Letter Sequence Acceptance Review |
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MONTHYEARGNRO-2011/00017, Request for Additional Information Regarding Extended Power Uprate2011-03-0909 March 2011
Request for Additional Information Regarding Extended Power Uprate
Project stage: Request
ML11112A0982011-04-21021 April 2011
Request for Additional Information Regarding Extended Power Uprate
Project stage: Request
GNRO-2011/00034, Request for Additional Information Regarding Extended Power Uprate2011-05-0303 May 2011
Request for Additional Information Regarding Extended Power Uprate
Project stage: Request
GNRO-2011/00076, License Amendment Request Criticality Safety Analysis and Technical Specification 4.3.1, Criticality2011-09-0909 September 2011
License Amendment Request Criticality Safety Analysis and Technical Specification 4.3.1, Criticality
Project stage: Request
ML1127700622011-10-0303 October 2011
Acceptance Review Email, License Amendment Request, Revise Criticality Safety Analysis and Technical Specification 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition
Project stage: Acceptance Review
ML12271A3022012-07-25025 July 2012
E-mail Grand Gulf Station, Unit 1 - Redacted, Request for Additional Information, Amendment Request to Revise Criticality Safety Analysis and Technical Specification 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Co
Project stage: RAI
GNRO-2012/00120, Responses to NRC Requests for Additional Information – GGNS Criticality Safety Analysis License Amendment Request2012-10-0101 October 2012
Responses to NRC Requests for Additional Information – GGNS Criticality Safety Analysis License Amendment Request
Project stage: Response to RAI
ML12312A2382013-01-0202 January 2013
Request for Withholding Information from Public Disclosure, 9/28/12 Affidavit Executed by L. Trosman, GNF-A, for Attachment 1 to GNRO-2012/00120 Dated 10/1/12
Project stage: Withholding Request Acceptance
ML13071A1542013-04-0101 April 2013
Redacted Version, Request for Additional Information, Round 2, License Amendment Request, Revise Criticality Safety Analysis and TS 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition
Project stage: RAI
ML13091A1952013-04-0101 April 2013
Proposed Audit Plan for 4/3/13-4/4/13 Audit of the Criticality Safety Analysis; Request to Revise Criticality Safety Analysis and TS 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition
Project stage: Other
ML13091A1922013-04-0101 April 2013
Email, Proposed Audit Plan for 4/3/13-4/4/13 Audit of the Criticality Safety Analysis; Request to Revise Criticality Safety Analysis and TS 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition
Project stage: Other
ML13121A3332013-05-17017 May 2013
Audit Report for the April 3-4, 2013 Audit of the Calculations Related to the Request to Revise the Criticality Safety Analysis and TS 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition
Project stage: Other
GNRO-2013/00050, Criticality Safety Analysis License Amendment Request - Responses to NRC Requests for Additional Information2013-07-0202 July 2013
Criticality Safety Analysis License Amendment Request - Responses to NRC Requests for Additional Information
Project stage: Response to RAI
GNRO-2013/00063, Notification of Spent Fuel Cask Use2013-09-0505 September 2013
Notification of Spent Fuel Cask Use
Project stage: Request
GNRO-2013/00066, Criticality Safety Analysis License Amendment Request - Supplemental Information2013-09-0505 September 2013
Criticality Safety Analysis License Amendment Request - Supplemental Information
Project stage: Supplement
GNRO-2013/00073, Criticality Safety Analysis License Amendment Request - Supplemental Information2013-09-16016 September 2013
Criticality Safety Analysis License Amendment Request - Supplemental Information
Project stage: Supplement
ML13261A2642013-09-25025 September 2013
Redacted Version, Issuance of Amendment No. 195, Revise Criticality Safety Analysis and Technical Specification 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition
Project stage: Approval
ML13197A1922013-11-25025 November 2013
Request for Withholding Information from Public Disclosure, 6/26/13 Affidavit Executed by L. Trosman, GNF-A, for Attachment 1 to GNRO-2013/00050 Dated 7/2/2013
Project stage: Withholding Request Acceptance
2013-01-02
[Table View] |
Acceptance Review Email, License Amendment Request, Revise Criticality Safety Analysis and Technical Specification 4.3.1, Criticality, and Delete Spent Fuel Pool Loading Criteria License Condition| ML112770062 |
| Person / Time |
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| Site: |
Grand Gulf  |
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| Issue date: |
10/03/2011 |
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| From: |
Wang A
Plant Licensing Branch IV |
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| To: |
Perino C, Burford F, Coulter D, Rolonda Jackson
Entergy Operations |
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| Wang, A B, NRR/DORL/LPLIV, 415-1445 |
| References |
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| TAC ME7111 |
| Download: ML112770062 (2) |
|
Text
From:
Wang, Alan Sent:
Monday, October 03, 2011 5:15 PM To:
'Perino, Christina'; 'COULTER, DENNIS M'; 'JACKSON, RITA R'; BURFORD, FRANCIS G Cc:
Lent, Susan; Burkhardt, Janet
Subject:
Acceptance of Grand Gulf Nuclear Station License Amendment Reqest Regarding Criticality Safety Analysis and Technical Specification 4.3.1 (ME7111)
By letter dated September 9, 2011 (Agencywide Documents Access and Management System (ADAMS)
Accession No. ML112521287), Entergy Operations, Inc. (Entergy, the licensee) requested an amendment to the Facility Operating License for the Grand Gulf Nuclear Station, Unit 1 (GGNS). The proposed license amendment request (LAR) includes: 1) a revision to the criticality safety analysis (CSA) for the spent fuel and new fuel storage racks; 2) additional requirements for the spent fuel and new fuel storage racks in Technical Specification (TS) 4.3.1, Criticality; and 3) deletion of the spent fuel pool loading criteria Operating License condition. The supporting TS Bases will also be revised.
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