ML23013A208

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Request for Additional Information
ML23013A208
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 01/13/2023
From: Audrey Klett
Plant Licensing Branch 1
To: Brown K
Susquehanna
Klett A
References
EPID L-2023-LLA-0003
Download: ML23013A208 (1)


Text

From:

Audrey Klett To:

Brown, Katie-Elizabeth Rosser Cc:

Smith, Derek

Subject:

NRC Request for Additional Information - Susquehanna License Amendment Request (EPID L-2023-LLA-0003)

Date:

Friday, January 13, 2023 7:34:00 PM Hi Katie, Please see NRCs RAI below:

REQUEST FOR ADDITIONAL INFORMATION (RAI)

SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 DOCKET NO. 05000388 EPID NO. L-2021-LLA-0184 ADAMS Accession No. ML23013A208

By letter dated January 10, 2023 (Agencywide Documents Access and Management System Accession No.ML23010A265), Susquehanna Nuclear, LLC (the licensee) submitted a license amendment request (LAR) for Susquehanna Steam Electric Station, Unit 2. The licensee requested to revise certain technical specifications for the control rods.

In response to the U.S. Nuclear Regulatory Commissions (NRCs) audit plan dated January 11,2023 (ML23010A087), the licensee provided responses to NRCs audit questions in its Web-based audit portal. The NRC staff has reviewed the information provided by the licensee on its audit portal and has determined that the NRC needs the following additional information to complete its review of the LAR.

As discussed with you via email on January 13, 2023, NRC is requesting the licensee to respond to the RAI as soon as practicable.

Regulatory Basis for RAIs Section 50.36(c)(2)(i) of Title 10 of the Code of Federal Regulations (10 CFR) states that technical specifications will contain limiting conditions for operation which are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by the technical specifications until the condition can be met. Section 50.36(c)(3) of 10 CFR states that surveillance requirements are requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met. To determine whether the proposed changes meet the regulations, the NRC staff needs the following information.

RAI-1

The NRC staff requests the licensee to supplement its application with the response it posted in its audit portal to NRC Audit Request No. 5 (Discussion of whether the inoperable rods along the periphery be withdrawn from the core).

RAI-2

The NRC staff requests the licensee to supplement its application with the information in the Response section (following the [Update 1/13/23] text) in its audit portal in response

to NRC Audit Request No. 11 (Provide core map layout of pull sequence similar to NEDO-21231 Figures 3-1 and 3-2 and discuss efforts to manage radial symmetry.). The staff is not requesting the documents that are attached to the audit response.

Audrey Klett, Senior Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Division of Operating Reactor Licensing Plant Licensing Branch 1 301-415-0489