NL-24-0045, Supplement to Response to Requests for Additional Information for Proposed Alternative ALT-VR-02
| ML24039A175 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 02/08/2024 |
| From: | Coleman J Southern Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NL-24-0045 | |
| Download: ML24039A175 (1) | |
Text
A Southern Nuclear Regulatory Affairs 3535 Colonnade Park w ay Birmingham , AL 35243
205 992 5000
February 8, 2024
Docket Nos.: 50-424 NL-24-0045 50-425
U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001
Vogtle Electric Generating Plant - Units 1 and 2 Supplement to Response to Requests for Additional Information for Proposed Alternative AL T-VR-02
Ladies and Gentlemen:
By letter dated May 1, 2023 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML23121A267), Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) and a proposed alternative request for Vogtle Electric Generating Plant (Vogtle), Units 1 and 2 regarding revisions to Technical Specification (TS) 3.4.14, "RCS Pressure Isolation Valve (PIV) Leakage", and an alternative to ASME OM Code for applicable Vogtle Pressure Isolation Valves to allow testing to be conducted at a performance based frequency, as specified in Nuclear Engineering Institute 94-01, Revision 3-A.
By letter dated November 17, 2023 (ADAMS Accession No. ML23321A242), SNC responded to an NRC request for additional information. A clarification call was held on Thursday, January 11, 2024, between SNC and the NRC regarding RAI response #3 for AL T-VR-02. Based on the results of the clarification call, SNC is issuing a supplement to clarify that SNC's request does not modify the requirement to meet 1 0CFR50.55a(b)(3)(iv), which states:
OM condition: Check valves (Appendix II). Appendix II of the ASME OM Code, 2003 Addenda through the 2012 Edition, is acceptable for use with the following requirements.
Trending and evaluation must support the determination that the valve or group of valves is capable of performing its intended function(s) over the entire interval. At least one of the Appendix II condition monitoring activities for a valve group must be performed on each valve of the group at approximate equal intervals not to exceed the maximum interval shown in the following table:
Table 3 to Paragraph (b)(3)( iv)-Maximum Intervals For Use When Applying Internal Extensions
Group size Maximum interval between activities of member valves in the groups Maximum interval between activities of each va lve in the group (years)
(years)
4.5 16
3 4.5 12
6 12
Not applicable 10 U. S. Nuclear Regulatory Commission NL-24-0045 Page 2
Subsequent to AL T-VR-02 approval, SNC will continue to meet this condition.
This letter contains no NRC commitments. If you have any questions, please contact Ryan Joyce at 205.992.6468.
Respectfully submitted,
~~
Jamie Coleman Regulatory Affairs Director
JMC/dsp/cbg
cc: Regional Administrator, Region II NRR Project Manager - Vogtle 1 & 2 Senior Resident Inspector - Vogtle 1 & 2 RType: CVC?000