ML19227A041
| ML19227A041 | |
| Person / Time | |
|---|---|
| Site: | Ginna  (DPR-018) |
| Issue date: | 08/14/2019 |
| From: | Marshall M, V Sreenivas Plant Licensing Branch 1 |
| To: | Hodge J Exelon Generation Co, Exelon Nuclear |
| Sreenivas V, NRR/DORL/LPL1, 415-2596 | |
| References | |
| EPID L-2019-LLA-0157 | |
| Download: ML19227A041 (2) | |
Text
From:
Marshall, Michael To:
Hodge, Jessie D:(Exelon Nuclear)
Cc:
James Danna (James.Danna@nrc.gov); Sreenivas V (V.Sreenivas@nrc.gov)
Subject:
R. E. Ginna Nuclear Power Plant - Acceptance of Requested Licensing Action Re: Request to Increase the Main Steam Safety Valve Lift Setpoint Tolerance (EPID: L-2019-LLA-0157) (EPID: L-2019-LLA-0157)
Date:
Wednesday, August 14, 2019 10:49:00 AM Hello Jessie,
By letter dated July 23, 2019 (Agencywide Documents Access and Management System (ADAMS) Accession No.ML19204A349), Exelon Generation Company, LLC submitted a license amendment request for the R. E. Ginna Nuclear Power Plant (Ginna). The proposed amendment would revise the Ginna Technical Specification Surveillance Requirement 3.7.1.1 to increase the allowable as-found main steam safety valve lift setpoint tolerance from +1 percent / -3 percent to +1.4 percent / -4percent.
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.
Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 360 hours0.00417 days <br />0.1 hours <br />5.952381e-4 weeks <br />1.3698e-4 months <br /> to complete. The NRC staff expects to complete this review by end of April 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,
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 Dr. V. Sreenivas at (301)4152597 or V.Sreenivas@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. 50-244