ML111520458

Email, Request for Additional Information, Nrr/Dra/Aadb Review, Round 2, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt

ML111520458
Person / Time
Site:	Grand Gulf
Issue date:	06/01/2011
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: ML111520458 (1)

Text

From: Wang, Alan Sent: Wednesday, June 01, 2011 1:48 PM To: Jerry Burford; MILLAR, DANA Cc: Burkhardt, Janet; Lent, Susan

Subject:

Grand Gulf Extended Power Uprate Accident Dose Branch Second Round Request for Information (ME4679)

Dana and Jerry, By letter dated September 8, 2010 (Agencywide Documents Access and Management System, Accession No. ML102660403), 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 May 26, 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 are second round RAIs related to your April 14, 2011, response to the Accident Dose Branch review:

1. In Attachment 1 to the letter dated April 14, 2011, it is stated that a weighted dose scaling factor is used to calculate the EPU dose results for the fuel handling accident (FHA), the control rod drop accident (CRDA), and the pressure controller failure event.

Please provide additional information describing the methodology used or provide the calculations used to develop the weighted dose scaling factors for the exclusion area boundary (EAB), low population zone (LPZ), and control room (CR) for the FHA, CRDA, and the pressure controller failure event. Please provide the basis for the weighted dose scaling factors that were used. Please provide any values that were used to develop the weighted dose scaling factors and describe any models that were used to calculate those values.

2. It is the NRC staff's understanding that the current GGNS analyses of record for the radiological dose consequences for design basis accidents is evaluated at a power level of 3910 MWt or lower depending on the accident scenario being evaluated. Please describe what the GGNS analyses of record will consist of for the proposed change at the EPU power level, provided a weighted dose scaling factor was used to calculate the EPU dose results instead of a reanalysis of the current radiological dose analyses for design-bases accidents.