ML100200274
| ML100200274 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 01/13/2010 |
| From: | Larson M Entergy Corp |
| To: | Rulemaking, Directives, and Editing Branch |
| References | |
| 74FR52822 00002, DG-1199, RG 1.183 | |
| Download: ML100200274 (2) | |
Text
NRCREP Resource From: Michael J. Larson [mlarson@entergy.com]
Sent: Wednesday, January 13, 2010 11:07 AM To: NRCREP Resource //
Response from "Comment on NRC Documents" 0 / 0
Subject:
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Below is the result of your feedback form. It was submitted by Michael J. Larson (mlarson(,enterqy.com) on Wednesday, January 13, 2010 at 11:06:54 DocumentTitle: Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors (ML090960464)
Comments: January 13, 2010 lell"112)ý Grand Gulf Nuclear Station, Unit 1 P. 0. Box 756 Port Gibson, MS 39150 Docket No. 50-416 License No. NPF-29
Subject:
Grand Gulf Nuclear Station Comment on Draft Regulatory Guide 1199
Background:
On October 14, 2009, the U.S. Nuclear Regulatory Commission (NRC) published Draft Regulatory Guide, DG-1199, "Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors". The NRC is currently requesting public comments by January 13, 2010. See 74 Fed. Reg. 52,822, 55,273. In response to this request, Entergy submits the following comment.
Comment:
Entergy is planning to submit an extended power uprate (EPU) request for the Grand Gulf Nuclear Station (GGNS) in July 2010. This change would involve a revision to the GGNS design basis dose analyses. GGNS is currently licensed to a full-scope application of the alternative source term and the associated dose analyses currently apply the assumptions and methodologies in Revision 0 to Regulatory Guide 1.183, Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors. This proposed guidance contains changes to the modeling assumptions for the Main Steam Isolation Valve (MSIV) release pathway that can have a significant effect on the GGNS LOCA dose analysis.
In support of the analysis updates currently underway to support the GGNS EPU, Entergy requests that the Staff state its position on the continued use of the existing NRC Regulatory Guide 1.183. Specifically, is a licensee who submits an EPU or other license amendment that involves updating the design basis dose analyses, expected to apply the new guidance or can licensees continue to apply the guidance in Revision 0 of Regulatorty Guide 1.183?
Contact Michael Larson =r- e)2j)
Licensing Engineer 1
Email: mlarson(Denterqy.com Ph: 601-437-6685 organization: Entergy Operations Inc., Grand Gulf Nuclear Station addressl: P.O. Box 756 address2:
city: PORT GIBSON state: MS zip: 39150 country: USA phone: 601-437-6685 2