ML110750132

Email, Dose Assessment Branch, Request for Additional Information, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt

ML110750132
Person / Time
Site:	Grand Gulf
Issue date:	03/16/2011
From:	Wang A Plant Licensing Branch IV
To:	Burford J, Millar D Entergy Operations
Wang, A B, NRR/DORL/LPLIV, 415-1445
References
TAC ME4679
Download: ML110750132 (1)

Text

From:

Wang, Alan Sent:

Wednesday, March 16, 2011 8:44 AM To:

Wang, Alan; 'MILLAR, DANA'; 'Jerry Burford' Cc:

Lent, Susan; Burkhardt, Janet

Subject:

GG EPU Dose Assessment Branch Request for Additional Information (ME4679)

Dana and Jerry, By letter dated September 8, 2010 (Agencywide Documents Access and Management System, Accession No. ML1002660403), Entergy Operations, Inc. (Entergy, the licensee), submitted a request to amend the Facility Operating License No. NPF-29 for Grand Gulf Nuclear Station, Unit 1 (GGNS). The licensee proposed a license amendment request (LAR) for an extended power uprate (EPU) to increase the maximum reactor core power operating limit from 3898 megawatts thermal (MWt) to 4408 MWt. The U.S. Nuclear Regulatory Commission (NRC) staff has determined that the following additional information is needed for the NRC staff to complete our review of this amendment. This request for additional information (RAI) was discussed with Mr. Jerry Burford of your staff on March 15, 2011, and it was agreed that a response would be provided within 30 days of receipt of this E-mail. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1445 or via e-mail at Alan.Wang@nrc.gov.

The following RAI is related to the Dose Assessment Branch portion of the LAR review:

1. In Section 2.9.2 and Section 2.9.3 of Attachment 5A, Safety Analysis Report for Grand Gulf Nuclear Station Constant Pressure Power Uprate, of your September 8, 2010, submittal, it is stated that all of the design basis accident (DBA) dose consequence analyses were updated to reflect minor changes to design inputs. The NRC staffs initial review of the EPU calculated doses compared to the current licensing basis (CLB) doses indicates more than minimal increase in the consequences of an accident. Because these analyses are a part of the basis for approval of the proposed EPU, the NRC staff needs additional information in order to complete its review. Provide additional information describing all the basic parameters used in for the DBA dose consequence analyses described in Section 2.9.2 and Section 2.9.3 of Attachment 5A of your submittal. For each parameter, please indicate the CLB value, the revised value where applicable, as well as the basis for any changes to the CLB. Also describe any methodologies that may have changed based on the proposed amendment. The NRC staff requests that the information be presented in a tabular form.