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OCR for page 199
D
Standards (Limits) Proposed
by Other Organizations
AMERICAN NATIONAL STANDARDS INSTITUTE
AND HEALTH PHYSICS SOCIETY
ANSI/HPS N13.12-1999 Surface and Volume
Radioactivity Standards for Clearance
The Health Physics Society (HPS) Standards Working Group developed this
standard. The standard was consensus balloted1 and approved by the American
National Standards Institute (ANSI) accredited HPS N13 Committee on October
19, 1998. Furthermore, ANSI, Inc., itself approved the standard on August 31,
1999. The standard defines primary (dose) and secondary screening (derived)
criteria.
Primary Dose Criterion
The primary criterion of this standard is to provide for the public health and
safety of an average member of a critical group such that the dose shall be limited
to 10 pSv/yr (1.0 mrem/yr) total effective dose equivalent (TEDE), above back-
ground, for clearance of materials from regulatory control. When justified on a
case-by-case basis, clearance shall be permitted at higher dose levels when it can
be ensured that exposures to multiple sources will be maintained as low as rea-
1A listing of the organizations and government agencies represented on the N13 Committee is
listed in an Appendix to the ANSI/HPS standard.
199
OCR for page 200
200
APPENDIX D
sonably achievable (ALARA) and will provide an adequate margin of safety
below the public dose limit of 1 mSv/yr (100 mrem/yr) TEDE.
Derived Screening Levels
Derived screening levels, above background, for the clearance of solid mate-
rials or items containing surface or volume activity concentrations of radioactive
materials are tabulated in the standard. In that table the radionuclides have been
divided into four groups based on similarity of exposure scenario results, with
screening levels ranging from 0.1 to 100 Bq/cm2 (or Bq/g), depending on the
group considered.2 A generic ALARA process was employed in developing the
derived screening levels. However, based on a detailed ALARA evaluation, it
shall be permissible to derive less restrictive screening levels on a case-by-case
basis using the primary dose criterion.
The standard includes a discussion of the collective dose in relation to the
screening levels. In reality, concentrations in cleared materials will likely average
about an order of magnitude less than the screening levels, which are intended to
define upper bounds. From the qualitative evaluation it is concluded that on the
average, individuals will likely receive no more than the 10 pSv/yr (1.0 mrem/yr)
primary dose criterion because of conservative modeling and assumed maximum
concentrations. Assuming an average U.S. background level of 3.0 mSv/yr (300
mrem/yr), the collective doses to the critical group resulting from clearance of
items using the criterion from this standard will be no more than 0.3 percent of
the dose the same population would receive from natural background radiation in
any one year. The magnitude of the potential collective doses to the critical group
associated with the items in accordance with this standard is so low that addi-
tional ALARA evaluations or analyses, or further reductions in the primary dose
standard, are not deemed necessary.
INTERNATIONAL ATOMIC ENERGY AGENCY
Safety Series No. 89: Principles for the Exemption of Radioactive Sources
and Practices from Regulatory Control
This document was jointly sponsored by the International Atomic Energy
Agency (IAEA) and the Nuclear Energy Agency of the Organization for Eco-
nomic Cooperation and Development and was published in 1988. It is based on
two principles for exemption:
2Surface and Volume Radioactivity Standards for Clearance: An American National Standard,
Health Physics Society Report, ANSI/HPS N13.12-1999.
OCR for page 201
APPENDIX D
201
1. Individual risk must be sufficiently low as not to warrant regulatory con-
cern.
2. Radiation protection, including the cost of regulatory control, must be
optimized.
Two approaches were followed in determining if the level of risk or dose is
trivial;3 first, choose a level of risk and the corresponding dose that is of no
significance to individuals; second, use the exposure to natural radiation, to the
extent that it is normal and unavoidable, as a relevant reference level.
Risk-Based Considerations
It is widely recognized that values of individual risk that can be treated as
insignificant correspond to a level at which individuals, aware of these risks,
would not commit significant resources of their own to reduce them. It is believed
that few people would commit their own resources to reduce an annual risk of
death of 10-5 and that even fewer would take action at an annual level of 10-6. By
considering a rounded risk factor Of 10-2 Sv-i (10-4 remet) for whole-body expo-
sure as a broad average over age and gender, the level of trivial individual effec-
tive dose equivalent would be in the range of 10 to 100 mSv/yr (1 to 10 mrem/
yr,.4
Natural Background Radiation Considerations
The natural background radiation has been estimated to give an average
individual dose of about 2.4 mSv/yr (240 mrem/yr).5 This average conceals a
wide variation due to different concentrations of radioactive materials in the
ground and in building materials, different altitudes, and different habits of people.
About half of this dose is due to radon exposure, which may be controlled. The
other half comes from cosmic rays, terrestrial gamma rays, and radionuclides in
the body for which control is not practical. Individuals do not usually consider
variation in exposure to natural background radiation when considering moving
3The word trivial is used extensively by the IAEA in Vienna and the European commission in
their safety guides when describing an individual effective dose equivalent in the range of lo to 100
mSv/yr (1 to 10 mrem/yr).
4Principles for the Exemption of Radiation Sources and Practices from Regulatory Control, Safety
series No. 89, International Atomic Energy Agency, Vienna, 1988.
5The background radiation varies significantly from country to country and from one location to
another within a country. There are several regions in the world where natural background radiation
gives doses that exceed the normal ranges by factors of 4 to 6. It is reported that no adverse health
effects have been discerned from doses arising from these high natural levels. see, sEIR v, National
Academy Press, Washington, D.C., 1990.
OCR for page 202
202
APPENDIX D
from one location to another or when going on a holiday. IAEA believes it can
therefore be judged that a dose level that is small in comparison with the variation
in natural background radiation can be considered trivial. A figure of whole-body
or effective dose equivalent of the order of one to a few percent of the natural
background, 20 to 100 mSv/yr (2 to 10 mrem/yr), has been suggested.
Conclusion on Individual Related Risk
The IAEA concluded that an individual radiation dose, regardless of its
origin, is likely to be trivial if it is of the order of some tens of microsieverts per
year (some millirems per year). It is noted that this dose corresponds to a few
percent of the annual dose limit for members of the public recommended by the
International Commission on Radiological Protection (ICRP) in 1977 and is much
lower than any upper bound set by competent authorities for practices subject to
regulatory control.
EUROPEAN COMMISSION
Radiation Protection 89: Recommended Radiological Protection Criteria
for the Recycling of Metals from the Dismantling of Nuclear Installations
This document provides recommended radiological protection criteria for
the recycling of metal arising from dismantling nuclear installations. The docu-
ment prepared by the Group of Experts established under the terms of Article 31
of the Euratom Treaty confirms and extends its previous recommendations, made
in IAEA Safety Series 89 of 1988. It has been demonstrated that metals below the
clearance levels specified can be released from regulatory control with negligible
risk, from a radiation point of view, for workers in the metals industry and for the
population at large.
Radiological Protection Criteria
The document references the IAEA recommendation in Safety Series 89 that
an individual dose of some tens of microsieverts is considered trivial and there-
fore the basis for exemption. The Working Group adopted radiation protection
levels of 10 ,uSv/yr (1 mrem/yr) and 1 man-Sv/yr (100 man-rem/yr) of practice
collective dose criteria. In addition, the skin dose was limited to 50 mSv/yr
(5 rem/yr).
Relating the dose received by individuals to a practice, and to the levels of
radioactivity involved in a practice, is difficult because the clearance criteria
must be defined for a largely hypothetical environment. The Working Group
constructed a set of exposure scenarios, which relate the activity content of the
OCR for page 203
APPENDIX D
203
recycled metals to an individual dose. The proposed clearance levels are derived
radioactivity levels from the most critical scenario.
Tables are provided that specify clearance levels for metal scrap recycling
for the radionuclides encountered in decommissioning. A similar table is pro-
vided specifying the more stringent clearance levels for direct reuse of the metal.
AMERICAN NUCLEAR SOCIETY
The American Nuclear Society (ANS) Special Committee on Site Cleanup
and Restoration Standards is responsible for reviewing draft regulations from
federal organizations related to the decommissioning of nuclear facilities and
providing ANS input to the rulemaking process.
