ML120060041: Difference between revisions

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=Text=
=Text=
{{#Wiki_filter:From: Wang, Alan Sent: Friday, January 06, 2012 8:51 AM To: JACKSON, RITA R; Perino, Christina; 'SEITER, JEFFERY ALAN' Cc: Burkhardt, Janet; Lent, Susan  
{{#Wiki_filter:From:                   Wang, Alan Sent:                   Friday, January 06, 2012 8:51 AM To:                     JACKSON, RITA R; Perino, Christina; 'SEITER, JEFFERY ALAN' Cc:                     Burkhardt, Janet; Lent, Susan


==Subject:==
==Subject:==
Acceptance of Grand Gulf Nuclear Station License Amendment Reqest Regarding Minimun Critical Power Ration Safety Limit TS Change (ME7531)
Acceptance of Grand Gulf Nuclear Station License Amendment Reqest Regarding Minimun Critical Power Ration Safety Limit TS Change (ME7531)
Rita, Jeff and Christina, By letter dated October 28, 2011 (Agencywide Documents Access and Management System, Accession No. ML113060150), 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." 
Rita, Jeff and Christina, By letter dated October 28, 2011 (Agencywide Documents Access and Management System, Accession No. ML113060150), 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.
 
The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's 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 purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's 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.  
 
Consistent with Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR),
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.  
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 NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the 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.
The NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the 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)
If you have any questions, please contact me at (301) 415-1445.  
Nuclear Regulatory Commission Division of Operating Reactor Licensing


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}}
Alan.Wang@NRC.gov Tel: (301) 415-1445 Fax: (301) 415-1222}}

Latest revision as of 10:58, 12 November 2019

Acceptance Review Email, 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
ML120060041
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 01/06/2012
From: Wang A
Plant Licensing Branch IV
To: Rolonda Jackson, Perino C, Seiter J
Entergy Operations
Wang, A B, NRR/DORL/LPLIV, 415-1445
References
TAC ME7531
Download: ML120060041 (1)
v • d • e


Text

From: Wang, Alan Sent: Friday, January 06, 2012 8:51 AM To: JACKSON, RITA R; Perino, Christina; 'SEITER, JEFFERY ALAN' Cc: Burkhardt, Janet; Lent, Susan

Subject:

Acceptance of Grand Gulf Nuclear Station License Amendment Reqest Regarding Minimun Critical Power Ration Safety Limit TS Change (ME7531)

Rita, Jeff and Christina, By letter dated October 28, 2011 (Agencywide Documents Access and Management System, Accession No. ML113060150), 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.

The purpose of this letter is to provide the results of the U.S. Nuclear Regulatory Commission (NRC) staff's 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.

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 NRC staff has reviewed your application and concluded that it does provide technical information in sufficient detail to enable the 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

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