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ES&H
Manual Radiation Control Supplement |
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Appendix 2B Contamination Control Limits |
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Summary
of Contamination Limits1
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Nuclide |
Removable2,4 (dpm/100 cm2) |
Total
(Fixed + Removable)2,3 (dpm/100 cm2) |
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U-natural, U-235, U-238 and associated decay products |
1,0007 |
5,0007 |
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Transuranics,
Ra-226, Ra-228, Th-230, Th-228, Pa-231, Ac-227, I-125, I-129 |
20 |
500 |
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Th-nat,
Th-232, Sr-90, Ra-223, Ra-224, U-232, I-126, I-131, I-133 |
200 |
1,000 |
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Beta-gamma emitters (nuclides with decay modes other than alpha
emission or spontaneous fission) except Sr-90, Be-7 and others noted above.5 |
1,000 |
5,000 |
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Tritium and Special Tritium Compounds (STC)6 |
10,000 |
See
Note 6 |
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Be-78 |
30,000 |
30,000 |
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Notes: 1.
The values in this table, with the
exception noted in footnote 6 below, apply to radioactive contamination
deposited on, but not incorporated into the interior or matrix of, the
contaminated item. Where surface
contamination by both alpha- and beta-gamma-emitting nuclides exists, the
limits established for alpha- and beta-gamma-emitting nuclides apply independently. 2.
As used in this table, dpm (disintegrations per minute) means the rate of
emission by radioactive
material as determined by correcting the counts per
minute observed by an appropriate detector for background, efficiency, and
geometric factors associated with the instrumentation. 3.
The levels may be averaged over one
square meter provided the maximum surface activity in any area of 100 cm2
is less than three times the value specified.
For purposes of averaging, any square meter of surface shall be
considered to be above the surface contamination value if: (1) from
measurements of a representative number of sections it is determined that the
average contamination level exceeds the applicable value; or (2) it is
determined that the sum of the activity of all isolated spots or particles in
any 100 cm2 area exceeds three times the applicable value. 4.
The amount of removable radioactive
material per 100 cm2 of surface area
should be determined by swiping the area with dry filter or soft absorbent
paper, applying moderate pressure, and then assessing the amount of radioactive
material on the swipe with an appropriate
instrument of known efficiency. (Note
- The use of dry material may not be appropriate for tritium.) When removable contamination on objects of surface area less than 100 cm2
is determined, the activity per unit area shall be based on the actual area
and the entire surface shall be wiped.
It is not necessary to use swiping techniques to
measure removable contamination levels if direct
scan surveys indicate that the total residual surface contamination levels
are within the limits for removable contamination. 5. This category of radionuclides includes mixed fission products, including
the Sr-90 that is present in them. It
does not apply to Sr-90 that has been separated from the other fission
products or mixtures where the Sr-90 has been enriched. 6. Tritium contamination may
diffuse into the volume or matrix of materials. Evaluation of surface contamination shall
consider the extent to which such contamination may migrate to the surface in
order to ensure the surface contamination value provided in this table is not
exceeded. Once this contamination
migrates to the surface, it may be removable, not fixed; therefore, a “Total”
value does not apply. In certain
cases, a “Total” value of 10,000 dpm/cm2
may be applicable either to metals of
the types from which insoluble special tritium compounds are formed,
that have been exposed to tritium, or
to bulk materials to which insoluble tritium compound particles are fixed to
a surface. 7. These limits apply only to the
alpha emitters within the respective decay series. 8. For use when Be-7 is suspected
or known to be the primary constituent in the contamination. This limit applies to use of equipment and
items in Controlled Areas only. Items
released from the Controlled Area shall meet applicable DOE requirements for release. Locations known to have Be-7 contamination
above the limits for beta-gamma emitters shall be identified and posted, marked or labeled to warn individuals not to enter
without the proper radiological control authorization. See exemption decision letter, June 8, 1998. |
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ISSUING
AUTHORITY |
CHAPTER
AUTHOR |
APPROVAL
DATE |
EFFECTIVE
DATE |
EXPIRATION
DATE |
REV. |
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RadCon Dept |
07/01/10 |
07/01/10 |
07/01/13 |
4 |
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