ML120270343: Difference between revisions

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| number = ML120270343
| number = ML120270343
| issue date = 01/27/2012
| issue date = 01/27/2012
| title = Palo Verde, Units 1, 2, and 3 - Acceptance Review Email, Request for Relief to Use Subsequent Edition/Addenda of ASME Code Section Xi, for the 3rd 10-Year Inservice Inspection Interval (TAC Nos. ME7805, ME7806, and ME7807)
| title = Acceptance Review Email, Request for Relief to Use Subsequent Edition/Addenda of ASME Code Section Xi, for the 3rd 10-Year Inservice Inspection Interval (TAC Nos. ME7805, ME7806, and ME7807)
| author name = Singal B K
| author name = Singal B K
| author affiliation = NRC/NRR/DORL/LPLIV
| author affiliation = NRC/NRR/DORL/LPLIV

Revision as of 02:07, 30 January 2019

Acceptance Review Email, Request for Relief to Use Subsequent Edition/Addenda of ASME Code Section Xi, for the 3rd 10-Year Inservice Inspection Interval (TAC Nos. ME7805, ME7806, and ME7807)
ML120270343
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 01/27/2012
From: Singal B K
Plant Licensing Branch IV
To: Stroud R M
Arizona Public Service Co
Singal, Balwant, 415-3016, NRR/DORL/LPL4
References
TAC ME7805, TAC ME7806, TAC ME7807
Download: ML120270343 (1)


Text

From: Singal, Balwant Sent: Friday, January 27, 2012 2:33 PM To: Russell.Stroud@aps.com

Subject:

Acceptance Review for Request for Approval to Use Subsequent American Society of Mechanical Engineers (ASME) Code Edition and Addenda - TAC Nos. ME7805, ME7806 and ME7807

By letters dated December 29, 2011, Arizona Public Service Company (APC) (licensee) submitted request for approval to use subsequent American Society of Mechanical Engineers (ASME) Code Edition and Addenda for examination categories B-L-1, B-M-1, and C-G in the third Inservice Inspection interval..

The purpose of this letter 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.

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