The ANS is not in the business of writing standards, although it does write
position papers and makes comments after reviewing rules. As of this date, the
ANS has not endorsed ANSI N13.12. However, in a letter of December 4, 2000,
ANS made the following comments regarding the Department of Energy's
(DOE's) standard:
.
ANS considers the 1 mrem/yr standard to be unreasonably low and with-
out a firm scientific justification.
· Scientific evidence would seem to support a dose limit several times
larger than the proposed 1 mrem/yr.
The ANS is currently working on a draft position paper on the standard for
clearance and expects it to be released in 2002.
INTERNATIONAL COMMISSION ON
RADIOLOGICAL PROTECTION
Publication 60
The ICRP recommends that the maximum permissible dose for occupational
exposure should be 20 mSv/yr (2,000 mrem/yr), averaged over five years (i.e.,
100 mSv total) with a maximum of 50 mSv in any one year. For public exposure,
1 mSv/yr (100 mrem/yr), averaged over 5 years, is the limit. In both categories,
the figures are over and above background levels and exclude medical exposure.
The ICRP proposed apportionment of the total allowable dose from all an-
thropogenic sources of radiation (excluding medical exposures). Hence for radio-
active waste management, authorities could allocate a fraction of the 1 mSv/yr
(100 mrem/yr), to establish an exposure limit for low-level radioactive waste
(LLRW). For example, the Environmental Protection Agency (EPA) in 40 CFR
Part 191 imposed a limit of 0.15 mSv/yr (15 mrem/yr), which is consistent with
the ICRP' s concept of apportionment.
OCR for page 204
204
APPENDIX D
THE EUROPEAN UNION
Basic Safety Standards
The scope of the Basic Safety Standards (BSS) adopted by the European
Union (KU) is defined in terms of practices and only indirectly in terms of
radioactive substances. Justification of any practice involving radioactivity is
required, i.e., determining whether the benefits to individuals and to society from
introducing or continuing the practice outweigh the harm (including radiation
detriment) resulting from the practice. If such practice is deemed justifiable, a
decision is made as to whether it should be placed under the system of reporting
and prior authorization as described by the BSS. Exempt practices are those that
do not fall under this system. Practices thought to involve appreciable potential
risks are put under the regulatory system without exception, including all of the
practices associated with the nuclear fuel cycle. However, practices can be ex-
empt from control if the associated risks are sufficiently low. Exemption levels
have been derived for the BSS that apply to radionuclide levels and activities per
unit mass from which the risks are regarded as trivial.
All associated activities and material movements are regulated after a prac-
tice has been placed within the regulatory system. Regulatory control can be
relinquished only by proceeding through the system of reporting and prior autho-
rization set out by the BSS. An ad hoc case-by-case procedure is followed for the
possible release of materials for recycling, reuse, and disposal, and implementa-
tion of this procedure is the responsibility of the competent national authorities.
Clearance is defined as the removal from regulatory control of a substance that
has radionuclide levels below the recommended specific limits. Cleared sub-
stances are automatically exempt from the requirements of reporting and authori-
zation.
The radiological protection criteria that have been adopted for clearance are
10 pSv/yr (1 mrem/yr), with a collective dose for the practice of 1 man-Sv/yr
(100 man-rem/yr).6 Additionally, the skin dose is limited to 50 pSv/yr.
European Union Directive 96/29/EURATOM allows clearance of "radioac-
tive substances where the concentration of activity per unit mass do not exceed
the exemption values set out in Column 3 of Table A to Annex I." Annex I is
reproduced at the end of this appendix (see Table D-1), as is a table of derived
clearance levels based on a primary dose standard of 10 pSv/yr from NUREG-
1640 (Table D-2.
6European Union Directive 96/29/EURATOM further provides that collective dose can exceed ~
man-sievert, provided that "an assessment of an optimization of protection shows that exemption is
the optimum option" (KU, 1996, p. 19).
