ML12305A049

Acceptance Review Email, Request for Relief RBS-R&R-2011-001 from ASME Code Class 3 Table ND-4622.7(b)-1 Requirements for Post-Weld Heat Treatment Exemption of Valves, Third 10-Year Inservice Inspection Interval

ML12305A049
Person / Time
Site:	River Bend
Issue date:	10/29/2012
From:	Wang A Division of Operating Reactor Licensing
To:	Burmeister B, Clark J Entergy Operations
Wang A
References
TAC ME9622
Download: ML12305A049 (1)

Text

Burkhardt, Janet From: Wang, Alan Sent: Monday, October 29, 2012 9:51 AM To: 'BURMEISTER, BARRY M'; Joseph Clark (JCLARK@entergy.com)

Cc: Burkhardt, Janet; Chen, Qiao-Lynn

Subject:

FW: Acceptance of RiverBend Station Request for Relief RBS-R&R-2011-001 (ME9622)

Barry and Joey, By letter dated September 20, 2011 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML2269A102), Entergy Operations, Inc. (Entergy, the licensee) submitted relief request RBS-R&R-20122-001 for the River Bend Station, Unit 1 (RBS). By letter dated October 26, 2012, Entergy informed the NRC staff that the correct citation for the relief request is 50.55a(a)(3)(ii) and not 50.55a(a)(3)(i) as stated in the September 20, 2012, letter. The proposed request for relief are the postweld heat treatment exemption of Table ND-4622.7 applicable to fillet and partial penetration welds. This relief is requested for the third 10-year interval of the Inservice Inspection Program. 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.

Pursuant to Section 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 NRC staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed requests for relief 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) 415-1445.

Alan Wang Project Manager (River Bend Station)

Nuclear Regulatory Commission Division of Operating Reactor Licensing Alan.Wang@NRC.gov Tel: (301) 415-1445 Fax: (301) 415-1222 1