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PRELIMINARY SAFETY ANALYSIS REPORT (PSAR)for N.E. 267
The term project report for N.E. 267 should contain the following:
Chapter 1. Introduction. How you intend to meet the NRC Policy on Advanced Reactors.
Chapter 2. Description of the Plant and the Site. A brief description of the principle plant safety features, the containment/confinement, and any site specific mitigating features. Do the features meet the General Design Criteria? A table, such as that in NUREG 1150, should be used in the text and in your formal presentation.
Chapter
3. Design Basis Accidents (DBA).
Describe one or two DBA's for each accident class, any postulated off-site
releases, and how they meet the intent of 10 CFR 100, the Reactor Site
Criteria.
Chapter 4. Severe Accidents.
Discuss the NRC Policy on Severe Accidents and how it pertains to your
design/site. Describe any beyond design basis accidents and any design
features to cope with them. Discuss accident progression and containment/confinement
modes and release categories.
Chapter 5. Risk Assessment, Risk Management and Safety Goals. What are the risks (IPE) and how do they stack up against the NRC Policy on Safety Goals. What severe accident prevention and mitigation schemes are or can be implemented, and how can they be evaluated?
Chapter 6. Seismic Safety. What additional design or operational features are required for your plant in order to construct it on the Diablo Canyon Site? Why? What are the seismic margins? What is the seismic risk (IPEEE)?
Chapter 7. Summary and Conclusions. Why you believe this reactor can be constructed and operated at the Diablo Canyon Site. Or, why you believe this reactor cannot be constructed and operated on this site. In either case, what further analyses are required, if any?