ML25176A144

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June 17, 2025, Summary of Public Pre-Submittal Meeting with Entergy Operations, Inc., to Discuss a Proposed License Amendment Request Regarding Pressurizer Heater Capacity for Arkansas Nuclear One, Unit 1
ML25176A144
Person / Time
Site: Arkansas Nuclear  Entergy icon.png
Issue date: 06/27/2025
From: Dennis Galvin
Plant Licensing Branch IV
To:
Galvin, Dennis
Shared Package
ML25176A148 List:
References
EPID L-2025-LRM-0028
Download: ML25176A144 (4)


Text

June 27, 2025 LICENSEE:

ENTERGY OPERATIONS, INC.

FACILITY:

ARKANSAS NUCLEAR ONE, UNIT 1

SUBJECT:

SUMMARY

OF JUNE 17, 2025, PUBLIC PRESUBMITTAL MEETING WITH ENTERGY OPERATIONS, INC. TO DISCUSS A PROPOSED LICENSE AMENDMENT REQUEST REGARDING PRESSURIZER HEATER CAPACITY FOR ARKANSAS NUCLEAR ONE, UNIT 1 (EPID L-2025-LRM-0028)

On June 17, 2025, an Observation public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) staff and representatives of Entergy Operations, Inc. (Entergy, the licensee) regarding Arkansas Nuclear One, Unit 1 (ANO-1). ANO-1 has insufficient pressurizer heater capacity with redundant emergency power to maintain natural circulation conditions in the event of loss of offsite power (LOOP) indefinitely. The insufficient pressurizer heater capacity is contrary to NUREG-0578, TMI-2 [Three Mile Island, Unit 2] Lessons Learned Task Force Status Report and Short-term Recommendations, dated July 1979 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML090060030),

Recommendation 2.2.1, which was imposed on ANO-1 by a Confirmatory Order dated January 2, 1980 (ML021220215). The purpose of the meeting was to discuss a proposed license amendment request (LAR) to modify the Confirmatory Order, by modifying NUREG-0578, Recommendation 2.1.1 for ANO-1, including (1) specifying a duration the pressurizer heaters would maintain natural circulation, (2) the assumed pressurizer code safety valve leakage, and (3) allowing high pressure injection as an alternate method of maintaining subcooling. The proposed LAR would also add the assumed pressurizer code safety valve leakage to Technical Specification (TS) 3.4.13, RCS [Reactor Coolant System] Operational LEAKAGE. The meeting notice and agenda were published on June 5, 2025 (ML25167A315)1 The licensees presentation for the meeting (ML25163A226) was made available prior to the meeting. Enclosed is a list of attendees at the meeting.

A previous meeting on this topic was held on August 15, 2023. The meeting summary and the licensee's presentation for the prior meeting can be found at ML23257A241 and ML23223A203, respectively.

During the meeting, the licensee presented on the background for the proposed LAR, the proposed changes to the ANO-1 TSs and compliance with NUREG-0578, and the technical justification for each of the changes. NRC staff and the licensee discussed each of the topics in the presentation and the information that the licensee should consider to include in the LAR beyond that identified in the presentation, as summarized below.

1 The meeting notice was updated in the NRC public meeting notification system to add the presentation to the meeting notice. This changed the meeting notice date to June 16, 2025, in ADAMS.

The revised TS BASES, provided in the LAR for information purposes, should reflect the revised TS, (e.g. reflect the proposed addition of the assumed pressurizer code safety valve leakage to TS 3.4.13).

The LAR should justify the sufficiency of the duration the pressurizer heaters would maintain natural circulation. The justification for the duration should consider the intent of Recommendation 2.1.1 of NUREG-0578 and the frequency and duration of LOOP events the pressurizer heaters in part mitigate.

The LAR should justify the use of the high pressure injection consistent with the NUREG-0578 language change proposed.

The LAR should discuss the basis for the assumed pressurizer code safety valve leakage.

The LAR should discuss if the pressurizer code safety valves open during a LOOP event, and if so, if they reseat or leak after they close, and the basis for those assumptions.

The code/method used for the analysis to determine the time to maintain adequate subcooling margin with only emergency powered pressurizer heaters and its approval status should be discussed in the LAR.

The analysis to determine the time to maintain adequate subcooling margin with only emergency powered pressurizer heaters should be submitted with the LAR, which would facilitate NRC staff review, or made available for audit.

No regulatory decisions were made as a result of this meeting. No members of the public identified themselves on the teleconference. No Public Meeting Feedback forms were received.

Please direct any inquiries to me at 301-415-6256, or by email at Dennis.Galvin@nrc.gov.

/RA/

Dennis Galvin, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-313

Enclosure:

List of Attendees cc: Listserv

Enclosure LIST OF ATTENDEES JUNE 17, 2025, PUBLIC PRESUBMITTAL MEETING WITH ENTERGY OPERATIONS, INC.

TO DISCUSS A PROPOSED LICENSE AMENDMENT REQUEST REGARD PRESSURIZER HEATER CAPACITY FOR ARKANSAS NUCLEAR ONE, UNIT 1 U.S. Nuclear Regulatory Commission Robert Beaton Adakou Foli Dennis Galvin Logan Gaul Hannah McLatchie Steve Smith Brian Tindell Entergy Operations, Inc.

Bob Clark Philip Couture Riley Keele David Williams

Meeting Package: ML25176A148 Meeting Notice: ML25167A315 Meeting Presentation: ML25163A226 Meeting Summary: ML25176A144

  • by eConcurrence NRC-001 OFFICE NRR/DORL/LPL4/PM*

NRR/DORL/LPL4/LA*

NRR/DEX/EEEB/BC*

NAME DGalvin PBlechman WMorton DATE 6/26/2025 6/26/2025 6/26/2025 OFFICE NRR/DSS/SNSB/BC*

NRR/DSS/STSB/BC*

NRR/DORL/LPL4/BC*

NAME DiFrancesco SMehta TNakanishi DATE 6/23/2025 6/26/2025 6/27/2025 OFFICE NRR/DORL/LPL4/PM*

NAME DGalvin DATE 6/27/2025