ML16183A130

E-mail from R. Guzman to W. Craft Acceptance Review Determination, Realistic Large Break LOCA Analysis License Amendment Request (MF7761)

ML16183A130
Person / Time
Site:	Millstone
Issue date:	07/01/2016
From:	Richard Guzman Plant Licensing Branch 1
To:	Craft W Dominion Nuclear Connecticut
Guzman R
References
CAC MF7761
Download: ML16183A130 (1)

Text

From: Guzman, Richard To: "wanda.d.craft@dom.com" Cc: RidsNRRLIC109 Resource

Subject:

Acceptance Review Determination - Millstone Power Station Unit 2 - Realistic Large Break LOCA Analysis License Amendment Request (MF7761)

Date: Friday, July 01, 2016 10:29:35 AM

Wanda, The purpose of this e-mail is to provide the results of the NRC staffs acceptance review of the subject license amendment request (LAR).

By letter dated May 25, 2016 (ADAMS Accession No. ML16153A026), Dominion Nuclear Connecticut, Inc. (DNC) submitted an LAR proposing to add the AREVA Topical Report, EMF-2103(P)(A) Realistic Large Break Loss of Coolant Accident analysis methodology for pressurized water reactors to the Millstone Power Station, Unit 2 (MPS2) Technical Specifications, Section 6.9.1.8.b, Core Operating Limits Report, as an acceptable analytical method used to determine the MPS2 core operating limits.

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.

The NRC staff has reviewed DNCs application and concludes that it does provide technical information in sufficient detail to enable the NRC staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. Given the lesser scope and depth of the acceptance review as compared to the detailed technical review, there may be instances in which issues that impact the NRC staffs ability to complete the detailed technical review are identified despite completion of an adequate acceptance review. You will be advised of any further information needed to support the NRC staffs detailed technical review by separate correspondence.

Thanks,

~~~~~~~~~~~~~~~~~~~~~~~~~~~~~~

Rich Guzman Sr. PM, Division Operator Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Office: O8E-10 l Phone: (301) 415-1030 Richard.Guzman@nrc.gov