OCR for page 205
APPENDIX D
205
UNITED NATIONS
United Nations Scientific Committee on the Effects of
Atomic Radiation (UNSCEAR)
Consistent with the current understanding of the related consequences, the
ICRP, National Council on Radiation Protection and Measurements (NCRP),
IAEA, and UNSCEAR have recommended that radiation doses above back-
ground levels to members of the public not exceed 1 mSv/yr (100 mrem/yr), for
continuous or frequent exposure from radiation sources other than medial expo-
sures.
Most countries imposing limits on radiation from anthropogenic sources
have endorsed the principle of apportionment of the total allowable dose. Many
countries are in the process of endorsing a dose limit of 10 ,uSv/yr (1 mremlyr) for
LLRW that is 1 percent of the total allowable dose.
MULTIAGENCY RADIATION SURVEY AND
SITE INVESTIGATION MANUAL
The Multi-Agency Radiation Survey and Site Investigation Manual
(MARSSIM) provides a nationally consistent consensus approach to conducting
radiation surveys and investigations at potentially contaminated sites. This ap-
proach is intended to be both scientifically rigorous and flexible enough to be
applied to a diversity of site cleanup conditions. MARSSIM's title includes the
term "survey" because it provides information on planning and conducting sur-
veys and the term "site investigation" because the process outlined in the manual
allows one to begin by investigating any site that may involve radioactive con-
tamination.
The decommissioning that follows remediation requires a demonstration to
the responsible federal or state agency that the cleanup effort was successful and
that the release criterion (a specific regulatory limit) was met. This manual assists
site personnel or others in performing or assessing such a demonstration. The
demonstration of compliance involves three interrelated steps:
1. Translating the cleanup or release criterion (e.g., millisieverts per year,
millirem per year, specific risk) into a corresponding derived contaminant
concentration level (e.g., becquerels per kilogram or picocuries per gram
in soil) through the use of environmental pathway modeling;
2. Acquiring scientifically sound and defensible site-specific data on the
levels and distribution of residual contamination, as well as levels and
distribution of radionuclides present as background, by employing suit-
able measurement techniques; and
OCR for page 206
206
APPENDIX D
3. Determining that the data obtained from sampling support the claim that
the site meets the release criterion, within an acceptable degree of uncer-
