ML23117A070

From kanterella
Revision as of 12:07, 22 May 2023 by StriderTol (talk | contribs) (StriderTol Bot insert)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search

NRR E-mail Capture - Acceptance Review Results for Browns Ferry, 1, 2, and 3, License Amendment Request to Revise Tech Specs Surveillance Requirements 3.4.3.2 and 3.5.1.11 Safety Relief Valves (BFN TS-540)
ML23117A070
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 04/26/2023
From: Kimberly Green
Plant Licensing Branch II
To: Eckermann J
Tennessee Valley Authority
References
L-2023-LLA-004
Download: ML23117A070 (3)


Text

From: Kimberly Green Sent: Wednesday, April 26, 2023 1:58 PM To: Eckermann, Jeremy Beau

Subject:

Acceptance Review Results for Browns Ferry, Units 1, 2, and 3, License Amendment Request to Revise Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540) (EPID L-2023-LLA-0045)

Dear Mr. Eckermann:

By letter dated March 30, 2023 (Agencywide Documents Access and Management System Accession No. ML23089A167), the Tennessee Valley Authority (TVA) submitted a license amendment request (LAR) for the Browns Ferry Nuclear Plant, Units 1, 2, and 3. The proposed amendments would revise Technical Specification (TS) Surveillance Requirements (SRs) 3.4.3.2 and 3.5.1.11 regarding safety relief valves (SRV) by supplementing the current requirement in these SRs to verify the safety relief valves open when manually actuated with an alternate requirement that verifies that the SRVs are capable of being opened and revising the SR frequency to be in accordance with the Inservice Testing Program.

The purpose of this email is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of the LAR. The acceptance review was performed to determine whether the scope and depth of the technical information was sufficient 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 applications regarding the 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 TVAs LAR 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 amendments 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 TVAs LAR, the NRC staff has estimated that this licensing request will take approximately 130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> to complete and that the review can be completed by February 15, 2024. 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 staffs initial review of the LAR, and

they could change due to several factors including requests for additional information and unanticipated addition of scope to the review.

If you have any questions, please contact me at (301) 415-1627.

Sincerely, Kimberly J. Green, Senior Project Manager Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Hearing Identifier: NRR_DRMA Email Number: 2058 Mail Envelope Properties (DM6PR09MB546259CCF9096594A31CAE938F659)

Subject:

Acceptance Review Results for Browns Ferry, Units 1, 2, and 3, License Amendment Request to Revise Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves (BFN TS-540) (EPID L-2023-LLA-0045)

Sent Date: 4/26/2023 1:58:04 PM Received Date: 4/26/2023 1:58:00 PM From: Kimberly Green Created By: Kimberly.Green@nrc.gov Recipients:

"Eckermann, Jeremy Beau" <jbeckermann@tva.gov>

Tracking Status: None Post Office: DM6PR09MB5462.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 3526 4/26/2023 1:58:00 PM Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: