ML19269C166

NRR E-mail Capture - Cooper Nuclear Station - Acceptance Review of LAR for Exception from Certain Leak Testing Interval Requirements of the Primary Containment Leakage Rate Testing Program (L-2019-LLA-0179)

ML19269C166
Person / Time
Site:	Cooper
Issue date:	09/26/2019
From:	Thomas Wengert Plant Licensing Branch IV
To:	Vanderkamp D Nebraska Public Power District (NPPD)
Wengert T
References
L-2019-LLA-0179
Download: ML19269C166 (3)

Text

NRR-DRMAPEm Resource From: Wengert, Thomas Sent: Thursday, September 26, 2019 9:48 AM To: Van Der Kamp, David W.

Cc: Forland, Thomas J.; Pascarelli, Robert

Subject:

Cooper Nuclear Station - Acceptance Review of LAR for Exception from Certain Leak Testing Interval Requirements of the Primary Containment Leakage Rate Testing Program (L-2019-LLA-0179)

By letter dated August 19, 2019 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML19238A065), Nebraska Public Power District (NPPD) submitted a license amendment request for Cooper Nuclear Station (CNS). The proposed amendment would revise CNS Technical Specification (TS) Section 5.5.2, Primary Containment Leakage Rate Testing Program, to allow for an exception to certain leak testing interval requirements of the program. Specifically, NPPD requests that the 10 CFR Part 50 Appendix J, Option B leak testing of Type C Residual Heat Removal (RHR) system heat exchanger relief valves, RHR-RV-20RV/21RV, and their associated Type B testable discharge flange tests, be performed at the same frequency as the visual examination, seat leakage testing, and set pressure testing performed for these valves under the requirements of the Inservice Testing Program per 10 CFR 50.55a(f).

The purpose of this e-mail 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 TSs) 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 staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment request 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.

Based on the information provided in your submittal, the NRC staff has estimated that this licensing request will take approximately 240 hours10 days <br />1.429 weeks <br />0.329 months <br /> to complete. The NRC staff expects to complete this review by the date requested in your application, which is August 19, 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 our routine interactions.

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 and unanticipated addition of scope to the review, and review by NRC advisory committees or hearing-related activities.

1

If you have any questions, please contact me.

Tom Wengert, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-4037 2

Hearing Identifier: NRR_DRMA Email Number: 221 Mail Envelope Properties (CH2PR09MB4347F1D778112914B2BD66CD8F860)

Subject:

Cooper Nuclear Station - Acceptance Review of LAR for Exception from Certain Leak Testing Interval Requirements of the Primary Containment Leakage Rate Testing Program (L-2019-LLA-0179)

Sent Date: 9/26/2019 9:47:42 AM Received Date: 9/26/2019 9:47:00 AM From: Wengert, Thomas Created By: Thomas.Wengert@nrc.gov Recipients:

"Forland, Thomas J." <tjforla@nppd.com>

Tracking Status: None "Pascarelli, Robert" <Robert.Pascarelli@nrc.gov>

Tracking Status: None "Van Der Kamp, David W." <dwvande@nppd.com>

Tracking Status: None Post Office: CH2PR09MB4347.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 3870 9/26/2019 9:47:00 AM Options Priority: Standard Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date:

Recipients Received: