ML111730746

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

ML111730746
Person / Time
Site:	Grand Gulf
Issue date:	06/22/2011
From:	Wang A Plant Licensing Branch IV
To:	Burford F, Millar D Entergy Operations
Wang, A B, NRR/DORL/LPLIV, 415-1445
References
TAC ME4679
Download: ML111730746 (1)

Text

From: Wang, Alan Sent: Wednesday, June 22, 2011 4:28 PM To: BURFORD, FRANCIS G; MILLAR, DANA Cc: Lent, Susan; Burkhardt, Janet

Subject:

Grand Gulf Extended Power Uprate Containment and Ventilation Branch 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 June 22, 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 is an additional RAI related to the Containment and Ventilation Branch review:

1) Refer to Entergys response to RAI # 25 in letter dated March 31, 2011 (ML110900586 and ML110900593). Provide a pressure and temperature profile for the containment analysis that resulted in the limiting peak pressure of 11.9 psig given in PUSAR Table 2.6-1 that Entergy proposes to use as Pa for the 10 CFR 50 Appendix J integrated leak rate testing (ILRT). Provide a detailed discussion explaining why the short term peak pressure of 14.8 psig (given in PUSAR Table 2.6-1) should not be used as Pa. In the discussion, include similar precedent Mark III containment examples that have been approved by NRC. Please note that in the current licensing basis the long term peak pressure of 11.5 psig (PUSAR Table 6.2-1) being greater than the short term peak pressure of 9.9 psig approximately (extracted from UFSAR Figure 6.2-10) justifies the current TS value of Pa as 11.5 psig. Also note that the definition of Pa given in 10 CFR Appendix J under II Explanation of Terms item I is: Pa (ps.g.) means the calculated peak containment internal pressure related to the design basis accident and specified either in the technical specification or associated bases.

Alan Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation