U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1 Page: 1-18
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"To ensure appropriate limitations to long-term ef-
fects on the population as a whole, the criteria set forth
a 2,000,000 man-rem whole body limitation on the exposure
to the total population in all three zones surrounding the
reactor for the duration of the accident. Because of the
inherent mobility of a shipboard reactor, the duration of
the accident is taken to be 24 hours maximum.
"It is this very mobility, however, that makes it
necessary to consider the varying position of the reactor
with respect to the port environment. Thus, irrespective
of an acceptable zone boundary based on individual expo-
sures, the total population dose level should also be met
at all times."
18.104.22.168 Other Aspects of the Criteria
In view of the many unique differences between siting a stationary
power reactor and berthing a nuclear merchant vessel, the ship site cri-
teria set forth in some detail the conditions for port entry and the ar-
rangements that must be made. Such conditions and arrangements implement
the general objectives of the criteria and ensure their attainment.
The specified conditions for port entry18 include the following:
1. invitation from port authorities,
2. evaluation of environmental conditions,
3. evaluation of port emergency capabilities,
4. notification of all organizations involved,
5. screening of suitable berths,
6. evaluation of access and egress routes,
7. preparation of detailed accident analysis,
8. availability of tugboats,
9. testing of emergency equipment,
10. approval of emergency plans,
11. limitations on shipboard visitors,
12. reporting and approval of above factors.
In addition to the above conditions for port entry, the ship site
criteria 8 give 24 "additional measures applied to initial operations."
These additional measures are specific provisions with respect to the
calculation of the specified zones or operating procedures and accident
assumptions that would, in effect, introduce extreme safety in the opera-
tion of the vessel and extreme conservatism in the calculation of the
exposure that might result from the maximum credible accident. The addi-
tional measures to be applied for initial operations are as follows:
1. use actual reactor power history,
2. take no credit for emergency cooling,
3. assume 50% iodine plateout in the containment vessel only,
4. assume containment-vessel leakage rate to be 2.5% per day,
5. assume iodine filter efficiency to be 99%,
6. take no credit for variable wind direction over the 24-hr period,
7. take no credit for other than inversion conditions over the 24-hr
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Cottrell, William B. & Savolainen, A. W. U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1, report, August 1965; Oak Ridge, Tennessee. (https://digital.library.unt.edu/ark:/67531/metadc101033/m1/46/: accessed March 21, 2019), University of North Texas Libraries, Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.