ML20199E384
| ML20199E384 | |
| Person / Time | |
|---|---|
| Issue date: | 12/18/1997 |
| From: | Obrien T NRC |
| To: | Salomon S, Usilton B NRC |
| Shared Package | |
| ML20199E212 | List: |
| References | |
| NUDOCS 9802020144 | |
| Download: ML20199E384 (37) | |
Text
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From:
Thomas O'Brien Tol ens,bgu Dates 12/10/97 11:10am Steve.
.I understand you will consolidate the UTAH review (#78326).
I reviewed sections R313-15 and R31348 I determined that these regulations are compatible and therefore have no comments.
As a side note, however, Utah's R313 15 1201 section adopts the proposed I
wording provided in the August 1997 drafC SSR equivalent part. Discussion w/
j Pat Larkins indicated this is acceptable even though it is much more l.
stringent. We have not yet approved this draft SSR (D. Blanton is in the l
process). My concern is if we do NOT approve the draft SSR wording, this may j
conflict with the finding of compatible for the Utah regs.
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~ Brenda-N,
- e Please close out my ticket on this task.
For your RATS:
The revisions to Utah's R313-15 implement the NRC rules listed below:
- Resolution of Dual Regulation of Airborne Effluents of Radioactive Materials (all parts)
- Criteria for Release of Individuals Administered Radioactive Material (all parts)
- Frequency of Medical Examinations for Use of Respiratory Protection Equipment (all parts)
- Radiation protection requirements: Amended Definitions and Criteria (all parts)
Low Level Waste Manifest (Part 20 only)
. - Medical Administration of' Radiation and Radioactive Materials (part 20 only)
- Termination or transfer of licensed activities: Housekeeping requirements-(part 20 only)
PDR s
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i State of Utah i DEFARTMENT OF ENVIRONMENTAL QUAL.lTY DIVISION OF RADIATION CONTROL i
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November 24,1997 Charles Ilackney State Agreements Program py,,/)m Nuclear Regulatory Commission N
611 Ryan Plaza Drive Suite 400 D ('T,:)>
[,lh I t, 30, S{}
r Arlington, Texas 76011 ()/C' )
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Dear Mr. llackney:
The Division of Radiati in Control (DRC)is currently working on a nu9 er of rulemaking actions which are l
compatibility items. We arejhroposing to change R31312, General Provisiotu; R31315, Standards for Protection Acainst Radiation; R31318, Notices. Instructions and Reoorts to Workers by 1.icensees or c '-
lkglitranti::.irupectiorul R313 25, License Reauirements for I and Disnosal oflbdioactive Waste--General 9
'w) Provision' and R313 32 Medical Use of radioactive Material.
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(,Phrh. O o Y B C ) S m 9 10#
Our rulemalping process involves the Utah Radiation Control Boaid, Aner presentation to the lloard, the rules are Oled with the Utah Division of Administrative Rules. At this time, a 30 day public comment period is expected to open on December 1,1997. The DRC expcets to Onalire and adopt the rules about January 23, 1998.
Please And enclosed a hard copy and a Wordperfect (version 6.1) electronic copy of the proposed rules. New s
text is shown with an underline. Deleted text is interlined and placed within brackets, ifyou have questions, please contact Craig Jones at (801) 536-4250.
Sincerely,:
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Vilham J. Sinclejr, Director Division of Raditnid Control
Enclosure:
LAs stated i
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R313. Environmental Quality, Radiation Control.
2 R313 14.
Notices, Instructions and Esports to Workers by Licensees or 3
Registrants **Inapections.
4 R313-18 1.
Purpose and Authority.
5 (1)
The purpose of this rule is to establish requirements for notices, 6
instructions and reports by licensees or registrants to individuals engaged in 7
work under a license or registration and options available to such individuals 8
in connectior, with inspections of licensees or registrants.
9 (2) The rules set forth herein are adopted pursuant to the provisions of l
10 sections 19-3-104(3) and 19-3-104 (6).
11 12 R313-18 2.
General.
13 The rules of R313-18 shall apply to all persons who receive, possess, use, 14 own or transfer a source of radiation licensed by or registered with the 15 Department pursuant to the rules in R313-16, R313-19 or R313-22, 16 17 R313-18-11.
Posting of Notices to Workers.
18 (1)
Licensees or registrants shall post current copies of the following a
19 documents:
20 (a) the rules in R313-15 and R313-18; 21 (b) the license, certificate of registration, conditions or documents 22 incorporated into the license by reference and amendments thereto; 23 (c) the operating procedures applicable to work under the license or 24 registrations and 25 (d) a notice of violation involving radiological wotsing conditions, 26 proposed imposition of civil penalty, order issued pursuant to R313-14, or any 27 response from the licensee or registrant.
28 (2)
If posting of a document specified in R313-10-11(1) (a), (b), or (c) 1
e 0
1 is not practicable, the lics. see or registrant may post a notice which describes 3
the document and states where it may be examined.
3 (3)
DRC-04 " Notice to Employees," shall be posted by licensees or 4
registrants wherever individuals work in or frequent a portion of a restricted 5
area.
l 6
(4)
Documents from the Executive Secretary which are posted pursuant to 7
R313-18 11 (1) (d) shall be posted within five working days after receipt of the 8
documents from the Executive Secretary; the licensee's or registrant's response, 9
if there is one, shall be posted for a minimum of five working days after 10 dispatch from the licensee or registrant. The documents shall remain posted for 11 a minimum of five working days or until action correcting the violation has been 13 competed, whichever is later.
13 (5) Documents, notices or forms posted pursuant to R313-10-11 shall appear 14 in a aufficient number of places to permit indiviouals engaged in work under the 15 license or registration to observe them on the way to or f rom any particular work 16 location to which the document applies, shall be conspicuous, and shall be 17 replaced if defaced or altered.
18 19 R313 18 12.
Instructions to Workers.
20 (1) All individuals who in the course of emolovment are likely to receive 31 in a year an occupational dose in excess of 1.0 msv (100 mrem):
23 (a) shall be kept informed of the storage, transfer, or use of sources of 23 radiation in the licensee's or recistrant's workolace; 34 (b) shall be instructed in the health protection considerations associated 35 with exposure to radiation or radioactive material to the individual and 36 potential offspring, in precautions or procedures to minimize exposure, and in 27 the purposes and functions of protective devices employed; 38 (c) e, hall be instructed in, and instructed to observe, to the extent 2
d 1
within the worker's control, the applicable provisions of these rules and F
2 licenses for the protection of personnel from exposure to radiation or 3
radioactive material; J
4 (d) shall be instructed as to their responsibility to report promptly to 5
the licensee or registrant a condition which may constitute, lead to, or cause 6
a violation of the Act, these rules, and licenses or unnecessary exposure to 7
radiation or radioactive materials 8
(e) shall be instructed in the appropriate response to warnings made in 9
the event of an unusual occurrence or malfunction that may involve exposure to 10 radiation or radioactive materials and 11 (f) shall be advised as to the radiation exposure reports which workers 12 shall be furnished pursuant to R313-18-13.
13 (2) In determinina thnaa individuals aubiect to the raauirements of R113-14 19-12(1).
licanmaan must take into consideration amnioned activities durina 15 normal and abnormal aituatinns involvina ernemure to radiation or radioactive 16 material which can romannably be evnacted to occur durina the life of a liennned 17 hellity. The extent of these instructions shall be commensurate with potential 18 radiological health protection considerations for the workolace.
19
-20 R313-is-13. Notifications and Reports to Individuals.
4 21 (1)
Radiation exposure data for an individual and the rdtits of 22-measurements, analyses, end calculations of radioactive material depesited se 23 retained in the body of an individual tshall be reported to the individual as 24 specified in R313-18-13. The information reported shell include data and resulta 25 obtained pursuant tc these rules, orders, or license conditions, as shown in 26 records maintained-by the licensee or registrant pursuant to R313-15-1107.
27 Notifications and reports shall 28 (a) be in writing:
3
1 (b) include appropriate identifying data such as the name of the licensee 2
or registrant, the name of the individual, and the individual's identification 3
number, preferably social security numbers I
4 (c) include the individual's exposure information; and 5
(d) contain the following statement:
6 "This report is furnished to you under the provisions of the Utah 7
Administrative Code Section R313-18-13.
You should preserve this report for l
8 further reference."
9 (2) Licensees or registrants shall [ advice) furnish to each worker annually 10 a written renort of the worker's dose as shown in records mainthined by the 11 licensee or registrant pursuant to R313-15-1107.
12 (3)
Licensees or registrants shall furnish a written report of the 13 worker's exposure to sources of radiation at the request of a worker formerly 14 engaged in activities controlled by the licensee or registrant. The report shall 15 include the dose record for each year the worker was required to be monitored 16 pursuant to R313-15-502.
The report shall be furn.shed within 30 days from the 17 date of the request, or within 30 days after the dose of the individual has been 18 determined by the licensee or registrant, whichever is later.
The report shall 19 cover the period of time that the worker's activities involved exposure to 20 sources of radiation and shall include the dates and locations of work under the al license or registration in which the worker participated during this period.
22 (4) When a licensee or registrant is required pursuant to R313-15-1202.
23 R313-15-1203 or R313-15-1204 to report to the Executive Secretary an exposure 24 of an individual to sources of radiation, the licensee or the registrant shall 25 also provide the individual a nitten report on the exposure data included 36 therein. Reports shall be transmitted at a time not later than the transmittal 27 to the Executive Secretary.
l 28 (5)
At the request of a worker who is terminating employment with the 4
1 licensee or registrant in work involving exposure to radiation or radioactive 2
material, during the current year, the licensee or registrant shall provide at
-3 termination to the worker, or to the worker's designee, a written report 4
regarding the radiation dose received by that worker f rom operations of the 5
licensee or registrant during the current year or fraction thereof.
If the most 6
recent individual monitoring results are not available at that time, a written 7
estimate of the dose shall be provided together with a clear indication that this 8
is an estimate.
9 10 R313-18-14. Presence of Representativee of Licensees er Registrants and workers 11 During Inspection.
118
- 3) Licensees or registrants shall-afford representatives of the Board or 13 the Executive Secretary, at reasonable times, the opportunity to inspect 14 materials, machines, activities, facilities, premises, and records pursuant to 15 these rules.
16 (2)
During an inspection, representatives of the Board or the Executive 17 Secreta:y may consult privately with workers as specified in R313-1B-15.
The 18 licensee or registrant may accompany representatives during other phases of an 19 inspection.
20.
(3)
If, at the time of inspection, an individual has been authorized by 21 the workers to represent them during Department inspections, the licensee or 22 registrant shall notify the representatives of the Board or the Executive 23.
Secretary of the authorization and shall give the workers' representative an 24 opportunity to accompany the representatives during the inspection of physical I
25 working conditions, 26 (4) The workers' representative shall be routinely engaged in work under 27 control of the licensee or registrant and shall have received instructions as 28 specified in R313-18-12.
5
1 (5) Different representatives of licensees or registrants and workers may 3
accompany the representatives of the Board or the Executive Secretary during 3
different phases of an inrpection if there is no resulting interference with the 4
conduct of the inspection. Ilowever, only one workers' representative at a timo 1
5 may accompany the representatives of the Board or tne Executive Secretary.
6 (6)
With the approval of the licensee or registrant and the workers' 7
representative, an individual who is not routinely engaged in work under control 8
of the licensee or registrant, for example, a consultant to the licensee or 9
registrant or to the workers' representative, shall be afforded the opportunity 10 to accompany representatives of the Board or the Executive Secretary during the 11 inspection of physical working conditions.
12 (7)
Notwithstanding the other provisions of R313-18-14, representatives 13 of the Board or the Executive Secretary are authorized to refuse to permit 14 accompaniment by an indivitia,' who deliberately interf eres with a fair and 15 orderly inspection.
With regard to areas containing information classified by 16 an Agency of the U.S.
Government in the interest of national security, an 17 individual who accompanies an inspector may have access to such information only 18 if authorized to do so.
With regard to areas containing proprietary information, 19 the workers' representative for that area shall be an individual previously 30 authorized by the licensee or registrant to enter that area.
31 22 R313-18-15.
Consultation with workers During Inspections.
33 (1)
Representatives of the Board or the Executive Secretary may consult 34 privately with workers concerning matters of occupational radiation protection 35 and other matters related to applicable provisions of these rules and licenses 36 to the extent the representatives deem necessary for the conduct of an effective I
s 37 and thorough inspection.
28 (2) During the course of an inspection, workers may bring privately to the I
l 6
1 I'
(
1-attention of the representatives of the Board or the Executive Secretary, either 2
orally or in writing, a past or present condition whica the worker has reason to 3
believe may have contributed to or caused a violation of the Act, these rules.
4-or license condition, or an unnecessary exposure of an individual to sources of 5'
radiation under the licensee's or registrant's control.. A notice in writing 6
shall comply with the requirements of R313-18 16 (1).
7 (3)
The provisions of R313 18-15 (2) shall not be interpreted as i
8 authorization to disregard instructions pursuant to R313-18-12.
9 10 m313-le 16.
Request by workers for Inspections.
11 (1) A worker or representative of workers believing that a violatien of
- 12
-the Act,'these rules, or-license conditions exists or has occurred in work under
- 13 a license or registration witi? regard to radiological working conditions in which 14 the worker'is engaged, may raquest an inspection by giving notice of the alleged 15 violation to the Executive Secretary. The notice shall be in writing, shall set
. 16 forth the specific grounds for the notice, and shall be signed by the worker or
- 17 representative of the workers.
A copy shall be provided _ to the licensee or
- 18 registrant by representatives of the Bott A or t he Executive Secretary no later 19 than at the time of inspection except that, upon the request of the worker giving 20 the notice, his name and the name of individuals referred to therein shall not 21 appear in a copy or on a record published, released, or made available by the 22 Department except for good cause shown.
23 (2)
If, upon receipt of the notice,' representatives of the Board or the 24 Executive Secretary, determine that the complaint meets the requirements set -
25L forth in R313-18-16 (1), and that there are reasonable grounda to believe that the 2 6 --
alleged violation exists or has occurred, an inspection shall be made as soon as
. 27; practicable to determine if the alleged violation exists or has occurred.
28 Inspections pursuant to R313-18-16 need not be limited to matters referred to in 7
\\
I 1
thel complaint.
2jfj(bf f
(3)
A-licensee, registrant-or contractor or subcontractor of a licensee 3
or registrant shall-not discharge or.discrimit. ate against a worker because that 4
worker has. filed a complaint or instituted or caused to be instituted a 5'-
proceeding under these rules or :has testified or is about to testify in a 6
proceeding or because of the exercise by the worker on behalf of the worker or 7
others of an option afforded by R313-18.
8 9
m313-1s-17.
Inspections not warranted -- Informal Review.
10_
(1) (a)
If the representatives of ' the Board or ' the Executive Secretary 11 determine, with respect to a complaint under Section R313-18 16, that an 12 inspection is not warranted because there are no reason:=bla grounds to believe 1 *,s that a violation exists or has occurred, the Executive Secretary shall notify the 14-complainant in writing of that determination. The complainant may obtain review 15 of the determination by submitting a written staterrent of psition.with the 16 Executive Secretary.
The Executive Secretary will provide the licensee or 17
- registrant with a copy of the statement-by certified mail, excluding, at the 18 request of the complainant, the name of the complainant.
'The licensee or
.19 registrant may submit an opposing written statement of position with the 20 Executive Secretary. The Executive Secretary will provide the complainant with 21' a copy of the statement by certified mail.
22 (b)
Upon the request of the complainant, the Board may hold an informal
'23 conference in which the complainant and the licensee or registrant may orally 24 present their views.. An informal' conference may also be held at the request of 25~
the licensee or registrant, but disclosure of the identity of the complainant 26-will -be made only following receipt of written authorization from the 27
. complainant. Af ter considering written and oral views presented, the Board shall 28 affirm,' modify, or reverse the determination of the representatives of the Board l
8 g
+-
e i
e 1
or the Executive Secretary and furnish the complainant and the licensee or 2
registrant a written notification of the decision and the reason therefor.
3 (2)
If the Executive Secretary determines that an inspection is not 4
warranted because the requirements of R313-18-16 (1) have not been met, the 5
complainant shall be notified in writing of the determination. The determination 6
shall be without prejudice to the filing of a new complaint meeting the 7
requirements of R313-18-16 (1).
8 9
xrY: radioactive material, inspection, radiation safety, licensing 10 (MH)12B 19-3-104 11 Notice of Continuation March 26, 1997 19-3 108 12 13 14 9
}-.T f c3 d J
1 R313.
Environmental Quality, Radiation Control.
l L-2 1313 15.
Standards for Protection Against Radiation.
3 R313-15-1.
Purpose, Authority and Scope.
h5 4
(1)
R313-15 establianes standards for protection against ionizing 5
radiation resulting from activities conducted pursuant to licenses issued by the 6
Executive Secretary. These rules are issued pursuant to Sections 19-3-104(3) and 7
19-3-104(6).
8 (2) The requirements of Rule R313-15 are designed to control the receipt, 9
possession, use, trasfer, and disposal of sources of radiation by any licensee g
10 or registrant so the total dose to an individual, including dosna resulting from 11 all sources of radiation other than background radiation, does not exceed the s
12 standards for protection against radiation prescribed jn Rule R313-15.
- However, 13 nothing in Rule R313-15 shall be construed as limiting actions that may be 14 necessary to protect health and safety.
15 (3) Except as specifically provided in other sections of these rules, Rule 16 R313-15 applies to persons licensed or registered by the Executive Secretary to l
17 receive, possess, use, transfer, or dispose of sources of radiation. The limits 18 in Rule R313-15 do not apply to doses due to background radiation, to exposure 19 of patients to radiation for the purpose of medical diagnosis or therapy, in 20 exeonure from individuals administered radioactive material and released in 21 accordance with Section R313-32-75. or to exposure from voluntary participacion 22 in medical research programs.
23 24 R313-25-2.
Definitious.
25
" Annual limit on intake" (ALI) means the derived limit for the amount of 26 radioactive material taken into the body of an adult worker by inhalation or 27 ingestion in a year. ALI is the smaller value of intake of a given radio 2clide 28 in a year by the reference man that would result in a committed effective dose 1
1 equivalent of 0.05 sv (5 retM or a committed dose etsivalent of 0.5 Sv (50 rem) 2 to any individual organ or tissue. ALI values for intake by 8tgestion and by 3
inhalation of selected radionuclides are given in Table I, c Oc.ts 1 and 2, if 4
Appendix B of 10 CFR 20.1001 to 20.2402, 199(3)2 ed., which is incorporated by 5
reference.
6
" Class" means a classification scheme for inhaled material according to its 7
rate of clearance from the pulmonary zegion of the lung.
Materials are 8
classified as D, W, or Y, which applie9 to a range of clearance half-times: for 9
Class D, Days, of less than ten dayr,, for Class W, Weeks, from ten to 100 days 10 and for Class Y, Years, of greater than 100 days. For purposes of these rules, 11 alung class" and " inhalation class" are equivalent terms.
12
" constraint (dose constraint)" means a value above which snecified licensee 13 stations are recuired.
14
" Declared pregnant woman" means a woman who has voluntarily informed her 15 employer, in writing, of her pregnancy and the estimated dat., of conception.
16
" Derived air concentration" (DAC) means the concentration of a given 17 radionuclide in air which, if breathed by the reference man for a working year 18 of 2,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> under conditions of light work, results in an intake of one ALI.
19 For purposes of these rules, the condition of light work is an inhalation rate 20 of 1.2 cubic meters of air per hour far 2,000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> in a year. DAC values are 21 given in Table I, Column 3, of Appendix B of 10 CFR 20.1001 to 20.2402, 199(s]2 22 ed., which is incorporated by reference.
23
" Derived air concentration-hour" mA0-hour) means the product of the 24 concentration of radioactive material in air, expressed as a fraction or multiple 25 of the derived air concentration for each radionuclide, and the time of exposure 26 to that radionuclide, in hours.
A licensee or registrant may take 2,000 DAC-27 hours to represent one ALI, equivalent to a committed effective dose equivalent 28 of 0.05 Sv (5 rem).
j i
2 i
1
_m
9
- s
if
' Dosimetry processor" means an individual or an organization that processes 2-
.and evaluates-individual monitoring devices in order to determine the radiation 3
dose delivered to the monitoring _ devices.
4
" Inhalation claes", refer to " Class".
5
" Labeled package" means a package labeled with a Radioactive White I,
6 Yellow II,'or Yellow III label as specified in U.S. Department of Transportation
-7 regulations'49 CFR 172.403 and 49 CFR 172.436-through 440, 199 [-}]2 ed.
Labeling
-8 of packages containing radioactive materials is required by the U.S. Department 9
of. Transportation if the amount and type of radioactive material exceeds the
!10 limits for an-excepted quantity or article as defined and limited by U.S.
11-Department of Transportation regulations 49 CFR 173.403 (m) and (w) and 49 CFR 12 173.421 through 424, 199(h)2 ed.
=13
" Lung class", refer to " Class".
14 "Nonstochastic effect" means a health effect, _the severity of which varies-15 with the dose and for which a threshold is believed to exist. Radiation-induced
_- 16
_ cataract formation is_an_ example of a:nonstochastic effect. -For purposes of 17-these rules, " deterministic etfect" is an equivalent term.
18.
" Planned special exposure" means -: an inf requent. exposure to radiation, 19 separate from and in addition to the annual occupational dose limits.
20
" Quarter" means a period of time equal to one-fourth of the year observed 21 by the licensee, approximately 13 consecutive weeks, providing that the beginning
'22
_of the-first quarter in a year coincides with the starting date of the year and
'23-that no day is omitted or duplicated in consecutive quarters.
24-
" Reference Man" means a hypothetical aggregation of human physical and 25 physic,.ogical characteristics determined by international consensus.
These 26 characteristics may be used by researchers and public health (us;kcr;]emolovees 27 to standardize results of experiments and to relate biological insult to a common 28 base.
A description of the Reference Man is contained in the International 3
1
1 commission c7 Radiological protection report, -ICRP Publication 23, " Report of the 2
. Task Group on Reference Man."
3'
" Respiratory protective equipment" means an apparatus, such as a 4
respirator, used to reduce an individual's intake of airborne radioactive 5 --
materials.
6
" sanitary sewerage" means a system of public sewers for carrying off waste 7_
water and refuse, but excluding sewage treatment facilities, septic tanks, and 8-leach fields owned or operated by the licensee or registrant.
l " stochastic effect" means a health effect that occurs randomly and for 10
-which the probability of the effect occurring,- rather than its severity, is
-11 assumed to be a linear function of dose without threshold. Hereditary effects 12 and cancer incidence are examples of stochastic effects.
For purposes of these 13 rules, "probabilistic effect" is an equivalent term.
14-
"Very high radiation area" means an area, accessible to individuals, in 15 which radiation levels could result in an-individua1Ireceiving an absorbed dose
'f 16 in excess of five-Gy (500 rad).in one hour at nna._ meter from a source of 17 radiation or from any surface that the radiation penetrates. At very high doses 18 received at high dose rates, units of absorbed dose, gray and rad, are 19 --
appropriate, rather than units of dose equivalent, sievert and rem.
20
" Weighting factor" wr for an organ or tissue (T) means the proportion of
'21 the risk of stochastic effects resulting from irradiation of that organ <>r tissue
-22 to the total risk of stochastic effects when the whole body is irradiated 23.
uniformly. For calculating the effective dose equivalent, the values of w r are:
24' 25 TABLE
.26 27 ORGAN DOSE WEIGHTING FACTORS 28 4
l
~
-e
- z. + Organ or Tissue w,
2L Gonads 0.25.
3-Breast-0.15 4
Red bone marrow 0.12
- 5 Lung 0.12 6
l Thyroid 0.03 7
sone-surfaces 0.03 i
s 8
Remainder 0.30(1)
L 9
Whole Body 1.00(2) 10 11-
.(1) 2.30 results from OLO6 for each of five " remainder" organs, excluding the 12 skin and the lens of-the eye, that receive the highest doses.
13 (2)
For -the. purpose of weighting the external whole body dose, for adding it 114 to the internal dose,.a single weighting factor, w, = 1. 0, has been specified.
15 The use of other-weighting factors for external exposure will be approved on a 16
' case-by-case basis until.such time as specific guidance is issued.
17 18
.R313-15-3.
Implementation.
19:
(1)
Any existing license or registration condition that is.more 20
-restrictive than Rule R31:-15 remains in 3rce until there is an' amendment or 21
-renewal'of the license or registration.
22 (2)
If a license or registration condition exempts a licensee or 23 registrant from a provision of Rule R313-15 in effect on or before January 1, 24-'
1994, it also exempts the licensee or registrant from the corresponding provision 25:
of Rule R313-15.
-26 (1) If a license or registration condition cites provisions of Rule R313-27 15 in effect prior to January 1, 1994, which do not correspond to any provirions 28' of Rule R313-15, the license or registration condition remains in force until 5
1 there is an amendment or renewal of the license or registration that modifies or 2
removes this condition.
3 4
R313-15-101.
Radiation Protection Programs.
5 (1)
Each licensee or registrant shall develop, document, and implement a 6
radiation protection program sufficient to ensure compliance with the provisions 7
of Rule R313-15.
See Section R313-15-1102 for recordkeeping requirements 8
relating to these programs.
9 (2)
The licensee or registrant shall
- use, to the extent 10
[pr::ticablcloractical, procedures and sugineering controle based upon sound 11 radiation protection principles to achieve occupational doses and public doses 12 that are as low as is reasonably achievable (ALARA),
13 (3)
The licensee or registrant shall, at intervals not to exceed 12 14 months, review the radiation protection program content and implementation.
15 (4)
To imnlement the ALARA recuirements of Subsection R313-15-101(2). and 16 notwithstandina the recuirements in Section R313-15-301. a constraint on air 17 emissions of radioactive material to the environment. excludina raden-222 and its 18 dauahters. shall be establish 7d by licensees or registrants such that the 19 individual member of the oublic likelv to receive the hichest dose will not be 20 exnected to receive a total effective dose eouivalent in excess of 0.1 mSv (10 21 mrem) ner year from these emissions. If a licensee or reaistrant subiect to this 22 recuirement exceeds this dose constraint. the licensee or reaistrant shall renort 23 the exceedance as nrovided in Section R313-15-1203 and nromntiv take annronriate 24 corrective action to ensure aaainst recurrence.
25 26 R313-15-201.
Occupational Dose Limits for Adults.
27 (1)
The licensee or registrant shall control the occupational dose to 28 individual adults, except for planned special exposures pursuant to Section R313-l 6
1 15-206, to the following dose limits:
2 (a) An annual limit, which is the more limiting of 3
(i)
The total effective dose equivalent being equal to 0.05 Sv (5 rem);
4 or 5
(ii) The sum of the deep dose equivalent and the comitted dose equivalent 6
to any individual organ or tissue other than the lens of the eye being equal to 7
0.50 sv (50 rem).
8 (b)
The annual limits to the lens of the eye, to the skin, and to the 9
extremities which are:
10 (i) Ar eye dose equivalent of 0.15 sv (15 rem), and 11 (ii) A shallow dose equivalent of 0.50 sv (50 rem) to the skin or to any 12 extremity.
13-(2)
Doses received in exccas of the annual limits, including doses 14 received during accidents, emergencies, and planned special exposures, shall be 15 subtracted from the limits for planned special exposures that the individual may 16 receive during the current year and during the individual's lifetime. See 17 Subsections R313-15-206 (5) (a) and R313-15-206 (5) (b),
18 (3)
The assigned deep dose equivalent and shallow dose equivalent shall 19 be for the portion of the body receiving the highest exposure determined as 20 follows:
21 (a)
The deep dose equivalent, eye dose equivalent and shallow dose 22 equivalent may be assessed from surveys or other radiation measurements for the 23 purpose of demonstrating compliance with the occupational dose limits, if the 24 individual monitoring device was not in the region of highest potential exposure, 25 or the results of individual monitoring are unavailable; or 26 (b)
When a protective apron is worn while workino with medical 27 fluoresconic ecuiement and monitoring is conducted as specified in Subsection 28 R313 502 (1) (d), the effective dose equivalent for external radiation shall be 7
4 1
determined as follows:
2 (i) When only one individual monitoring device is used and it is located 3
at the neck outside the protective apron, and the reported dose exceeds.25 4
percent of the limit specified in Subsection R313-15-201(1), the reported deep dose equivalent value multiplied by 0.3 shall be the effective dose equivalent for external radiation; or 7
ai) r;2n individual monitoring devices are worn, both under the 8
protective apron at the waist and outside the protective apron at the neck, the 9
effective done equivalent for external radiation shall be assigned the value of 10 the sum of the deep dose equivalent reported for the individual monitoring device 11 located at the waist under the protective apron multiplied by 1.5 and the deep 12 dose equivalent reported for the individual monitoring device located at the neck 13 outside the protective apron multiplied by 0.04.
14 (4)
Derived air concentration (DAC) and annual limit on intake (ALI) 15 values are (prc cr.ted}snecified in Table I of Appendix B cf 10 CFR 20.1001 to 16 20.2402, 199 (G)2 ed., which is incorporated by reference, and may be used to 17 determine the individual's dose and to demonstrate compliance with the s
18 occupational dose limits. See Section I 7~-15-1107.
19 (5) Notsithstanding the annual dose limits, the licensee shall limit the 20 soluble uranium intake by an individual to ten milligrams in a week in 21 consideration of chemical toxicity. See footnote 3, of Appendix B of 10 CFR 22 20.1001 to 20-2402, 199(a]2 ed., which is incorporated by reference.
23 (6)
The licensee or registrant shall reduce the dose that an individual 24 may be allowed to receive in the current year by the amount of occupational dose 25 received while employed by any orher person. See Subsection R313-15-205 (5).
26 27 R313-15-202. Compliance with Requirements for Summation of External and Internkl N
28 Doses.
i f
8
(
l 0
1 (1) If the licensee or registrant is required to monitor pursuant to both 2
Subsections R313-15-502 (1) and R313-15-502 (2), the licensee or registrant shall 3
demonstrate compliance with the dose lim,a by summing external and internal 4
doses.
If the licensee or registrant is required to monitor only pursuant to l
5 Subsection R313-15-502 (1) or only pursuant to Subsection R313-15-502 (2), then 6
summation is not required to demonstrate compliance with the dose limits. The 7
licensee or registrant may demonstrate compliance with the requiremet.ts for 8
summation of external and internal doses pursuant to Subsections R313-15-202 (2),
l 9
R313-15 *.02 (3) and R313-15-202 (4). The dose equivalents for the lens of the eye, i
l 10 the skin, and the extremities are not included in the summation, but are subject i
11 to separate limits.
12 (2)
Intake by Inhalation.
If the only intake of radionuclides is by 13 inhalation, the total effective dose equivalent limit is not exceeded if the sum 14.
of the deep dose equivalent divided by the total effective dose equivalent limit, h
15 and one of the following, does not exceed unity:
16 (a) The sum of the fractions of the inhalation ALI for each radionuclide, 17 or 18 (b)
The total number of derived air concentration-hours (DAC-hours) for 19 all radionuclides divided by 2,000, or 20 (c) The sum of the calculated committed effective dose equivalents to all 21 significantly irradiated organs er tissues (T) calculated from bioassay data 22 using appropriate biological models and expressed as a fraction of the annual 23 limit.
For purposes of this requirement, an organ or tissue is deemed to be 24 significantly irradiated if, for that organ or tissue, the product of the 25 weighting factors, w;, and the committed dose equivalent, Hr,so, per unit intake 26 is greater than ten percent of the maximum weighted value of H so that is, n
27 w Hr,so, per unit intake for any organ or tissue.
r 28 (3)
Intake by oral Ingestion. If the occupationally exposed individual 9
l l
I 1
(e4ee-) receives an intake of radionuclides by oral ingestion greater than ten 2
percent of the applicable oral ALI, the licensee or registrant shall account for 3
this intake and include it in demonstrating compliance with the limits.
4 (4)
I.atake through Wounds or Absorption through Skin.
The licensee or 5
registrar e, shall evaluate and, to the extent practical, account for intakes 6
through wounds or skin absorption.
The intake through intact skin has been 7
included in the calculation of DAC for hydrogen-3 and does not need to be 8
evaluated or accounted for pursuant to Subsection R313-15-202 (4).
9 10 R313-15-203. Determination of External Dose from Airborne Radioactive Material.
11 (1)
Licensees or registrants shall, when determining the dose from 12 airborne radioactive material, include the contribution to the deep dose 13 equivalent, eye dose equivalent, and shallow dose equivalent from external 14 exposure to the radioactive cloud. See footnotes 1 and 2 of Appendix B of 10 CFR 15 20.1001 to 20.2402, 199(4)2 ed., which is incorporated by reference.
16 (2) Airborne radioactivity measurements and DAC values shall not be used 17 as the primary means to assess the deep dose equivalent when the airborne 10 radioactive material includes radionuclides other than noble gases or if the 19 cloud of airborne radioactive material is not relatively uniform.
The 20 determination of the deep dose equivalent to an individual shall be based upon 21 measurements using instru-ents or individual monitoring devices.
22 23 R313-15-204.
Determination of Internal Exposure.
24 (1)
For purposes of assessing dose used to determine compliance with 25 occupational dose equivalent limits, the licensee or registrant shall, when 26 required pursuant to Section R313-15-502, take suitable and timely measurements 27 of:
20 (a) concentrations of radioactive materials in air in work areas; or i
2 10
1-(b)
Quantities of radionuclides in the body; or 2 -
(c)
Quani.ities of radionuclides excreted from the body; or 4
1 3
(d)
Combinations of these measurements.
4-(2)
Unless respiratory protective equipment is used, as p rovidad in l
5 Section R313-15-703, or the assessmer.t of intake is based on bioassays, the 6
licensee or registrant sht.ll assume that an individual inhales radioactive 7
material at the airborne concentration in which the individual is present.
8 (3) When specific information on the physical and biochemical properties 9
of the radionuclides taken into the body or the behavior of the material in an 10 individual is known, the licensee or registrant may:
1 (a)
Use that information to calculate the committed effective dose l
.2 equivalent, and, if used, the licensee or registrant shall document that l
13 information in the individual's record; and 14 (b) Upon prior approval of the Executive Secretary, adjust the DAC or ALI 15 values to reflect the actual physical and chemical characteristics of airborne 16 radioactivs material, for example, aerosol size distribution et density; and 17 (c)
Separately assess the contribution of fractional intakes of Class D, 18 W,
or Y compounds of a given radionuclide to the committed ef fective dose 19 equivalent. See 7ppendix B of 10 cFR 20.1001 to 20.2402, 199 (a]2 ed., which is 20 incorporated by reference.
21 (4)
If the licensee or registrant chooses to assess intakes of Class Y 22 material using the measurements given in Subsections R313-15-204 (1) (b) or R313-23 15-2 04 (1) (c), the licensee or registrant may delay the recording and reporting 24 of the assessments for periods up to seven months, unless otherwise required by 25 Sectio 1 R313-15-1202 or Section R313-15-1203.
This delay permits the licensee 26 or registrant to make additional measurements basic to the assessments.
27 (5)
If the identity and concentration of each radionuclide in a mixture 28 are known, the fraction of the DAC applicable to the mixture for use in 11
1 calculating DAC-hours shall be either:
2 (a)
The sum of the ratios of the concentration to the appropriate DAC 3
value, that is, D, W, or Y, from Appendix B of 10 CFR 20.1001 to 20.2402, 199(4]2 4
ed., which is incorporated by reference, for each radionuclide in the mixture; 5
or 6
(b)
The ratio of the total concentration for all radionuclides in the 7
mixture to the most restrictive DAC value for any radionuclide in the mixture.
8 (6)
If the identity of each radionuclide in a mixture is known, but the 9
concentration of one or more of the radionuclides is the mirture is not known, 10 the DAC for the mixture shall be the most restrictive DAC of any radionuclide in 11 the raixture.
12 (7)
When a mixture of radionuclides in air exists, a licensee or 13 registrant may disregard certa;a radionuclides in the mixture if:
14 (a) The licensee or registrant uses the total activity of the mixture in r
15 demonstrating compliance with the dose limits in Section R313-15-201 and in 16 complying with the monitoring requirements in Subsection R313-15-502 (2), and 17 (b)
The concen 'ation of any radionuclide disregarded is less than ten 18 percent of its DAC, and 19 (c) The sum of these percentages for all of the radienuclides disregarded 20 in the mixture does not exceed 30 percent.
21 (8)
When determining the committed effective dose equivalent, the 22 following information may be considered:
23 (a)
In order to calculate the committed effective dose equivalent, the 24 licensee or registrant may assume that the inhalation of one ALI, or an exposure 25 of 2,000 DAC-hours, results in a committed effective dose equivalent of 0.05 Sv 26 (5 rem) for radionuclides that have their ALIs or DACs based on the committed 27 effective dose equivalent.
28 (b)
For an ALI and the associated DAC determined by the nonstochastic 12 i
i
s 1
organ l dose limit-of~0.50 sv (50 rem), the intake of radionuclides that would-2 result-in a comitted effective dose equivalent of _0.05 sv (5 rem), that is, the 3
. stochastic ALI, is listed in parentheses in Table I of Appendix _ B of 10 CFR
'I
'4 20.1001 to 20.24 02, - 199 (4)2 ed., which. is incorporated by reference.
The
}
-S licensee or registrant may,-as a simplifying assumption, use the st'ochastic ALI
- 6 to determine' committed ef fective dose aquivalent. However, if the licensee or 7.
registrant uses the stochastic ALI, the licensee' or registrant shall also 5
8 demonstrate that the limit in Subsection R313-15-201(1) (a) (ii) is met.
9
- 10 R313-15-205.
Determination of Prior Occupational Dose.
[
11 (1)
For each individual (xh: ::y ::tcr the li :::::'
- ::gistr :t';
12.
- tricted :: :.tr:lled ar;; ::
i
]likely to receive, in a year, an i
13-
' occupational dose requiring monitoring pursuant to Section R313-15-502, the 14' licensee or registrant shall:
15-(a) Determine the occupational radiation dose received during the current l
-:16 years and "17 (b) -Attempt to obtain the records of (lif ti;; ] cumulative occupational
~ ' radiation dose. A licennae or recintrant may accent. as the record of cumulative 4
. 519 ~
Indiation done. an un-to-date form Dac-os or eauivalent. nioned by the individual
'20
- and counternioned by an annronriate of ficial of the most recent amnlover for work 21 involvino radiation evnenure. or che individual's current emnlover. if the
- ' 22 individual-is not emnloved by the licannee or recintrent.
23 (2) Prior to permitting an individual to participate in a planned special 24-
-exposure, the licensee or registrant shall determine
- -25:
(a)
The internal and external doses from all previous planned special 26' exposures; and a
27 (b)
All doses in excess of the limits, including doses received during 28 accidents and emergencies, received during the lifetime of the individual (t-and].
