NUREG-1537, Part 2 - NRC

THE FACILTIY
Applicants are expected to use pertinent information from these and other reactors
in their design, and the reviewer should compare'the submitted information with
the referenced facility designs. Areas of the SAR that may be reviewed by
comparison or reference to similar facilities could include the following:
Chapter 4, "Reactor Description," and Chapter 13 for'the bases of NRC's
acceptance of fuel performance [e.g.,- SPERT, the Oak Ridge Research
Reactor (ORRR), the system for nuclear auxiliary power (SNAP), the
General Atomics reactor for training and isotope production (TRIGA), the
MTR, and the advanced test reactor (ATR)]
* Chapters 4 and 13 forthe bases for reactor core critical size and geometry
[e.g., BSF, TRIGA, CP-5, the Argonne nuclear assembly for CP-1 I
(Argonaut), and SPERT]
* Chapter 6, "Engineered Safety Features," for the bases of accident
mitigation systems (most reactor types)
* Chapter 7, "Instrumentation and Control Systems," for thie bases of
redundancy and diversity in instruments and controls, including scram
(reactor shutdown) systems [e.g., BSF, TRIGA, Omega West Reactor
(OWR), MTR, and CP-5]
* other specific license conditions acceptable to NRC of other facilities that
demonstrate acceptable technical performance (previously licensed facilities
with similar thermal power level, similar fuel type, and similar siting
considerations)
Acceptance Criteria
The acceptance criteria for the comparison of this facility with similar facilities
include the following:'
* The comparisons should show that the proposed facility would not exceed
the safety envelope of the similar facilities.
* There should be reasonable 'assurance that radiological exposures of the
public would not exceed the regulations and the guidelines of the proposed
facility ALARA program.
Review Procedures
The reviewer should confirm that the characteristics of any facilities compared
with the proposed facility are similar and relevant. The reviewer should verify that
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