site Vice President Commitments made in the letter: None Attachments
- 1. 1 O CFR 72.48 Summary Description of Facility Changes, Tests and Experiments cc:
Document Control Desk Mark Miller - Region II NRC Senior Resident Inspector-North Anna Power Station
ATTACHMENT 1 10 CFR 72.48
SUMMARY
DESCRIPTION OF FACILITY CHANGES, TESTS AND EXPERIMENTS NORTH ANNA POWER STATION ISFSI VIRGINIA ELECTRIC AND POWER COMPANY (DOMINION ENERGY VIRGINIA)
10 CFR 72.48
SUMMARY
DESCRIPTION OF FACILITY CHANGES, TESTS AND EXPERIMENTS 10 CFR 72.48 EVALUATION - Document Evaluated: ETE-NAF-2021-0068 Rev. 3 Brief
Description:
Calculation 593520-0218 evaluates the stresses on a DSC shell with a reduced thickness from 0.5 nominal to 0.42". The calculation also evaluates a localized flaw as observed on DSC NAN-EOS-37PTH-009-84H/84L after the 2023 ISFSI campaign. The structural and confinement design functions are evaluated due to the shell thickness reduction to 0.42". Design functions of thermal, criticality, shielding and the evaluation of the flaw screened out and are not adversely affected by the nonconforming condition of the shell.
Reason for Change: The purpose of this report is to document the written evaluations required by Section 72.212 of Title 10 of the Code of Federal Regulations, Part 72, *(10 CFR 72) "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor Related Greater than Class C Waste." The written evaluations are based on the use under a general license of the NUHOMS EOS System using a 37PTH DSC in accordance with NRC Certificate of Compliance No.
1042, Docket No. 72-1042.
Section 72.210 of 10 CFR 72 grants a general license for the storage of spent nuclear fuel at an Independent Spent Fuel Storage Installation (ISFSI) to holders of a 10 CFR 50 license at the associated reactor site. Section 72.212 gives the conditions for this general license and delineates requirements that the general licensee must meet.
Dominion Virginia Power (Dominion Energy) has selected the NUHOMS EOS System using a 37PTH DSC for storage of spent nuclear fuel. Dominion Energy has evaluated the NUHOMS EOS dry storage system for use at the North Anna Power Station (NAPS)
ISFSI. Pursuant to 10 CFR 72.212, this report documents the evaluations performed by Dominion Energy to demonstrate that the safety analyses for the NRC approved NUHOMS EOS storage system bound the NAPS plant-specific parameters, and the use of this storage system does not require a change to the facility Technical Specifications.
ETE-NAF-2021-0068 provides summary documentation of the ISFSl's compliance with 10 CFR 72.212. Per procedure NF-AA-NSF-102, a 72.48 screen is required to evaluate changes to the 72.212 Evaluation Report. This is to satisfy the requirement of 10 CFR 72.212(7) that changes to the evaluations required by 10 CFR 72.212 evaluatioR report be addressed through the 10 CFR 72.48 process. Per procedure CM-AA-ETE-101 Section 2.2, the requirement that ETE-NAF-2021-0068 be reviewed under the 10 CFR 72.48 process forces a designation of Level 2 for ETE and under Section 2.5.h, this ETE implements the results of various calculations noted in the document and therefore is a Level 2 ETE requiring a 72.48 review.
Summary: Calculation 593520-0218 evaluates the DSC shell related to the as found condition of DSC NAN-EOS-37PTH-009-84H/84L. To address the scoring on the DSC shell, stresses were evaluated with a reduced thickness from 0.5 nominal to 0.42"
using the UFSAR methodology. The calculation shows that increased shell stresses remain below the ASME Code Allowable and therefore the activity does not require prior NRG approval.
Additionally, the calculation evaluates a localized flaw as observed on DSC NAN-EOS-37PTH-009-84H/B4L after the 2023 ISFSI campaign using ASME Section XI, Appendix C as the method of evaluation. The flaw in the subject DSC shell was induced by mechanical means during loading activities. The NUHOMS EOS UFSAR does not contemplate or evaluate a flaw of this nature in the base metal of the DSC shell. The method of evaluation is described in the NUHOMS EOS UFSAR for a circumferential weld flaw in the outer top cover plate weld, not for flaws in base metal (i.e. shell). For this reason, changes to method of evaluation were screened out and question 8 of this evaluation was marked "N/ A".
Criteria 1-7 of this 72.48 evaluation 'have been answered no. Therefore, it has been determined that NRG approval is not required for this activity and the calculation may be implemented through the North Anna EOS 72.212 Evaluation Report via 72.48.