ML14192A925

Endorsement Letter of NEI 08-01

ML14192A925
Person / Time
Site:	Nuclear Energy Institute
Issue date:	07/31/2014
From:	Cheok M C Division of Construction Inspection and Operational Programs
To:	Bell R J Nuclear Energy Institute
Bloom S D, NRO/DCIP/IGCB, 415-2431
References
NEI 08-01
Download: ML14192A925 (7)

Text

July 31, 2014

Mr. Russell J. Bell Senior Director, New Plant Licensing Nuclear Generation Division

Nuclear Energy Institute

1201 F Street, NW, Suite 1100 Washington, DC 20004

SUBJECT:

ACCEPTANCE FOR ENDORSEMENT OF NUCLEAR ENERGY INSTITUTE 08-01, REVISION 5 - CORRECTED: INDUSTRY GUIDELINE FOR THE ITAAC CLOSURE PROCESS UNDER 10 CFR PART 52

Dear Mr. Bell:

The Nuclear Regulatory Commission (NRC) received your letter dated June 30, 2014, requesting endorsement of Nuclear Energy Institute's (NEI's) 08-01, "Industry Guideline for the ITAAC Closure Process Under 10 CFR Part 52," Revision 5 - Corrected (Agencywide Documents Access Management System (ADAMS) Accession No. ML14182A1580).

The staff has reviewed the document to ensure that prior NRC comments provided on April 23, 2014 (ADAMS Accession No. ML14031A195) were adequately addressed. The Revision 5 -

Corrected version of NEI 08-01 provided in your June 30, 2014, letter addresses comments previously provided by the sta ff. Therefore, the NRC finds NEI 08-01, Revision 5 - Corrected, dated June 2014, acceptable for use by licensees during formal NRC endorsement via the NRC's regulatory guide process with the clarifications noted below.

1. The subject line for all submitted ICNs should state "ITAAC Closure Notification on Completion of {SiteName and Unit #}." When the licenses are issued, the ITAAC will be contained in an appendix to the COL, which is the appropriate reference in an ICN since it is possible that the site-specific ITAAC could represent a departure from the design certification document (DCD) ITAAC. This cl arification is needed because some of the examples identify the ITAAC in the ICN example as coming from a particular technology. For the same reason, when the ICN refers to a table in the ITAAC, the reference should not be to the DCD, but should be to the table in the ITAAC appendix in the license.

2. In numerous ICN examples, the determination basis simply refers to the ASME Code Section III or some other relevant Code. While not required, it could be beneficial, as a reference for the staff, for the ICN to cite the specific relevant Code section(s) or article(s) used in performing the ITAAC. In addition, if the Code or article has been endorsed by a Regulatory Guide (RG), the RG should be referenced especially if there are specific conditions or restrictions on the use of the Code or article (e.g., use of ASME Code XXX is conducted as accepted in RG 1.YYY).

3. Although, there is no current guidance in NEI 08-01 for the content of the 10 CFR 52.103 Scheduled Fuel Load Notification, the staff provides the following: The initial notification should include the anticipated date (270 days in the future) for initial loading of fuel. The updates required by 10 CFR 52.103 should include updates to the anticipated date, if applicable. In determining the anticipated date, the licensee should use NRC guidance on timeframes for the NRC's completion of its review and the making of the 10 CFR 52.103(g) finding. This NRC guidance will be developed in the future.

The Office of Management and Budget has determined that the NRC's endorsement of NEI 08-01 is not a major rule within the meaning of the Congressional Review Act.

If you have any concerns or questions, please contact Mr. Steven Bloom, Senior Project Manager, at (301) 415-2431, or via email at Steven.Bloom@nrc.gov. Sincerely,

/RA/ Michael Cheok, Director Division of Construction Inspection

and Operational Programs Office of New Reactors

Project No.: 689

cc: Kati Austgen, NEI

ML14192A925 NRO-002

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