ML120240124: Difference between revisions

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| number = ML120240124
| number = ML120240124
| issue date = 01/24/2012
| issue date = 01/24/2012
| title = Grand Gulf, Unit 1 - Acceptance Review Email, License Amendment Request, Revise Technical Specification 3.17, Standby Liquid Control (SLC) System, to Support Use of Sodium Pentaborate Solution Enriched with Boron-10 Isotope (TAC No. ME7860)
| title = Acceptance Review Email, License Amendment Request, Revise Technical Specification 3.17, Standby Liquid Control (SLC) System, to Support Use of Sodium Pentaborate Solution Enriched with Boron-10 Isotope
| author name = Wang A B
| author name = Wang A
| author affiliation = NRC/NRR/DORL/LPLIV
| author affiliation = NRC/NRR/DORL/LPLIV
| addressee name = Burford F G, Coulter D M, Davant G H, Jackson R R, Perino C L
| addressee name = Burford F, Coulter D, Davant G, Jackson R, Perino C
| addressee affiliation = Entergy Operations, Inc
| addressee affiliation = Entergy Operations, Inc
| docket = 05000416
| docket = 05000416
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=Text=
=Text=
{{#Wiki_filter:From: Wang, Alan Sent: Tuesday, January 24, 2012 9:20 AM To: 'Perino, Christina'; 'COULTER, DENNIS M'; 'JACKSON, RITA R'; 'BURFORD, FRANCIS G'; 'DAVANT, GUY H' Cc: Lent, Susan; Burkhardt, Janet Subject: Acceptance of Proposed Grand Gulf License Amendment Request Related to Stanby Liquid Control System (ME7860) Christina, Dennis, Jerry, Guy, and Rita,   By letter dated January 23. 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12023A242), Entergy Operations, Inc. (Entergy, the licensee) requested an amendment to the Facility Operating License for the Grand Gulf Nuclear Station, Unit 1 (GGNS). The licensee has proposed to revise Technical Specification 3..1.7, "Standby Liquid Control (SLC) System.Implementation of the Grand Gulf Nuclear Station (GGNS) Cycle 19 core design results in increased core reactivity, which requires a corresponding increase in negative reactivity to be provided by the SLC system. The proposed TS changes reflect the change in the enrichment of the boron-10 (B-10) isotope in the sodium pentaborate (SPB) solution, which is the credited neutron absorber. Increasing the enrichment of the B-10 isotope in the SPB solution effectively increases the available negative reactivity inserted by the SLC system without having to increase the system's storage capacity. The proposed change is needed to ensure appropriate shutdown margin can be maintained during reload design for future cycles beginning with Cycle 19. In addition, TS 3.1.7 will be modified from a graphical limiting condition for operation (LCO) to an LCO based on the product of the SPB solution concentration (C) and the B-10 enrichment (E) in the SPB solution being be greater than or equal to 420. 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.  
{{#Wiki_filter:From:                     Wang, Alan Sent:                     Tuesday, January 24, 2012 9:20 AM To:                       'Perino, Christina'; 'COULTER, DENNIS M'; 'JACKSON, RITA R'; 'BURFORD, FRANCIS G'; 'DAVANT, GUY H' Cc:                       Lent, Susan; Burkhardt, Janet
 
==Subject:==
Acceptance of Proposed Grand Gulf License Amendment Request Related to Stanby Liquid Control System (ME7860)
Christina, Dennis, Jerry, Guy, and Rita, By letter dated January 23. 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12023A242), Entergy Operations, Inc. (Entergy, the licensee) requested an amendment to the Facility Operating License for the Grand Gulf Nuclear Station, Unit 1 (GGNS). The licensee has proposed to revise Technical Specification 3..1.7, Standby Liquid Control (SLC) System. Implementation of the Grand Gulf Nuclear Station (GGNS) Cycle 19 core design results in increased core reactivity, which requires a corresponding increase in negative reactivity to be provided by the SLC system. The proposed TS changes reflect the change in the enrichment of the boron-10 (B-10) isotope in the sodium pentaborate (SPB) solution, which is the credited neutron absorber. Increasing the enrichment of the B-10 isotope in the SPB solution effectively increases the available negative reactivity inserted by the SLC system without having to increase the systems storage capacity. The proposed change is needed to ensure appropriate shutdown margin can be maintained during reload design for future cycles beginning with Cycle 19. In addition, TS 3.1.7 will be modified from a graphical limiting condition for operation (LCO) to an LCO based on the product of the SPB solution concentration (C) and the B-10 enrichment (E) in the SPB solution being be greater than or equal to 420.
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)
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      
Nuclear Regulatory Commission Division of Operating Reactor Licensing Alan.Wang@NRC.gov Tel: (301) 415-1445 Fax: (301) 415-1222}}
}}

Latest revision as of 10:24, 12 November 2019

Acceptance Review Email, License Amendment Request, Revise Technical Specification 3.17, Standby Liquid Control (SLC) System, to Support Use of Sodium Pentaborate Solution Enriched with Boron-10 Isotope
ML120240124
Person / Time
Site: Grand Gulf Entergy icon.png
Issue date: 01/24/2012
From: Wang A
Plant Licensing Branch IV
To: Burford F, Coulter D, Davant G, Rolonda Jackson, Perino C
Entergy Operations
Wang, A B, NRR/DORL/LPLIV, 415-1445
References
TAC ME7860
Download: ML120240124 (1)


Text

From: Wang, Alan Sent: Tuesday, January 24, 2012 9:20 AM To: 'Perino, Christina'; 'COULTER, DENNIS M'; 'JACKSON, RITA R'; 'BURFORD, FRANCIS G'; 'DAVANT, GUY H' Cc: Lent, Susan; Burkhardt, Janet

Subject:

Acceptance of Proposed Grand Gulf License Amendment Request Related to Stanby Liquid Control System (ME7860)

Christina, Dennis, Jerry, Guy, and Rita, By letter dated January 23. 2012 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML12023A242), Entergy Operations, Inc. (Entergy, the licensee) requested an amendment to the Facility Operating License for the Grand Gulf Nuclear Station, Unit 1 (GGNS). The licensee has proposed to revise Technical Specification 3..1.7, Standby Liquid Control (SLC) System. Implementation of the Grand Gulf Nuclear Station (GGNS) Cycle 19 core design results in increased core reactivity, which requires a corresponding increase in negative reactivity to be provided by the SLC system. The proposed TS changes reflect the change in the enrichment of the boron-10 (B-10) isotope in the sodium pentaborate (SPB) solution, which is the credited neutron absorber. Increasing the enrichment of the B-10 isotope in the SPB solution effectively increases the available negative reactivity inserted by the SLC system without having to increase the systems storage capacity. The proposed change is needed to ensure appropriate shutdown margin can be maintained during reload design for future cycles beginning with Cycle 19. In addition, TS 3.1.7 will be modified from a graphical limiting condition for operation (LCO) to an LCO based on the product of the SPB solution concentration (C) and the B-10 enrichment (E) in the SPB solution being be greater than or equal to 420.

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