ML12333A072

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Acceptance Review Email, License Amendment Request to Revise TS Table 3.3.6.1-1 to Support Correction of Non-Conservative Allowable Value for Primary Containment and Drywell Isolation Instrumentation
ML12333A072
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 11/27/2012
From: Wang A
Plant Licensing Branch IV
To: Rolonda Jackson, Perino C, Seiter J
Entergy Operations
Wang A
References
TAC ME9910
Download: ML12333A072 (1)


Text

Lent. Susan From: Wang, Alan Sent: Tuesday, November 27,20124:43 PM To: SEITER, JEFFERY ALAN; JACKSON, RITA R; Perino, Christina Cc: Burkhardt, Janet; Lent, Susan

Subject:

Acceptance Review of Grand Gulf Nuclear Station License Amendment Request Regarding RCIC Steam Supply Line Pressure-Low (TAC No. ME9910)

Christina, Jeff and Rita, By letter dated November 2012 (Agencywide Documents Access Management System No.

ML 1 8A 119) (GNRO-2012100132), Entergy Operations, Inc. (Entergy, the licensee) requested an amendment to the Facility Operating License for the Grand Gulf Nuclear Station, Unit 1 (GGNS). The license amendment request (LAR) proposes to revise Technical Specification (TS) Table 3.3.6.1-1 Allowable Value for Primary Containment and Drywell isolation Instrumentation Function 3.c, "Reactor Core Isolation Cooling (RCIC) Steam Supply Line Pressure - Low." This request was submitted to correct a non- conservative TS and, consistent with the guidance of NRC Administrative Letter 98-10, "Dispositioning of Technical Specifications that are Insufficient to Assure Plant Safety," dated December 29,1989.

Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), an amendment to the license (including the technical specifications) must fully describe the changes requested, and following as far as applicable, the form prescribed for original applications. Section 50.34 of 10 CFR addresses the content of technical information required. This section stipulates that the submittal address the design and operating characteristics, unusual or novel design features, and principal safety considerations.

The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staffs acceptance review of this amendment request. The acceptance review was performed to determine if there is sufficient technical information in scope and depth to allow the NRC staff to complete its detailed technical review. The acceptance review is also intended to identify whether the application has any readily apparent information insufficiencies in its characterization of the regulatory requirements or the licensing basis of the plant.

The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the NRC staff to proceed with its detailed technical review and make an independent assessment regarding the acceptability of the proposed amendment in terms of regulatory requirements and the protection of public health and safety and the environment. If additional information is needed for the staff to complete its technical review, you will be advised by separate correspondence.

If you have any questions, please contact me at (301) 415-1445.

Alan Wang Project Manager (Grand Gulf Nuclear Station)

Nuclear Regulatory Commission Division of Operating Reactor Licensing Alan. Wang@NRC.gov Tel: (301) 415-1445 Fax: (301) 415-1222 1