ML23053A218

Correction of Amendment Nos. 321 and 266 Regarding License Amendment Request to Revise the (National Fire Protection Association) NFPA-805 Fire Protection Program

ML23053A218
Person / Time
Site:	Hatch
Issue date:	03/03/2023
From:	Dawnmathews Kalathiveettil Plant Licensing Branch II
To:	Gayheart C Southern Nuclear Operating Co
Kalathiveettil, D
References
EPID L-2022-LLF-0000
Download: ML23053A218 (1)

Text

March 3, 2023 Mr. R. Keith Brown Regulatory Affairs Director Southern Nuclear Operating Co., Inc.

3535 Colonnade Parkway Birmingham, AL 35243

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2 - CORRECTION OF AMENDMENT NOS. 321 AND 266 REGARDING LICENSE AMENDMENT REQUEST TO REVISE THE [NATIONAL FIRE PROTECTION ASSOCIATION]

NFPA-805 FIRE PROTECTION PROGRAM (EPID L-2022-LLF-0000)

Dear Mr. Brown:

On February 15, 2023, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment Nos. 321 and 266 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML22363A393) to Renewed Facility Operating Licenses (RFOLs) DPR-57 and NPF-5 for the Edwin I. Hatch Nuclear Plant (Hatch), Units 1 and 2, respectively.

The amendments consist of changes to the Hatch approved fire protection program (FPP) in response to your application dated March 31, 2022 (ML22090A279 [publicly available], and ML22090A278 [non-publicly available], as supplemented by letters dated August 19, 2022 (ML22231B201) and November 18, 2022 (ML22325A228 [publicly available] and ML22325A229

[non-publicly available]).

The March 31, 2022, non-publicly available application was inadvertently listed in the amendment as ML22325A278. The non-publicly available application dated March 31, 2022, is ML22090A278, as noted above.

The proposed license amendment request (LAR) revises three modifications as described in LAR Attachment S, Table S-2, Plant Modifications Committed, and add one new modification to the table referenced in Hatch FPP Transition License Conditions 2.(C)(3)(c) for Unit 1 and 2.(C)(3)(a)(3) for Unit 2.

An administrative error on the part of the NRC staff was made on the attachments that show the changes being made to the license pages. This would also result in changes to the Remove and Insert attachment pages for Hatch, Unit 2.

Corrections made for Hatch, Unit 1, license pages

- For page 3, removed period at the end of the (5) paragraph

- For page 3, added Amendment 321 in bottom right corner of the page footer

- For page 4, removed the word for in the first line of (C) paragraph

R. K. Brown Correction made for Hatch, Unit 2, license pages

- Replaced Page 5 with earlier version of page 5 from Amendment No. 249. SNC had page 5 as one of the pages to be revised because of a page roll that resulted in the word would moving from page 4 to page 5. But NRC staff were able to accommodate this on page 4 itself.

Consistent with NRC staff guidance dated January 16, 1997 (ML103260096) and based on the NRCs policy established by SECY-96-238, these errors can be corrected by a letter to the licensee from the NRC staff. These changes do not affect the NRC decision approving amendment Nos. 321 and 266 and do not affect the No Significant Hazards Consideration as published in the Federal Register.

Enclosed please find (1) the corrected Hatch, Unit 2, attachment with the Remove and Insert license pages, (2) the corrected Hatch, Unit 1, license pages 3 and 4, and (3) the correct Hatch, Unit 2, license page 5.

If you have any questions, please contact me at 301-415-5905 or Dawnmathews.Kalathiveettil@nrc.gov .

Sincerely,

/RA/

Dawnmathews T. Kalathiveettil, Project Manager Plant Licensing Branch II-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos.: 50-321 and 50-366

Enclosure:

As stated cc: Listserv

ATTACHMENT EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS.1& 2 TO LICENSE AMENDMENT NO. 321 RENEWED FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 AND TO LICENSE AMENDMENT NO. 266 RENEWED FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the License and the Appendix A, Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.

