NL-22-0340, Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical

Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical

ML22131A331
Person / Time
Site:	Vogtle, Farley
Issue date:	05/10/2022
From:	Gayheart C Southern Nuclear Operating Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-22-0340
Download: ML22131A331 (14)

Text

Cheryl A. Gayheart 3535 Colonnade Parkway Regulatory Affairs Director Birmingham, AL 35243 205 992 5316

cagayhea@southernco.com

May 10, 2022

Docket Nos.: 50-348 50-424 NL-22-0340 50-364 50-425

U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001

Joseph M. Farley Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2 Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical Specifications to a Licensee Controlled Document

Ladies and Gentlemen:

By letter dated December 22, 2021 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML21356B484), Southern Nuclear Operating Company (SNC) submitted a license amendment requests (LARs) for the Joseph M. Farley Nuclear Plant (FNP)

Units 1 and 2, and Vogtle Electric Generating Plant (VEGP), Units 1 and 2. SNC proposed to revise the FNP Technical Specifications (TS) by relocating some detailed information from TS 5.5.16, Main Steamline Inspection Program, to the FNP Updated Final Safety Analysis Report (UFSAR). SNC also proposed a similar change to revise the VEGP TS by relocating some detailed information from TS 5.5.16, MS and FW Piping Inspection Program, to the VEGP UFSAR.

By email dated April 14, 2022, the US NRC notified SNC that additional information is needed for the staff to perform their review.

The Enclosure to this letter provides the SNC response to the NRC request for additional information (RAI). Attachments 1 and 2 provide Marked-Up UFSAR pages for FNP and VEGP for information only, in response to RAI 1. Attachments 3 and 4 provide Updated Proposed Technical Specification Changes, in response to RAI 2.

The conclusions of the No Significant Hazards Consideration and Environmental Consideration contained in the original application have been reviewed and are unaffected by this response.

If you have any questions, please contact Ryan Joyce at 205.992.6468.

U. S. Nuclear Regulatory Commission NL-22-0340 Page 2

I declare under penalty of perjury that the foregoing is true and correct. Executed on the

__th day of May 2022.

Respectfully submitted,

Cheryl A. Gayheart Regulatory Affairs Director

CAG/dsp/cbg

Enclosure:

SNC Response to Request for Additional Information (RAI)

FNP UFSAR Section 3K Marked-up Pages (For Information Only) : VEGP UFSAR Section 6.6 Marked-up Pages (For Information Only) : Updated FNP Proposed Technical Specification Changes (Marked-up Pages) : Updated VEGP Proposed Technical Specification Changes (Marked-up Pages)

cc: Regional Administrator, Region ll NRR Project Manager - Farley NRR Project Manager - Vogtle 1 & 2 Senior Resident Inspector - Farley Senior Resident Inspector - Vogtle 1 & 2 RType: CGA02.001

Joseph M. Farley Nuclear Plant - Units 1 and 2 Vogtle Electric Generating Plant - Units 1 and 2 Response to Request for Additional Information Related to Request for License Amendment to Relocate Augmented Piping Inspection Program Details from Technical Specifications to a Licensee Controlled Document

Enclosure

SNC Response to Request for Additional Information (RAI)

Enclosure to NL-22-0340 SNC Response to Request for Additional Information (RAI)

RAI-1

In Section 2.4, Description of the Proposed Change, of the subject LAR, the licensee states that the current detailed augmented inservice inspection program description contained in TS 5.5.16 will be relocated to the UFSARs for Farley and Vogtle. Specifically, the entirety of the verbiage in Farley TS 5.5.16 will be relocated to the Farley UFSAR, Section 3K, Part II, Item D.

Likewise, the entirety of the verbiage in Vogtle TS 5.5.16 will be relocated to the Vogtle UFSAR, Section 6.6.8. The licensee also states that UFSAR information that duplicates the relocated TS information may be edited for clarity. The UFSARs for each plant will be updated in accordance with 10 CFR 50.71.

To support the NRC staffs review of the subject LAR, the licensee is requested to provide its proposed UFSAR update with the inclusion of the relocated TS information.

