ML23284A064
| ML23284A064 | |
| Person / Time | |
|---|---|
| Site: | 07201004 |
| Issue date: | 10/11/2023 |
| From: | Shaw D TN Americas LLC |
| To: | Office of Nuclear Material Safety and Safeguards, Document Control Desk |
| References | |
| E-62842 | |
| Download: ML23284A064 (1) | |
Text
October 11, 2023 E-62842 Orano TN 7160 Riverwood Drive Suite 200 U. S. Nuclear Regulatory Commission Columbia, MD 21046 Attn: Document Control Desk USA Tel: 410-910-6900 One White Flint North Fax: 434-260-8480 11555 Rockville Pike Rockville, MD 20852
Subject:
Supplement to Submittal of Biennial Reports of 72.48 E valuations Performed for the Standardized NUHOMS System, Certificate of Compliance (CoC) 1004, for the Periods 07/26/2016 to 07/25/2018 and 7/28/2020 to 7/27/2022, Docket 72-1004
Reference:
(1) Letter from Jayant Bondre (TN) to Document Contr ol Desk, Submittal of Biennial Report of 10 CFR 72.48 Evaluations Perfo rmed for the Standardized NUHOMS System, CoC 1004, for the Period 07/26/2016 to 07/25/2018, Docket 72-1004, July 25, 2018
(2) Letter from Donis Shaw (TN) to Document Control Desk, Submittal of Biennial Report of 10 CFR 72.48 Evaluations Perfo rmed for the Standardized NUHOMS System, CoC 1004, for the Period 7/28/2020 to 7/27/2022, Docket 72-1004, July 27, 2022
Pursuant to the requirements of 10 CFR 72.48(d)(2), the submitt als referenced above provided 72.48 evaluations performed for the CoC 1004 Standardi zed NUHOMS System, for the periods indicated. Enclosure 1 provides additi onal 72.48 evaluation summaries that were inadvertently omitted for LRs 721004-1572, Revision 0, approved on 3/8/2017; 721004-1591, Revision 0, approved on 2/20 /2017; and 721004-1856, Revision 0, approved on 9/8/2020. The summaries in clude indication as to whether the evaluations had associated Updated Final Safe ty Analysis Report (UFSAR) changes that were incorporated into the UFSAR for the Standardized NUHOMS Horizontal Modular Storage System for Irradiated Fuel, NUH003. 0103.
This situation has been entered into TN Americas LLCs (TNs) c orrective action program and actions are in progress to prevent recurrence.
E-62842 Document Control Desk Page 2 of 2
Should you or your staff require additional information, please do not hesitate to contact me at 410-910-6878 or Doug Yates at 434-832-3101.
Sincerely,
Digitally signed by Don Shaw Don ShawDate: 2023.10.11 08:18:16
-04'00'
Don Shaw Licensing Manager
cc: Christian J. Jacobs (NRC DFM/STLB)
Enclosure:
- 1. Supplemental Report of 10 CFR 72.48 Evaluations Performed fo r CoC 1004 for the Periods 07/26/2016 to 07/25/2018 and 7/28/2020 to 7/27/2022
Enclosure 1 to E-62842
Supplemental Report of 10 CFR 72.48 Evaluations Performed for CoC 1004 for the Periods 07/26 /2016 to 07/25/ 2018 and 7/28 /2020 to 7/27 /2022
LR No. Description of Change, Test, or Experiment Summary of Evaluation 721004-The licensing review evaluates the storage of fuel assemblies A review shows that there are two categories of debris present (FAs) containing debris/foreign material within a NUHOMS within the FAs which required evaluation: (1) stainless steel or 32PTH1 Type 2-W DSC. The utility has provided a list of all carbon steel metal debris in various geometries and (2) rubber, foreign material identified in the associated spent fuel assemblies. plastic, fiber, or unknown debris (cloth strings, string mesh, plastic, This material is not readily retrievable before loading into a plastic tape, and nylon wrap). The loading plan that was provided NUHOMS DSC under CoC 1004 Amendment 14 in a future would be enveloped by the analysis evaluated in this LR. The loading campaign. The data identified instances of debris in 293 conservative option (worst case) was to determine the highest fuel assemblies. The foreign material has been identified as metal, amount of non -metal debris that could be loaded in one single plastic, fiber, rubber, or unknown. DSC. Plastic, rubber, fiber, and unknown debris provided by the utility shows the maximum cumulative weight of the pieces of debris in a single DSC to be 0.113 lbs. However, this is conservative as the loading plan shows not all of these fuel assemblies will be loaded in a single DSC.
