Letter Sequence Acceptance Review |
|---|
TAC:ME4679, Clarify Application of Setpoint Methodology for LSSS Functions (Open) |
Initiation
- Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request, Request
- Acceptance
- Supplement, Supplement
Administration
- Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance, Withholding Request Acceptance
- Meeting
Results
Other: ENOC-11-00021, Entergy Operations, Inc., Entergy Nuclear Operations, Inc., Submittal of Planned Reorganization of Quality Control Reporting Relationship, GNRO-2012/00150, Final Report for Replacement Steam Dryer, GNRO-2017/00039, Steam Dryer Visual Inspection Results for the First Two Scheduled Refueling Outages, ML111720830, ML112560396, ML112790370, ML12167A257, ML12167A269, ML12170B091, ML12177A287, ML13108A217, NRC-2012-0105, Environmental Assessment and Finding of No Significant Impact Related Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
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Notice of Forthcoming Conference Call with Indiana Michigan Power Company to Discuss the Proposed Responses to Requests for Additional Information Associated with GL 2004-02 for the D. C. Cook Nuclear Plant
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GE-Hitachi Nuclear Energy Americas LLC - Affidavit of Edward Schrull Withholding from Public Disclosure Proprietary Report NEDC-33477P
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NEDO-33477, Revision 0, Safety Analysis Report for Grand Gulf Nuclear Station Constant Pressure Power Uprate
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License Amendment Request Extended Power Uprate
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NEDO-33601, Revison 0, Engineering Report Grand Gulf Replacement Steam Dryer Fatigue Stress Analysis Using Pble Methodology. Cover Through Appendix a
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ML1030102002010-11-0909 November 2010
Supplemental Information Needed for Acceptance of License Amendment Request, Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Megawatts Thermal
Project stage: Acceptance Review
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Supplemental Information, License Amendment Request, Extended Power Uprate
Project stage: Supplement
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Supplemental Information License Amendment Request, Extended Power Uprate
Project stage: Supplement
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Project stage: Withholding Request Acceptance
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Request for Withholding Information from Public Disclosure, 11/19/10 Affidavit Executed by E. Schrull, GE-Hitachi, Regarding NEDC-33621P
Project stage: Withholding Request Acceptance
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E-mail, Request for Additional Information Instrument and Controls, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
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E-mail, Request for Additional Information Fire Protection, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1102701872011-01-27027 January 2011
Request for Additional Information, Emcb Non-Steam Dryer Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
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E-mail, Request for Additional Information, Vessels and Internal Integrity Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
GNRO-2011/00005, Core Operating Limits Report Cycle 18 Mid-Cycle Revision2011-02-0808 February 2011
Core Operating Limits Report Cycle 18 Mid-Cycle Revision
Project stage: Request
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Email, Request for Additional Information, Nrr/Dci/Csgb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
GNRO-2011/00007, Request for Additional Information Regarding Extended Power Uprate2011-02-23023 February 2011
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Request for Additional Information Regarding Extended Power Uprate
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E-mail, Request for Additional Information, Nrr/Dirs/Ihpb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
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E-mail, Request for Additional Information, Nrr/Dra/Apla Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
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Request for Withholding Information from Public Disclosure, 8/20/10 Affidavit Executed by E. Schrull, GEH, for NEDC-33477P
Project stage: Withholding Request Acceptance
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Email Request for Additional Information, Round 2, Nrr/Dci/Cvib Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
ML1105504752011-03-0202 March 2011
Request for Additional Information (Redacted), Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
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Request for Additional Information Regarding Extended Power Uprate
Project stage: Request
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Email, Dose Assessment Branch, Request for Additional Information, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
Project stage: RAI
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Email, Request for Additional Information, Nrr/Dss/Srxb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
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Email, Request for Additional Information, Nrr/De/Eeeb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
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Request for Additional Information, Nrr/De/Eeeb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
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Email, Request for Additional Information, Nrr/Dss/Snpb Review, Amendment Request for Extended Power Uprate to Increase the Maximum Reactor Core Power Operating Limit from 3898 to 4408 Mwt
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Project stage: RAI
2011-03-01
[Table View] |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 9, 2010 Vice President, Operations Entergy Operations, Inc.
Grand Gulf Nuclear Station P.O. Box 756 Port Gibson, MS 39150
SUBJECT:
GRAND GULF NUCLEAR STATION, UNIT 1 - SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF LICENSE AMENDMENT REQUEST FOR AN EXTENDED POWER UPRATE (TAC NO. ME4679)
Dear Sir or Madam:
By letter dated September 8, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102660409), Entergy Operations, Inc. (Entergy, the licensee),
submitted a license amendment request for the Grand Gulf Nuclear Station, Unit 1. The proposed amendment will increase the maximum reactor core power operating limit from 3,898 megawatts thermal (MWt) to 4,408 MWt. 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. 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 ofFederal 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 the information delineated in the enclosure to this letter is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment.
In order to make the application complete, the NRC staff requests that Entergy supplement the application to address the information requested in the enclosure by December 1, 2010. This will enable the NRC staff to begin its detailed technical review. If the information responsive to the NRC staff's request is not received by the above date, the application will not be accepted for review pursuant to 10 CFR 2.101, and the NRC will cease its review activities associated with the application. If the application is subsequently accepted for review, you will be advised of any further information needed to support the staff's detailed technical review by separate correspondence.
- 2 The information requested and associated time frame in this letter were discussed with Mr. Jerry Burford of your staff on October 25, 2010.
If you have any questions, please contact me at (301) 415-1445.
Sincerely,
(~ v Alan Wang, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-416
Enclosure:
As stated cc w/encl: Distribution via Listserv
SUPPLEMENTAL INFORMATION NEEDED FOR ACCEPTANCE OF LICENSE AMENDMENT REQUEST BY THE OFFICE OF NUCLEAR REACTOR REGULATION EXTENDED POWER UPRATE GRAND GULF NUCLEAR STATION, UNIT 1 DOCKET NO. 50-416 By letter dated September 8,2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML102660409), Entergy Operations, Inc. (Entergy, the licensee),
submitted a license amendment request for an extended power uprate (EPU) for the Grand Gulf Nuclear Station, Unit 1. The proposed amendment will increase the maximum reactor core power operating limit from 3,898 megawatts thermal (MWt) to 4,408 MWt. As part of the acceptance review process the U.S. Nuclear Regulatory Commission (NRC) staff has concluded that the information delineated below is necessary to enable the staff to make an independent assessment regarding the acceptability of the proposed amendment request in terms of regulatory requirements and the protection of public health and safety and the environment:
- 1)
Equipment Qualification (EQ) evaluation of all Group II items should completed including determination regarding remaining life and required modification to the components or replacement of them. In case of replacement, please identify the replacement components and discuss how the replacement components will satisfy the EQ rule under EPU conditions.
- 2)
Group III items need to be replaced prior to EPU implementation. Please identify the replacement components and discuss how the replacement components will satisfy the EQ rule under EPU conditions.
- 3)
Please provide supplemental information regarding analysis of the Spent Fuel Pool under increased decay heat loads and the analysis of the enhanced ultimate heat sink performance credited in the accident analyses.
- 4)
In Sections 2.8.6.1, "New Fuel Storage," and 2.8.6.2, "Spent Fuel Storage," of its submittal, the licensee cites NEDC-33004P-A, Revision 4, "Constant Pressure Power Uprate," Class III, July 2003, Section 6.3.4 as the basis for demonstrating compliance with 10 CFR Appendix A General Design Criterion 62, "Prevention of criticality in fuel storage and handling." However, NEDC-33004P-A, Section 6.3.4 addresses the increased decay heat load associated with a constant pressure power uprate and does not address criticality. Therefore, there is no information in the licensee's submittal that addresses criticality in fuel storage and handling and the NRC staff has insufficient information to begin its review. The NRC staff requests the licensee provide the nuclear criticality safety analysis that demonstrates compliance with GDC 62.
Enclosure
ML103010200
- via e-mail OFFICE NRRIDORL/PM NRR/DORL/LA DE/EEEB/BC DSS/SXRB/BC DSS/SBPB/BC NRRIDORL/BC NRR/DORL/PM NAME AWang JBurkhardt RMathew (A)'
AUlses' GCasto' MMarkley AWang (NKalyanam for)
DATE 10/28/10 10/28/10 10/22/10 10/28/10 10/28/10 11/9/10 11/9/10
