ML23052A044
| ML23052A044 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 02/21/2023 |
| From: | Ameren Missouri, Union Electric Co |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML23052A041 | List: |
| References | |
| ULNRC-06796, EPID L-2022-LLA-0132 | |
| Download: ML23052A044 (1) | |
Text
Enclosure 2 to ULNRC-06796 Page 1 of 3 ENCLOSURE 2 SUPPLEMENT TO LICENSE AMENDMENT REQUEST to ULNRC-06796 Page 2 of 3 SUPPLEMENT TO LICENSE AMENDMENT REQUEST
References:
References are provided at the end of this enclosure.
While developing the core design/loading pattern for operating cycle 27, the Reactor Engineering group at Callaway identified a situation in which the new fuel would not be explicitly bounded by the analyses associated with the spent fuel storage license amendment request identified in Reference 1.
The issue manifested itself on January 31, 2023, with the finalization of the operating cycle 27 core loading plan.
To address this issue, Ameren Missouri instructed Holtec International to provide an analysis of the effect the parameters of the fuel ordered for operating cycle 27 will have on the results of the previously provided criticality safety analysis given in Reference 3. The results of the supplementary analysis are presented in Section 4.0, "Calculations with a Different IFBA Loading," of Enclosure 8.
The issue involves the acquisition of Westinghouse fuel for operating cycle 27 that will contain 200 integral fuel burnable absorber (IFBA) rods with a maximum absorber content of 2.40 mg 10B/inch.
This combination of IFBA rods at this maximum absorber content is not explicitly bounded by the inputs used in the criticality safety analysis supporting the LAR described in Reference 1. That analysis was documented in Reference 3 and was included in the LAR as Attachment 6 to Enclosure 1.
The SFP criticality safety analysis documented in Reference 3 addresses IFBA rods in section 3.3.6.3, "Integral and Removable Burnable Absorbers." In the 4th bullet in section 3.3.6.3.4, "Approach Used in the Burnup Credit Evaluation," the bounding reactivity effect of IFBA rods and removable burnable absorbers during depletion are discussed in terms of the number of IFBA rods and the associated maximum absorber content (expressed in mg 10B/inch) in combination with the number of removable burnable absorber rods.
Section 4.0 of Enclosure 8 provides the supplemental analyses that conclude that the fuel assemblies ordered for operating cycle 27 with the specified number of IFBA rods, at the higher 10B loading, and the absence of the WABA, is bounded by the cases presented in Reference 3.
Ameren Missouri requests that the staff supplement the license amendment request described in Reference 1 and its supporting analyses given in Reference 3 with the supplemental analysis results given in Enclosure 8 (Reference 4).
The proposed supplement addressing the storage of fuel containing IFBA requirements for operating cycle 27 continues to support the conclusions reached in Section 4.0, "Regulatory Evaluation," of the LAR submitted in Reference 1. This includes the determination that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c). In addition, this includes the determination that the proposed change continues to meet the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9).
to ULNRC-06796 Page 3 of 3
References:
- 1.
Ameren Missouri letter ULNRC-06723, "License Amendment Request Regarding Proposed Technical Specification Changes for Spent Fuel Storage (LDCN 22-0015)," dated August 29, 2022 (ADAMS Accession No. ML22242A122)
- 2.
NRR e-mail capture, "Final - Request for Additional Information - Callaway Plant, Unit 1 -
LAR for proposed changes to TS for SFP - EPID: L-2022-LLA-0132," dated January 24, 2023 (ADAMS Accession No. ML23026A021)
- 3.
HI-2220020, Revision 2, "Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station," dated October 21, 2022, which was previously provided to the NRC as Attachment 6 to Enclosure 1 of ULNRC-06723 (i.e., Reference 1)
- 4.
HI-2230125, Revision 0, "Supplemental Criticality Safety Analysis of SFP for Callaway Nuclear Generating Station," dated February 14, 2023.