13
---=>e,-
-m w
,n
1
(( :
1.11 lifetim cumulativ :::upati n:1 :: diction d;;;,)
2 (3)
In complying with the requirements of Subsection R313-15-205 (1), a 3
licensee or registrant may:
4 (a)
Accept, as a record of the occupational duse that the individual 5
received during the current year, a written signed statement from the individual, 6
or from the individual's most recent employer for work involving radiation 7
exposure, that discloses the nature and the amount of any occupational oose that 8
the individual received during the current years and o
9
(
(h'
. : pt,
- the rc: rd of lifeti cu ulativ: radiati n d :, an up to l
10 dat for-Onc OS :: quivalent, signed by th: individu 1 and countersigned hy.n 11 approprint cfficini of th: ::t :: cent : ployer for ucrh irvalving :: diction 12 q: urc, or the individual's current ;picycr, if th: individual is not ; played 13 by the licens : cr registrant, __ :nd) 14
[4e+].(h)..Obtain reports of the individual's dose equivalenta from the most 15 recent employer for work involving radiation exposure, or the individual's 16 current employer, if the individual is not employed by the licensee or 17 registrant, by telephone, telegram, facsimile, other electronic media or letter, 18 The licensee or registrant shall request a written verification of the dose data 19 if the authenticity of the transmitted report cannot be established.
20.
(4) (4*)-)
The licensee or registrant shall record the exposure history, as 21 required by Subsection R313-15-205 (1), on form DRC-05, or other clear and legible 22 record, of all the information required on that form.
13
.Lal.
The form or record shall show each period in which the individual 24 received occupational exposure to radiation or radioactive material and shall be 25 signed by the individual who received the exposure.
For each period for which 26 the licensee or registrant obtains reports, the licensee or registrant shall use 27 the dose shown in the report in preparing form DRC-05 or equivalent. For any I
28 period in which the licensee or registrant does not obtain a report, the licensee 14 1
f C
e
1 ~
or registrant'shall place a notation on form DRC-05 or equivalent indicating the 2
periods of-time for which data are not available.
3 (b)
For the nurnome of crunnivina with this reauirement. [is] licensees or 1
1
'4 registrants are not required to reevaluate the separate external dose equivalents 5
- and internal committed dose equivalents or intakes of radionuclides assessed 6-pursuant to the rules in Rule R313-15 in effect before January 1,1994.
- Further, l
-1 7
occupational exposure histories - obtained and recorded on form DRC-05 or-8 equivalent before January 1,
1994, would not have included effective dose 9
equivalent, but may be used in the absence of specific information on the intake of radionuclides by the individual.
11 (5)
If the licensee or registrant is unable to obtain a complete record 12-of an individual's' current and previously accumulated occupational dose, the
-13 licensee or registrant shall assume:
14 (a)
In establishing administrative controls under Subsection R313 15 201(6) for the current year, tnat the allowable dose limit for the individual is 16 reduced by 12.5 mSv (1.25 rem) for each quarter for which records were 17 unavailable and the individual was engaged in activities that could have resulted 18 in occupational radiation exposure; and p.
19 (b) That the individual is not available for planned special exposures.
20 (6) The licensee or registrant shall retain the records on form DRC-05 or l
21 equivalent until the Executive Secretary terminates each pertinent license or 22 registration requiring this record. The licensee or registrant shall retain 23 records usfi in preparing form DRC-05 or equivalent for three years after the z24 record is made.
-25 26 R313-15-206.
Planned Special Exposures.
27 A licensee or registrant may authorize an adult worker to receive doses in 28 addition to and accounted f r separately from the doses received under the limits 15
1 specified in Section R313-15-201 provided that each of the following conditions 2
is satisfied:
3 (1) The licensee or registrant autho*izes a planned special exposure only 4
in an exceptional situation when alternatives that might avoid the higher l
5 exposure are unavailable or impractical, i
6 (2) The licensee or registrant, and employer if the employer is not the 7
licensee or registrant, specifically authorizes the planned special exposure, in 8
writing, before the exposure occurs.
9 (3) Before a planned special exposure, the licensee or registrant ensures 10 that each individual involved is:
11 (a)
Informed of the purpose of the planned operation; and 12 (b)
Informed of the estimated doses and associated potential risks and 13 specific radiation levels or other conditions that might be involved in 14 performing the tasks and 15 (c)
Instructed in the measures to be taken to keep the dose ALARA 16 considering other risks that may be present.
17 (4)
Prior to permitting an individual to participate in a planned special 18 exposure, the licensee or registrant ascertains prior doses as required by 19 Subsection R313-15-205(2) during the lifetime of the individual for each 20 individual involved, 21 (5) Subject to Subsection R313-15-201(2), de licensee or registrant shall 22 not authorize a planned special exposure that would cause an individual to 23 receive a dose from all planned special exposures and all doses in excess of the 24 limits to exceed:
25 (a) The numerical values of any of the dose limits in Subsection R313 26 201(1) in any yeart and 27 (b) Five times the annual dose limits in Subsection R313-15-201(1) during 1
28 the individual's lifetime.
1 16 e
1 (6)
The-licensee or_ registrant maintains records of the conduct of a 2
planned special exposure in accordance with Section R313-15-1106 and submits a 3
written report in accordance with Section R313-15-1204.
4 (7)
The licensee or registrant records the best estimate of the dose 5
resulting f rom the planned special exposure in the individual's record and l
6 informs the individual, in writing, of the dose within 20 days from the date of l
7 the planned special exposure. The dose from planned special exposures shall not 8
be considered in controlling future occupational dose of the individual cursuant 9
to Subsection R313-15-201(1) but shall be included in evaluations required by 10 Subsections R313-15-206 (4) and R313-15-206 (5).
11 12 R313-15-207.
Occupational Dose Listite for Minors.
13 The annual occupational dose limits for minors are ten percent of the
.14 annual occupational-dose limits specified for adult workers in Section R313 15 201.
16 17 R313-15-208.
Dose to an Embryo / Fetus.
18 (1)
The licensee or registrant shall ensure that the dose to an 19 embryo / fetus during the entire pregnancy, due to occupational exposure of a 20 declared pregnant woman, does not exceed five mSv (0.5 rem).
See Section R213-21 15-1107 for recordkeeping requirements.
22
-(2) -The licensee or registrant shall make efforts to avoid substantial 23 variation tove a uniform monthly exposure rate to a declarad pregnant woman so 24-as to satisfy the limit in Subsection R313-15-208 (1).
25 (3)
The dose to an embryo / fetus shall be taken as the sum of:
26 (a)
The (d:g d :: cwivaler.t t; th ] dose to the embrvo/ fetus from 27 radionuclides in the embrvo/ fetus and radionuclides in the declared pregnant 28 woman; and 17
e l
l 1
l (b) The dose that is most reeresentative of the dose _to the embryo / fetus 3 l from external radiation, that is.
in the mother's lower torso recion.(
3 endienue14 des in th; c;bryc/ fetus cad radicauclid:: in th; declecca p c nand 4
womanr]
5 (1)
If multiole measurements have not been made. ansianment of the hiahest 6
deen dose eauivalent for the declared preanant woman shall be the dose to the 7;
embryo / fetus, in accordance with Subsection R313-15-205(3); or 8
(ii)
If multiole measurements have been made. assianment of the deen dose
\\9j eauivalent for the declared creanant woman from the _ndividual monitorina device i
10 which is most recresentative of the dose to the embrvo/ fetus shall be the dose R
11 to the embryo fetus.
Assianment of the hiahest deen dose eauivalent for the 4 )
12 1_
declared creanant woman to the embrvo/ fetus is not reaulted unless that dose is 13 k also the most representative deen dose eauivalent for the recion of the i
A g,Oy(c(ii) 14 embrvo/ fetus.
15 _
(4)
If by the time the woman declares pregnancy to the licensee or 16 registrant, the dose to the embryo / fetus has exceeded 4.5 mSv (0.45 rem) the 17 licensee or registrant shall be deemed to be in compliance with Subsection R313-18 15-208(1) if the additional dose to the embryo / fetus does not exceed 0.50 mSv 19 (0.05 rem) during the remainder of the pregnancy.
20 21 R313-15-301.
Dose Limits for Individual Members of the Public.
22 (1)
Each licensee or registrant shall conduct operations so that:
23 (a)
[The]Excent as nrovided in Subsection R313-15-3 01 f1) (c). the total 24 effectivo dose equivalent to individual members of the public from the licensed 25 or registered operation does not exceed one mSv (0.1 rem) in a year, exclusive 26 cf the dose contribution from backaround radiation.
from any medical 27 administration the individual has received. from exrosure to individuals
[
k 28 administered radioactive material and released in accordance with Section R313-18 I
e a
4.
4
-- l -
32-75. from voluntarv narticination in medical research nrocramm. and from the 2-licensee's or registrant's disposal of radioactive material into sanitary-
'3 sewerage in accordance with Section R313-15-1003 [r]1 and 4
(b) The dose in any unrestricted area from external sources. exclusive of 5
the done contributient natienta administered radioactive material and-l 6
relmaned in accordance with section R313-12-75. does not exceed 0.02 mSv (0.002
-7 rem) in any one hour (v) : and 8
(c)
The total effective done eauivalent to ir_dividual members of the 9
public from infrecuent arnonure to radiation from radiation machines does not 10 exceed s msv to.s rami in a vear.
11 (2)
If the licensee or registrant permits members of the public to have 12 access to controlled areas, the limits for members of the public continue to 13 apply to those individuals.
14 (3) A licensee, registrant, or an applicant for a license or-registration
(
[-
15 may apply for prior Executive Secretary authorization to operate up-to an annual 16 dose' limit for an individual member of the public of five mSv (0.5 rem).
This 17 application shall include the following information:
18 (a) Demonstration of the need for and the expected duration of operations
.19-in excess of the limit in Subsection R313-15-301(1) ; and 20 (b)
The licensee's or registrant's program to assess and control dose 21 within the five mSv (0.5 rem) annual limit; and 22.
(c)
The procedures to be followed to maintain the dose ALARA.
-23 (4)
The Executive Secretary may impose additional restrictions on 24-radiation levels in unrestricted areas and on the total quantity of radionuclides 25 that a licensee or registrant may release in effluents in order to restrict the 26 collective dose.
27 28 R313-15-302.
Compliance with Dose Limits for Individual Members of the Public.
19
1-(1) The = licensee or registrant'shall make orf cause to be made surveys _ of 2
radiation levels in unrestricted and controlled areas and radioactive materials 3-in of fluents released to unrestricted and controlled. ar.ias to demonstrate 4-compliance with the dose. limits for-individual members of the public in Section 5
.R313-15-301.
6' (2)
A licensee or registrant shall show compliance with the annual dose 7
limit in section R313-15-301 by:
8 (a)
Demonstrating by measurement or calculation that the total effective 9
dose equivalent to the individual-likely to receive.the highest dose from the 10 licensed or registered operation does not exceed the annual dose limit; or 11 (b)
Demonstrating that:
.12..
_(i)
The annual average concentrations of radioactive material released in
-13
. gaseous and liquid effluents at the boundary'of the unrestricted area do not 14:
exceed the values specified in Table II of Appendix B of 10 CFR 20.1001 to
- 15 20.2402, 199(412 ed., which is incorporated by(reference; and
'16 '
(ii)
If an individual were continu(el4y]ousiv present in an unrestricted
-17 area, the dose f rom external sources would not exceed 0.02 mSv (0.002 rem) in'an
-18 hour and 0.50 mSv (0.05 rem) in a= year.
19 (3) Upon approval from the Executive Secretary, the licensee or registrant 20 may adjust the effluent concentration values in Appendix B, Table II of 10 CFR 21 20.1001 to 20.2402, 199(4)2 ed., which is incorporated by re{erence, for meubers J22 of the public, to-take into account the actual physical and chemical 23'
' characteristics of the ef fluents, such as, aerosol size distribution, solubility, 24 density, radioactive decay equilibrium, and chemical form.
25 26 R313-15-401.
Testing for Leakage or Contamination of Sealed Sources.
27 (1)
The licensee or registrant in possession of any sealed source shall 28 assure that 20
1-(a) Each sealed source, except as specified in Subsection R313-15-401(2),
2
.is tested'for leakage'or contamination'and the-test results are-received before
'3 the sealed source is 'put into use unless the licensee or registrant has a t-4 certificate from the transferor indicating that the sealed source was tested 5
within six months before transfer to the licensee or registrant.
i 6.
'(b)
Each sealed source that is not designed to emit alpha particles is 7
tested for leakage or contamination at intervals not to exceed six months or at I
8;
. alternative intervals approved by the Executive Secretary, an Agreement State, 9
a Licansing State,. or the U.S. Nuclear Regulatory Ce:.anission.
l 10-(c) Each sealed source-that is designed to emit alpha particles is tested 11-for leakage or contamination at intervals not to exceed three months or at.
12' alternative intervals approved by the Executive Secretary, an Agreement State, 13 a Licensing State, or the Nuclear Regulatory Commission, 14
-(d).For each sealed source that is required to be tested for-leakage or 115 contamination, at any other time there is reason to suspect that the sealed 16 source might-have been damaged or might-be leaking, the licensee or registrant 17
. shall asoure that the sealed source is tested for leakage or-contamination before 18 further use.
19:
(e) Tests for leakage for-all sealed sources, except brachytherapy sources
'20 manufactured -to contain radium, shall-be capable of detecting the presence of 185 21
.. Bq : (0.005 uCi) o: radioactive material on-a test sample.
Test samples shall be 22 taken-from the sealed source or from the surfaces of the container in which the 23 sealed source is stored or mounted on which one might expect contamination to
-24' accumulate. For a sealed source contained in a device, test samples are obtained 25 when the source is in the "off" position.
26' (f) The test for leakage for brachytherapy sources manufactured to contain 27 radium shall be capable of detecting an absolute leakage rate of 37 Bq (0.001 28' uCi) of radon-222 in a 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period when the collection efficiency for radon-21
e p
1' 222.and its daughters has been determined with respect to collection. method, 2.-
volume and time.
3-
-(g)
Tests for contamination from radium daughters shall be taken on the 4
interior _ surface of brachytherapy source storage containers and shall be capable 5-of detecting the presence of 185 Bq (0.005 uCi) of a radium daughter which has 1
_6
-a half-life greatet than four. days.
. 7 --
(2)
A licensee or registrant need not perform tests for leakage or 8
contamination on the following sealed' sources:
9_
(a)
Sealed sources ciuntaining only radioactive material with a half-life 10 of less than 30 days;
-11 (b)
Sealed sources containing only radioactive material as a gas; 12-(c) Sealed sources containing 3.7 MBq (100 uCi) or less of beta or photon-i
-13 emitting material or 370 kBq (ten uci) or less of alpha-emitting material; 14 (d)
Sealed sources containing only hydrogen-3; 15 (e)
Seeds of iridium-192 encased in nylon ribbon; and 16-(f)
Sealed sources, except teletherapy and brachytherapy sources, which-
-17 are stored, not being used and identified as in storage.
The licensee or 18 registrant ~ shall, however, test each such sealed at cce for leakage or 19 --
contamination and receive the test results before any use or transfer unless it 20 has been tested for leakage-or contamination within six months before the date
-21
.of use or transfer, 22 (3)
Tests. for leakage or contamination from sealed sources shall be f23 performed by_ persons specifically authorized by the Executive Secretary, an 24 Agreement State, a Licensing State, or the U.S. Nuclear Regulatory Commission to 25 perform a.uch services.
26 (4)
Test results shall be kept in units of becquerel or microcurie and 27 maintained for inspection by representatives of the Executive Secretary. Records
.28 of test results for sealed sources shall be made nursuant to Section R313 d 22 l
1 i
-a
4
-1
- 1104, 2-(5); - The following shall be considered evidence that a sealed ' source is 3
leaking:
?4 (a) The presence of 185 Bq (0.005 uC1) or more of removable contamination 5
.on any test sample.
6 (b)'
Leakage ' of 37 Bq. (0.001 uci) of radon-222 per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for l
7 brachytherapy sources manufactured to contain radium, l
-t
,8' (c)' The presence of removable contamination resulting from the decay of I
l 9
185 Bq (0.005 uci) or more of radium.
10 (6) The licelsee or registrant shall immediately withdraw a leaking sealed i
11-source from use and shall take action to prevent'the spread of contamination.
12_
.The leaking sealed source shall be repaired or disposed of'in accordance with
' 13
~ Rule'R313-15.
-14:
(7)
Reports of test results for leaking or contaminated sealed-sources 15 shall be made pursuant to Section R313-15-1208.
>16
.17-R313-15-501.
surveys and Monitoring - General.
18'
-(1). Each licensee or registrant shall make, or cause to be made, surveys 19-that:
20:
-(a)
Are necessary for the licensee or-registrant to comply with Rule R313-15; and 32 (b) ~Are necessary under the circumstances to evaluate:
23 (i) -Radiation levels; and 24;
_ ii)
Concentrations or quantities of radioactive material; and
(
25 (iii)
The potential radiological hazards that could be present.
26 (2). The licensee or registrant shall ensure that instruments and equipment
.27 used for quantitative radiation measurements, for example, dose rate and effluent 28 monitoring, are calibrated at intervals not to exceed 12 months for the radiation 23
4
.1 measured. except when a more freauent interval is anecified in annther annlicable 2
,part of these rules or a licanae condition.
3 (3)
All personnel dosimeters, except for direct and indirect reading i
4 pocket ionization chambers and those dosimeters used to measure the dose to any 5
extremity, that require processing to determine the radiation dose and that are-6-
used by licensees and registrants to comply with Section R313-15-201', with other 7
applicable provisions of these rules, or with conditions specified in a license 8
or registration shall be processed and evaluated by a dosimetry processor l
9 (a)
Holding current personnel dosimetry accreditation from the National 10 voluntary Laboratory Accreditation Program (NVLAP) of the National Institut of 11~
Standards and Technology; and 12 (b)
Approved in this accreditation process for the type of radiation or 131 radiations included in the NVLAP program that most closely' approximates the type 14 of radiation or radiations for which the individual wearing the dosimeter is 15 monitored.
16 (4) The licensee or registrant shall ensure that adequate precautions are 17; taken to prevent a deceptive exposure of an individual monitoring device.
18 19; R313-15-502. Conditions Requiring Individual Monitoring of External and Internal 20.
occupational Dose.
. 31 Each licensee or registrant shall monitor exposures from sources of 22 radiation at levels sufficient to demonstrate compliance with the occupational 23.
-dose limits of Rule R313-15.
As a minimum 24-(1)
Each licensee or registrant shall monitor occupational exposur6 to
'25 radiation and shall supply and require the use of individual monitoring devices 26 by:
i
- 27 (a)
Adults likely to receive, in one year from sources external to the
~
l 28
. body, a dose in excess of ten percent of the limits in Subsection R313-15-201(1) ;
[
4 24
1 and 2
(b) Minors and declared pregnant women likely to receive, in one year from 3
sources external to the body, a done in excess of ten percent of any of the 4
applicable limits in Sectiona R313-15-207 or R313-15 208; and 5
(c)
Individuals entering a high or very high radiation area; and 6
(d)
Individuals working with medical fluoroscopic equipment.
7 (1)
An individual monitoring device used for the dose to an embryo / fetus i
8 of a declared pregnant woman, pursuant to Subsection R313-15-20B (1), shall be 9
located under the protective apron at the waist.
10 (A)
If an individual monitoring device worn by a declared pregnant woman 11 has a monthly reported dose equivalent value in excess of 0.5 mSv (50 mrem), the 12 value to be used for determining the dose to the embryo / fetus, pursuant to 13 Subsection R313-15-208 (3) (a) for radiation from medical fluoroscopy, may be the 14 value reported by the individual monitoring device worn at the waist underneath 15 the protective apron which has been corrected for the potential overestimation 16 of dose recorded by the monitoring device because of the overlying tissue of the 17 pregnant individual. This correction shall be performed by a radiation safety 18 officer of an institutional radiation safety committee, a qualified expert 19 approved by the Board, or a representative of the Executive Secretary.
20 (ii)
An individual monitoring device used for eye dose equivalent shall 21 be located at the neck, or an unshielded location closer to the eye, outside the 22 protective apron.
23 (iii) When only one individual monitoring device is used to determine the 24 effective dose equivalent for external radiation pursuant to Subsection R313 i 25 201 (3 ) (b), it shall be located at the neck outside the protective apron.
When 26 a second individual monitoring device is used, for the same purpose, it shall be 27 located under the protective apron at the waist. Note: The second individual 28 monitoring device is required f3r a declared pregnant woman.
25
\\
1 (2)
Each licensee or registrant shall mon!ter, to determine compliance 2
with Section R313-15-204, the occupational intake of radioactive material by and 3
casess the committed effective dose equivalent to:
4 (a)
Adulta likely to receive, in one year, an intake in excess of ten 5
percent of the applicable ALI in Table I, Columns 1 and 2, of Appendix B of 10 6
CFR 20,1001 to 20.2402, 199[3]2 ed., which is incorporated by reference; and 7
(b) Minors and declared pregnant women likely to receive, in one year, a 8
committed effective dose equivalent in excess of 0.50 mSv (0.05 rem),
9 10 R213-is-503.
Location of Individuni Monitorina Devices.
11 Each licensee or recistrant shall ensure that individuals who are recuired 12 to monitor occupational doses in accordance with Subsection R313-15-502(1) wear 13 individual monitorina devices as follower 14 (1)
An individual monitorina device used for monitorino the dose to the 1
15 whole body shall be worn at the unnhielded location of the whole bodv likely to 16 receive the hiahest exnosure.
When a erotective aeron is worn. the location of 17 the individual monitorina d(11ee is tvnically at the neck (collar).
18 (2)
An individual monitorina device used for monitorina rhe dose to an 19 embrvo/ fetus of a declared creanant woman. nursuant to subsection R313-15-20B fi).
20 shall be located at the waist under any orotective aeron beina worn by the woman.
21 (3)
An irdividual monitorine device used for monitorina the eve dose 22 ecuivalent. to demonstrate comn11ance with Subsection R313-15-201(1) (b) (1). shall 23 be located at the neck (collar). outside any orotective anron beine worn by thm
-24 monitored individual. or at an unnhielded location closer to the eve.
25 (4)
An individual monitorina device used for monitorina the dose to the 26 extremities. to demonstrate comoliance with subsection R313 2 01 (1) (b) (11).
5 27 shall be worn on the extremity likelv to receive the hichest exrosure.
Each 28 individual monitorina device shall be oriented to measure the hiahest dose to the j
26 i
t
-e 4'
l' extremity beino mnnitored, 2
L3, R313-15-601.
control of Access to High' Radiation Areas.
4E (1) The licensee or registrant shall ensure that each entrance or access pointuto a high radiation area has one or more of the following features:
6 (a) A control device that, upon' entry into the area, causes the level of radiation to be reduced-below that level at which an individual might receive a 8
deep dose equivalent of one mSv (0.1 rem) in one hour at 30 centimeters from the 9
source of radiation nr_from any surface that the radiation penetrates; or 10 (b)
A. control device that energizes a conspicuous visible or audible alarm i
11; signal so that the individual entering the high radiation area and the supervisor
- 12 of the activity are made aware of the entry; or 13 (c)
Entryways that are locked, except during periods when access to the 14 areas is required, with positive control over each individual entry.
2 15.
(2)
In place of the controls required by Subsection R313-15 601(1) for a 16 high radiation area, the licensee or registrant may substitute continuous direct.
17 or electronic surveillance that is capable of preventing unauthorized entry.
18 (3) ' The licensee or registrant may apply to the Executive Secretary for 19' approval of alternative methods =for controlling access to high radiation areas.
12 0 (4)
The licensee or registrant shall establish the controls required by 21~
Subsections R313-15-601(1) and R313-15-601(3) in a way that does not prevent i-22 individuals from leaving a high radiation area.
23 (5) The licensee or registrant is not required to control each entrance 24 or access point to a room or other area that is a high radiation area solely
. 25 because of the presence of radioactive materials prepared for transport and 1
j 26 packaged and labeled in accordance with the rules of the U.S. Department of 27-
-Transportation provided that:
r 28 (a)
The packages do not remain in the area longer than three days; and 27
4 1
(b)
The dose rate at one meter from the external surface of any package
?
2 does not exceed 0.1 mSv (0.'01 rem) per hour.
3 (6)-
The licensee-or registrant is not.-required to control entrance or i4 access to rooms or other areas in hospitals solely because of the presence'of
.5
. patients:containing radioactive material, prorided that there are personnel in 6
attendance who are taking the necessary precautions to prevent the exposure of.
-7 individuals to radiation-or radioactive material in excess of.the establiched
'8.
limits in Rule R313-15 and to operate within the ALARA provisions. of - the licensee's or registrant's radiation protection program.
10 (7) The registrant is not required to control entrance or access to rooms
~11' or: other areas containing sources of radiation capable of producing a' high 12' radiation area as described in Section R313-15-601 if the registrant has met all..
(13
.the specific requirements for access and control specified in other applicable-14 sections of these rules,.such as, Rule R313-36 for industrial radiography,- Rule 15 R313-28 for x rays-.in the healing arts, kula R313-30 for theraneutic radiation
-16 machinan. and Rule R313-(44)21 for ( ;rti;l; ;;;;l;;;;;;;)indnatrial une of x-rav r
17.
systems.
18
-13 R313-15-602, control of Access to very High Radiation Areas.
20 (1)
In addition to the requirements in Section-R313-15-601, the licensee 21 or registrant shall institute measures to ensure that an individual is not able 22
- to gain unauthorized or inadvertent act or,s to areas in which radiation levels 2'3 could be encountered at five uy (500 rad) or more in one hour at one meter from
'24 a source of radiation or any surface through which the radiation penetrates. This requirement-does not apply to rooms or areas in which diagnostic x-ray 26 systems are the only source of radiation, or to non-self-shielded irradiators.
27 (2) The registrant is not required to control entrance or access to rooms p
5e 28 or other areas containing sources of radiation capable of producing a very high k.
28
(
e
I radiation area as described in Subsection R313-15-602(1) if the registrant has 2
met all the specific requirements for access and control speef fied in other 3_
spplicable sections of t.ese rules, such as, Rule R313-36 for industrial 4
radiography, Rule R313 28 for x rays in the healing arts, nule n111-10 for 5
theranautic radiation machinaa.
and nui a R313-[44)31 for
[pertici; 6
- l;.;;;;;) industrial uma of x-rav avatama, 7
8 R313-15-603.
Control of Access to Very Nigh Radiation At as.. Irradiators.
9 (1) section R313-15-603 applies to licensees or registrants with sources 10 of radiation in non self shielded irradiators.
Lection R313 15 603 does not 11 apply to sources of radiation that are used in teletherapy, in industrial l
18 radiography, or in completely self-shielded irradiators in which the source of 13 radiatfor (a both stored and operated within the same shielding radittion barrier
'14 and, in designed configurktion of the irradiator, is always physiedily 15 inaccessibae to any individual and cannot create a high levels of radiation in 16 an area that is accessible to any individual, 17 (2) Each area in which there may exist radiation levels in excess of five 18 oy (500 rad) in one hour at one meter from a source of radiation that is used to 19 irradiate materials shall meet the following requirementa 80 (a)
Each entrance or access point shall be equipped with entry control 21 devices which:
28 (1)
Punction automatically to prevant any individual f rom inadvertently 1R3 entering a very high radiation arent and 24-(ii)
Permit deliberate entry into the area only after a control device is 85 actuated that causes the radiation level wiudn the area, from the source of
- --- 2 d -
radiation,- to be reduced below.that ac which it wculd be possible for an 17 individual to receive a deep done equivalent in excess of one mSv (0.1 rem) in 38 one houri and 29
1 (iii)
Prevent operation of the source of radiation if it would produce 3
radiation levels in the area that could result in a deep dose equivalent to an 3
individual in excese of one mSv (0.1 rem) in one hour.
4 (b) Additional control devices shall be providsJ so that, upon failure of 5
the entry control-devices to function as required by subsection x313 6 603 (2) (a) :
7 (1) The radiation level within the area, from the source of radiation, is 8
reduced below that at which it would be possible for an individual to receive a 9
deep dose equivalent in excess of one msv (0.1 rem) in ene hour; and 10 (ii) conspicuous visibl9 and audible alarm signals are generated to make 11 an individual attempting to er.ter the area aware of the hazard and at least one 13 other authorized individual, who is physically present, familiar with the 13 activity, and prepared to render or summon assistance, aware of the failure of 14 the entry control devices.
15 (c) The licensee or registrant ePall provide control devices so that, upon 16 failure or removal of physical radiation 5arriers other than the sealed source's 17 shielded storage container:
18 (i) The radiation level from the tource of radiation is reduced below that 19 at which it would be possible for an individual to receive a deep dose equivalent 20 in excess of one mSv (0.1 rem) in one hours ant l, 31 (11) conspicuous visible and audible alarm signals are generated to make 33 potentially affected individuals aware of the hazard and the licensee or 33 registrant or at least one other individual, who is familiar with the activity 24 and prepared to render or summon assistance, aware of the failure or removal of 35 the physical barrier.
36 (d)
When the shield for stored sealed sources is a liquid, the licensee 37 or registrant chall provide means to monitor the integrity of the shield and to 38 sigual, automatically, loss of adequate nhielding.
30 m
9 i
1 (e)
Physical radiation barriers that comprise permanent structural 2
components, such a6 walls, that have no credible probability of failure or 1
3 removal in ordinary circumstances need not meet the requirements of Subsections 4
R313-15 603 (2) (c) and R313-15-603 (2) (d).
