water Reactors, " GE Hitachi Nuclear Energy (GEH) is submitting this report to document any emergency core cooling system (ECCS) evaluation model changes or errors that affect the temperature calculation for the ESBWR Standard Plant Design. This is the first annual report for the ESBWR Standard Plant Design as submitted in letter number MFN 10-352 (Reference 1) dated December 2, 2010 and it documents that no changes have occurred. The information included in this letter is generic and is expected to apply to all COL applications referencing the ESBWR Design Certification Application. By copy of this letter, COL Applicants are hereby notified of any changes or errors in the ESBWR Standard Design PCT as required by 10 CFR 50.46(a)(3)(iii...
Loss-of-coolant accidents (LOCA) are postulated accidents that would result from the loss of reactor...
RAI Number 6.3-88 Enclosure 1 contains the GE Hitachi Nuclear Energy (GEH) response to the subject N...
The purpose of this letter is to provide a status of the NRC staffs review of the hydrodynamic load ...
The purpose of this letter is to provide the annual report of changes or errors discovered in the Em...
In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for li...
The purpose of this letter is to report the impact of changes or errors in the emergency core coolin...
The purpose of this letter is to report the impact of changes or errors in the emergency core coolin...
The NRC staff requested that GE-Hitachi Nuclear Energy (GEH) evaluate the potential non-conservatism...
accordance with 10 CFR 50.46(a)(3)(ii) Ladies and Gentlemen: In accordance with 10 CFR 50.46(a)(3)(i...
In accordance with 10CFR50.46 (a)(3)(ii), Grand Gulf Nuclear Station (GGNS) is required to report to...
The RSB reviews the information presented in the applicant's safety analysis report (SAR) regar...
This section describes the design bases, system design, performance evaluation, testing, and inspect...
Letter No. 231- Related To ESBWR Design Certification Application- RAI Number 14.3-399 The purpose o...
Pursuant to 1OCFR50.46(a)(3)(ii), Entergy Operations, Inc. (EOI) hereby submits for the Waterford 3 ...
Other written product issued by the General Accounting Office with an abstract that begins "Pursuant...
Loss-of-coolant accidents (LOCA) are postulated accidents that would result from the loss of reactor...
RAI Number 6.3-88 Enclosure 1 contains the GE Hitachi Nuclear Energy (GEH) response to the subject N...
The purpose of this letter is to provide a status of the NRC staffs review of the hydrodynamic load ...
The purpose of this letter is to provide the annual report of changes or errors discovered in the Em...
In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for li...
The purpose of this letter is to report the impact of changes or errors in the emergency core coolin...
The purpose of this letter is to report the impact of changes or errors in the emergency core coolin...
The NRC staff requested that GE-Hitachi Nuclear Energy (GEH) evaluate the potential non-conservatism...
accordance with 10 CFR 50.46(a)(3)(ii) Ladies and Gentlemen: In accordance with 10 CFR 50.46(a)(3)(i...
In accordance with 10CFR50.46 (a)(3)(ii), Grand Gulf Nuclear Station (GGNS) is required to report to...
The RSB reviews the information presented in the applicant's safety analysis report (SAR) regar...
This section describes the design bases, system design, performance evaluation, testing, and inspect...
Letter No. 231- Related To ESBWR Design Certification Application- RAI Number 14.3-399 The purpose o...
Pursuant to 1OCFR50.46(a)(3)(ii), Entergy Operations, Inc. (EOI) hereby submits for the Waterford 3 ...
Other written product issued by the General Accounting Office with an abstract that begins "Pursuant...
Loss-of-coolant accidents (LOCA) are postulated accidents that would result from the loss of reactor...
RAI Number 6.3-88 Enclosure 1 contains the GE Hitachi Nuclear Energy (GEH) response to the subject N...
The purpose of this letter is to provide a status of the NRC staffs review of the hydrodynamic load ...