ML22354A277
| ML22354A277 | |
| Person / Time | |
|---|---|
| Site: | 07201026 |
| Issue date: | 11/08/2023 |
| From: | Yoira Diaz-Sanabria Office of Nuclear Material Safety and Safeguards |
| To: | Westinghouse |
| Shared Package | |
| ML22354A263 | List: |
| References | |
| Download: ML22354A277 (1) | |
Text
NRC FORM 651 U.S. NUCLEAR REGULATORY COMMISSION (3-1999) 10 CFR 72 CERTIFICATE OF COMPLIANCE Page 1 of 4 FOR SPENT FUEL STORAGE CASKS
The U.S. Nuclear Regulatory Commission is issuing this Certificate of Compliance pursuant to Title 10 of the Code of Federal Regulations, Part 72, "Licensing Requirements for the Independent Storage of Spent Nuclear Fuel, High-Level Radioactive Waste, and Reactor-Related Greater than Class C Waste" (10 CFR Part 72). This certificate is issued in accordance with 10 CFR 72.238, certifying that the storage design and contents described below meet the applicable safety standards set forth in 10 CFR Part 72, Subpart L, and on the basis of the Final Safety Analysis Report (FSAR) of the cask design. This certificate is conditional upon fulfilling the requirements of 10 CFR Part 72, as applicable, and the conditions specified below.
Certificate No. Effective Date Expiration Date Docket No. Amendment No. Amendment Effective Date Package (Certificate) Identification No.
1026 02/15/2001 02/15/2021 72-1026 3 05/07/2003 USA/72-1026 Renewed Renewed Revision No. Revision Effective Date Effective Date Expiration Date TBD 02/15/2061 0 N/A Issued To: (Name/Address)
Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township, PA 16066
Safety Analysis Report Title
FuelSolutionsTM Safety Analysis Report for the FuelSolutions TM Storage System Docket No. 72-1026
CONDITIONS
This certificate is conditioned upon fulfilling the requirements of 10 CFR Part 72, as applicable, the attached Appendix A (Technical Specifications), and the conditions specified below:
- 1. CASK
- a. Model No.: FuelSolutionsTM Storage System
The FuelSolutionsTM Storage System (the cask) consists of the following components: (1) canister for dry storage of spent nuclear fuel (W21 and W74); (2) transfer cask for canister loading, closure and handling capability (W100); and (3) storage cask which provides passive vertical dry storage of a loaded canister (W150). The cask stores up to 21 pressurized water reactor (PWR) assemblies or 64 boiling water reactor (BWR) assemblies.
- b. Description
The FuelSolutionsTM Storage System is certified as described in the Safety Analysis Report (SAR) and in NRCs Safety Evaluation Report (SER) accompanying the Certificate of Compliance (CoC). The cask comprises three discrete components: the W21 and W74 canisters, the W100 transfer cask, and the W150 storage cask.
The canister is the confinement system for the stored fuel. A typical canister consists of a shell assembly, top and bottom inner closure plates, vent and drain port covers, internal basket assembly, top and bottom shield plugs, and top and bottom outer closure plates. All structural components are constructed of high-strength carbon (electroless nickel coated) or stainless steel. The canister shell, top and bottom inner closure plates, and the vent and drain port covers form the confinement boundary. The W21 fuel basket is a right circular cylinder configuration with 21 stainless steel guide tubes for the PWR contents. The guide tubes are laterally supported by a series of spacer plates held in position by support rods that run through sleeves between the
NRC FORM 651A U.S. NUCLEAR REGULATORY COMMISSION (3-1999) Certificate No. 1026 10 CFR 72 CERTIFICATE OF COMPLIANCE FOR SPENT FUEL STORAGE CASKS Amendment No. 3 Supplemental Sheet Renewed Yes Page 2 of 4
- 1. b. Description (continued)
spacer plates. The guide tubes include neutron poison sheets (Boral) on all four sides. The W21 canister has two classes of canister, W21M and W21T, differing in materials of construction used for the canister shell and basket assembly. Each class of canister has four different types. The W21T canister class consists of a long lead (LL), long steel (LS), short lead (SL), and short steel (SS) canister. The W21M canister has long, depleted uranium (LD); long steel (LS); short, depleted uranium (SD), and short steel (SS) designs. The W74 fuel basket assembly consists of two right circular cylindrical baskets, with a total of 74 cell locations and a capacity of up to 64 BWR assemblies. The ten unfueled cell locations are mechanically blocked to prevent loading in these positions. The guide tubes are supported by a series of spacer plates, held in position by support tubes that run through sleeves placed between the spacer plates. The guide tubes include neutron poison sheets (borated stainless steel) in an arrangement that assures there is a poison sheet between all assemblies. The W74 canister has two classes of canister, W74M and W74T, differing in materials of construction used for the canister shell and basket assembly. Each canister class has only a long steel (LS) design.
The W150 is the storage overpack for both the W21 and W74 canisters. There is a long and a short version of the cask, both of reinforced concrete with a steel liner. The W150 provides structural support, shielding, protection from environmental conditions, and natural convection cooling of the canister during long-term storage. The storage cask has an annular air passage to allow the natural circulation of air around the canister. The spent fuel decay heat is transferred from the fuel assemblies to the guide tubes, and then via conduction through the spacer plates and radiation to the canister wall. Heat flows by radiation and convection from the canister wall to the circulating air and is exhausted through the air outlets. The passive cooling system is designed to maintain acceptable reinforced concrete and peak cladding temperatures for the authorized fuel types during storage.
