ML120740035
| ML120740035 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 03/14/2012 |
| From: | Beltz T Plant Licensing Branch III |
| To: | Jim Costedio Point Beach |
| beltz T, NRR/DORL/LPL3-1, 301-415-3049 | |
| References | |
| TAC ME7974, TAC ME7975 | |
| Download: ML120740035 (2) | |
Text
ADAMS Accession No.: ML120740035 From:
Beltz, Terry Sent:
Wednesday, March 14, 2012 7:51 AM To:
'Costedio, James' Cc:
'Locke, Kim'; Williams, Shawn; Audrain, Margaret; Lingam, Siva; Boyle, Patrick
Subject:
Point Beach Nuclear Plant, Units 1 and 2 - Acceptance Review re: Relief Requests RR-2 and RR-3 (TAC Nos. ME7974 and ME7975)
Dear Mr. Costedio:
By letter dated February 15, 2012, (Agencywide Documents Access and Management System Accession No. ML12046A796), NextEra Energy Point Beach, LLC, submitted relief requests (RR-2 and RR-3) for the Point Beach Nuclear Plant, Units 1 and 2.
RR-2 requests the use of Code Case N-532-5 whenever completion of Forms NIS-1 and NIS-2 or inservice inspection summary report is required in ASME Section XI (2007 Edition with the 2008 Addenda). Code Case N-532-5 was published in Supplement 5 to the 2010 Edition of the Nuclear Code Case Book.
RR-3 requests relief from the requirements of ASME Section XI, IWA-5250(a)(2), on the basis that the proposed alternative provides an acceptable level of quality and safety. Specifically, when a leak is identified at a bolted connection in systems borated for the purpose of controlling reactivity, the licensee proposed to either meet the requirements of IWA-5250(a)(2) or IWA-5251, or stop the leak, address the cause of the leak via through corrective action program, and replace all of the bolting at the connection in accordance with IWA-4000. As such, VT-3 of the removed bolting will not be performed as all the bolting will be discarded and not reused.
Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations, the applicant shall demonstrate that the proposed alternative(s) 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 purpose of this letter is to provide the final results of the 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 and make an independent assessment regarding the acceptability of the proposed change. 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 and make an independent assessment regarding the acceptability of the proposed relief request 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.
Should you have any questions rega Sincerely, Terry A. Beltz, Senior Project Manager Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation (301) 415-3049 Terry.Beltz@nrc.gov arding this review, please contact me at (301) 415-3049.