tainty, by applying a statistically based decision rule.
MARS SIM provides standardized and consistent approaches for planning,
conducting, evaluating, and documenting environmental radiological surveys,
with a specific focus on the final status surveys that are carried out to demonstrate
compliance with cleanup regulations.
TABLE D-1 Exempt Quantities Established by Council Directive
96/291EURATOM
Quantity Concentration Quantity Concentration
Nuclide (Bq) (kBq/kg) Nuclide (Bq) (kBq/kg)
H-3 109 1o6 Ga-72 105 10
Be-7 107 103 Ge-71 1o8 104
C-14 107 104 As-73 107 103
0-15 109 1o2 As-74 1o6 10
F-18 1o6 10 As-76 105 1o2
Na-22 105 10 As-77 1o6 103
Na-24 105 10 Se-75 1o6 1o2
Si-31 1o6 103 Br-82 1o6 10
P-32 105 103 Kr-74 109 1o2
P-33 108 105 Kr-76 109 1o2
S-35 1o8 105 Kr-77 109 1o2
C1-36 1o6 104 Kr-79 105 103
C1-38 105 10 Kr-81 107 104
Ar-37 1o8 1o6 Kr-83m 1ol2 105
Ar-41 109 1o2 Kr-85 104 105
K-40 1o6 1o2 Kr-85m lolo 103
K-42 1o6 1o2 Kr-87 109 1o2
K-43 1o6 10 Kr-~8 109 1o2
Ca-45 107 104 Rb-86 105 1o2
Ca-47 1o6 10 Sr-85 1o6 1o2
Sc-46 1o6 10 Sr-85m 107 1o2
Sc-47 1o6 1o2 Sr-87m 1o6 1o2
Sc-48 105 10 Sr-89 1o6 103
V-48 105 10 Sr-90+ 104 1o2
Cr-51 107 103 Sr-91 105 10
Mn-51 105 10 Sr-92 1o6 10
Mn-52 105 10 Y-90 105 103
Mn-52m 105 10 Y-91 1o6 103
Mn-53 109 104 Y-9lm 1o6 1o2
Mn-54 1o6 10 Y-92 105 1o2
Mn-56 105 10 Y-93 105 1o2
Fe-52 1o6 10 Zr-93+ 107 103
Fe-55 1o6 104 Zr-95 1o6 10
OCR for page 207
APPENDIX D
TABLE D-1 continued
207
Quantity Concentration Quantity Concentration
Nuclide (Bq) (kBq/kg) Nuclide (Bq) (kBq/kg)
Fe-59 1o6 10 Zr-97+ 105 10
Co-55 1o6 10 Nb-93m 107 104
Co-56 105 10 Nb-94 1o6 10
Co-57 105 1o2 Nb-95 1o6 10
Co-58 1o6 10 Nb-97 1o6 10
Co-58m 107 104 Nb-98 105 10
Co-60 105 10 Mo-90 1o6 10
Co-60m 1o6 103 Mo-93 1o8 103
Co-61 1o6 1o2 Mo-99 1o6 1o2
Co-62m 105 10 Mo-101 1o6 10
Ni-59 1o8 104 Tc-96 1o6 10
Ni-63 1o8 105 Tc-96m 107 103
Ni-65 1o6 10 Tc-97 1o8 103
Cu-64 1o6 1o2 Tc-97m 107 103
Zn-65 1o6 10 Tc-99 107 104
Zn-69 1o6 104 Tc-99m 107 1o2
Zn-69m 1o6 1o2 Ru-97 107 1o2
Ru-103 1o6 1o2 Cs-134 104 10
Ru-105 1o6 10 Cs-134 107 104
Ru-106+ 105 1o2 Cs-136 105 10
Rh-103m 1o8 104 Cs-137+ 104 10
Rh-105 107 1o2 Cs-138 104 10
Pd-103 1o8 103 Ba-131 1o6 1o2
Pd-109 1o6 103 Ba-140+ 105 10
Ag- 105 1o6 1o2 La- 140 105 10
Ag-108m+ 1o6 10 Ce-139 1o6 1o2
Ag-l lOm 1o6 10 Ce-141 107 1o2
Ag- 111 1o6 103 Ce- 143 1o6 1o2
Cd- 109 1o6 104 Ce- 144+ 105 1o2
Cd-115 1o6 1o2 Pr-142 105 1o2
Cd-115m 1o6 103 Pr-143 1o6 104
In- 111 1o6 1o2 Nd- 147 1o6 1o2
In-113m 1o6 1o2 Pm-147 107 104
In-114m 1o6 1o2 Pm-149 1o6 103
In-115m 1o6 1o2 Sm-151 1o8 1o2
Sn-113 107 103 Sm-153 1o6 1o2
