ML26034A400

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Supplemental Information Needed for Acceptance of Alternate Request Containment Isolation Valves
ML26034A400
Person / Time
Site: Hope Creek 
Issue date: 02/09/2026
From: Marshall M
Plant Licensing Branch 1
To: Mcfeaters C
Public Service Enterprise Group
References
EPID L-2026-LLR-0006
Download: ML26034A400 (0)


Text

February 9, 2026 Mr. Charles V. McFeaters President and Chief Nuclear Officer PSEG Nuclear LLC - N09 Hope Creek Generating Station P.O. Box 236 Hancocks Bridge, NJ 08038

SUBJECT:

HOPE CREEK GENERATING STATION - SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF ALTERNATE REQUEST RE:

CONTAINMENT ISOLATION VALVES (EPID L-2026-LLR-0006)

Dear Mr. McFeaters:

By letter dated January 6, 2026 (Agencywide Documents Access and Management System Accession No. ML26006A183), PSEG Nuclear, LLC (PSEG) submitted an alternative request for Hope Creek Generating Station. The proposed Alternative Request VR-04 concern containment isolation valves and the proposed use of Code Case OMN-30, Alternative Valve Position Verification Approach to Satisfy ISTC-3700. The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this alternative request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Pursuant to Sections 50.55a(z)(1) and 50.55a(z)(2) of Title 10 of the Code of Federal Regulations (10 CFR), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.

The NRC staff has reviewed your application and concluded that the information delineated in this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed alternative request in terms of regulatory requirements for the protection of public health and safety and the environment. Alterative Request VR-04 does not include a list of the specific American Society of Mechanical Engineers Operation and Maintenance Code components affected. PSEG needs to:

Supplement its application with a list of affected components.

In order to make the application complete, the NRC staff requests that PSEG supplement the application to address the information requested in this letter within 13 working days of the date of this letter. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staffs request is not received by the above date, the

application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staffs detailed technical review by separate correspondence.

If you have any questions, please contact me at (301) 415-2871 or michael.marshall@nrc.gov.

Sincerely,

/RA/

Michael L. Marshall, Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-354 cc: Listserv

ML26034A400

  • via eConcurrence NRR-004 OFFICE NRR/DORL/LPL1/PM*

NRR/DORL/LPL3/LA*

NRR/DEX/EMIB/BC*

NAME MMarshall SLent SBailey DATE 2/3/2026 2/3/2026 2/5/2026 OFFICE NRR/DORL/LPL1/BC*

NRR/DORL/LPL1/PM*

NAME UShoop MMarshall DATE 2/5/2026 2/9/2026