ND-22-0882, (VEGP) Units 3 and 4 - Report of UFSAR Chapter 14 Changes to the Initial Test Program in Accordance with License Condition 2.D.(7)(a)
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| ML22321A233 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 11/17/2022 |
| From: | Coleman J Southern Nuclear Operating Co |
| To: | Andrea Veil Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| ND-22-0882 | |
| Download: ML22321A233 (1) | |
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|---|---|
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3/4. Southern Nuclear Jamie M. Coleman Regulatory Affairs Director 7825 River Road Waynesboro, Georgia 30830 Vogtle 3 & 4 706 848 6926 tel November 17, 2022 ND-22-0882 10 CFR 52.97(c)
Docket Nos.: 52-025 52-026 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001 Ms. Andrea Veil Director, Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington , DC 20555-0001 Southern Nuclear Operating Company Vogtle Electric Generating Plant (VEGP) - Units 3 and 4 Report of UFSAR Chapter 14 Changes to the Initial Test Program In accordance with License Condition 2.D.(7)(a)
Ladies and Gentlemen:
In accordance with license condition 2.D.(7)(a) of the Vogtle Electric Generating Plant (VEGP)
Units 3 and 4 Combined Licenses, Numbers NPF-91 and NPF-92, respectively, Southern Nuclear Operating Company (SNC) is required to report, within 30 days, a change made to the Initial Test Program (ITP) described in Final Safety Analysis Report Chapter 14, in accordance with 10 CFR 50.59(d) or in accordance with 10 CFR Part 52, Appendix D, Section VIII, "Processes for Changes and Departures."
On November 2, 2022, SNC approved Licensing Document Change Request LDCR-2022-035 changing the ITP described in the VEGP Units 3&4 Updated Final Safety Analysis Report (UFSAR)
Subsection 14.2.9. The change was made to revise the inspection terminology in UFSAR Subsection 14.2.9.1.1 0.e to be consistent with terminology in UFSAR Subsection 6.2.5.2.2.
These changes to the ITP described in the UFSAR (which includes the plant-specific DCD) were evaluated in accordance with 10 CFR 50.59 and 10 CFR 52 Appendix D Section VI 11 , and it was determined that they did not involve a change to Tier 1 information , Tier 2* information, or the Technical Specifications. The evaluation also determined that prior NRC approval for these changes was not required. This letter has been reviewed and determined not to contain security related information.
U.S. Nuclear Regulatory Commission ND-22-0882 Page 2 of 2 This letter contains no regulatory commitments.
Should you have questions, please contact Will Garrett at (706) 848-7154.
Respectfully submitted,
~~m1/4V Jamie M. Coleman Regulatory Affairs Director Vogtle 3 & 4 Southern Nuclear Operating Company JMC/CAC/sfr Regional Administrator, Region II Director, Office of Nuclear Reactor Regulation (NRA)
Director, Vogtle Project Office NRA Senior Resident Inspector - Vogtle 3 & 4