NUREG-1537, Part 2 - NRC

CHAPT6
* The design that should reduce below regulatory limits the potential J
radiological exposures to the facility staff and members of the public for the
accidents discussed at the beginning of this chapter. Any additional
reduction in potential radiological exposures below the regulatory limits is
desirable and should be a design goal if it can be reasonably achieved.
* The containment should not interfere with either normal operation or
reactor shutdown.
* The design features and surveillance program should ensure that the
containment will be available and operable if the ESF system is needed.
* The design of the containment should not transfer undue radiological risk
to the health and safety of the public in order to reduce potential exposures
to the facility staff.
* The I&C system of the containment ESF system should be as basic and fail
safe as possible. They should be designed to operate in the environment
created by the accident scenario.
* The discussions should identify operational limits, design parameters, and
surveillances to be included in the technical specifications.
Review Procedures
The reviewer should review the accident scenarios and the applicable design bases
for a containment ESF and the design and functional features of the ESF and the
mitigating effects on the radiological consequences evaluated The net projected
radiological exposures should be compared with the limits of 10 CFR Parts 20 or
100 to determine if the design is acceptable.
Evalualion Findings
This section of the SAR should contain sufficient informnation to support the
following types of conclusions, which will be included in the safety evaluation
report:
* The applicant has identified a potential or maximum hypothetical accident
as a result of which projected exposures to the public without containment
would be greater than acceptable limits.
* The design and functional features proposed for a containment reasonably
ensure that exposures will be reduced below the limits of 10 CFR Part 20
for research reactors, or 10 CFR Part 100 for test reactors, with an
NUR.EG.1537, PT 2 6-10 REv 0.2/96
NUREG- 1537, PART 2 6-10 REV 0, 2J96