Sn-125 1o6 1o2 Eu-152 1o6 10
Sb-124 1o6 10 Eu-152m 1o6 1o2
Sb-125 1o6 1o2 Eu-154 1o6 10
Te-123m 107 1o2 Eu-155 107 1o2
Te-125m 107 103 Gd-153 107 1o2
Te-127 1o6 103 Gd-159 1o6 103
Te-127m 107 103 Tb-160 1o6 10
Te- 129 1o6 1o2 Dy- 166 1o6 103
continues
OCR for page 208
208
TABLE D-1 continued
APPENDIX D
Quantity Concentration Quantity Concentration
Nuclide (Bq) (kBq/kg) Nuclide (Bq) (kBq/kg)
Te- 129m 1o6 103 Ho- 166 105 103
Te-131 105 1o2 Er-169 107 104
Te-131m 1o6 10 Er-171 1o6 1o2
Te-132 107 1o2 Tm-170 1o6 103
Te-133 105 10 Tm-171 1o8 104
Te-133m 105 10 Yb-175 107 103
Te-134 1o6 10 Lu-177 107 103
I-123 107 10 Hf-181 1o6 10
I-125 1o6 10 Ta-182 104 10
I-126 1o6 1o2 W-181 107 103
I-129 105 1o2 W-185 107 104
I-130 1o6 10 W-187 1o6 1o2
I-131 1o6 1o2 Re-186 1o6 103
I-132 105 10 Re-188 105 1o2
I-133 1o6 10 Os-185 1o6 10
I-135 1o6 10 Os-191 107 1o2
Xe-131m 104 104 Os-19lm 107 103
Xe-133 104 103 Os-193 1o6 1o2
Xe-135 lolo 103 Ir-190 1o6 10
Cs-129 105 1o2 Ir-192 104 10
Cs-131 1o6 103 Ir-194 105 1o2
Cs-132 105 10 Pt-l91 1o6 1o2
Cs-134m 105 103 Pt-193m 1o6 103
Pt-197 1o6 103 U-235+ 104 10
Pt-197m 1o6 1o2 U-236 104 104
Au-198 1o6 1o2 U-237 1o6 1o2
Au-l99 1o6 1o2 U-238+ 104 10
Hg- 197 107 1o2 U-238sec 103 1
Hg- 197m 1o6 1o2 U-239 1o6 1o2
Hg-203 105 1o2 U-240 107 103
T1-200 1o6 10 U-240+ 1o6 10
T1-201 1o6 1o2 Np-237+ 103 1
T1-202 1o6 1o2 Np-239 107 1o2
T1-204 104 104 Np-240 1o6 10
Pb-203 1o6 1o2 Pu-234 107 1o2
Pb-210+ 104 10 Pu-235 104 1o2
Pb-212+ 105 10 Pu-236 104 10
Bi-206 105 10 Pu-237 107 103
Bi-207 1o6 10 Pu-238 104 1
Bi-210 1o6 103 Pu-239 104 1
Bi-212+ 105 10 Pu-240 103 1
Po-203 1o6 10 Pu-241 105 1o2
Po-205 1o6 10 Pu-242 104 1
Po-207 1o6 10 Pu-243 107 103
Po-210 104 10 Pu-244 104 1
At-211 107 103 Am-241 104 103
OCR for page 209
APPENDIX D
TABLE D-1 continued
209
Quantity Concentration Quantity Concentration
Nuclide (Bq) (kBq/kg) Nuclide (Bq) (kBq/kg)
Rn-220+ 107 104 Am-242 1o6 103
Rn-222+ 1o8 10 Am-242m+ 104 1
Rn-223+ 105 1o2 Am-243+ 103 1
Rn-224+ 105 10 Cm-242 105 1o2
Rn-225 105 1o2 Cm-243 104 1
Rn-226+ 104 10 Cm-244 10 10
Rn-227 1o6 1o2 Cm-245 104 1
Rn-228+ 105 10 Cm-246 103 1
Ac-228 1o6 10 Cm-247 104 1
Th-226+ 107 103 Cm-248 104 1
Th-227 104 10 Bk-249 1o6 103
Th-228+ 104 1 Cf-246 1o6 103
Th-229+ 103 1 Cf-248 104 10
Th-230 104 1 Cf-249 103 1
Th-231 107 103 Cf-250 104 10
Th-232sec 103 1 Cf-251 103 1
Th-234+ 105 103 Cf-252 104 10
Pa-230 1o6 10 Cf-253 105 1o2
Pa-231 103 1 Cf-254 103 1
Pa-233 107 1o2 Es-253 105 1o2
U-230+ 105 10 Es-254 104 10
U-231 107 1o2 Es-254m 104 10
U-232+ 103 1 Fm-254 107 104
U-233 104 10 Fm-255 1o6 103
U-234 104 10
SOURCE: EU (1996).
