1. SUBPART B: DEFINITIONS
      2. 62-460
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      6. 62-465
      7. Section 1000.503: Other Provisions
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ILLINOIS POLLUTION CONTROL BOARD
January 24,
1985
IN THE MATTER OF:
)
TITLE 35:
ENVIRONMENTAL PROTECTION
)
R82—2
SUBTITLE
I:
ATOMIC RADIATION
CHAPTER
I:
POLLUTION CONTROL BOARD
PART 1000:
RADIATION HAZARDS
)
PROPOSED RULE.
FIRST NOTICE.
PROPOSED OPINION AND ORDER
OF
THE BOARD
(by J.
D.
Dumelle):
This matter comes before the Board upon the January 27,
1982, petition to adopt regulations concerning radiation hazards
filed on behalf of the Department of Nuclear Safety
(DNS) by the
Attorney General’s Office.
The DNS submitted a revised proposal
on March
5,
1982, which codified the proposed rules.
Hearings
were held to consider the proposal on May 11, 1982,
in Chicago
and May
14,
1982, in Springfield.
The DNS filed a second
revision of the proposed rules on August 26,
1982.
The
Department of Energy and Natural Resources
(DENR) filed its
Economic Impact Study (EcIS) on October
28, 1983.
Hearings were
held to consider that study on January
24, 1984, and February 17,
1984.
The comment period closed on March 26,
1984.
The DNS proposal, Subtitle
I,
Part 1000, would establish
standards and limitations governing radiological air pollution
from NRC—licensed facilities and materials which substantially
duplicate portions of current regulations of the United States
Nuclear Regulatory Commission
(NRC).
(See
10 C.F.R.
20 and 45
Fed. Reg. 65521ff, October
3,
1980).
Under Ill. Rev. Stat. ch.
127, par.
63617 the DNS is the executive agency responsible for
enforcing and implementing radiological air pollution regulations
promulgated pursuant to Section 25(b) of the Environmental
Protection Act (Act).
DNS will assure compliance with the
requirements of Subtitle I by means of the monitoring, testing,
record—keeping, and reporting provisions.
While
DNS presently regulates non—NRC—licensed materials and
facilities under statutes other than the Act, neither DNS nor any
other Illinois agency regulates NRC—licensed materials and
facilities for radiation protection purposes.
The effect .of
proposed Subtitle
I is to provide DNS with the authority and the
means to protect the public from radiation hazards associated
with the large number of NRC-licensed activities in Illinois.
62-445

2
History of Atomic Radiation Regulations
In 1971 the Attorney General’s Office submitted a proposal
to the Board
(R7l-9)
pursuant to Section 25(a)
of the Act to
develop radiation protection standards for nuclear power plants
jfl Illinois is subject to regulation and licensing by the NRC under
the Atomic Energy Act.
However,
Section 25(a)
now
Section
25(b)
was subsequently declared unconstitutional by an Illinois
appellate court which found that regulation of the radiation
hazards of nuclear power plants
is preempted by the Atomic Energy
Act.
Commonwealth Edison Co. v.
Pollution Control Board,
5
Ill.
App.3d 800,
284
N.E-.2d
432
(3d Dist.
1972), citing Northern
States Power Co
V.
Etate of Minnesota,
447 F.2d 1143
(6th Cir.
1971),
sum.aff’d 405
~
1035
(1972),
No further act±~~
was taken on R71—9 until the Attorney
General moved the Boa:d in 1980 to institute hearings on the
Board’s powers under ~3ection25(a)
in light of new developments
in federal
law.
The Board docketed the State’s motion as R80—l,
consolidated R80—l with R71—9, and, after a motion by Commonwealth
Edison Company to dismiss the consolidated proceedings, considered
briefs on the question of the Board’s authority to regulate
airborne radiation hazards following the federal Clean Air Act
Amendments of 1977.
In an Opinion and Order of August
7,
1980
(39 PCB 307) the Board determined that it has jurisdiction under
Section 25(a) to regulate airborne radiation hazards from materials
and activities licensed by the NRC.
R7l—9 and R80—1 were, however, dismissed by that same order
since the original proposal was nine years old by that time and
the Board felt that it was outdated,
The petition filed in this
matter contains the first subsequent proposal filed which addresses
atomic radiation issues.
Board Authority
The Board’s authority to promulgate these regulations has
again been called into question.
In
a comment filed on May
14,
1982,
Kerr-McGee Chemical Corporation requests the Board to
reconsider whether the adoption of the proposed rules
is preempted
“by the federal government through the regulatory,
licensing and
enforcement authority of the NRC”
(KM Comment,
p.
21).
The Board has considered Kerr—McGee’s arguments, but finds
in them no reason to depart from the holding or reasoning of its
August
7, 1980 Opinion and Order in R7l-9, R80-1 consolidated.
The Board notes in this regard that its position has been strongly
supported by John-Mark Stensvaag who states, after lengthy analysis,
that “the power of individual
states to regulate radioactive air
emissions from NRC licensed facilities is indisputable”
Stensvaag,
“State Regulations of Nuclear Generating Plants Under the Clean
Air Act Amendments of 1977,”
55
S.
Cal. L.Rev. 511,
536
(March,
1982).
82-446

3
!!1~.
929S
DNS has proposed rules which would regulate radiological air
pollutants emitted from NRC regulated facilities.
They establish
permissible levels of radiation exposure to persons in unrestricted
areas
(areas in which access is not controlled by the NRC licensee);
maximum concentrations of radiological air emissions; record
keeping and environmental monitoring requirements; and notification
requirements.
The provisions are very similar to those found
in
existing federal regulations.
The proposed regulations also establish permissible levels
of radiation exposure to individuals in unrestricted areas which
are the same in current NRC regulations
(10 CFR 20.105): 500
millirems in any one year,
100 millirems in any seven consecutive
days, and
2 millirems
in any one hour,
They also limit annual
exposure in unrestricted areas from commercial power reactor
operations and nuclear fuel reprocessing to 75 millirems to the
thyroid and 25 millirems to the whole body and other organs.
These limitations are identical to U.S. EPA regulation 40 CFR
190.10.
Limits on radioactive air emissions to unrestricted areas,
set forth in Appendix A of the proposal, are identical to the
limits in Appendix B of 10 CFR 20.
The record keeping requirements set forth in the proposal
are the same as those
in existing NRC regulations.
However, the
proposal also allows DNS to require reports in addition to those
provided the NRC, and requires all licensees to maintain such
environmental monitoring equipment as may be required.
tINS has
not yet established any such requirements.
Finally,
the proposed rules require NRC licensees to notify
DNS “of incidents or conditions arising from the use or possession
of
NRC—
licensed materials or facilities which may have caused
or threaten to cause
emissions of radiation
levels
in
excess of
those allowed” under the proposal
(8/26/82 proposal,
p.
14).
The
notification requirement is the same as
in existing NRC regulations.
Need
For
The
Proposed
Regulations
The
proposed
rules
are
intended
to
provide
a
legal
basis
for
DNS
enforcement
authority
under
the
Act,
Dr.
John
W.
Cooper,
a
radiation
biologist
and
Assistant to
the
Director
of
DNS,
who
was
previously
employed
by
the NRC, testified
regarding
the
necessity
for
the
proposed
rules.
He
explained that
the
NRC
lacks
independent
environmental monitoring and, therefore, must rely on licensee
data for information about licensee performance.
Dr. Cooper
concluded that NRC’s limited resources for monitoring and its
non—environmental focus result in a limited ability to assess
licensee performance and enforce air emission standards.
62-447

4
Dr. Cooper described the DNS program as one which
is designed
to independently evaluate licensee
emissions and radiation levels in unrestricted
areas.
The program is heavily oriented toward
environmental monitoring and includes primarily
equipment designed to measure levels in the en-
vironmental area (5/11
R. l8).*
Dr. Cooper contrasted the NRC’s environmental effort, which
is “primarily involved with auditing licensee performance”,
to
DNS’s, which is “prir~rilyinvolved with direct field measure-
ments of licensee petormance”
(5/11
R.
20 and 5/14 R.
11).
Dr.
Cooper stated that
:L~ the area of environmental surveillance
DNS has the higher car~city,”with its staff of five health
physicists,
three
nuc~~ar
engineers,
a radiochemist, a radiation
biologist, and an in~wtria1hygienist, most of whom are involved
with environmental ra~iation exposure and environmental measure-
ments
(5/11
R.
20).
Dr. Cooper further testified that independent assessment of
licensee environmental performance
is valuable
in protecting the
public from airborne radioactive materials (5/14
R. 18), and that
the major benefit of the proposed rules
is to focus attention on
licensee environmental performance rather than on reactor design
and operation and to give DNS the power to make efficient use of
its independently obtained environmental data
(5/14
R.
22—23).
Dr. Cooper further indicated that if DNS’s monitoring teams
detected a radiation safety hazard and reported the situation to
NRC, NRC would take such report “as information only” and would
do an independent assessment before proceeding to any enforcement
action
(5/11
R.
25—26).
The testimony of
Commonwealth
Edison’s
witnesses corroborated
Dr. Cooper’s
testimony
regarding
the absence of independent NRC
environmental assessment.
John Golden described Commonwealth
Edison’s activities and its reporting to NRC and indicated that
there is nearly no independent monitoring by NRC, nor does NRC
sample air, gases released from the stack, and liquids, and it
does not perform any remote monitoring
of site releases.
(See
5/11
R.
195—208).
In sum, DNS demonstrated that the proposed rules do not
duplicate the NRC’s regulatory efforts but,
rather, complement
them.
As Board Member Goodman suggested, DNS should not have to
depend on the good will of licensees
in order to conduct monitor-
ing activities
(5/11
R.
66).
Further, neither DNS nor the general
public should be obliged to rely on the NRC’s limited capacity to
enforce compliance with its standards,
Because the radiological
*References
tc
the
May 11,
1984, transcript will be cited as
(5/11
R.),
the
Ma~ 14,
1984,
transcript will be cited as
(5/14
R.
),
and the
Feb
ry
.7,
1984, transcript will be cited as
(2/17
R.
).
62-448

5
air
pollutants
associated with NRC
licensees
present
dangers
to
public health and safety,
licensees should be treated like other
air pollution sources in Illinois and be made subject to Board
regulation under the Act,
The NRC regulates and licenses possession and use of certain
materials
and
facilities
under the Atomic Energy Act:
(1)
source
material
(the
naturally
occurring
radioactive
elements,
uranium
and
thorium,
from
which nuclear
fuel
is
made),
(2)
special
nuclear
material
(nuclear fuel or fissionable material),
(3)
byproduct
material
(material produced by fission or irradiated during
fission, and uranium and thorium mill tailings),
(4) production
facilities
(facilities for producing nuclear fuel),
(5) utilization
facilities (facilities which utilize nuclear fuel——i.e.,
reactors,
both commercial and research)
(42 U.S.C.
2092,
2111,
2073,
2131, and 2201),
Under some circumstances the NRC holds a public
adjudicatory hearing
in
connection with the granting of licenses
and permits.
On applications for permits to construct a utiliza-
tion or production
facility,
the
NRC
must
hold
a
hearing;
on
applications
for
licenses
to operate
a
utilization
or
production
facility
and
on
other
license
applications,
the NRC must hold a
hearing
only
if one is
requested
(42
U.S.C.
2239).
In
either
case,
a
person
may
be
admitted
as
a
party
to
a
hearing
only
if
he
can
put
forward
at
least
one
contention
which
the
NRC
determines
to
be
sufficiently
specific
and
supported
10
C.F.R.
2.714(a)(b).
When a final order is entered following the hearing, an appeal
may be taken to the Circuit Court of Appeals
(28 U.S.C. 2341).
Under the NRC’s procedural
rules, one may bring a complaint
against a licensee on~yby requesting the NRC to institute a
“show—cause” proceeding
(10 C,F,R,
2.202,
2.206), which will not
be instituted unless the NRC determines that circumstances so
warrant.
DNS contends that no court has ever reversed an NRC
decision refusing to institute a show—cause proceeding and that
the NRC very rarely grants such proceedings.
Further a com-
plainant before the NRC
is entitled to judicial review under the
“abuse
of
discretion”
standard
as
opposed to Illinois’
“manifest
weight
of
the evidence” standard,
Thus,
the
ability
of
States
or
private
citizens to enforce federal radiation standards is limited.
Economic Impact
Study
Commonwealth Edison stated
in
its
March
26,
1984,
comments
that:
The proposed regulation
is unnecessary.
An
effective state and federal regulatory~scheme
already exists which accomplishes all of the
objectives of the proposed regulation.
Moreover,
the Illinois Department of Energy and Natural
Resources~statutorily mandated study of the
economic impact of R82—2 shows that its cost
to
the
State,
the regulated
industry
and
the
public would outweigh any benefits
it may
provide.
62-449

6
Also, near
the
close of hearings, counsel
for
Illinois
Power
stated
that
he
believed
this
to
be
“the
one
regulatory
proposal
he
had
ever
seen
that is unwarranted,
on
the
sole
basis
of
economics”
(2/17
R.
169),
The
DNS,
unsurprisingly,
disagrees
with
both
of
these
assessments,
The Economic Impact Study
(EcIs), which was filed as Exhibit
No.
8 in this proceeding on February
17, 1984, reached the following
conclusions:
1.
Administrative
costs
would increase $135,000 annually;
2.
Increased
litigation and plant shutdowns would cost
zero
to $3~375 million annually;
and
3.
Reducing nuclear power plant emissions by 10
would
cost
$l30~OtO
annually but
would
re~sult in
a health
benefit ot $12,600 per year.
The first component of increased administrative costs
is
$60,000 per year to the DNS resulting from hiring two additional em-
ployees to inspect DNS—monitoring devices, collect samples of air,
water,
and vegetation, and process reports from NRC licensees.
An
additional component is equipment costs resulting from installation
of radiation monitoring devices around major NRC licensees in the
state,
considered to be
negligible
by DNS.
The final component
is added management supervision and overhead costs related to the
employment of two additional nuclear engineers,
estimated by DNS
at $75,000 per year
(EcIS, pp.
37—38).
During the May 11 and
14,
1982 hearings, representatives
of Commonwealth Edison and Illinois Power indicated concern about
the potential effect of the regulation on the amount of litigation
for the companies and on the frequency of shutdown of their nuclear
facilities.
The law firm of Martin, Craig, Chester and Sonnenschein
investigated and commented on the potential for increased litigation
as an appendix to the EcIS~ The cost
estimate
appears
to
be
based
solely upon the 1982 costs
to
Commonwealth
Edison in connection with
a
lawsuit
concerning
its LaSalle
County
nuclear power plant which
totalled $639,380
(EcIS,
pp.
45—46).
While admitting that “the
estimate of the costs resulting from increased litigation and fre-
quency of nuclear power plant shutdowns due to R82-2 is difficult
to make because of the many uncertainties involved,” the authors of
the EcIS estimate a range of zero to $1.0 million per year
(EcIS,
p.
49).
The authors go on to
explain
that “the latter estimate re-
flects a substantial
increase in litigation for the industry and was
chosen in order to represent an upper bound on the increased litigation
expenses.
This estimate exceeds the costs associated with the legal
action connected with the LaSalle County facility since this previous
legal action was only presented for illustrative purposes and con-
sequently does not necessarily represent an upper bound on increased
litigation for the nuclear power industry due to R82—2”
(EcIS,
pp.
49—50).
62-450

7
The
increase
in the average frequency of nuclear power plant
shutdowns
is estimated to range between zero to 5 days per year
based upon the fact that the previously—discussed legal action
against the LaSalle County facility resulted in a delay in the
start—up of 17 days, which,
if such a shutdown
is presumed to
occur every three years results
in an average annual increase
in shutdowns of approximately 5 days, which,
in turn, translates
into an increase in costs for the utility industry of $l.725 mil-
lion to $2,375 million annually (EcIS, p.
50).
In considering the costs to the nuclear industry of reduc-
ing emissions, the authors of the EelS conclude that “the range
of estimates for the annual costs associated with increased direct
litigation costs along with the resulting greater frequency of plant
shutdowns
is zero to $3~375million”
(EelS,
p.
50).
The authors of the EcIS indicated that:
increases
in equipment,
personnel,
and other
costs
for
nuclear
power
plant
operators re-
sulting from 1(82-2 would be relatively minor
or nonexistent insofar as the utilities’s
representatives understood the manner in
which
R82-2 would be implemented.
For
example,
it was indicated that no changes
in
equipment
or
design
of
Commonwealth
Edison’s
nuclear
power
plants
would
result
from
R82-2.
In
addition,
reporting
require-
ments
were
not
expected
to
increase
since
all
emission reports currently filed with
the
NRC
are
sent
to
DNS
as
a
courtesy.
The
major
reason
for
concluding
that
R82—2
will
not
result in increases in
equipment,
person-
nel,
and operating expenses
is that the R82—2
requirements are very similar
to
those
in NRC
regulations,
with which the
utilities
are
currently
complying
(EelS,
p.
39).
Despite
those findings,
the authors of
the
study
proceeded
to calculate the cost to nuclear power
plants
to
reduce emissions
10
percent,
that cost being $130,000 per year (EelS, pp.
40—42).
The
only
potential beneficial
effect
noted
by
the
authors
of
the study is the public health benefit
of
reducing
emissions
10
percent
(EelS,
pp. 66—72),
The summary of beneficial effects
states that there would be a very slight reduction in death rate
as cancer fatalities are reduced by roughly one every 100 years.
This benefit results from a 10 percent reduction in emissions of
radiological air pollutants from major NRC licensees in Illinois.
The monetary value associated with the reduction in death rate
was estimated to be $12,600 per year,
This estimate is based: on
studies
of
people’s willingness to pay for
measures
affecting
safety and survival.
62-451

