LR-N17-0034, Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 1, Introduction and General Description of Plant

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Salem Generating Station, Units 1 & 2, Revision 29 to Updated Final Safety Analysis Report, Section 1, Introduction and General Description of Plant
ML17046A235
Person / Time
Site: Salem  PSEG icon.png
Issue date: 01/30/2017
From:
Public Service Enterprise Group
To:
Office of Nuclear Reactor Regulation
Shared Package
ML17046A230 List: ... further results
References
LR-N17-0034
Download: ML17046A235 (2)


Text

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  • SECTION 1 INTRODUCTION AND GENERAL DESCRIPTION OF PLANT 1.1 PROJECT IDENTIFICATION This Updated Final Safety Analysis Report is submitted pursuant to the requirements of 10CFR50.71 by Public Service Electric and Gas Company (PSE&G) for the two nuclear power units at its Salem Generating Station. PSE&G and Westinghouse Electric Corporation have jointly participated in the design and construction of each unit. On August 21, 2000, the operating licenses for Salem Units 1 & 2 were transferred from PSE&G to PSEG Nuclear LLC. Each unit employs a pressurized water reactor nuclear steam supply system furnished by Westinghouse which is similar in design concept to several other projects licensed by the Nuclear Regulatory Commission. The only systems shared by the two units are Compressed Air, the Control Room Area intake air radiation monitors, parts of the Control Room Area Ventilation System, bulk Nitrogen Supply, Demineralized Water, and the Solid Radwaste Handling System. There are a minimum of shared components; chemical drain and laundry hot shower tanks and pumps and the 20,000 barrel Bulk Fuel Oil Storage Tank are the only components in common. The licensed core power for both units is 3459 MWt. The approximate values for gross and net electrical outputs are 1178 MWe and 1135 MWe respectively for Unit 1 and 1182 MWe and 1139 MWe respectively for Unit 2. The reactors are expected to be capable of outputs of approximately 3570 MWt, which corresponds to the valves-wide-open rating of the turbine generators of 1209 MWe gross and 1163 MWe net for Unit 1 and 1220 MWe gross and 1174 MWe net for Unit 2. The containment and engineered safety features for both units have been designed and evaluated at the maximum power rating of 3570 MWt. Loss-of-coolant accidents and those postulated accidents offsite dose consequences have been analyzed at the power rating of 3570 MWt. 1.1-1 SGS-UFSAR Revision 19 November 19, 2001 I I The remainder of Section 1 of this summarizes the features and criteria of the nuclear units, design out the similarities and differences with nY'C.CH:,,-ri zed water nuclear to other and basic power the same features as the Salem Station. Sec::icn 2 contains a description and evaluation of the site and environs, supporting the suitability of the site for a nuclear plant of the size and type described. Section 3 discusses the identification, description, and discussion of t:Ie archjt.ec::Jral and engineering design of structures, and to safety. The reactor is described in Section 4. Section 5 discusses the Reactor Coolant and related systems, and Sections 6 1 the emergency and systems. Section 13 describes the Company's program for organization and training of plan:: personnel. Section 14 contains an outline and description of the initial tests and operations associated with plant startup. Section 15 is a safety evaluation summarizing the analyses which demonstrate the features. SGS-IJFSAR of the Reactor Protection The consequences of various set forth in the and 10CFR50.67, Accident Source Term. 1.1-2 and the accidents are within the Commission's Rules and Revision 25 October 26, 2010