ML23013A151

NRR E-mail Capture - Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Request to Use Later ASME OM Code Edition and Alternative Requests BFN-IST-01 Through BFN-IST-05

ML23013A151
Person / Time
Site:	Browns Ferry
Issue date:	01/13/2023
From:	Kimberly Green Plant Licensing Branch II
To:	Eckermann J Tennessee Valley Authority
References
L-2022-LLR-0086
Download: ML23013A151 (3)

Text

From: Kimberly Green Sent: Friday, January 13, 2023 10:33 AM To: Eckermann, Jeremy Beau

Subject:

Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Request to Use Later ASME OM Code Edition and Alternative Requests BFN-IST-01 through BFN-IST-05 (EPID L-2022-LLR-0086)

Dear Mr. Eckermann:

By letter dated December 12, 2022 (ADAMS Accession No. ML22346A189), Tennessee Valley Authority (TVA) requested approval to use a later edition of the American Society of Mechanical Engineers (ASME) Code for Operation and Maintenance of Nuclear Power Plants (OM Code),

in accordance with Title 10 of the Code of Federal Regulations Section 50.55a(f)(4)(iv) and Regulatory Issue Summary (RIS) 2004-12, Clarification on Use of Later Editions and Addenda to the ASME OM Code and Section XI, for Browns Ferry Nuclear Plant (Browns Ferry), Units 1, 2, and 3. TVA also requested five alternatives (i.e., BFN-IST-01 through -05) to 10 CFR 50.55a(b)(3)(xi) for implementing ASME OM Code subsections ISTC-3500, ISTC-3700, and OM Code Mandatory Appendix IV, in accordance with 10 CFR 50.55a(z)(1) or (z)(2), for Browns Ferry, Units 1, 2, and 3. The purpose of this e-mail is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this relief 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 request has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Pursuant to 10 CFR 50.55a(f)(4)(iv), inservice tests of pumps and valves may meet the requirements set forth in subsequent editions and addenda that are incorporated by reference in 10 CFR 50.55a(a)(1)(iv), subject to the conditions listed in paragraph 10 CFR 50.55a(b), and subject to NRC approval. Portions of editions or addenda may be used, provided that all related requirements of the respective editions or addenda are met.

Pursuant to 10 CFR 50.55a(z)(1) and 50.55a(z)(2), the applicant shall demonstrate that the proposed alternatives would provide an acceptable level of quality and safety, or that compliance with the specified requirements of Section 50.55a would result in hardship or unusual difficulty without a compensating increase in the level of quality or safety.

The NRC staff has reviewed your requests and concluded that they do 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 requests in terms of regulatory requirements. 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 submittal, the NRC staff has estimated that it will take approximately 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> to complete, and that the review can be completed by August 31, 2023. The estimate is based on the staffs initial review of the requests and could change, due to several factors including requests for additional information and unanticipated addition of scope to the review. 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.

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

Sincerely, Kimberly 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: 1910

Mail Envelope Properties (DM6PR09MB5462DAB788937774303F56D98FC29)

Subject:

Acceptance Review Results for Browns Ferry Nuclear Plant, Units 1, 2, and 3, Request to Use Later ASME OM Code Edition and Alternative Requests BFN-IST-01 through BFN-IST-05 (EPID L-2022-LLR-0086)

Sent Date: 1/13/2023 10:33:05 AM Received Date: 1/13/2023 10:33:00 AM 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

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