The purpose of this letter is to report the impact of changes or errors in the emergency core cooling system (ECCS) evaluation models used by Westinghouse Electric Company. A description of the changes to the Westinghouse small-break LOCA and large-break LOCA ECCS evaluation models for 2009 is provided as an attachment. Westinghouse has categorized these changes or errors into two separate groups: * Non-Discretionary Changes * Discretionary Changes This annual notification is being provided since it affects information previously submitted in Westinghouse topical reports. It is noted that plant-specific peak cladding temperature (PCT) variations are not addressed in this letter. These should be treated, as appropriate, on a plant-specific b...
hereby reports a significant change in the calculated peak cladding temperature (PCT) for the Duane ...
ANALYSIS METHODOLOGY (TAC NO. MC8427) Dear Mr. Kansler: The Commission has issued the enclosed Amend...
The amendment revises the Appendix A Technical Specifications (TSs) relating to Reactor Coolant Syst...
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 provide the annual report of changes or errors discovered in the Em...
The purpose of this letter is to report the impact of changes or errors in the emergency core coolin...
water Reactors, " GE Hitachi Nuclear Energy (GEH) is submitting this report to document any eme...
The purpose of this letter is notify the NRC of a change in the WBN ECCS evaluation models for peak ...
accordance with 10 CFR 50.46(a)(3)(ii) Ladies and Gentlemen: In accordance with 10 CFR 50.46(a)(3)(i...
Pursuant to 1OCFR50.46(a)(3)(ii), Entergy Operations, Inc. (EOI) hereby submits for the Waterford 3 ...
In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for li...
Other written product issued by the General Accounting Office with an abstract that begins "Pursuant...
In accordance with 10CFR50.46 (a)(3)(ii), Grand Gulf Nuclear Station (GGNS) is required to report to...
This section describes the design bases, system design, performance evaluation, testing, and inspect...
Loss-of-coolant accidents (LOCA) are postulated accidents that would result from the loss of reactor...
hereby reports a significant change in the calculated peak cladding temperature (PCT) for the Duane ...
ANALYSIS METHODOLOGY (TAC NO. MC8427) Dear Mr. Kansler: The Commission has issued the enclosed Amend...
The amendment revises the Appendix A Technical Specifications (TSs) relating to Reactor Coolant Syst...
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 provide the annual report of changes or errors discovered in the Em...
The purpose of this letter is to report the impact of changes or errors in the emergency core coolin...
water Reactors, " GE Hitachi Nuclear Energy (GEH) is submitting this report to document any eme...
The purpose of this letter is notify the NRC of a change in the WBN ECCS evaluation models for peak ...
accordance with 10 CFR 50.46(a)(3)(ii) Ladies and Gentlemen: In accordance with 10 CFR 50.46(a)(3)(i...
Pursuant to 1OCFR50.46(a)(3)(ii), Entergy Operations, Inc. (EOI) hereby submits for the Waterford 3 ...
In accordance with 10 CFR 50.46, "Acceptance criteria for emergency core cooling systems for li...
Other written product issued by the General Accounting Office with an abstract that begins "Pursuant...
In accordance with 10CFR50.46 (a)(3)(ii), Grand Gulf Nuclear Station (GGNS) is required to report to...
This section describes the design bases, system design, performance evaluation, testing, and inspect...
Loss-of-coolant accidents (LOCA) are postulated accidents that would result from the loss of reactor...
hereby reports a significant change in the calculated peak cladding temperature (PCT) for the Duane ...
ANALYSIS METHODOLOGY (TAC NO. MC8427) Dear Mr. Kansler: The Commission has issued the enclosed Amend...
The amendment revises the Appendix A Technical Specifications (TSs) relating to Reactor Coolant Syst...