OCR for page 210
210
TABLE D-2 Derived USNRC Clearance Levels Assum~ng a 10 ,uSv/yr
Primary Dose Standard (All Metals)
APPENDIX D
Mass Clearance Levels
Radi on ucli de
Surficial Clearance Levels
NRC (Bq/g)
Radi on ucli de
NRC (Bq/cm2)
H-3 2.E+04 H-3 2.E+04
C-14 6.E+02 C-14 7.E+02
Na-22 2.E-02 Na-22 3.E-02
P-32 8.E+O1 P-32 9.E+01
S-35 1.E+03 S-35 2 E+03
C1-36 4.E+OO C1-36 5 E+OO
K-40 2.E-O1 K-40 3 E-01
Ca-41 8.E+01 Ca-41 1 E+02
Ca-45 1.E+02 Ca-45 2.E+02
Cr-51 4.E+OO Cr-51 5.E+OO
Mn-54 l.E-O1 Mn-54 l.E-01
Fe-55 1.E+04 Fe-55 1 E+04
Co-57 3.E+OO Co-57 3 E+OO
Co-58 l.E-O1 Co-58 l.E-01
Fe-59 9.E-02 Fe-59 1 E-01
Ni-59 2.E+04 Ni-59 3 E+04
Co-60 4.E-02 Co-60 5 E-02
Ni-63 8.E+03 Ni-63 1 E+04
Zn-65 5.E-02 Zn-65 6 E-02
Cu-67 5.E+OO Cu-67 6 E+OO
Se-75 3.E-O1 Se-75 4.E-01
Sr-85 2.E-O1 Sr-85 2 E-01
Sr-89 9.E+O1 Sr-89 1 E+02
Sr-90 l.E+OO Sr-90 1 E+OO
Y-91 3.E+O1 Y-91 3 E+01
Mo-93 7.E+02 Mo-93 9.E+02
Nb-93m 1.E+03 Nb-93m 2 E+03
Nb-94 6.E-02 Nb-94 7 E-02
Nb-95 l.E-O1 Nb-95 2 E-01
Zr-95 l.E-O1 Zr-95 2 E-01
Tc-99 5.E+O1 Tc-99 7.E+01
Ru-103 2.E-O1 Ru-103 3.E-01
Ru-106 5.E-O1 Ru-106 6.E-01
Ag-108m 6.E-02 Ag-108m 7 E-02
Cd- 109 2.E+O1 Cd- 109 3 E+01
Ag-llOm 4.E-02 Ag-llOm 4 E-02
Sb-124 6.E-02 Sb-124 6 E-02
I- 125 4.E+OO I- 125 5.E+OO
Sb-125 2.E-O1 Sb-125 3 E-01
I-129 2.E-O1 I-129 2 E-01
I-131 4.E-O1 I-131 5 E-01
Ba-133 4.E-O1 Ba-133 4 E-01
Cs- 134 2.E-02 Cs- 134 2.E-02
Cs- 137 4.E-02 Cs- 137 5.E-02
OCR for page 211
APPENDIX D
211
TABLE D-2 continued
Mass Clearance Levels
Radi on ucli de
Ce-141
Ce- 144
Pm- 147
Eu-152
Eu-154
Eu-155
Re-186
Ir-192
Pb-210
Po-210
Bi-210
Rn-222
Ra-223
Ra-224
Ac-225
Ra-225
Ra-226
Ac-227
Th-227
Th-228
Ra-228
Th-229
Th-230
Surficial Clearance Levels
NRC (Bq/g)
4.E+OO
3.E+OO
9.E+02
9.E-02
8.E-02
9.E+OO
4.E+01
8.E-02
7.E-02
2.E-O1
3.E+02
l.E-O1
6.E-O1
2.E-O1
7.E-O1
6.E+OO
6.E-02
3.E-02
2.E+OO
8.E-02
l.E-O1
2.E-02
2.E-O1
Radi on ucli de
NRC (Bq/cm2)
Ce-141
Ce- 144
Pm- 147
Eu-152
Eu-154
Eu-155
Re-186
Ir-192
Pb-210
Po-210
Bi-210
Rn-222
Ra-223
Ra-224
Ac-225
Ra-225
Ra-226
Ac-227
Th-227
Th-228
Ra-228
Th-229
Th-230
4.E+OO
4.E+OO
1.E+03
l.E-O1
l.E-O1
l .E+O 1
5.E+01
l.E-O1
9.E-02
2.E-O1
4.E+02
l.E-O1
6.E-O1
2.E-O1
8.E-O1
7.E+OO
7.E-02
4.E-02
2.E+OO
9.E-02
l.E-O1
3.E-02
2.E-O1
Representative terms from entire chapter:
quantity concentration