Remove Pages Insert Pages License License License No. DPR-57, Page 3 License No. DPR-57, Page 3 License No. DPR-57, Page 4 License No. DPR-57, Page 4 License No. NPF-5, Page 5 License No. NPF-5, Page 5 TSs TSs n/a n/a

 

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(6) Southern Nuclear, pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

& This renewed license shall be deemed to contain, and is subject to, theconditions specified in the following Commission regulations in 10 CFR Chapter I:Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the

rules, regulations, and orders of the Commission now or hereafter in effect; and the

additional conditions specified or incorporated below:

 Maximum Power Level Southern Nuclear is authorized to operate the facility at steady-statereactor core power levels not in excess of 2,804 megawatts thermal.

 Technical Specifications The Technical Specifications (Appendix A) and the Environmental

Protection Plan (Appendix B), as revised through Amendment No. 321,are hereby incorporated in the renewed license. Southern Nuclear shalloperate the facility in accordance with the Technical Specifications and the

Environmental Protection Plan.

The Surveillance Requirement (SR) contained in the Technical

Specifications and listed below, is not required to be performedimmediately upon implementation of Amendment No. 195. The SR listedbelow shall be successfully demonstrated before the time and conditionspecified:

SR 3.8.1.18 shall be successfully demonstrated at its next regularly scheduled performance.

(3) Fire Protection Southern Nuclear Operating Company shall implement and maintain in effect all provisions of the approved fire protection program that comply with 10 CFR 50.48(a) and 10 CFR 50.48(c), as specified in the licensee amendment request dated April 4, 2018, supplemented by letters dated May 28, August 9, October 7, and December 13, 2019, and February 5, and March 13, 2020, and license amendment request dated March 31, 2022, supplemented by letter dated November 18, 2022, and as approved in the NRC safety evaluations (SE) dated June 11, 2020 and February 15, 2023. Except where NRC approval for changes or deviations is required by 10 CFR 50.48(c), and provided no other regulation, technical specification, license condition or requirement would require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.

Renewed License No. DPR-57 Amendment No. 321

require prior NRC approval, the licensee may make changes to the fire protection program without prior approval of the Commission if those changes satisfy the provisions set forth in 10 CFR 50.48(a) and 10 CFR 50.48(c), the change does not require a change to a technical specification or a license condition, and the criteria listed below are satisfied.

(1) Risk-Informed Changes that May Be Made Without Prior NRC Approval A risk assessment of the change must demonstrate that the acceptance criteria below are met. The risk assessment approach, methods, and data shall be acceptable to the NRC and shall be appropriate for the nature and scope of the change being evaluated; be based on the as-built, as-operated, and maintained plant; and reflect the operating experience at the plant. Acceptable methods to assess the risk of the change may include methods that have been used in the peer-reviewed fire PRA model, methods that have been approved by NRC through a plant-specific license amendment or NRC approval of generic methods specifically for use in NFPA 805 risk assessments, or methods that have been demonstrated to bound the risk impact.

a) Prior NRC review and approval is not required for changes that clearly result in a decrease in risk. The proposed change must also be consistent with the defense in-depth philosophy and must maintain sufficient safety margins. The change may be implemented following completion of the plant change evaluation.

b) Prior NRC review and approval is not required for individual changes that result in a risk increase less than 1x10-7/year (yr) for CDF and less than 1x10-8/yr for LERF. The proposed change must also be consistent with the defense-in-depth philosophy and must maintain sufficient safety margins. The change may be implemented following completion of the plant change evaluation.

(2) Other Changes that May Be Made Without Prior NRC Approval a) Changes to NFPA 805, Chapter 3, Fundamental Fire Protection Program Prior NRC review and approval are not required for changes to the NFPA 805, Chapter 3, fundamental fire protection program elements and design requirements for which an engineering evaluation demonstrates that the alternative to the Chapter 3 element is functionally equivalent or adequate for the hazard. The licensee may use an engineering evaluation to demonstrate that a change to an NFPA 805, Renewed License No. NPF-5 Amendment No. 249

ML23053A218 OFFICE NRR/DORL/LPL2-1/PM NRR/DORL/LPL2-1/LA NRR/DORL/LPL2-1/BC NRR/DORL/LPL2-1/PM NAME DKalathiveettil KGoldstein MMarkley DKalathiveettil DATE 02/21/2023 03/03/2023 03/03/2023 03/03/2023