8
DNS takes the position that DENR should have declared “that
the
economic
impact of R82—2 is so difficult
to
measure
that
a
formal
study would not generate useful
information, or that the
cost of making a formal study outweighs its value in determining
economic
impact”
(DNS Memo,,
3/26/84,
p.
2),
Since that did not
occur,
however,
DNS
presented
testimony
demonstrating
that
“the
EelS
has
limited usefulness,
providing
at
most
a
rough
guide
to
some
of
the
economic
issues raised by
regulation
of
radiological
pollutants”
(ibid,
p.
2),
DNS’
major
concern is that the EelS does not identify all of
the
costs
and
benefits of R82-2 and does not
explain
its
methodology.
DNS
states
that the EcIS did not address the social and institutional
benefits
of
reduced uncertainty about licensee
performance
which
would result from authorized independent state monitoring and
enforcement capability ~ and it failed to consider the suffering
and sickness associated with nonfatal cancers and the medical and
disability costs.
DNS also points out that the authors of the
EelS made a number of arbitrary choices of cost and benefit
estimates which it continually failed to acknowledge
(ibid,
p.
4).
More
specifically,
DNS finds it hard
to
understand why
potential
litigation
was considered in the economic impact. All
Board regulations can lead to litigation and,
if industry is
fully
in compliance with the federal limitations, enforcement
actions are unlikely;
if it is not, enforcement may well be
necessary.
Thus, DNS concludes that litigation costs to industry
are directly associated with health and other benefits due to
reduced radiation exposure.
DNS noted at the February 17, 1984,
hearing,
that the authors relied on a “sample of one” in determining
litigation costs,
and the EelS does not even indicate whether the
expenditures are typical of expected
expenditures.
The same
considerations
apply to the analysis of Board
ordered
shutdowns.
The
Board
accepts the uncontested administrative cost figure
of
$135,000
as
reasonable, but has serious
reservations
about
the
other
cost
figures,
As DNS pointed out, there is nearly no
indication
in
the EelS whether the costs would more likely be
near
the
low end of the range
(zero)
or the high end
($3.5
mil-
lion).
Furthermore, there
is the barest support for the high end
figures,
and
several important considerations have been ignored.
A
particular
issue was made about
enforcement
against
“threatened”
releases.
Section
9(a)
of the Act
prohibits
causing or
threatening
air pollution; and concern was expressed that any citizen could
file a judicial complaint asserting on hypothetical grounds that
an accident or release in excess of applicable standards may
occur which will result in air pollution
(5/il R. 130—131).
The
Board
sees no reason to believe that claims of threatened ra-
diation pollution, whether characterized as
a statutory violation
under Section
9(a)
or a prospective common law nuisance,
will be
treated by the Board or the courts any differently than other
62-452

9
claims
of
threatened pollution.
The mere
hypothetical possibility
of
pollution
is insufficient to
warrant
injunctive
relief.
There
must rather
be
a
“definite danger” or
“very
definite
danger”
A1laertRende~jn9~
v.
Pollution Control Board,
91
Ill.
App.3d,
46 Ill,Dec.
608, 414 N.E.2d 492
(3d Dist.
1980); Rocke
v. Pollution
Control
Board,
78 Ill.App.3d,
33 Ill.Dec. 717,
397,
~
For a prospective nuisance, an
activity will not be enjoined unless it is “highly probable” that
it will result
in a nuisance (Vill~geof Wilsonville
v.
SCA
Services,
Inc.,
86 Ill.2d
1,
55 Ill,Dec, 499,
426 N.E.2d, 824
(1981).
commonwealth Edison also expressed concern that the enforce-
ment power which would result from the proposed regulations would
enable people with anti~nuclearsentiments to harrass the company
through a “flood of litigation”
(5/li
R.
94—95).
Counsel stated
his concern that “in a statutory system” any citizen can file a
complaint and that “we are at the mercy of the most radical and
obdurate of our opponents”
(5/Il
R. 101), implying that the
enforcement mechanism will result in a great deal of factually
baseless litigation.
Hcwever, the possibility that some citizens
will file complaints which are found to be factually baseless
should be of little concern,
as should its fear of multiple
lawsuits in different forums,
Under Section 31(b)
of the Act the
Board can not allow enforcement actions to proceed if they are
frivolous
(without a legal or factual basis) or duplicitous
(already
filed
before the Board or some
other forum).
Further,
citizen
suits
have been available
under the Act since its in-
ception
and
there
has never been a “flood of litigation” despite
recurring
concerns that there would be,
The Board believes that consideration
of the costs and
benefits of potential litigation is not appropriate in reaching a
decision in this regulatory proceeding,
The cost of litigation
in enforcing fair and reasonable substantive
regulations promul-
gated to
protect
the public interest and welfare must be presumed
justified.
Indeed, that proposition goes to the heart of our
legal system.
The Board, therefore, finds no net cost of litigation.
The Board notes that the Economic Technical Advisory Committee
which reviewed the EelS also questioned the inclusion of litigation
costs
(Ex,
8,
ETAC Opinion,
p.
2).
Similarly, the Board seriously questions the cost associated
with potential shutdowns,
Industry expressed concern during the
hearings that an increase of reactor shutdowns can be expected as
a result of
state
enforcement power.
However, the proposed
regulations
are no different than the
Board’s other regulations,
except that
DNS rather than the Agency
will
be
the
implementing
agency.
The
Board presumes that DNS will
exercise its prosecutional
discretion
in
a
manner much like the
Agency’s.
Furthermore, the
Board
will
certainly be aware of the cost of
a
shutdown when it
considers
whether such an order should be entered,
and if it
finds
that
the cost of a shutdown outweighs
the
public health
62-453

10
benefit,
no
shutdown
will be
ordered
The
Board,
therefore,
finds no net cost of
shutdowns.
The
Board
finds
the
cost
of
reducing
emissions
by
10
percent
and
the
related
health
benefits
interesting,
but
not particularly
useful.
Industry
indicates
that
it
is
presently
in
substantial
compliance
with
the
proposed
limitations,
indicating
that
the
cost
of
compliance
is
little
or
nothing.
The
proposed regul-
ations
would
not
require
a
10
percent
reduction,
or
any
reduction
at
all
There
is, in
fact,
no
evidence
in
the
record
to
suggest
that
such
a
reduction
would
result
from
the
proposed
regulation.
Therefore,
the
Board
finds
compliance
costs
to
be
negligible,
as
well
as
the
health
benefits
associated
with
them.
Based
on
the
ECIS,
then,
the
Board
is
led
to
the
conclusion
that
the
cost
of
thet proposed
regulation
is
about
$135,000
annually
with
no
associated
health
benefits.
However,
this
ignores
the
possibility
that
the
proposed
regulations
will
result
in
greater
oversight
of
the
nuclear
industry
and
that
potential,
or
real,
problems
may
be
uncovered
and
remedied
which
would
not
be
absent
the
regulations.
That
such
benefits
are
expected
to
follow
from
these
regulations
is
demonstrated
by
Governor
Thompson’ s
amendatory
veto
statement
issued
September
18,
1980,
regarding
the
creation
of
DES
The
Governor
stated
that
DES’
regulatory
function
insures
greater
accountability
to
the
State
and
safer
operation
and
handling
of
radiological
facilities
and
materials.
This
legislation
represents
an
enormous
step
forward
for
Illinois
nuclear
safety...
In
addition,
the
(DES
will
par—
tic
ipate
with
the
federal
government
both
on
the
regulatory
and
legislative
levels
to
en-
sure
state
input
into
the
questions
which
so
significantly
affect
us...
This
state,
which
is
more
dependent
on
nuclear
power
than
any
other
state
in
the
nation,
must
be
first in nuclear safety as well.
The
hearing
record
demonstrates
that
the
proposed
regulations
should
help
fulfill
the
expectations
that
state
oversight
of
nuc-
lear
materials
and
facilities
can
and
should
complement
federal
oversight, and the
Board
fipds
that
the
$135,000
cost
of
adminis-
tration
is
a
reasonable
expense
for
the
added
protection
which
will
result
from
these
regulations.
General
Provisions
and
Definitions
The
Board
proposes to adopt
proposed
Sections 1000
101,
1000.102, 1000.103 and 1000.201 (Authority, Purpose and Policy,
Scope and Definitions, respectively)
as
proposed
with
minor
changes and proposes to delete proposed Section 1000.104 (Duties
of the
Department)
as
unnecessary.
Since
DES’
enabling
act
sets
out
these
duties,
the
Board
finds
no
reason
to
set
them
out
here.

II
Kerr—McGee
was
the
only
participant to attack these proposed
sections
(KM Comment, pp~3~4)~It points out that proposed
section 1000.102(b), adapted from 10 C.F.R. 20.1(c), contains two
significant changes:
the word “should” in the NRC’S regulation
which states that affec~ed persons “should” make every reasonable
effort to maintain radi~ionexposures to unrestricted areas as
low as
is reasonably achievable, has been changed “shall,” and
the definition of
“as low as is reasonably achievable” has been
changed to delete the word “reasonably.”
It believes that these
changes limit the Board~sdiscretion and result in “significantly
more stringent standards
at significantly greater cost
——
than
the NRC” standards
(KM Coooent, p~4),
DNS
responds
that t~:o~
words
“should”
and
“shall”
are
equally
mandatory.
It further
stw:~os
that
it
deleted
the
word
“reason-
ably”
from
the
definitig~.of uALARA~*
because
it
is
“surplussage”
used to define itself in~
federal
definition
(DNS
8/26/82
Memo.,
p.
4).
While the Board agrees with the changes made by DNS and the
reasons for those changes, the Board will propose the federal
language rather than the DNS language simply to avoid any possible
arguments that the changes
result
in substantive differences.
Standards and Limitations
No one has commented adversely on Sections 1000.301, 1000.302
or 1000.303
(Permissible Levels of Radiation in Unrestricted
Areas, Radioactive Emissions to Unrestricted Areas, and Additional
Requirements, respectively)
in
their present form, and the Board
will propose
Sections
l000~30land 1000,302 as requested by DNS.
The
Board
will
not,
however,
propose
Section 1000.303 as requested.
As proposed by DNS,
that
section
simply
incorporates
40
CFR
90
by
reference.
Since Part
90
is
only
two pages long, the Board sees
no
reason
not
to
set
forth
those
provisions rather than incorporate
by
reference,
and the
Board
will
do so
as
Subpart
D
and
the
originally
proposed
Subpart
D
will
be
redesignated
as
Subpart
E.
Also, the Board will not propose the
sections
on
variances
or
the
effective date provisions contained in Part 90.
The latter are
unnecessary and the
former
are
being
deleted for the same reasons
as Section
l000~304~as
discussed
below.
These rules reflect the
federal rules with which
affected
facilities
must
already
comply
and
with
which
those facilities are
apparently
in
compliance.
The
Board
will
not, however,
propose
Section
1000.304
regarding
variances.
That
section
includes
information
that
the
Board
“shall consider” in reviewing variance petitions under Subtitle
I.
*The term
“as
low al
reasonably
achievable”
(ALARA)
means
as
low as
is
~n!~l
achievable
taking into account the state of
technology, and the
economics
of
improvement...(lO C.F.R.
20.3)
82~455

Kerr-McGee
objects
that
while
the
Board is only required to
consider
that
information,
the
NRC
must
grant
the
variance
if
all
the
listed
conditions
are
satisfied~
See
10
C.F.R.
20.106(b).
DNS
states that the
reason
Section
1000.304
differs
from
the
federal rule
is that the Board~svariance authority is circum-
scribed by the Act which allows the Board to grant variance only
upon “presentation of adequate proof that compliance with any
rule or regulation, request or order of the Board would impose an
arbitrary or unreasonable hardship~’~(See Section 35 of the
Act).
Thus,
satisfaction of the Section 1000.304 factors will
not necessarily be sufficient to obtain a variance.
The Board
agrees
with
DNS
that
it
cannot adopt the federal
language~ Absent superceding statutory authority, the Board’s
power to grant variances must be constrained by Section 35 of the
Act.
Further,
in accordance with that section the Board has
adopted procedures fcE obtaining variance relief at 35
Ill. Adm.
Code 104.
The Board has found those provisions to be adequate
for all other variances,
and there is nothing
in this record that
convinces the Board that different procedures are necessary under
these proposed rules~
The information which would be required
under DNS’ proposal
is information which would be expected to be
supplied to the Board by a variance petitioner under the current
rules*.
Therefore,
the
Board
will
delete Section 1000.304 from
its first
proposaL
*The
proposed
rule
is
as
follows:
Section
l000~3O4: Variances From Limitations of Appendix A
(a)
(1)
In reviewing petitions
for
variances
from
the
limi-
tations
specified in Appendix A, the
Board
shall
consider
generally:
(A)
The petitioner’s efforts to minimize the radioactivity
contained
in releases to unrestricted
areas;
and
(B)
The possibility that radioactive material
released
might result
in the exposure of an individual to concen-
trations of radioactive material
in air exceeding the limits
specified
in Appendix A of this Part,
(2)
In
reviewing
petitions
for
variances from the limi-
tations specified
in Appendix A,
the
Board
shall
consider
specifically:
(A)
Information as to flow
rates,
total quantity of re-
leases, peak concentration of each radionuclide
in the
releases
averaged
over
a
period
of
one year at the point
where
the
emission
leaves
a
stack,
tube, pipe, or similar
conduit
(B)
The properties of the releases,
including:
(continued on
next
page)
62-456

and
Other
Re
irements
Subpart
0
of
the
DNS
proposal
establishes requirements for the
submission
of records,
monitoring,
and
notification
of
incidents,
It
also
establishes
procedures
under
which
the
DNS
can adopt rules
requiring additional
records
to
be
submitted and to establish
monitoring requirements.
The
only
information
in this record
adverse to the. proposal
of these
rules
is that included in
Commonwealth
Edisonts
March
26,
1984,
comments~ Edison argues
that
the
proposed
rules
give
the
DNS the
authority
to impose equipment requirements and standards
on
regulated
facilities without limitation:
a redelegation of
authority
which the Act gives to the Board,
Section 1e:O~O.403(a)(l)
of the proposed regulation states that
“all
persons
su~bj~ectto
this
Part
shall
maintain such environmental
monitoring:
instruments
as
may
be
required in procedures adopted
by
the
Department.”
Those
procedural requirements involve
minimal
public comment and no provis-
ion
for required hearings.
DNS could point to nothing in~the pro-
posed rules
or
the
record
guiding
DNS~
ability
to~req~ire
equipment
(2/17
R.
92)~.
(i)
Chemical
composition;
(ii)
Physical
characteris—
tics and nature of the gas
or aerosol; and
(iii)
The size range
of
par—
ticulates in releases
in
air.
(C)
The anticipated
human
occupan-
cy
in
the
unrestricted
area
where
the
highest
concentration
of
radio-
active
material
from
the
releases
is
expected,
(D)
Information as to
the
highest
concentration of each radionuclide
in an unrestricted area at any
point of human occupancy including
anticipated concentrations averaged
over a period of one year,
(E)
The environmental monitoring
equipment and procedures and ca1c~u—
lations to determine
concentrations
of radionuclides in the unrestricted
area and possible reconcentrations
of radionuclides.
(F)
The waste treatment facilities
and procedures used to reduce the
concentration of radionuclides
prior
to
their
release.

14
When
the
state
I
~
~u
created
the DNS,
it gave the DNS
the authority
to
~ex~uu
~dminister,
and enforce all rights,
powers
and
duties
“eF~
r
l~i~
Environmental
Protection
Agency”
under
Section
4
of
the
I
this
section
does
not
give
DNS
any
authority
to adopt
Stct
~
~r
requirements
for monitoring
equipment
at regulat ~
~
On
the contrary, as Com-
monwealth
Edison per
it~
the Act
places exclusive respon-
sibility
for
the de
.~,
f
such
regulations with the Board
under Section
10(a)
o~ ~ie
~‘t
which
states that the Board may
prescribe
“requiremunt~
an
~tandards
for equipment and procedures
for monitoring
contami;ctizt
discharges at their sources,
the
collection of
samples
~$ ~
~ ‘ollection,
reporting and retention
of data resulting
fr
r
nicl
~oritoring.”
The adoption of such
regulations involve~s
~ci. c
procedures to insure a fully developed
record.
(See Section~‘6
2
of
the
Act),
Thus,
commonweal4
1o
~in
argues that the legislature obviously
intended
the
Board
to
:
a’s
this
aspect
of
its
pollution
control
program,
and
~r~n
~hc
legislature
delegates authority to
an agency,
that
agenc~
d~ee
words
in
the Act sanctioning such
horizontal
redelegat~oi~ a;~,
~iot
redelegate,
since redeleqation
of a discretionary
po~v~
~y
an
administrative
agency
to
another
agency
is void~
Comoor
~n
?ddBofl
Co. v.
Pollution
Control
Board,
25 Ill.
App.
3d
271,
Z8~
~‘
~t
0ist~
1974),
rev’d
on
other
grounds,
62
Ill.
2d 494
(1976)
The Board
agree~
same argument
applies
reporting
requireiren
grants DNS
the
pow~
propose them to
th~
the Board declines tr.
Section 1000.403
~
monitoring” of Sectir
l000.402(a)(6),
whior
Board’s proposaL
F
as Subpart E and
app~
Otherwise, the Board
for first
notice
as
That
Board
not
January
18,
1985,
i~.
governing
certain
~
Department
facilit
e~
Regulatory
Commiss;
opportunity
to
exarri~
Board
will
have
to
-v
regulations
are
no
~:
fore, while
the
Boain.
comment on
the
etfsc~
n
and,
in fact, believes that the
r
adoption
of
the
establishment
of
Nothing
in Section 4 of the Act
ostantive
rules:
it may only
~c
Ins. Board’s
adoption.
Therefore,
~
of
subsection
1000.402(b)
and
~finition of “environmental
~ 4
sill
be
incorporated into
y
place
the
term
is
used
in
the
~ic~e
sections
will be redesignated
renumbered as 1000.501 et
~.
~
the adoption of these sections
‘rh
Street Journal dated Friday,
~
USEPA
has “promulgated regulations
l~w~level
radiation...from
Energy
~
Items
regulated by the Nuclear
~rd
has
not, however, had an
.clations.
It
may
be
that
the
~ posal
to insure that any adopted
-~
r:t
that
the USEPA rules.
There—
~ed
to
first notice,
it invites
~s
USEPA
rules on this proceeding.

15
ORDER
The Board
hereby proposes for first
notice the following
amendments to:
TITLE
35:
ENVIRONMENTAL PROTECTION
SUBTITLE
I:
ATOMIC RADIATION
CHAPTER I:
POLLUTION CONTROL BOARD
PART 1000:
RADIATION HAZARDS
SUBPART
A:
GENERAL PROVISIONS
Section
1000.101:
Authority
The
Pollution
Control Board adopts the
rules
and
regulations
contained in this title pursuant to the authority of Title VI—A
of the Illinois Environmen,tal Protection Act.
Section 1000.102:
Purpose and Policy
(a)
The
regulations
in
this
Part
establish standards for
protection against radiological air pollutants associated
with materials and activities under licenses issued
by the United States Nuclear Regulatory Commission
pursuant to the Atomic Energy Act of 1954, as amended,
and the Energy Reorganization Act of 1974.
(b)
It
is the policy of
the
Pollution Control Board that
persons subject to
this
Part
shall,
in addition to
complying with the requirements of this Part, make
every
reasonable effort to maintain radiation
exposures
in,
and releases of radioactive
materials to,
un-
restricted areas as low as is reasonably achievable.
The
term
~as
low
as
is
reasonably
achievable”
means
as
low as
is
reasonably achievable
taking
into
account
the state of technology, the economics of improvements
in relation
to
benefits to the public health and
safety,
and
other
societal
and socioeconomic consider-
ations,
in
relation
to
the utilization of atomic
energy
in the
public interest.
Persons licensed by
the United States Nuclear Regulatory Commission to
operate light-~~water—coolednuclear power reactors
shall be deemed to satisfy the requirements of this
subsection if they achieve the
design objectives and
limiting conditions for operation
set out in 10
C.F.R,
50, Appendix
I.
Section
1000,103:
Scope
The
requirements
of
this
Part apply to all
persons who receive,
possess, use,
or
transfer
material
licensed
pursuant to
Parts
30
through
35,
40,
or
70,
or
who are licensed to operate a production
or utilization facility pursuant to Part 50 of the regulations of
the United States Nuclear Regulatory Commission codified in Title
10 of the Code of Federal Regulations.
62-459

16
SUBPART B:
DEFINITIONS
Section
1000.201;
Definitions
As
used
in
this
Part;
“Act”
means the
Illinois Environmental Protection Act, ch.
111-
1/2
Ill,Rev.Stat,,
§SlOOl etj.
“Board”
means
the
Illinois
Pollution
Control
Board,
“Department”
means
the Illinois Department of Nuclear Safety.
“Dose” means
the
quantity
of
radiation absorbed, per unit of
mass,
by
the
body
or by any portion of the body.
When these re-
gulations
specify
a
dose
during a period of time, the dose means
the total quantity of
radiation absorbed, per
unit of mass,
by
the body or by any
portion
of the body during such period of
time.
Several
different
units
of
dose
are
in
current
use,
Def-
initions
of
units as used
in these regulations
are
set
forth
in
the definitions of
“Rad” and “Rem” in this Section.
“Individual” means
any human
being.
“Licensed activity~’means any activity engaged in under a gen-
eral or specific
license issued by the NRC.
“Licensed facility” means any facility constructed or operated
under
a
permit
or a general or specific license issued by the
NRC.
“Licensed material” means any material received, possessed,
used, or transferred under a general or specific license issued
by
the
NRC.
“Licensee’s means any person to whom a permit or a general or
specific license has been issued by the NRC.
“NRC”
means
the United States Nuclear Regulatory Commission.
“Rad” means a measure of the dose of any radiation to body tis-
sues
in terms of the energy absorbed per unit mass of the tissue.
One rad is the
dose corresponding to the absorption of
100 ergs
per gram of tissue.
(One millirad
(mrad)
=
0.001 rad),
“Radiation”
means any
or all of the following;
alpha rays,
beta rays, gamma rays,
X—rays, neutrons, highspeed electrons,
high-speed protons,
and
other atomic particles; but not sound or
radio waves, or visible,
infrared, or ultraviolet light.
“Radioactive material” and “radioactive emissions” means any
radioactive
material
in the form of dusts, particulates, fumes,
mists, vapors, or gases.
62-460

17
“Rem”
means
a
measure
of
the
dose
of any ionizing radiation to
body tissue in terms of its estimated biological effect relative
to
a dose received from an exposure to one roentgen of X-rays.
(One millirem (mrem)
=
0,001
rem).
The relation of rem to
other dose units depends upon
the
biological
effect under consid-
eration
and upon the condition of irradiation.
For the purpose of
this part,
any of the following
is considered to be equivalent to
a dose of one rem:
(a)
An exposure to one roentgen of
X— or gamma radiation;
(h)
A dose of one rad due to X—,
gamma,
or beta radia-
tion;
(c)
A dose of
0.1
rad
due to neutrons or high energy
protonS
(d)
A dose of 0.05 rad due
to
particles heavier than
protons and
with
sufficient energy to reach the
lens of the
eye.
If
it tS more convenient to
measure
the
neutron
flux,
or
equivalent,
than
to determine the neutron dose in rads~one rem
of neutron radiation may for purposes of this
part be
assumed
to be equivalent to 14 million
neutrons
per
square centimeter incident upon
the body;
or,
if there exists sufficient infor-
mation to estimate with reasonable accuracy
the approximate distribution in energy of neu-
trons, the incident number of neutrons per
square
centimeter equivalent to one rem may be
estimated
from
the following table.
Neutrca~
Theriral
.
.
.
.
.
.
.
.
0.0001
.
.
.
.
.
.
4
.
0.005
.
.
.
*
*
.
.
4
4
0,02
-
.
,
.
.
S
4
0.1
.
.
.
.
,
.
.
,
.
S
0
0
S
S
I
1.0
.
.
.
.
4
S
0
2.5
.
.
.
.
S
4
I
0
S
5.0
..
.
.
.
7,5
0
0
0
4
10.0
.
.
.
.
lOto3O
24x
24x
*
4
5
.
.
.
.
670
S
S
S
a
S
S
5
500
S
*
4
5
.
.
.
570
.
.
S
S
S
S
S
S
~
280
.
.
.
S
S
P
5
,
80
.
4
S
S
S
S
30
a
0
S
S
S
0
0
4
18
.
S
S
4
5
5
20
.
S
4
5
5
5
S
S
5
18
4
S
S
*
S
S
S
S
5
17
S
5
5
0
5
5
5
.
17
0
5
5
5
0
5
0
5
5
S
.
10
-
~utron
Flux
1~seEquivalents
Ni~nberof
neutrons
per
square
centineter
equivalent
to
a
Average
flux to
doliver
dose
of
1
100
millirem.J.n
40
hours
970 x
720
x
820 x
400 z
12~0x
43x
26x
29x
26x
4
a
a
0•
0
4
.
I
0
S
S
0
a
S
S
S
S
S
0
*
0
0
S
S
••
S
S
S
4•
S
S
S
P
14x
62-461

18
“Restricted area” means any
area
access
to
which
is
controlled
by
the
licensee for purposes of
protection of individuals from ex-
posure to radiation and radioactive
materials.
“Restricted area”
shall
not
include
any
areas
used
as
residential
quarters,
although
a separate room or rooms
in a residential building may be set
apart
as
a
restricted
area.
“Unrestricted
area”
means
any
area
access
to
which
is
not
con-
trolled
by
the
licensee
for
purposes of protection of individuals
from
exposure
to
radiation
and radioactive materials, and any
area
used
for
residential
quarters.
SUBPART
C~
STANDARDS
AND
LIMITATIONS
Section
i000.301’.~
Permissible
Levels
of
Radiation
in
Unrestricted
Areas
No
person
shall
possess~use, receive, or transfer licensed mater-
ial
or
engage
in
licensed
activities
in
such
manner
as
to
create
in
any
unrestricted
area
(a)
Radiation
1evei~
in
air
such.that any indi-
vidual
would
he
likely,.when
all radioactive
emissions by the
licensee,
are
taken
into
ac-
count,
to
receive
a
dose to the whole body
in excess of 0~5rein~.inany~oneyear;
(:b)
Radiation levels
in~air,
which,
if
an
indivi-
dual
were
continuously
present
in the area,
could~result,
when
all, radioactive emissions
by
the
licensee
are
taken
into
account,
in
his
receivinq
a
dose
in excess of
2 millirems
in any one
hour;
or
(c~
Radiation
1e~i~sin
air
which,
if
an indivi-
dual
were
cor~t~aous1ypresent
in
the
area,
could resui~
when
all
radioactive
emissions
by
ttie
lic
see
are
taken
into
account,
in
his receivinq
a
dose
in
excess of 100 milli—
rems
in
any
seven
consecutive
days.
Section
GOO. 302~ Ra~cactiveEmissions to Unrestricted Areas
(e~
No
person
sh~i... possess,
use, receive, or
~ransfer
.isens.ed
material
or engage
in, 14—
sensed
activ
..L:ics
so
as
to
release to ai~in
anunrestricrad
area
radioactive
material
in
concentrations
which
exceed
the
limits
~speci-
fled
in
Appendix
A
of
this
Part.
For pur—
~0~3CS
of this section concentrations may b~
averaged
over
a
period
not
greater
than
one
year
62-462

19
(b)
For
the
purpose
of
this section the concentration
limits
in
Appendix A
of this Part shall apply at the
boundary
of
the restricted
area.
The
concentration of
radioactive material
discharged through a stack, pipe
or similar conduit
may be determined with respect to
the point where the
material leaves the conduit.
If
the conduit discharges
within the restricted area,
the
concentration at the boundary may be determined by
applying established
factors for dilution, dispersion,
or decay betweeen the point of discharge and the boundary.
SUPBART
~
ADDITIONAL
REQUIREMENTS
Section l000~40l: Applicability
The provisions
of
this part apply to radiation doses received by
members of the public
in
the
general environment and to radio-
active materials introduced
into
the
general environment as the
result
of
operations which are
part of a nuclear fuel cycle.
Section 1000.402:
Definitions
As used in this
Subpart:
“Curie”
(Ci)
means
that quantity
of radioactive material
producing
37
billion nuclear transformations
per second•
(One
millicurie (mCi)=0,00l Ci.)
“Dose
equivalent” mean~
the
product
of
absorbed
dose and
appropriate factors to
account
for differencies in biological
effectiveness
due
to
the
quality
of radiation
and
its spatial
distribution
in
the
body.
The unit
of
dose equivalent is the
“rem,”
(One millirem (mrem)=0.0~lremj
“General
environment”
means
the
total
terrestrial,
atmospheric
and
aquatic
environments
outside
sites upon which any operation
which
is
part
of
a
nuclear
fuel
cyc’Ie is conducted.
“Gigawatt~year”
refers to
the quantity
of electrical energy
produced at the
busbar of
a generating station.
A gigawatt is
equal
to one billion
watts.
A gigawatt—year is equivalent to the
amount
of
energy output represented by an
average electric power
level
of
one gigawatt sustained
for one year.
“Member
of the public” means
any individual that can receive a
radiation dose
in
the
general
environment, whether he may or may
not
also be exposed
to
radiation
in
an occupation associated with
a
nuclear fuel cyc1e~ However,
an individual
is not considered a
member
of
the
public
dbring any period
in which he
is engaged in
carrying out any opera’tiofl
which
is part of a nuclear fuel cycle.
62.483

20
“Nuclear’
fuel
cycle”
means the’ operations defined to be
associated with the production~of
electrical
power
for
public
use
by any fuel cycle’throtigh
utilization of nuclear energy.
“Organ” means any
human
organ
exclusive
of
the
dermis,
the
epidermis,
or
the
cornea.
“Radiation”’
means
any
or all of the following:
Alpha, beta,
gamma, or X—rays;
neutronsi and high-’energy electrons, protons,
or
other
atomic
particles;
but not sound or radio waves, nor
visible,
infrared, or
ultra—violet light.
“Radioactive material”
means any material which spontaneously
emits
radiation.
“Site” means the area contained within the boundary of a
location
under the
control
of
persons possessing or
using
radioactive material
on’which is conducted one or more operations
covered
by
this
part.
“Uranium
fuel
cycle”
means the operations of milling of uranium
ore,
chemical
conversion
of uranium,
isotopic enrichment of
uranium,
fabrication
of uranium fuel, generation of electricity
by
a
light~water~’cooled.nuclear
power plant using uranium fuel,
and
reprocessing
of
spent
uranium fuel, to the extent that these
directly support
the
production of electrical power for public
use
utilizing
nuclear
energy, but excludes mining operations,
operations
at
waste
‘disposal sites, transportation of any
radioactive
material
in
support of these operations, and the
reuse
of
reeove~ed
nonuranium
special nuclear and by—product
materials
from the
cycle.
Section 1000,403:
Environmental
Standards for the Uranium
Fuel
Cycle
Operations covered
by
this
Subpart shall be conducted
in
such
a
manner
as
to
provide
reasonable assurance that:
(a)
Th’e
annual
dose
equivalent does not exceed 25 millirems
to the whole
body’,
75inillirems to the
thyroid,
and 25
millirems
to
any other organ
of any member of the
public
as
the result of exposures to planned discharges
of
radioactive
materials,
radon and its daughters
excepted,
to
the
general
environment
from uranium fuel
cycle operations
and to radiation from these operations.
(b)
The
total
quantity
of radioactive materials entering the
general environment
from the entire uranium fuel cycle,
per
gigawatt~-year
of electrical energy produced by the fuel
cycle, contains
less than 50,000 curies of krypton—85,
5
millicuries
of iodine—129, and 0.5 millicuries combined
of
plutonium-~239
and other alpha—emitting transuranic
radionuclides
with halflives greater than one year.
82464

21
SUBPART E:
RECORDS
Section
1000.501:
Records
(a)
All persons subject to this Part shall submit
to
the Department, with respect,
to any material
or
facility permitted or licensed by the NRC or
for
which
an
NRC permit or license
is sought:
(1)
Preliminary Safety Analysis Report
and
Final Safety Analysis Report,
as
described
in
10
C.F.R.
50.34
(2)
Appliostion
for Construction Permit
and for
all amendments thereto, in—
cludinc
information required by 10
C.F.R.
50.34a,
50.36, and 51.20
(3)
Environmental
Impact
Appraisal,
Draft
and Final Environmental
Impact
Statement, ~1egativeDe-
claration, or other document
prepared
by the NRC under
10
C.F.R.
51.5.
(4)
Operating
Permit
and
all amend-
ments thereto, including Techni~
cal
Specifications under 10
C.F.R,
50.36a.
(5)
i~plicationfor Amendment to
uperating License
(~)
ru
data, records, and reports
submitted
to the NRC in commec—
t:Lon
with
determining
or pre-
dicting radiation levels in air
in
unrestricted areas or the type
or
amount
of radioactive materials
emitted
into air conducted by or
for such
persons.
(b)
All records,
reports, and data received by
the Oartment pursuant to this Subpart shall
he
av~:’ilable
for public inspection at reason-
able times and upon reasonable notice.
Section 1000.502:
Notification of Incidents
All
person
subject
to
this Part shall immediately notify by
telephone
arid
telegraph,
mailgram, or facsimile, the Manager
of the
Office of Nuclear
Facility Safety of the Illinois Depart-
ment of Nuclear Safety,
1035 Outer Park Drive, Springfield,
Illinois
62704~of
any
incident or condition arising from the
62-465

22
use
or
possession of
licensed materials or facilities or
the
conducting
of
licensed
activities
which
may
have
caused
or
threatens
to
cause
emissions
or
radiation
levels
in
excess
of
those
allowed
under
this
Part.
Section 1000.503:
Other Provisions
(a)
The definitions set out in Subtitle B,
Part 201.102 apply to this Part.
tb)
All persons subject to this Part are sub—
ject
t~
the
requirements and provisions
35
Ill.
Adm~
Code 201,122,
201,123, 201.124,
201.125, 20Ll26,
201.141, 201.150 and
201
151.
62-466

23
APPENDIX A—CONCENT~ATIQfl$IN
AIR ABOVE
NATURAL
BACKGROUI~ID
Element (atomic
number)
Isotope1
pc.t/,nl
Actinium
(89).
.....~.
,...,...,.,Ac 227...
..s
8 x
I
9X1013
Ac 228.....S
3 X 10~
I
6X10~°
Americium
~
241~.....S
2 X
I
4X1012
Am 242iit....S
2 X
I
9X10~12
Am 242....S
1 X l0~
2 X
Am 243.....S
2 X io13
I
4Xl0~2
Am 244.....S
1 X
I
8X107
6 X
I
5X109
Sb
124.....S
5
x
I
7XI0~°
Sb
125. ....S
2
x
io8
I
9X10~°
Argon
(~8)..................,..A
37.......Sub2
1
X
10~
A 41.......Sub
4 X io_8
7X108
I
1X108
As 74......S
1
x
io8
I
4X109
As 76
4 X 10~
I
3X109
As 77......S
2 X
10
3:
1X1O’8
82-467

24
Astatine
(BS)...........,....,...At 213.....S
2 X 10~°
I
1X109
Barium
(5~).....,...............Ba131.....S
4 X io8
I
1X1O8
Ba 140.....S
4
X
10~
I
1X10~
Berkelium (97).......,.,,,..,...Bk 249....S
3
x
I
4X109
Bk
250....S
5 X 10~
I
4X108
Berylium t4).,,...........,.,,.~.Be7......S
2 X
I
4X108
Bismuth (83)..,,,,...,,,,,,,,,...Bi 206.....S
6 X
I
5X109
Bi 207.....S
6 X 10~
I
5X10~°
Ri 210.....S
2 X io10
I
2X10~°
Bi 212.....S
3 X
I
7X109
Bromine (35).....,,,,,,,,.,....,.Br82......S
4 X108
I
6X109
2X109
I
3X10~
Cd L15m....S
1 X l0~
I
1X109
Cd 115.....S
8 X
10~
I
6 X109
Calci~n(~0),.,.,,..,.,,,,..,..,.Ca45......S
1X 10~
i
4 X109
Ca 47......S
6 X
I
6X109
Californium ~
249.....S
5 X io_14
I
3X10~2
Cf
250.....S
2
X
io13
I
3X10~2
Cf
251.....S
6
X 10~
62-468
I
3
~

25
~f
252.....S
2
X
io~3
I
1X1012
Cf
253......s
3
x
I
3XlO~
Cf 254.....S
2 X io13
I
2X10~3
Carbon
(6).,,,..,.........~,,.C14.......S
1 X10~7
(C02).....Sub
1 X ~
6
2X108
I
5X109
Ce
143.....S
9
X
10~
I
7X109
Ce 144...,.S
3 x io~°
I
2X10~0
Cesium (55),....,
~
..,,,..,,.~s131.....S
4
x
10~
I
1X107
Cs
134.m....S
1 x io6
I
2X107
Cs
l34.....S
1 X
I
4X10~0
Cs
13~.....S
2
X
io~8
I
3X109
Cs
136.....S
1
x
io8
I
6X10~9
Cs L37.....S
2 x i0~
I
5Xl0~0
Chlorime fl7)...,.........,,..,,..C3.
36.....S
1 X io~8
I
8 X10~°
Cl. 38......S
9 x io8
I
7X10~
Chromium
(ad)..~.
~
.
....,...,.Cr 51....
.S
4 X
I
8X108
Cobalt
t27)......,...............Co
57......S
3. X10~
I.
6X109
Co
58m.....S
6
X
I
3X107
62-489

26
Co 58.....S
I
Co 60......S
I
I
I
Cm
243~.
.‘.
~.
~.
S
I
Cm
244,....S
I
Cm 245.....S
I
Cm
2~46.....S
I
Cm 247.,..s
I
Cm
248.....S
I
Cm 249.....s
I
I
Dy
L66.....S
I
253..
..
.5
I
Es
254m....S
I
Es
254,...S
I
Es
255..’.~.S
I
3 X
2
X
l0~~
1 X io~8
3
X
7 x io~
4
x
4 X~io~2
6
X
io~12
2~
x.
3
x
3
x
3 X io12
2
X
4 X
2 .X
4
x
2
X
io13
4 x
2
X
io14
4 X
4 x io~
4 x
9
X i08
7 X io~~
B X
7
X
l0~~
3 X
2
X
2 X
2
X
6 ‘X
4
IC
2
.X
1 X
Copp•r
(39)...,..,.,,,.,,,..,..,Cu
64......S
Curii.*m
(96)
.
. .
.
.
.
.,...,
,,...
. .
Cm
242.
.
. .
S
Dysprosium
(66)
.
.1
• •..•
,
~
.
.Dy
165....
.S
Einat~Lniwnt99).......,..,,.,..Es
82-470

27
Erbium
(68)............,..........Er369...,.$
I
Zy
.1
Europium
(63)
..,..
~
~
~?~3*9,2
brs)
.1
Eu
152.....S
(T/2.13
yrs)
.1
Eu
154....
.S
I
Eu
3.55....
.5
I
Fermium ~
I
TTA2SS.....S
.1
Fm
2S6.,
. .
I
Fluorine
(9)..
...
I
Gadolinium
(64)...~.,........,.....’Gd
2.53.....S
i
-Gd
l59.....S
Galli~im(31)-.....,........,.....,...Ga72......S
I
Germanium (32)_......,..,.,,..,..Ge
7l.......s
I
Gold
(7-9)-.
..
..
- .
-.
.-.•-••....
.....~u
396...
....-.s
I
Ma
~3.98..,..S
I
Au 19-9.....S
I
2
IC 10~
1
X io6
2.X
io8
2 X io8
1 X10~
1
IC
io8
4
x
6
IC
1o~~
1. X
2 X
io10
3
X
10~
3
X
2
X
2 X
6 X
.4
X io10
1
x
io10
6 X
2
IC
9
x
io8
8
IC
3 X
2
IC
io~
1 X
8
X
6 X 10~
4 X
io~
2
X
4
IC
2
x
io~8
1
IC
8 x
4
IC
io—B
3
IC io~8
62-471

28
hafnium
(73),,....,....,.,......Jf
l8l,~....S
1 X
10~
I
3X10~9
flo$mtu7n
(~7),..•.,,..,..,........Ho166.....S
7 X
I
6X10~9
$fy4go9en
~
2
IC
I
2X107
Sub
4
X 10~
Ir~4jum(49).,....................n
113m....S
3
X
l0~
3:
2X107
In 114m....S
4
IC
l0~
I
7X10~°
In 115m....S
8
IC
.3:
6X108
In L15.....S
9
IC
I
1X10~9
Iodine
(53).......,..............X
25......S
B X
I
6X109
I 126......s
9
IC 1011
I
1X108
I 129.,,...S
2
IC
I
2X109
I 133.......S
1
x
I
ixio~
I 132......S
3 X 10~
I
3X10~
I
133......S
4
X
10~
I
7Xl0~~9
I
134......S
6
x
1
.X
I 135.....S
I
x 1O~
I
X10~
Xyidtssrn
(771....,................Ir
190.....S
4
x
I
1X10~
Zr
192..,..S
4
X
I
9X10~0
82-472

6_Ot
X
I.
8e0t~t
60t
S
6e0t
X~C
8_0t
S
6
a_at S t
a_at S
C
8~~at
x £
a_at
S
V
a_at
S
£
6_ot * I
a_at
x 4
6_ot
x
S
6_0t S
1.
a_at
S
V
S
V
S
L
0t~ ~
Vt_Ot
5
8
Vt_Ot
S
P
a_at
S
~
8_OtS4
6e0t
S
P
6e0t
*
a_at
S
V
8_Ot
S
V
L_Ot t
£
L_Ottt
6_ot
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6_otxs
8_at t
£
8_ot
S £
6_otSc
I
i.e.
.ett ci
I
I
8’•••~Pt
q~g.
.~•.~
‘8.8
qfl••••••L.
31
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sr° •tce 3*’
I
P.S......
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I
r.I...SS
N1
I
25

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30
Neodymitun
(60),..,,,,...,.....Nd144.....S
3X
I
1 x :to~1
Nd 147.
-..S
1
IC
8
IC I0~
Nd 149.....S
6
IC
I
5XJL0~
Neptunium
(91).,,,,,•...,.,......Np 237.....S
1Xl0~”~
I
4
)C
Np 239.....S
3
IC
I
2
IC
:L0~
Nickel
(2~3)...,,.,..,....,.....Ni59......S
I
3X10
Ni 63....,.S
2
IC
i0~
-
-
I
I
1 X 10’
Ni 65......S
3
x io8
I
2X10~
Niobium (Columbiwn)
f41)..,,..•..Nb 9m.....S
4 X
10~’
I
5X10~~~9
Nb
95......s
2
IC
-
~
~
I
3X10~
~b 97......S
2
IC 1O~
I
2
IC
l0~
Osmiwn
(76).....,,,..,,.,.,...,..0s185.....S
2
I
2Xi0~
Os
191m..
.
.S
6 X 10
-
I
3X10’
Os
193.....S
4
IC
iU~
I
lxi
~
Os
193.....S
1
IC
I
9Xi0~
5X1u
I
3X10~
Pd 109.....S
2x~r~
I
82-474

31
?hosphorgs
(1St,..,..
...,.,..~..,..P
32. . .-...
,S
2
x10~
I
3Xl0~9
Platinum
(71)
,....,.,,..,..,
..,..-..
Pt
3.91.-.-..
.
S
3 X 10
8
I
2X10~
-Pt
393m....S
I
2X10~7
Pt
19~3-.....s
4 x
i
1x1o8
Pt
3.97m..-..S
2
x
I
2X10~7
Pt
3.97$
3
X1O~8
I
2X108
Plutonium
~
238.-.,..S
7
x
ixio~2
-Pu 239.-...-.S
6
IC
io—14
I
lXl0~2
-Pu
240.,......-S
6 X
I
IIC10~2
-Pu -2414....S
3X1O~2
I
lx
l0~
Pu
242.....S
6
IC
I
1IC10~
Pu 243....S
6 x
108
I
8X108
-Pu 244.... .5
6
IC
1O~14
I
1Xl0~2
Polonium
1$4),.,,,,~.,.,-,-.,-.,....,..Po
23.0... ,,.S
2
x
I
7X10~2
potassium
~
42......
.5
7
,X
10~
I
4Xl0~
p~~o4ym~~m
~
142-..
..S
7
X
10~
I
5Xl0’~9
Pr
143..,...S
ix
I
6Xl0~9
62-475

32
~ronethiun
(61),,,,...........,..Pm
147.~-.•.S
2~i01~
I
3X10~’
Pm 149... .-.S
1X401
I
8XlO~
P~otoaatinium
(93),•,..,,,.....Pa
230.....S
6 X
3X10~
Pa 231......S
4
IC
1O1~
I
4
IC
Pa
233.....S
2
X
6
x :~o~9
Rac~4um(88).•.,....... .........~.Ra223.....S
6X10~
I
BXIO
12
Ra
224.......S
I
2XiO~1
Ra
226.....s
3
X
lu
I
2X1C)~
Re 228.....S
2
x
i0~12
I
lx
Radon
(B6),,,,......,,....,...,..Rn220.....S
1 Xl0~8
3
Rn
222
~
3X10
9X10~8
I
5X10
Re
106.-....S
2
X
io8
I
8Xl0~
~e
187.....S
3 X
10’
I
2XiO~~
Re
188.~...-.S
1~x10~
I
6Xl0~
3-ICiO~.
I
2X10~4
Rb
105-.....s
3
X
lO~
I
2X10’~
Rubidium
(37)...............,..-.,Rb86......S
1Xl0”~8
I
2X10’~9
Rb 87......S
2’
IC
10~
I
2
IC
10
62-478

33
~tuthenium
(44)..,........,,.......Ru97.......$
8X108
I
6X108
Ru
103.....S
2
x
I
3X109
Ru 105..-.. .S
-2
X
10~
I
-2X10”8
Ru 106.....S
3 X
I
2X1010
Samarium
(62)...,...,..,,..,.,..,..$xn 147...-..S
2 X io’12
I
9X10~2
Sm
151.....S
2
X
I
5X109
Sm
L53.....S
2
X
I
1X108
Scandium
(21).,,...,......,........$c
4~......S
B X 10’~
I
8X10~°
Sc
47......S
2
IC
10~
I
2X108
Sc
48......S
6
X
I
5X109
Selenium (34)...,,.,.,,..,.....,..Se 75......S
4
x i0~
I
4X109
Silicon ~
.Si 31..... .5
2 X
I
3X108
Silver
~
105....eS
2
IC
10~
I
3X109
Ag
llOm....S
7
X l0~
I
3X10”10
Ag.
U1.....E
1
X
10~
I
8X109
Sodium (11).........,..,..-........Na 22......S
6
X l0~
-I
3
X
Na 24......S
4 X 10—B
I
5X109
62-477

34
Strontium
(3B).,................Sr
85m.....S.
1X
I
1X1O’6
Sr 85......S
8 X 10~
I
4X109
Sr
89......S
3 X 10~
I
1X.0~
Sr 90......S
3
X
I
2X10~0
Sr 93.......S
2 X 10~
I
9X109
Sr
92......S
2 X 10~
I
1X1O”8
~u1fur
(16)..,.,,,,,..,....,.$
35•••••.•$
9
X
10~
I
9X109
Tantalum
~
1X109
I
7X101°
Technetium
(43),..,........,.....Tc96m.....S
3X106
I
1X1O6
Tc 96......S
2 X
10~
I
8X109
Ta 97m.....S
B
IC
I
5X109
Ta
97......S
4
x io~
I
1X10~8
Tc
99m.....S
1 X io6
I
5X10~7
Ta 99......S
7
X
10~
I
2Xl09
Tellurium (52)..,.,,,.,........,.Ts125m....S
lX1O~8
I
4X109
Te .12.7m.,.... .S
5 X 10~
I
1X109
Te 127.....S
6
X l0~
I
3X10’8
Ta l29m....S
3 X 10~
I
1X109
62-478

35
Te
129....S
2
X
I
ixio7
Te
l3lin..,.$
1-
X
io8
I
6X10’~
Te
132.....$
7
X 10~
I
4X109
Terbium
(6fl-...~.,
..,.1,.,,.....-,,,..--.-.Tb 160.
. ..
.5
3 X
1O~
I
1X1O9
Thallium
~
~.,.T3.
200.....S
9
IC 108
I
4X108
TI. 20l.....S
7 X io8
I
3Xi0~
Ti 202.....S
3 X
I
B. X
Ti 204.....S
2-
X~IO~
I
9X101°
Thorium ~
227.....S
I. X
I
6 X io12
Th
228.....s-
3 x
I
2 X
iodl3
Tb 230.....S
B X l0~~
I
3X10”13
Tb 231..,...S
5 X
I
4Xi0’~
Th 232.,....S
3.
X
I
1 X 10~
Tb
naturai.S
2
X
I
2
X
Tb
234.
.
.
.
S
2 X
I
1X10~9
Thulium
(69-)--....-..........~......-.
.,.
.
.Tm
170.
.
.
.S
1, X 10~
I
1XiO9
Tm 171.....S
4
X10~9
I
BX1O’9
62-479

36
Tin
(50).....,....,....~........Snl13.,...S
ixio’~
I
2X309
Sn
125......S
4 X l0~
I
3X109
Tungsten
(Wolfram)
(74)..........W
181......s
B
x
I
4X109
w
~
3
-X
I
4Xl0~9
2~Xl08
I
lXlO8
Uranium(92).........---
,.,..,..U230,..,..S
I
U
232......S
3
x
I
9X1013
U
233......S
2
X
I
4Xi0~2
U
234..
~
1~
x-
io~
I
4X1012
U
235....,S4
2
IC
I
4X1012
U
236.....S
2
X
I
4X3.0d12
U 238......S~
3
X
I
5X10~12
U
240.....S
B
X l0~
I
6X109
U-natural.
~4
5
)~lO~
I
5Xl0~2
Vanadium(23).,..,.,.,............V48,..,..S
6XlO’9
I
2X109
Xenon (54).......,,.,...,.......Xe
131m....-.Sub
4 Xl0~
Xe
133.....Sub
3
X
10
Xe133m....Sub
3X107
Xe 135....Sub
1 X 10
82-480

37
Ytterbium
(70).
. . . . • .
.
.
.
.
.
•.
.
.
.
.Yb
175.,
.
.
.
I
Yttrium
(39)
• •.
. • ..
. .
.
.
.
.
. . .
.
.
Y 90,
.
.
.
.
.
S
I
Y 9lm..,...S
I
Y 9l.......S
3:
Y
92
.
.
.
.
.
.
.
S
I
Y 93.......S
I
Zinc
(3D)
•..-....
..
•...
~-
-.......
.
.
Zn
65.,..
.
.S
I
Zn
69m......S
I
Zn
69......S
I
Zirconium
(40),.,.4.,,.,.,,.
.-.-..
.
.
.Zr
93.....
.S
I
Zr
95.......S
I
Zr
97..-....S
I
Any
single
radiomua3.ide
not..4....444
.
....
.Sub
listed
above:
with
decay
mode
other than alpha
emission
-
or s~ntaneous
fission
and~
with-
radio-
active half-life
3.eas-
than 2
hourz~
Any
single radionuclide not...
..
.
.....
0~
lflted
above
with decay
mode
other
than
alpha
emission- or
spontaneous
fission and
-
with radio-
active-
ha~f.u3~if*
grsa~r
than 2 hours.
2 X io8
2
X
4 X 1O~
3
X 10~~
8 X
6
1
1 X
1 x-
1 X 10’~
1 X
6 1
5
X
4 X
2 X 10~~
1 X
1
x
2 X
3X
4
X
10’~
1.
X
10~~
4 1
10~~
3.
X
4
X
3 X
3
IC
i
x
82-481

38
Any
single
radionuclide
~ot........,.....,,,,
2 1
io14
listed
above,
which
de~
cays
by alpha
emission
or spontaneous fission.
~‘So1ub1eCS); Insoluble
(I).
~
means
that
values given are for
submersion
in a semispherical
infinite
cloud
of
airborne
material.
3These
radon
concent
~tione
are
appropriate
for
protection
from
radon-222
combined
wit,
s
short-lived
daughters.
The
value
may
be
replaced
by
one-thirti
~l/30)
of
a
“working
level.”
(A
“working
level”
is
defined
as
a
mbination
of
short-lived
radon—222 daugh-
ters,
pol.onium—218, 1e~
-:~-i------:~
14~
bisinuth—2 14
and
poloniurn—214
-,
in
one
liter of air, without ~
to the degree pf equilibrium, that
will.
result
in
the
ultimate
~-:~::~~sionof
I ~3
X’ l0’~ May
of
-
alpha -particle
energy.)
4For
soluble
mixture~
~:;:-f
U-238, U-234
and
U-235
in
air
chemical
toxicity
may
be
the
lim~-:~:::~:,ng
factor,
The concentration value is
0.007 milligrams uraniwt~ er cubic meter o.~air.
The specific
activity
for natural uranium i-s 6.77 x 10
curies per gram U.
The
specific activity for other mixtures of t~—238,U—235
and
U—234, if
not
known,
shall be:
SA=3.6 X 10~ curies/gram U
U-depleted
SA=(0.4
+
0.38
E + 0.0034 E2)
io6
E ~
0.72
where Eis the percentage
by weight of U-235, expressed as percent.
NOTE:
In
any case where there
is a mixture in air
of
more
than
one
rada.onuclide,
the
limiting
values
for
purposes
of
this
Apoendis
should
be determined as follows:
1.
If
the
identity
and
concentration of each radionuclide
in
the mixture
are
known,
the
limiting
values
should
be
derived
as
follows:
Determine,
for
each radionuclide in the n~ixture,the
ratio
between
the
quantity present in
the
mixture
-and the limit
otherwise established
in
Appendix
A for
the
specific
radionuclide
when
not
in
a
mixtures
The
eum of
such
ratios
for
all
the
radio—
nuclides
in
the
mixture
may
not exceed “1”
(i.e.,
“unity”)
EXAWLE:
If
radionuelides
A,
B, and C are
present in concen-
trat~~nsCA
C5,
C~,
and
if
the applicable
MPC’s
are
MPCA,
and
MPCB,
and
MPC~
respectively, then the concentrations shall be
limited
so
that
the
followix~grelationship
--exi~ta;.
(CA/NPCA)
+ (CB/MPCB)
+
(Cc/I4PCc)
~
2.
If either the identity or the concentration of any radio-
nuclide
in
the
mixture
is
not
knownL1~he
limiting
values
for
pur-
poses
of
Appendix
A
shall
be
2 X
10
3.
If
any
of
the
th-~~itionsspecified
below
are
met,
the
car—
responding
values
specii~:~d
below
may be
used in lieu of those
specified in paragraph
~bove,
62-482

39
a.
If
the
identity
of
each
radionuclide
in
the
mixture is
known
but the
concentration
of
one
or
more
of
the
radionuclides
in the
mixture
is not
-
known the
concentration
limit for the
mix-
ture
is
the
limit specified in Appendix A for the
radionucl,ide
in the mixture having the lowest
concentration
limit;
or
b.
If
the
identity of each
radionuclide
in
the
mixture is
not
known,
but it
is
known
that
certain
radionuclides,
specified-
in
Appendix
A are not-present in the mixture,
the concentra-
tion limit for the mixture
is
the
lowest
concentration
limit
specified in Appendix A
for
any
radionuclide
which
is not
known
to be absent from
the ~isture; or
c.
Element
(atom~
number)
and isotope
pCi/mi
If it is
known
that
alpha—emitters
and
Sr
90,
1 X
I
129,
Pb
210,
Ac
227,
Ba
228,
Pa
230,
Pu 241, and Bk
249
are
not
present.
If it is known that alpha—emitters and
Pb 210,
1
X
Ac 227,
Ba 228,
and Pu 241 are not present.
If it is known that alpha-emitters and Ac 227
1
IC 1012
are not present.
If it is known that Ac 227, Tb 230, Pa
231,
1
X
Pu 238, Pu 239r Pu 240, Pu 242, Pu
244,
Cm 248, Cf 249 and
Cf
251
are
not
present.
4.
If a mixture
of
radionuclides consists of uranium
and its
daughters in
ore
dust
p~rior
to
chemical
separation
of
the
uranium.
from
the
ore,
the
following
values
may
be
used
for
uranium
and
its
daughters
through
radiura-226,
instead
of
those
from
paraqraphs
1,
2,
or 3 above:
3
x
io~2
pci/mi
gross
alpha
activity;
2
X
io~2
pci/mi
natural
uranium~ or
3
micrograms per cubic meter
of
air
natural
uranium.
For
purposes
of
this
note,
a
radionuclide
may
be
consie~ered~
as not present
in a
mixture if
(a) the ratio of the
concentration-
of
that
raclionuclide
in
the
mixture
(~)
to the
concentration
~
for that radionuclide
specified in A~ndix A
(MPC
)
does ~ot
exceed
1/10
(i,e~,C,~/MPç
~
1/10),
and
(b)
the
sum
of
su&h
ratios for aU
the
radionud1ideS’~considered
as
not
present
in
the
mixture does
not
exceed 1/4,
i.e.
(CA/MPCA +
CB/MPCB~.
.+~
1/4).
82-483

40
IT
IS SO ORDERED-~
Board Member
J
Th-eodore
Meyer concurred.
I,
Dorothy
M,
Gunn~
Clerk of the Illinois Pollution Control
Board, hereby
certify
that
the ab
ye Opinion and Order was
adopted on the
c~k~-
day
of
________________,
1985
by
a
voteof
5—0
.
/
4~L7
/1~/L~lA)
Dorothy
M.
,öunn,
Clerk
Illinois
Pollution
Control
Board
62-484

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