SNC Response:

contains the proposed UFSAR updates for FNP Units 1 and 2, and Attachment 2 contains the proposed UFSAR updates for VEGP Units 1 and 2. These Attachments are provided for information only.

Note that for the FNP UFSAR update provided in Attachment 1, in addition to relocating information from the TS to the UFSAR, reference to the Code addenda through summer 1975 are removed and reference to Category C-F is removed. The change to remove reference to the Code addenda through summer 1975 is justified. Specifically, there were no changes to Category C-G in Code addenda through summer 1975 which have any impact on the augmented examinations performed, therefore, the Code year is made consistent with the relocated information from the TS. Additionally, removal of Category C-F is appropriate because in the ASME Code,Section XI, Category C-F relates to systems that circulate reactor coolant which is not applicable to the main steam piping, therefore, Category C-F is removed to be consistent with relocated information from the TS.

RAI-2

In Section 2.4 under subsection, Proposed TS Change, the licensee describes its proposed changes for the Farley, Units 1 and 2, TS 5.5.16, Main Steamline Inspection Program, and the Vogtle, Units 1 and 2, TS 5.5.16 MS and FW Piping Inspection Program, respectively. The licensee states that the program description will remain in TS 5.5.16 for each plant while the details of the respective augmented inspection program will be relocated to the UFSARs for Farley and Vogtle.

However, the licensees proposed TS 5.5.16 changes do not refer to those relevant UFSAR sections that will be updated to contain the details of the augmented inservice inspection program. The licensee is requested to include a pointer to the relevant UFSAR sections in its proposed TS changes.

E-1 Enclosure to NL-22-0340 SNC Response to Request for Additional Information (RAI)

SNC Response:

SNC provides the proposed updates associated with the above-mentioned LAR to FNP Unit 1 and 2 TS in Attachment 3, and to the VEGP Units 1 and 2 TS in Attachment 4. Attachment 3 reflects changes in the proposed TS to point to Section 3K of the UFSAR for the FNP Augmented Inservice Inspection program. Attachment 4 reflects changes in the proposed TS to point to Section 6.6 of the UFSAR for the VEGP Augmented Inservice Inspection program.

E-2 Attachment 1

FNP UFSAR Section 3K Marked-up Pages (For Information Only)

FNP-FSAR-3K

In summary the ANSI portion of the main steam piping is equivalent to the ASME Section III portion. However, the "N" stamp cannot be applied to ANSI piping because of items i and ii above. This difference does not affect the quality of material or workmanship.

D. Augmented Inservice Inspection

Inservice examination and related design provisions in the containment penetration area and throughout the no break region should be in accordance with the following:

1. The protective measures, structures, and guard pipes should not prevent the access required to conduct the inservice examinations specified in the This program ASME Boiler and Pressure Vessel Code,Section XI, Division 1, "Rules Delete ",".

applies to those for Inspection and Testing of Components in Light-Water Cooled Plants." Add "."

2. For those portions of fluid system piping identified in B.2.c of APCSB 3-1, the extent of inservice examinations completed during each inspection interval (IWA-2400, ASME Code, 1974 Edition with Addenda through Summer 1975,Section XI) should provide 100-percent volumetric examination of circumferential and longitudinal pipe welds within the boundary of these portions of piping to the extent practical.

3. The areas subject to examination should be defined in accordance with Examination Categories C-F and C-G for Class 2 piping welds in Table IWC-2520.

The three main steamlines from the rigid anchor points of the containment penetrations downstream to and including the main steam header, shall be inspected. The extent of the inservice examinations completed during each inspection interval (IWA 2400, ASME Code, 1974 Edition,Section XI) shall provide 100 percent volumetric examination of circumferential and longitudinal pipe welds to the extent practical. The areas subject to examination are those defined in accordance with examination category C-G for Class 2 piping welds in Table IWC-2520.

3K.A-12 REV 21 5/08 Attachment 2

VEGP UFSAR Section 6.6 Marked-up Pages (For Information Only)

Attachment 3

Updated FNP Proposed Technical Specification Changes (Marked-up Pages) 3URJUDPVDQG0DQXDOV





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