ML120040501

Email, Request for Additional Information, License Amendment Request to Revise Minimum Critical Power Ratio Safety Limit in Technical Specification 2.1.1.2 for Two-Loop and Single Recirculation Loop

ML120040501
Person / Time
Site:	Grand Gulf
Issue date:	01/04/2012
From:	Wang A B Plant Licensing Branch IV
To:	Jackson R R, Perino C L Entergy Operations
Wang, A B, NRR/DORL/LPLIV, 415-1445
References
TAC ME7531
Download: ML120040501 (1)

Text

From: Wang, Alan Sent: Wednesday, January 04, 2012 4:20 PM To: 'JACKSON, RITA R'; Perino, Christina Cc: Lent, Susan; Burkhardt, Janet

Subject:

GG SLMCPR TS LAR (ME7531)

Rita, and Christina, By letter dated October 28, 2011 (Agencywide Documents Access and Management System, Accession No. ML1113060150), 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) to revise Minimum Critical Power Ratio Safety Limit (MCPR) values for both two loop and single loop operation in accordance with the requirements set forth in GE Nuclear Energy Topical Report NEDC-33173P, "Applicability fo GE Methods to Expanded Operating Domains, Rev. 0." As a result of our review, 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. Jeff Seiter of your staff on January 4 , 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. On page 7 of Attachment 3 of the submittal [Ref. 1], it was stated, "In approving the Fitz patrick Safety Limit MCPR change, the NRC accepted this evaluation method for assessing the effect of the GNF2 bent spacer wing." It appears that Entergy relied on the Fitz patrick evaluation method to justify acceptability of GNF2 bent spacer wing fuels in GGNS Cycle 19 core (first EPU cycle). Please provide the following additional information:

a) In Cycle 19 of GGNS (first EPU cycle), how many GNF2 fuel rods with bent spacer wing will be residing in the core?

b) If the number of fuel rods in response to part (a) is higher than the number of rods used in Fitz patrick (Cycle 20), then explain how the FitzPatrick evaluation method is still applicable to GGNS having a larger number of defective rods in the core compared to that of Fitz patrick. c) Discuss how the Fitz patrick evaluation method is still applicable to GGNS Cycle 19 which has a significantly higher power level and a flatter power profile due to EPU.

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