ML112500329: Difference between revisions

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| number = ML112500329
| number = ML112500329
| issue date = 09/07/2011
| issue date = 09/07/2011
| title = Acceptance Review Email, Relief Request A-1 for Approval of Risk-Informed Alternative to ASME Code, Section Xi for Class 1 and 2 Piping Welds, Third 10-Year Inservice Inspection Interval (TAC No. ME6827)
| title = Acceptance Review Email, Relief Request A-1 for Approval of Risk-Informed Alternative to ASME Code, Section Xi for Class 1 and 2 Piping Welds, Third 10-Year Inservice Inspection Interval
| 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 23:08, 8 February 2019

Acceptance Review Email, Relief Request A-1 for Approval of Risk-Informed Alternative to ASME Code, Section Xi for Class 1 and 2 Piping Welds, Third 10-Year Inservice Inspection Interval
ML112500329
Person / Time
Site: Comanche Peak Luminant icon.png
Issue date: 09/07/2011
From: Singal B K
Plant Licensing Branch IV
To: Hope T
Luminant Generation Co
Singal, Balwant, 415-3016, NRR/DORL/LPL4
References
TAC ME6827
Download: ML112500329 (1)


Text

From: Singal, Balwant Sent: Wednesday, September 07, 2011 1:39 PM To: 'Hope, Timothy' Cc: Burkhardt, Janet; 'Hicks, Jack'

Subject:

Acceptance Review Comanche Peak Nuclear Power Plant Relief Request A TAC ME6827

By letter dated August 2, 2011 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML11220A261), Luminant Generation Company LLC submitted Relief Request No. A-1 for Comanche Peak Steam Electric Station, Unit 1. The relief request requests for approval of the application of an alternative to the ASME Boiler and Pressure Vessel Code Section XI examination requirements for Class 1 and Class 2 piping welds for the Third Inservice Inspection (ISI) Interval. 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