NUREG-1537, Part 2 - NRC

CHAPTER 3
Surveillance to verify design functions of associated systems, including
applicable instrumentation and controls, should be specified in the technical
specifications, and other appropriate SAR chapters should be referenced
for details. For example, if a seismically induced scram is a required
instrumentation and control protective system, the applicant should
propose and justify surveillance of this reactor trip function.
Review Procedures
The reviewer should examine the site description and historical data to ensure that
appropriate seismic inputs have been considered in the analysis of the structures,
systems, and components discussed in the SAR. For any structure, system, or
component damaged, the SAR should contain analyses that show the extent to
which potential seismic damage impairs the safety function of the structure,
system, or component. The evaluation of seismic damage should be coordinated
with the Chapter 13 accident analyses of seismic events or should be shown to be
bounded by other accidents considered in Chapter 13.
Acceptable analysis criteria are established in the section on geology and
seismology in American National Standards Institute/American Nuclear Society
(ANSIANS) 15.7.
With regard to seismic design, Section 3.2(2) of ANSI/ANS 15.7 states,
'(R)eactor safety related structures and systems shall be seismically designed
such that any seismic event cannot cause an accident which will lead to dose
commitments in excess of those specified in 3. L' "Any seismic event' should be
the maximum historical intensity earthquake in accordance with the guidance on
the design-basis earthquake in Section 3.1.2.1 of International Atomic Energy
Agency document IAEA-TECDOC403. This LAEA document gives additional
guidance and references IAEA-TECDOC-348, which contains guidance on the
seismic design of structures, systems, and components.
With regard to the allowed dose commitments for seismic events specified in
Section 3.1 of ANSI/ANS 15.7, the terms 'site boundary," "rural zone," and
"urban boundary' are used. For most NRC-licensed non-power reactors, "rural
zone' should not be used and 'urban boundary' should be assumed to begin at the
'site boundary." However, given applicable site characteristics and emergency
preparedness requirements, the criteria as specified in Section 3.1 of ANSI/
ANS 15.7 could be used.
The above guidance is applicable to research reactors licensed by NRC. For test
reactors the requirements of 10 CFR Part 100 must be applied. The guidance and
criteria of 10 CFR Part 100 are complete and are adequate for assessing test
reactors.
NUREG-1537,1'ART2 3.6 REV. 0.2/96
NUREG-1537,PART2 3-6 REV. O. 2/96
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