1572 The metal debris (stainless steel, carbon steel, or a combination)
Rev. 0 shows the maximum cumulative weight of all listed metal debris of 1.32 lbs. The debris is split between many DSCs and the total weight of metal debris in a single DSC is 0.18 lbs. The tentative loading plan shows the maximum cumulative weight per any single DSC for plastic, rubber, fiber, and unknown debris is 0.013 lbs. In addition, LR 721004-1074 [ML13196A04] previously evaluated up to 0.17 lb of metal debris and 0.0331 lb of plastic/fiber debris to be acceptable for storage in a single 32PT DSC with Westinghouse 14X14 fuel.
The evaluation concluded that the overall form, fit and function of the DSC remains unchanged due to the potential addition of this small amount of debris. All eight 72.48 evaluation criteria were met.
- No associated UFSAR changes were required.
Page 1 Enclosure 1 to E-62842
LR No. Description of Change, Test, or Experiment Summary of Evaluation 721004-This change evaluates a non-conforming condition where the The basket structure consists of assemblies of stainless steel fuel 61BTH Type 1 DSC aluminum outer basket plates between the compartments held in place by basket rails and the hold down basket and the rails were fabricated below the required thickness ring. The overall design function of the basket assembly is to resulting in the basket to shell gap requirement being exceeded. provide structural support for the fuel assemblies, to form a rigid structure to ensure criticality control, and to provide a heat transfer path from the fuel assemblies to the DSC Shell. The bounding under-thickness aluminum rails were evaluated in a thermal calculation that showed that the under-thickness plates and 1591 thinner shims caused the temperature of internal DSC Rev. 0 components to rise because the gap between the basket and shell affects heat transfer. The larger gap reduces heat transfer from the basket to the shell which in turn increases the temperature of the basket structural components and the fuel cladding. However, the increased temperature is bounded for normal, off-normal, and accident conditions by the current evaluation in the UFSAR. All eight 72.48 evaluation criteria were met.
- No associated UFSAR changes were required.
The change deletes the specific code and edition (i.e., ACI 318-The basemat and approach slab are reinforced concrete
- 95) to be applied for the design and construction of the ISFSI foundations which perform a structural design function in support basemat and approach slab from a horizontal storage module of the HSM-H and transfer cask (TC), respectively. Although (HSM) Model HSM-H SAR drawing. Use of ACI 318 and or ACI these components are credited to perform a structural design 349 codes for the design and construction of the basemat and function, they are classified as NITS since there is no credible approach slab are appropriate and acceptable per NUREG-1536. mechanism that could result in gross structural failure of these ACI 318 is a commercial building code for reinforced concrete components, and as such they are non-licensed components that 1856 structures. ACI 349 is a more specific code intended to address may be designed and constructed to commercial standards. The Rev. 0 the design and construction of nuclear safety-related structures, LR determined that the change does not affect the safety where design conditions for nuclear containment building functions of the HSM-H and that the structural design function of structures such as elevated temperatures and pressures are the basemat and approach slab to provide structural support to considered. Such conditions do not apply to the design of the the HSM-H and transfer trailer loaded with the TC, respectively, ISFSI basemat and approach slab. The drawing is revised to continues to be satisfied by use of appropriate ACI design and state that the basemat and approach slab shall be designed and construction codes which are acceptable per NUREG-1536. All constructed in accordance with ACI 318 and/or ACI 349 with no eight 72.48 evaluation criteria were met.
specific code editions specified.
- Changes were incorporated into UFSAR Revision 19.
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