ML26048A070
| ML26048A070 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 02/12/2026 |
| From: | Ed Miller NRC/NRR/DORL/LPL2-1 |
| To: | Sparkman W Southern Nuclear Operating Co |
| Miller E, NRR/DORL/LPL2-1 | |
| References | |
| EPID L-2025-LLA-0145 | |
| Download: ML26048A070 (0) | |
Text
From:
Ed Miller To:
Sparkman, Wesley A.
Subject:
Draft RAI for Farley Allowable Value LAR (L-2025-LLA-0145)
Date:
Thursday, February 12, 2026 8:57:00 AM Attachments:
Draft RAI L-2025-LLA-0145.docx Mr. Sparkman,
By letter dated September 4, 2025 (Agencywide Documents Access and Management System Accession No. ML25254A180), Southern Nuclear Operating Company submitted an amendment request for the Farley Nuclear Plant Units 1 and 2. The amendment would revise selected Allowable Values for Technical Specification (TS) 3.3.1, Reactor Trop System (RTS) Instrumentation and 3.3.2 Engineered Safety Feature Actuation System (ESFAS) Instrumentation.
Attached is the NRC staffs draft RAI for the subject request. The question is being transmitted to you to determine 1) If the question clearly conveys the NRC information needs, 2) Whether the regulatory basis for the question is clear, and 3) If the information has already been provided in existing docketed correspondence. Additionally, review of the draft question will allow you to determine what response time you can support. After youve had a chance to review, please let me know if you would like to have a clarification call to discuss. Thank you.
Ed Miller (301) 415-2481
1 DRAFT REQUEST FOR ADDITIONAL INFORMATION FARLEY - UNITS 1 AND 2 - LAR - REVISE TS 3.3.1 AND 3.3.2 ALLOWABLE VALUES SOUTHERN NUCLEAR OPERATING COMPANY FARLEY NUCLEAR PLANT, UNITS 1 & 2 DOCKET NOS.05-348 & 05-364
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Background===
By application dated September 4, 2025 (ML23318A074), Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) pertaining to the Joseph M.
Farley Nuclear Plant (FNP) Units 1 and 2 Technical Specifications (TS). The proposed changes would revise TS 3.3.1, "Reactor Trip System (RTS) Instrumentation" Table 3.3.1-1 and TS 3.3.2, "Engineered Safety Feature Actuation System (ESFAS) Instrumentation" Table 3.3.2.-1 Allowable Values (AV) for specified functions.
Regulatory Basis 10 Code of Federal Regulations (CFR) Section 50.36(c)(1)(ii)(A) requires:
Where a limiting safety system setting is specified for a variable on which a safety limit has been placed, the setting must be so chosen that automatic protective action will correct the abnormal situation before a safety limit is exceeded. If, during operation, it is determined that the automatic safety system does not function as required, the licensee shall take appropriate action, which may include shutting down the reactor.
Draft RAI 1 Table 4-1 of WCAP-13751-P gives a visual representation of the Allowable Value (AV) relationship to the terms provided in Table 3-32A of WCAP-13751-P. Per the RTS and ESFAS functions listed in Table 2.4-1 and 2.4-2 in the enclosure, their Allowable Values are updated using Equation 2.1 of WCAP-13751-P and the terms associated with the functions listed in Table 3-32A of WCAP-13751-P. However, the STEAMFLOW IN 2 STEAMLINES - HIGH, SLI (AT 20% TURBINE POWER) in Table 3-32A (ESFAS function 4.e of Table 2.4-2) does not have the typical supporting terms (i.e. span, margin, SAL.) that demonstrate how the AV was calculated.
Please provide clarification or additional details, as applicable, that demonstrates how the Allowable Value of 40.7% for STEAMFLOW IN 2 STEAMLINES - HIGH, SLI (AT 20%
TURBINE POWER) in Table 3-32A was obtained.