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Final Safety Evaluation Report Related to
Certification of the AP1000 Standard Design (NUREG-1793)
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Publication Information
Manuscript Completed: September 2004
Date Published: September 2004
Division of Regulatory Improvement Programs
Office of Nuclear Reactor Regulation
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
Availability
Notice
Abstract
This final safety evaluation report documents the technical review of
the AP1000 standard
nuclear reactor design by the U.S. Nuclear Regulatory Commission (NRC).
Westinghouse
Electric Company submitted the application for the AP1000 design on March
28, 2002, in
accordance with Title 10 of the Code of Federal Regulations (10 CFR)
Part 52, Subpart B,
“
Standard Design Certifications,” and 10 CFR Part 52, Appendix O, ”Standardization
of Design:
Staff Review of Standard Designs.”
The AP1000 nuclear reactor design is a pressurized water reactor with
a power rating of 3415
megawatts thermal (MWt) and an electrical output of at least 1000 megawatts
electric (MWe).
The AP1000 design contains many features that are not found in current
operating reactors.
For example, a variety of engineering and operational improvements provide
additional safety
margins and address the Commission’s severe accident, safety goal,
and standardization policy
statements. The most significant improvement to the design is the use
of safety systems that
employ passive means, such as gravity, natural circulation, condensation
and evaporation, and
stored energy, for accident mitigation. These passive safety systems
perform safety injection,
residual heat removal, and containment cooling functions.
Some features of the AP1000, compared to currently operating reactors,
include a longer
reactor core design, a larger pressurizer, an in-containment refueling
water storage tank, an
automatic depressurization system, a revised main control room design
with a digital
microprocessor-based instrumentation and control system, hermetically
sealed canned reactor
coolant pump motors mounted to the steam generator, and increased battery
capacity. In
addition, the facility is designed for a 60-year life, which exceeds
the projected 40-year
combined operating license period, and employs structural modules.
On the basis of its evaluation and independent analyses, as set forth
in this report, the NRC
staff concludes that Westinghouse’s application for design certification
meets the requirements
of 10 CFR Part 52, Subpart B, that are applicable and technically relevant
to the AP1000
standard design. Appendix G includes a copy of the report by the Advisory
Committee on
Reactor Safeguards, as required by 10 CFR 52.53.
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