ML19179A251

Acceptance of Requested Licensing Action Increase Allowable Main Steam Isolation Valve Leakage Rates

ML19179A251
Person / Time
Site:	Nine Mile Point
Issue date:	06/27/2019
From:	Marshall M Plant Licensing Branch 1
To:	Reynolds R Exelon Generation Co
Marshall M
References
EPID L-2018-LLA-0115
Download: ML19179A251 (2)

Text

From: Marshall, Michael To: [Licensee] Ron Reynolds (Exelon)

Cc: Loomis, Thomas R:(GenCo-Nuc); Kristensen, Kenneth J:(Exelon Nuclear); Demko, Rose M:(GenCo-Nuc)

(Rose.Demko@exeloncorp.com); James Danna (James.Danna@nrc.gov)

Subject:

NINE MILE POINT NUCLEAR STATION, UNIT NO. 2 - ACCEPTANCE OF REQUESTED LICENSING ACTION RE:

INCREASE ALLOWABLE MAIN STEAM ISOLATION VALVE LEAKAGE RATES (EPID: L-2018-LLA-0115)

Date: Thursday, June 27, 2019 11:27:00 AM Hello Ron, By letter dated May 31, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML19151A537), Exelon Generation Company, LLC (Exelon) submitted a license amendment request for the Nine Mile Point Nuclear Station, Unit 2.

The proposed amendment would revise the surveillance requirements for containment leakage and main steam isolation valve leakage rate.

The purpose of this email is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this amendment 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.

Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.

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 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.

The NRC staff will review the amendment request to ensure that it meets the NRC regulations specified in 10 CFR 50.67, Accident source term. The staff will conduct the review using the guidance contained in NUREG-0800, Chapter 15, Section 15.0.1, Revision. 0, "Radiological Consequence Analysis Using Alternate Source Terms," dated July 2000 (ADAMS Accession No. ML003734190), which identifies Regulatory Guide 1.183, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors," dated July 2000 (ADAMS Accession No. ML003716792). In its review, the staff will also consider Regulatory Issue Summary 2006-04, "Experience with Implementation of Alternative Source Terms," dated March 7, 2006 (ADAMS Accession No. ML053460347), and the main steam isolation valve leakage pathway evaluation included in

the previously issued safety evaluation on implementation of alternative radiological source term (ADAMS Accession No. ML081230439).

Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 1600 hours66.667 days <br />9.524 weeks <br />2.192 months <br /> to complete. The NRC staff expects to complete this review by the end of June 2020. 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 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 (RAls),

timely responses to RAls (i.e., within 30 days), ability of Exelon to support any audit requests, unanticipated addition of scope to the review, and review by NRC advisory committees or hearing-related activities. Delays by Exelon in responding to RAls or inability to support audits will likely impact the NRC staff's ability to adhere to the review schedule. 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 at (301) 4152871 or Michael.Marshall@nrc.gov.

Sincerely, Michael L. Marshall, Jr., Senior Project Manager Plant Licensing Branch I Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-410