ML112800475

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Acceptance Review Email, Relief Request RR-ENG-3-06 from ASME Code Requirements for Leak Testing Boundaries of Class 1 Pressure-Retaining Components, Third 10-Year Inservice Inspection Interval (TAC ME7053-ME7054)
ML112800475
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 10/07/2011
From: Balwant Singal
Plant Licensing Branch IV
To: Harrison A
South Texas
Singal, Balwant, 415-3016, NRR/DORL/LPL4
References
TAC ME7053, TAC ME7054, RR-ENG-3-06
Download: ML112800475 (1)


Text

From:

Singal, Balwant Sent:

Friday, October 07, 2011 1:03 PM To:

Harrison, Albon Cc:

Walker, Philip

Subject:

Acceptance Review for Relief Request RR-ENG-3 TAC Nos ME7053 and ME7054 By letters dated August 31, 2011, STP Nuclear Operating Company (licensee) submitted Relief Request No RR-ENG-3-06 for South Texas Project, Units 1 and 2. The licensee request relief from the requirements of American Society of Mechanical Engineers Boiler and Pressure Vessel Code,Section XI, Table IWB-2500-1 for examination of Class 1 pressure-retaining components from the third 10-year inspection interval. Approval of this relief request will exempt Class 1 components from being tested at full Reactor Coolant System (RCS) pressure if they are normally isolated from full RCS pressure. The purpose of this letter 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 application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

Pursuant to Sections 50.55a(a)(3)(i) and 50.55a(a)(3)(ii) of Title 10 of the Code of Federal Regulations (10 CFR), 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 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 amendment 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) 415-3016.

Balwant K. Singal Senior Project Manager (Comanche Peak and STP)

Nuclear Regulatory Commission Division of Operating Reactor Licensing Balwant.Singal@nrc.gov Tel: (301) 415-3016 Fax: (301) 415-1222