The W100 transfer cask provides shielding during canister movements between the spent fuel pool and the storage cask. The cask is a multi-wall (steel/lead/steel/water/steel) design. Covers are bolted on each end of the cask to allow access to the cask cavity from either end. The top cover includes a secondary central cover for ram access during horizontal loading and unloading operations. The W100 neutron shield cavity is filled with clean water either prior to placement in or following removal from the spent fuel pool. To prevent contamination of the annular region between the W100 and the canister, an inflatable annulus seal is used during loading. Heat transfer from the transfer cask is primarily by conduction through the cask wall. A thermocouple probe is included to ensure that the transfer cask system temperatures are within limits during horizontal transfer.
- 2. OPERATING PROCEDURES
Written operating procedures shall be prepared for cask handling, loading, unloading, movement, surveillance, and maintenance. The users site-specific written operating procedures shall be consistent with the technical basis described in Chapter 8 of the SAR.
- 3. ACCEPTANCE TEST AND MAINTENANCE PROGRAM
Written cask acceptance tests and a maintenance program shall be prepared consistent with the technical basis described in Chapter 9 of the SAR.
NRC FORM 651A U.S. NUCLEAR REGULATORY COMMISSION (3-1999) Certificate No. 1026 10 CFR 72 CERTIFICATE OF COMPLIANCE Amendment No. 3 FOR SPENT FUEL STORAGE CASKS Renewed Yes Supplemental Sheet Page 3 of 4
- 4. QUALITY ASSURANCE
Activities in the areas of design, procurement, fabrication, assembly, inspection, testing, operation, maintenance, repair, modification of structures, systems and components, and decommissioning that are important to safety shall be conducted in accordance with a Commission-approved quality assurance program which satisfies the applicable requirements of 10 CFR Part 72, Subpart G, and which is established, maintained, and executed with regard to the cask system.
- 5. HEAVY LOADS REQUIREMENTS
Each licensed facility must ensure that cask lifting is evaluated in accordance with the existing heavy loads requirements and procedures of the licensed facility in which the lift is made. An additional safety review by the facility (under 10 CFR 50.59 or 10 CFR 72.48, if applicable) is required to show operational compliance with existing facility/site-specific heavy loads requirements.
- 6. APPROVED CONTENTS
Contents of the FuelSolutionsTM Storage System must meet the specifications given in Appendix A to this certificate.
- 7. DESIGN FEATURES
Features or characteristics for the site, cask, or ancillary equipment must be in accordance with Appendix A to this certificate.
- 8. CHANGES TO THE CERTIFICATE OF COMPLIANCE
The holder of this certificate who desires to make changes to the certificate, which includes Appendix A (Technical Specifications), shall submit an application for amendment of the certificate.
- 9. AUTHORIZATION
The FuelSolutionsTM Storage System, which is authorized by this certificate, is hereby approved for use under the general license issued pursuant to 10 CFR 72.210, subject to the conditions specified by 10 CFR 72.212, this certificate, and the attached Appendices A, B, and C.
The CoC holder shall submit updated FSARs to the Commission, in accordance with 10 CFR 72.4, within 90 days after the effective date of the CoC renewal. The updated FSARs shall reflect the changes and CoC holder commitments resulting from the review and approval of the CoC renewal.
The CoC holder shall continue to update the FSARs pursuant to the requirements of 10 CFR 72.248.
NRC FORM 651A U.S. NUCLEAR REGULATORY COMMISSION (3-1999) Certificate No. 1026 10 CFR 72 CERTIFICATE OF COMPLIANCE FOR SPENT FUEL STORAGE CASKS Amendment No. 3 Supplemental Sheet Renewed Yes Page 4 of 4
- 11. 10 CFR 72.212 EVALUATIONS FOR RENEWED CoC USE DURING THE PERIOD OF EXTENDED OPERATION
Any general licensee that initiates spent fuel dry storage operations with the FuelSolutions' Storage System after the effective date of the CoC renewal and any general licensee operating a FuelSolutions' Storage System as of the effective date of the CoC renewal, including those that put additional storage systems into service after that date, shall:
- a. As part of the evaluations required by 10 CFR 72.212(b)(5), include evaluations related to the terms, conditions, and specifications of this CoC amendment as modified (i.e., changed or added) as a result of the CoC renewal.
- b. As part of the document review required by 10 CFR 72.212(b)(6), include a review of the FSAR changes resulting from the CoC renewal and the NRC Safety Evaluation Report related to the CoC renewal.
- c. Ensure that the evaluations required by 10 CFR 72.212(b)(7) and determinations required by 10 CFR 72.212(b)(8) capture the evaluations and review described in (a.) and (b.) of this CoC condition.
- d. Complete this condition prior to entering the period of extended operation or no later than 365 days after the effective date of the CoC renewal, whichever is later.
- 12. AMENDMENTS AND REVISIONS FOR RENEWED CoC
All future amendments and revisions to this CoC shall include evaluations of the impacts to aging management activities (i.e., time-limited agi ng analyses and aging management programs) to ensure they remain adequate for any changes to structures, systems, and components within the scope of renewal.
FOR THE NUCLEAR REGULATORY COMMISSION
Yoira K. Diaz-Sanabria, Chief Storage and Transportation Licensing Branch Division of Fuel Management Office of Nuclear Material Safety and Safeguards Washington, D.C., 20555
Attachments:
Appendix A - FuelSolutions TM Storage System Technical Specifications Appendix B - FuelSolutions TM W21 Canister Technical Specifications Appendix C - FuelSolutions TM W74 Canister Technical Specifications
Dated: TBD