NUREG-1537, Part 2 - NRC

ENaNEERED SAFT FEATuRES
derived from the accidents analyzed. The reviewer should compare the dispersion
and diffusion of released airborne iadionuclides discussed in SAR Chapters 6 and
13 with methods described in SAR Chapter 11 as applicable.
Evalualion Findings
This section'of the SAR should contain sufficient information to support the
following types of conclusions, which Will be included Minthe safety evaluation
report:
* -The scenarios for all potential accidents at the reactorfadility have been
analyzed by the applicant and reviewed by the'staff. Mitigation of
consequences by a confinement system has b;een proposed in the SAR
analyses for any accident that could lead to potential uniacceptable
radiological exposures to the public, the facility sta% or'the environment.
The staff has reviewed the designs and functional descriptions of the
confinement ESF; they reasonably ensure that the consequences will be
limited to the levels found acceptable in the accident analyses of Chapter 13
of the SAR.
* The designs and functional descriptions of the confinement ESF reasonably
ensure that control of radiological exposures or releases during normal
operation will not be degraded by the ESF.
* The radiological consequences from accidents to the public, the
environment, and the facility staff will be reduced by the confinement ESF
'to values that do not exceed the applicable limits of IO CFR Part 20 for
research reactors, orIO CFR Part 100 for test'reactors, -and in both cases
are as far below'the'regulatory limits as can be reasonable achieved.
6.2.2 Containment
If the HVAC and any air exhaust or liquid release systems associated with the.
containment are designed to change configuration or operating mode mi response
to a potential accident analyzed in Chapter 13 and thereby mitigate its
consequences, they should be considered part of the con'taiment ESF and should
be discused in this section of the SAR.
Because the potential risk'to the public from accidents at non-power reactors is
generally low, most non-power reactors can'be 'designed, sited, and operated so
'that a cofitaiment is not required for normal operation or accident mitigation.
However, the safety analyses may'show that a confiue'ment does not provide
sufficient mitigation and a containment is necessary.
REV 0,2196 6-7 STANDARD REVIEW PLAN
REV 0, 2/96 6-7 - -1 .1 STANDARDREviEwPLAN