ML18304A139

Acceptance of Requested Licensing Action Risk-Informed Approach to Closure for Generic Safety Issue-191 (EPID L-2018-LLA-0222 and EPID L-2018-LLE-0013)

ML18304A139
Person / Time
Site:	Calvert Cliffs
Issue date:	10/30/2018
From:	Marshall M Plant Licensing Branch 1
To:	Enrique Villar Exelon Generation Co
Marshall M, NRR/DORL/LPLI, 415-2871
References
EPID L-2018-LLA-0222, EPID L-2018-LLE-0013, GSI-191
Download: ML18304A139 (2)

Text

From: Marshall, Michael To: Villar, Enrique:(GenCo-Nuc)

Cc: James Danna (James.Danna@nrc.gov)

Subject:

Calvert Cliffs Nuclear Power Plant, Units 1 And 2 - Acceptance of Requested Licensing Action Re: Risk-Informed Approach To Closure For Generic Safety Issue-191 (EPID L-2018-LLA-0222 AND EPID L-2018-LLE-0013)

Date: Tuesday, October 30, 2018 1:38:00 PM Hello Rick, By letter dated August 13, 2018 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML18226A189) as supplemented by letter dated October 10, 2018 (ADAMS Accession No. ML18283A034), Exelon Generation Company, LLC (Exelon) submitted a license amendment and exemption request for Calvert Cliffs Nuclear Power Plant, Units 1 and 2 (Calvert Cliffs). The proposed amendments would change the Calvert Cliffs licensing bases, including the affected portions of the Technical Specifications and Updated Final Safety Analysis Report. Additionally, Exelon requested exemptions from certain requirements in Section 50.46(a)(1) of Title 10 of the Code of Federal Regulations (10 CFR). Specifically, the proposed amendments and exemptions would allow the use of a risk-informed approach to address safety issues discussed in Generic Safety Issue -191, Assessment of Debris Accumulation on Pressurized-Water Reactor Sump Performance and close out generic letter (GL) 200402, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors (ADAMS Accession No. ML042360586).

The NRC staff has reviewed your application and concluded 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 and exemption 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. If additional information is needed, you will be advised by separate correspondence.

Based on the information provided in your submittal, the NRC staff has estimated that this license amendment request will take approximately 2160 hours90 days <br />12.857 weeks <br />2.959 months <br /> to complete and the exemption request will take approximately 320 hours13.333 days <br />1.905 weeks <br />0.438 months <br /> to complete. The NRC staff expects to complete both reviews by the end of October 2019. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant changes in the forecasted hours, the reasons for the changes, along with the new estimates, will be communicated to Exelon during the routine interactions with the assigned project manager.

These estimates are based on the NRC staffs initial review of the application and they could change, due to several factors including requests for additional information, unanticipated addition of scope to the review, and review by NRC advisory committees or hearing-related activities. Additional delay may occur if the submittal is provided to the NRC in advance or in parallel with industry program initiatives or pilot applications.

If you have any questions, please contact me.

Michael L. Marshall, Jr.

Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301-415-2871 Docket No. 50-317 and 50-318