ML20266G303

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NRR E-mail Capture - Exelon Generation Company, LLC - Fleet Request to Use Paragraph IWA-5120 of the 2017 Edition of the ASME B&PV Code, Section XI
ML20266G303
Person / Time
Site: Calvert Cliffs, Dresden, Peach Bottom, Nine Mile Point, Byron, Braidwood, Limerick, Ginna, Clinton, Quad Cities, FitzPatrick, LaSalle  Constellation icon.png
Issue date: 09/22/2020
From: Blake Purnell
NRC/NRR/DORL/LPL3
To: Tom Loomis
Exelon Generation Co
References
L-2020-LLR-0118
Download: ML20266G303 (3)


Text

From: Purnell, Blake Sent: Tuesday, September 22, 2020 8:11 AM To: Loomis, Thomas R:(GenCo-Nuc) (thomas.loomis@exeloncorp.com)

Cc: Gudger, David T:(GenCo-Nuc); Salgado, Nancy

Subject:

Exelon Generation Company, LLC - Fleet Request to Use Paragraph IWA-5120 of the 2017 Edition of the ASME B&PV Code, Section XI (EPID: L-2020-LLR-0118)

Mr. Loomis:

By application dated September 2, 2020 (ADAMS Accession No. ML20246G739), Exelon Generation Company, LLC (Exelon) submitted a request in accordance with Paragraph 50.55a(g)(4)(iv) of Title 10 of the Code of Federal Regulations (10 CFR) to use a specific provision in a later edition of the American Society of Mechanical Engineers (ASME) Boiler and Pressure Vessel (B&PV) Code at Braidwood Station, Units 1 and 2; Byron Station, Unit Nos. 1 and 2; Calvert Cliffs Nuclear Power Plant, Units 1 and 2; Clinton Power Station, Unit No. 1; Dresden Nuclear Power Station, Units 2 and 3; James A. FitzPatrick Nuclear Power Plant; LaSalle County Station, Units 1 and 2; Limerick Generating Station, Units 1 and 2; Nine Mile Point Nuclear Station, Units 1 and 2; Peach Bottom Atomic Power Station, Units 2 and 3; Quad Cities Nuclear Power Station, Units 1 and 2; and R. E. Ginna Nuclear Power Plant. Specifically, Exelon requested approval to use paragraph IWA-5120 of the 2017 Edition of the ASME B&PV Code, Section XI, for periodic system pressure test exemptions at each facility.

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

The NRC staff has reviewed your application and concluded that it provides technical information in sufficient detail to enable the staff to complete its detailed technical review and make an independent assessment regarding the acceptability of the 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 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 staffs detailed technical review by separate correspondence.

Based on the information provided in your submittal, the NRC staff estimates that review of this request will take approximately 150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> to complete. The staff expects to complete its review by September 30, 2021. These estimates are based on the staffs initial review of the application and they could change due to several factors, including requests for additional information. If there are emergent complexities or challenges in our review that would cause changes to the initial forecasted completion date or significant changes to the forecasted hours, I will inform you of the reason for the change and provide the new estimates.

Sincerely,

Blake Purnell, Project Manager Plant Licensing Branch III Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission ph: 301-415-1380 Docket Nos. 50-456, 50-457, 50-454, 50-455, 50-317, 50-318, 50-461, 50-237, 50-249, 50-333, 50-373, 50-374, 50-352, 50-353, 50-220, 50-410, 50-277, 50-278, 50-254, 50-265 and 50-244

Hearing Identifier: NRR_DRMA Email Number: 799 Mail Envelope Properties (BLAPR09MB6481B115CC57264195DCFC3FE63B0)

Subject:

Exelon Generation Company, LLC - Fleet Request to Use Paragraph IWA-5120 of the 2017 Edition of the ASME B&PV Code, Section XI (EPID: L-2020-LLR-0118)

Sent Date: 9/22/2020 8:11:10 AM Received Date: 9/22/2020 8:11:10 AM From: Purnell, Blake Created By: Blake.Purnell@nrc.gov Recipients:

"Gudger, David T:(GenCo-Nuc)" <David.Gudger@exeloncorp.com>

Tracking Status: None "Salgado, Nancy" <Nancy.Salgado@nrc.gov>

Tracking Status: None "Loomis, Thomas R:(GenCo-Nuc) (thomas.loomis@exeloncorp.com)" <thomas.loomis@exeloncorp.com>

Tracking Status: None Post Office: BLAPR09MB6481.namprd09.prod.outlook.com Files Size Date & Time MESSAGE 3473 9/22/2020 8:11:10 AM Options Priority: Normal Return Notification: No Reply Requested: No Sensitivity: Normal Expiration Date: