ML23079A210

Correction of Amendment Nos. 216 & 199 Issuance of Amendments Regarding Revision to Technical Specifications to Relocate Augmented Piping Inspection Program Details to a Licensee-Controlled Document

ML23079A210
Person / Time
Site:	Vogtle
Issue date:	03/22/2023
From:	John Lamb NRC/NRR/DORL/LPL2-1
To:	Brown R Southern Nuclear Operating Co
References
EPID L-2021-LLA-0235
Download: ML23079A210 (1)

Text

March 22, 2023

Mr. R. Keith Brown Regulatory Affairs Director Southern Nuclear Operating Co., Inc.

3535 Colonnade Parkway Birmingham, AL 35243

SUBJECT:

VOGTLE ELECTRIC GENERATING PLANT, UNITS 1 AND 2 - CORRECTION OF AMENDMENT NOS. 216 AND 199 RE: ISSUANCE OF AMENDMENTS REGARDING REVISION TO TECHNICAL SPECIFICATIONS TO RELOCATE AUGMENTED PIPING INSPECTION PROGRAM DETAILS TO A LICENSEE-CONTROLLED DOCUMENT (EPID L-2021-LLA-0235)

Dear Mr. Brown:

On November 8, 2022, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 216 and 199 (Agencywide Documents A ccess and Management System (ADAMS)

Accession No. ML22286A074) to Facility Operating Licenses NPF-68 and NPF-81 for the Vogtle Electric Generating Plant (Vogtle), Units 1 and 2, respectively. This amendment was based on the license amendment request dated Dece mber 22, 2021 (ML21356B484), as supplemented by letter dated May 10, 2022 (ML22131A331).

The amendments revised the Vogtle, Units 1 and 2, Technical Specification (TS) by relocating augmented piping inspection detailed information from TS 5.5.16, MS [Main Steam] and FW

[Feedwater] Piping Inspection Program, to the Vogtle, Units 1 and 2, Updated Final Safety Analysis Report (UFSAR). A program description will remain in TS 5.5.16.

The amendments contained an omission and spelling mistake on TS page 5.5-16. The Amendments were issued with TS page 5.5-16 reflecting the letter dated December 22, 2021.

However, this is incorrect. The letter dated May 10, 2022, superseded the TS page 5.5-16, and added a sentence to TS 5.5.16.

TS 5.5.16 reads:

In accordance with the augmented inservice inspection program for high energy lines outside of containment, examinations of welds in the main steam and main feedwater lines of each unit shall be performed to provide assurance of the continued integrity of the piping systems over their service lifetime. These requirements apply to welds in piping syst ems or portions of systems located outside of containment where protection from the consequences of postulated ruptures is not provided by a system of pipe whip restraints, jet impingement barriers, protective enclosures and/or other measures sesigned specifically to cope with such ruptures.

R. Brown

The corrected TS 5.5.16 reads:

In accordance with the augmented inservice inspection program for high energy lines outside of containment, examinations of welds in the main steam and main feedwater lines of each unit shall be performed to provide assurance of the continued integrity of the piping systems over their service lifetime. These requirements apply to welds in piping systems or portions of systems located outside of containment where protection from the consequences of postulated ruptures is not provided by a system of pipe whip restraints, jet impingement barriers, protective enclosures and/or other measures designed specifically to cope with such ruptures. This augmented inservice inspection is consistent with Section 6.6 of the FSAR.

The NRC staff confirmed that the letter dated May 10, 2022, contained the correct TS 5.5.16.

Therefore, consistent with NRC staff guidance dated January 16, 1997 (ML103260096), based on the NRCs policy established by SECY-96-238, this error can be corrected by a letter to the licensee from the NRC staff.

Enclosed please find the corrected Vogtle, Units 1 and 2, TS page 5.5.16. This correction does not change any of the conclusions in the safety evaluation associated with Amendment Nos. 216 and 199.

If you have any questions, please contact me at 301-415-3100 or John.Lamb@nrc.gov.

Sincerely,

/RA/

John G. Lamb, Senior Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Docket Nos.: 50-424 and 50-425

Enclosure:

As stated

cc: Listserv

Programs and Manuals 5.5

5.5 Programs and Manuals (continued)

5.5.16 MS and FW Piping Inspection Program

In accordance with the augmented inservice inspection program of the high energy lines outside of containment, examinations of welds in the main steam and main feedwater lines of each unit shall be performed to provide assurance of the continued integrity of the piping system over their service lifetime. These requirements apply to welds in piping systems or portions of systems located outside of containment where protection from the consequences of postulated ruptures is not provided by a system of pipe whip restraints, jet impingement barriers, protective enclosures and/or other measures designed to specifically to cope with such ruptures. This augmented inservice inspection is consistent with Section 6.6 of the UFSAR.

5.5.17 Containment Leakage Rate Testing Program

A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Nuclear Energy Institute (NEI)

Topical Report (TR) NEI 94-01, Industry Guideline for Implementing Performance-Based Option of 10 CFR 50, Appendix J, Revision 3-A, dated July 2012, and the conditions and limitations specified in NEI 94-01, Revision 2-A, dated October 2008, as modified by the following exceptions:

1. Leakage rate testing for containment purge valves with resilient seals is performed once per 18 months in accordance with LCO 3.6.3, SR 3.6.3.6 and SR 3.0.2.

2. Containment personnel air lock door seals will be tested prior to reestablishing containment integrity when the air lock has be en used for containment entry. When containment integrity is required and the air lo ck has been used for containment entry, door seals will be tested at least once per 30 days during the period that containment entry(ies) is (are) being made.

3. The visual examination of containment concrete surfaces intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified by ASME Section XI Code, Subsection IWL, except where relief or alternative has been authorized by the NRC. At the discretion of the licensee, the containment concrete visual ex aminations may be performed during either power operation, e.g., performed concurrently wi th other containment inspection-related activit ies such as tendon testing, or during a maintenance/refueling outage.

(continued)

Vogtle Units 1 and 2 5.5-16 Amendment No. 216 (Unit 1)

Amendment No. 199 (Unit 2)

ML23079A210 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME JLamb KGoldstein MMarkley (SWilliams for) JLamb DATE 03/16/2023 03/20/2023 03/22/2023 03/22/2023