NL-25-0013, Units 1 and 2, License Renewal Commitment Item 20
| ML25016A339 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 01/16/2025 |
| From: | Coleman J Southern Nuclear Operating Co |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NL-25-0013 | |
| Download: ML25016A339 (1) | |
Text
.. Southern Nuclear January 16, 2025 Docket Nos.: 50-424 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Regulatory Affairs Vogtle Electric Generating Plant - Units 1 and 2 License Renewal Commitment Item 20 Ladies and Gentlemen:
3535 Colonnade Parkway Birmingham, AL 35243 205 992 5000 NL-25-0013 Commitment Item No. 20 of NUREG-1920, Safety Evaluation Report Related to the License Renewal of the Alvin E. Vogtle Electric Generating Plant (VEGP), Units 1 and 2, requires the submission of an inspection plan to the staff for the VEGP reactor internals for review and approval at least 24 months prior to entering the periods of extended operation for the VEGP units. The period of extended operation for VEGP, Unit 1 begins on January 16, 2027, and February 9, 2029, for Unit 2. Since establishing this commitment, the industry and Nuclear Regulatory Commission (NRC) have adopted a strategy to proceed with a generic approach through the Electric Power Research Institute (EPRI) Materials Reliability Program (MRP). MRP-227 Revision 1 was submitted to the NRC for approval and was subsequently approved by the NRC as captured in version MRP-227 Revision 1-A. VEGP Unit 1 and 2 Reactor Internals inspection plan is compliant with MRP-227 Revision 1-A. MRP-227 Revision 1-A, Appendix B requires an applicability assessment to ensure that the plant has operated within the specific operational requirements post 30-years of operation. Southern Nuclear Operating Company (SNC) has confirmed that MRP-227 Revision 1-A is applicable to both VEGP Units 1 and 2. MRP-227 Revision 2 is currently under review by the NRC. Once approved, VEGP will update to this revision as outlined in the schedule provided by the EPRI MRP.
The Reactor Internals inspections provided in MRP-227 Revision 1-A have been incorporated into the VEGP Reactor Internals Strategic Plan. MRP-227 Revision 1-A addresses the bases, inspection methods, and acceptance criteria associated with aging management of the reactor vessel internals. A summary of the primary inspection elements is provided in Tables 1 and 2 of the Enclosure. This table incorporates interim guidance of MRP-2023-005, MRP-2024-004, and MRP-2024-008. Acceptance criteria for these examinations are developed in accordance with WCAP-17096 Revision 3-A. Scope expansion is evaluated per the Corrective Action Program. In addition, thermal sleeve aging management is in compliance with materials initiative requirements contained in PWROG-16003, Rev. 2, Appendix A.
Core support lugs (along with the associated support pads and attachment welds) are inspected in in accordance with ASME Section XI 10-year B-N visual examinations. SNC believes that there is not a need for additional staff review and approval of the technical details and/or basis for the VEGP Units 1 and 2
US Nuclear Regulatory Commission NL-25-0013 Page 2 of 2 plant specific inspection plans because the technical basis for the scope, periodicity, nondestructive examination requirements, and acceptance criteria are all now generically approved through MRP-227 Revision 1-A.
If guidance is not implemented in accordance with the latest applicable requirements of MRP-227, SNC will submit a deviation in accordance with the latest approved requirements of NEI 03-08.
SNC believes that this notification effectively fulfills the intent of commitment item 20 contained in NUREG-1920, which was established prior to staff approval on the generic method provided in MRP-227 Revision 1-A. This letter contains no new NRC commitments.
If you have any questions, please contact Ryan Joyce at (205) 992-6468.
Respectfully submitted, Co~~
Jamie M. Coleman Regulatory Affairs Director JMC/btr/cbg
Enclosure:
Primary Reactor Internals Inspection Schedule for Vogtle 1 and 2 cc:
Regional Administrator NRR Project Manager - Vogtle 1 & 2 Senior Resident Inspector - Vogtle 1 & 2 RType: CVC?000 2
Vogtle Electric Generating Plant - Units 1 and 2 Primary Reactor Internals Inspection Schedule for Vogtle 1 and 2 Enclosure to NL-25-0013 Primary Reactor Internals Inspection Schedule for VEGP 1 and 2
Enclosure to NL-25-0013 Primary Reactor Internals Inspection Schedule for Vogtle 1 and 2 Table 1 - Primary Reactor Internals Inspection Schedule for VEGP Unit 1 1R22 1R23 1R25 1R26 1R28 1R32 1R33 Component(s)
F-24 S-26 S-35 S-20 F-21 (dual outage)
S-29 (dual outage)
F-36 Measurement/
Measurement /
Control Rod Guide Measurement/ V VT-3 I relocate VT-3 l 9new W I Tube Assembly -
T-3 Relocated C09, (N11, M08, guide tube Guide Plates (Cards)
C II L03, J13 and K06) installations Control Rod Guide W2 Tube Assembly -
EVT-1 EVT-1 Lower Flange Welds Core Barrel Assembly W3
- Upper Flange and EVT-1 EVT-1 Upper Girth Weld W4 Core Barrel Assembly UT UT
- Lower Girth Weld Baille Former W6 Assembly - Baille to UT UT Former Bolts Baille Former W7 Assembly - High VT-3 VT-3 Fluence Seam W8 Internals Hold Down NIA to VEGP-1, VEGP-1 does not have a 304 stainless steel hold down spring Spring W9 Thermal Shield NIA to VEGP-1, VEGP-1 utilizes a neutron panel design; therefore, does not have thermal shield flexures Flexures Lower Radial Support Clevis Insert X-750 UT UT Bolts Core Barrel Assembly
- Middle and Lower EVT-1 EVT-1 Axial Welds Beginning of License Renewal Period, 1/27 E-1
Enclosure to NL-25-0013 Primary Reactor Internals Inspection Schedule for Vogtle 1 and 2 Table 2 - Primary Reactor Internals Inspection Schedule for VEGP Unit 2 2R22 2R23 2R24 2R25 2R26 2R31 2R32 ID Component(s)
S-22 F-23 S-25 F-26 S-28 F-35 S-37 (dual outage)
(dual outage)
(dual outage)
Control Rod Guide Tube Measurement/
Relocated BI 0, Measurement/
12 Guide Tube W l Assembly - Guide Plates VT-3 G03, G 13, J03, VT-3/Relocate Replacements (Cards)
N09, P08 P04, F08 Control Rod Guide Tube W2 Assembly - Lower EVT-1 EVT-1 Flange Welds Core Barrel Assembly -
W3 Upper Flange and Upper EVT-1 EVT-1 Girth Weld W4 Core Barrel Assembly -
UT UT Lower Girth Weld W6 Baffle Former Assembly UT UT
- Baffle to Former Bolts W7 Baffle Former Assembly VT-3 VT-3
- High Fluence Seams W8 Internals Hold Down NIA to VEGP-2, VEGP-2 does not have a 304 stainless steel hold down spring Spring W9 Thermal Shield Flexures NIA to VEGP-2, VEGP-2 utilizes a neutron panel design; therefore, does not have thermal shield flexures Lower Radial Support Clevis Insert X-750 UT UT Bolts Core Barrel Assembly -
Middle and Lower Axial EVT-1 EVT-1 Welds Begmnmg of License Renewal Pen od, 2129 E-2