ML110480551: Difference between revisions
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| stage = Acceptance Review | |||
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{{#Wiki_filter:From: Gratton, Christopher Sent: Thursday, February 17, 2011 12:19 PM To: 'Matthews, Thomas C IV' | |||
==Subject:== | |||
Acceptance Review Results: BFN Unit 3 request for relief 3-ISI-25 Mr. Mathews: | |||
By letter dated January 21, 2011, the Tennessee Valley Authority requested relief from weld examination coverage requirements specified in American Society of Mechanical Engineers Boiler and Pressure Vessel Code, Section XI, 2001 Edition, 2003 Addenda as amended by Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(b)(2)(xv)(A)(2), for seven full penetration welds due to access limitations caused by design. The request was for Browns Ferry Nuclear Plant, Unit 3. The request was made pursuant to 10 CFR 50.55a(g)(5)(iii). | |||
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff | |||
=s acceptance review of this request for approval. 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 does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review consistent with 10 CFR 50.55a(g)(5)(iii), and make an independent assessment regarding the acceptability of the proposed action in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence. | |||
If you have any questions, please contact me at (301) 415-1055. | |||
Christopher Gratton Senior Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation}} | |||
Revision as of 06:12, 14 August 2018
| ML110480551 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 02/17/2011 |
| From: | Gratton C Plant Licensing Branch II |
| To: | Matthews T C - No Known Affiliation |
| Gratton C, NRR, DORL, 415-1055 | |
| References | |
| Download: ML110480551 (1) | |
Text
From: Gratton, Christopher Sent: Thursday, February 17, 2011 12:19 PM To: 'Matthews, Thomas C IV'
Subject:
Acceptance Review Results: BFN Unit 3 request for relief 3-ISI-25 Mr. Mathews:
By letter dated January 21, 2011, the Tennessee Valley Authority requested relief from weld examination coverage requirements specified in American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, 2001 Edition, 2003 Addenda as amended by Title 10 of the Code of Federal Regulations (10 CFR), Section 50.55a(b)(2)(xv)(A)(2), for seven full penetration welds due to access limitations caused by design. The request was for Browns Ferry Nuclear Plant, Unit 3. The request was made pursuant to 10 CFR 50.55a(g)(5)(iii).
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff
=s acceptance review of this request for approval. 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 does provide technical information in sufficient detail to enable the staff to proceed with its detailed technical review consistent with 10 CFR 50.55a(g)(5)(iii), and make an independent assessment regarding the acceptability of the proposed action in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.
If you have any questions, please contact me at (301) 415-1055.
Christopher Gratton Senior Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation