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14 декабря, 2021
During the licensing process at the times of the construction and operating license applications, evaluations of the reactor system safety must be submitted for consideration. They are called the Preliminary Safety Analysis Report (PSAR) and the Final Safety Analysis Report (FSAR).
There is approximately a three-year gap between them so that the analysis can be revised and updated if required (see Fig. 6.6). The national research and development safety program is so organized that there will be new information constantly appearing, which may enable the plant to be better optimized rather than to have it overemphasize safety.
The production of these safety analysis reports is standardized according to 10 CFR 50 and some interpretive documents (7b). This standardization allows the licensing authorities to relate safety evaluations to each other and to check rapidly whether all the required information is present. The safety analysis document is divided into separate parts:
I. |
Introduction and summary |
II. |
Site |
III. |
Reactor |
IV. |
Reactor coolant system |
V. |
Containment system |
VI. |
Engineered safeguards |
VII. |
Instrumentation and control |
VIII. |
Electrical systems |
IX. |
Auxiliary and emergency systems |
Section |
X. Steam and power conversion systems
XI. Radioactive wastes
XII. Conduct of operations
XIII. Initial tests and operation
XIV. Safety analysis
XV. Technical specifications
Although this format is not strictly adhered to by all applicants, the formats of most PSARs are approximately the same. It is, however, possible that this format may vary in the future with the advent of a standardized SAR with even standard sections and wordings.