5 (f)
Each area shall be equipped with devices that will nutomatically 6
generate conspicuous visible and audible alarm signals to alert personnel in the 7
area before the source of radiation can be put into operation and in time for any 8
individual in the area to operate a clearly ident! tied contro. device, which i
1 9
shall be installed in the area and which can prevent the source of radiation from 10 being put into operation.
11 (g) Each area shall be controlled by use of such administrative procedures 12.
and such devices as are necessary to ensure that the area is cleared of personnel 13 prior to each use of the source of radiation.
14 (h) Each area shall be checked by a radiation measurement to ensure that, 15 prior to the first individual's entry into the area 6fter any use of the source 16 of radiation, the radiation level from the source of radiation in the area is 17 below that at which it would be possible for an individual to receive a deep dose 18 equivalent in excess of one mSv (0.1 rem) in one hour.
19 (i)
The entry control devices required in Subsection R313-15-603 (2) (a) 30 shall be tested for proper functioning.
See Section R313-15-1110 for 21 recordkeeping requirements.
22 (1) Testing shall be conducted prior to 4..
al operation with the source 23 of radiation on any day, unless operations were continued uninterrupted from the 24 previous days and 25 (ii) Testing shall be conducted prior to resumption of operation of the
-- 8 6 -
source of radiation after any unintentional interruption; and 37 (iii) The licensee or registrant shall submit and adhere to a schedule for 3B periodic tests of the entry control and warning systems.
31
1 (j)
The licensee or registrant shall not conduct operations, cther than 3
those necesse:y to place the source of radiation in safe condition or to effect 3
repairs on controls, unless control devices are functioning properly.
4 (k) Entry and exit portals that are used in transporting materials to and 5
from the irradiation area, and that are not intended for use by individuals, 6
shall be controlled by such devices and administrative procedures as are 7
necessary to J ysically protect and warn against inadvertent entry by any 8
individual through these portals.
Exit portals for irradiated materials shall 9
be equipped to detect and signal the presence of any loon 2 idioactive material 10 that is carried toward such an exit and automatically to provent loose 11 radioactive material from being carried out of the area.
la (3)
Licensees, registrants, or applicants for licenses or registrations 13 for sources of radiation within the pury.ew of Subsection R313 15-603 (2) which 14 will be used in a variety of positions or in locations, such as open fielos or 15 forests, that make it (smpeacefeehkelimnractical to comply with certain 16 requirements of Subsection R313-15-603(2), such as those for the automatic 17 control of radiation J evels, may apply to the Executive Secretary for approval 18 of alternative safety measures.
Alternative safety measures shall provide 19 personnel protection at least equivalent to thost specified in Subsection R313-30 15-603(2).
At least one of the alternative measures shall include an entry-21 preventing interlock control based on a measurement of the radiation that ensures 33 the absence of high radiation levels before an individual can gain access to the 23 area where such sources of radiation are used.
24 (4)
The ently control devices required by Subsections R313-15-603 (2) and 35 R313-15-603(3) shall be established in such a way that no individual will be 26 prevented from leaving the area.
37 28 R313-15 701.
Oso of Process or other Engineering Controls.
32 A
1 The licensee or registrant shall
- use, to the extent i
2
(;;;:tirril;) practical, process or other engineering controls, such as, 4
J 3
containment or ventilation,- to control the concentrations of radioactive material 4
in air.
5 6
m313 15-703.
Use of other controls.
-7 When it is not (p.;;;ir:il;) practical to apply process or other engineering 8
controls to control the concentrations of radioactive material in air to values 9
below those that define an airborne radioactivity area, the licensee or 10 registrant shall, consistent with maintaining the total effective dose equivalent 11 ALARA, increase monitoring and limit intakes by one or more of the following 12 means:
13 (1) control of accessa or 14 (2)
Limitation of exposure times; or 15 (1)
Use of respiratory protection equipments or 16 (4)- Other controls.
17 18
-R313-15 703. Use of Individual Respiratory Protection Equipment.
1 19-
-(1)
If the licensee or registrant uses respiratory protection equipment 20 to limit intakes pursuant to Section R313-15-702:
21 (a)- Except as provided in Subsection R313-15-703 (1) (b), the licensee or 32 registrant shall use only respiratory protection equipment that is tested and 23 certified or had certification extended by the National Institute for 24 Occupational Safety and Health and the Miue Safety and Health Administration, 35
.(b)
(M-+)The licensee or registrant (wi;h;; ;)may use equipment that haa
-- 8 6 --
not:been tested or certified by the National Institute for Occupational Safety
' 87-and. Health and' the _ Mine Safety and Health Administration. has not had' 28 certification extended ' by the National Institute - for Occupational Safety and 33
1 Health and the Mine Safety and Health Administration, or for which there is no 2
schedule for testing or certification, providad the licensee or registrant 3
(;h:11 ;d nib)hm= m'o=4tted to t h.
armeutive secretarv and rh.
executive 4
sacratary ham aporoved an. application for authorized use of that equipment, j
5 including-a demonstration by testing, or a demonstration on the basis of G
[re44ebl+-] test information, that the material and performance characteristics 7
of the equipment are capable of providing the proposed degree of protection under 8'
anticipated conditions of use.
9 (c) The licensee or registrant shall implement and maintain a respiratory 10-protection program that includes:
11 (1)
Air sampling sufficient to identify the potential hazard, permit 13 proper equipment selection, and estimate exposures; and 13 (ii) surveys and bioassays, as appropriate, to evaluate actual intakes; v
[
14 and 15 (iii)
Testing of respirators for operability immediately prior to eachL 16 use; and 17 (iv)
Written procedures regarding selection,-
fitting, -issuance, 18 maintenance,- and testing of respirators, including testing. for operability 19 immediately prior to each uses supervision and training of personnel; monitoring, 30-including air sampling and bioassayas and recorJxeeping; and alt (v) Deterinination by a physician prior to initial fitting respirators, 33 and (;t ic;;tinither every 12 months thereafter or oeriodically at a freauenev 33 determined by a'chysician, that the individual user is (phy;ic;11y) medically 24-(ablel111 to use the respiratory protection equipment.
a 35 (d) The licensee or registrant shall issue a written policy statement on 36-respirator usage covering:
27 (1)
The use of process or other engineering controls, instead of 38 respiratores and 34 l
u
-n e
v.
r
,--w.
-.,.,.-,.,.-,n,,,_
4 0
1 (ii)
The routine, nonroutine, and emergency use of respirators; and 2
(iii) The length of periods of respirator use and relief from respirator 3
use.
4 (e) The licensee or registrant shall advise each respirator ser that the 5
user may leave the area at any time for relief from respirator use in the event 6
of equipment malfunction, physical or psychological distress, procedural or 7
comunication f ailure, significant deterioration of operating conditions, or any 8
other conditions that might require such relief.
9 (f) The licensee or registrant shall use respiratory protection equipment 10 within the equipment manufacturer's expressed limitation.s for type and mode of 11 use and shall provide proper visual, communication, and other special 12 capabilities, such as adequate skin protection, when needed.
13 (2)
When estimating exposure of individuals to airborne radioactive 14 materials, the licensee or registrant may make allowance for respiratory 15 protection equipment used to limit intakes pursuant to Section R313-15-702, 16 provided that the following conditions, in addition to those in Subsection R313-17 15 703(1), are satisfied:
18 (a)
The licensee or registrant selects respiratory protection equipment 19 that provides a protection factor, specified in Appendix A of 10 CFR 20.1001 to 20 20.2402, 199 (G]2 ed., which io incorporated by reference, greater than the 21 multiple by which peak concentrations of airborne radioactive materials in the 22 working area are expected to exceed the values specified in Appendix B, Table I, 33 Column 3 of 10 CFR 20.1001 to 20.2402, 199[4)2 ed., which is incorporated by 84 reference, floweve r, if the selection of respiratory prottetion equipment with 15 a protection factor greater than the (p::N car.ccr.t :ticr.]multinle defined in the 36 precedino sentence is inconsistent with the goal specified in Section R313-15-702 27 of keeping the total effective dose equivalent ALARA, the licensee or registrant 28 may select respiratory protection equipment with a lower protection factor 35
4
- 1 provided that such a selection would result in a total effective dose equivalent 2
that is ALARA.
The concentratie of radioactive material ir *,he air that is 3
inhaled when respirators - are worn may be-initially estimated by dividing the 4
-average concentration in air, during each period of uninterrupted use, by the 5
protection factor.
If the exposure is later found to be greater than initially 6
estimated, the corrected value shall be useds if the exposure is later found to 7.
be less than initially estimated, the corrected value may be used.
8 (b)
The licensee or registrant shall obtain authorization from the 9
Executive Secretary before assigning respiratory protection factors in excess of 10 those specified in Appendix A of 10 CFR 20.1001 to 20.2402, 199[s)2 ed., which 11 is incorporated by reference. The Executive Secretary may authorize a licensee 13 or registrant to use higher protection factors on receipt of an application that:
13 (i) Describes the situation for which a need exists for higher protection 14 factors, and 15-(ii) Demonstrates that the respiratory protection equipment provides these 16 higher protection factors under the proposed conditions of use.
17-(c)
In an emergency, the licensee or registrant shall use as emergency a
18 equipment only respiratory protection equipment that has - been specifically 19 certified or had. certific. ion extended for emergency use by the National 30 Institute for Occupational Safety and Health and the Mine Safety and Health
- 31 Administration.
l 33 (d)
The licensee or registrant shall notify the Executive Secretary in 33:
writing-at least 30 days before.he date that respiratory protection equipment 34 is - first used pursuant 'to either Subsections R313-15-703 (1) or R313-15-703 (2).
35 36 R313 15-s01. security
=d control of Licanned or m.aiatumL.[heced) sources of l
- 37 Radiation.
L L
38 (Th; lic;;;;; :
- gistrant
- h
- 11 :::;;; f;;; un: th: i::d ;; a c;1 l
36 le
-m _m
.e f
si e-l..
x.:: li
--_xd ::. ;i:tx :d x _ ;.; cf ;;dictd:. tint ::: :t;. d ir x::::11 d 2
- ;.x: ;i;t:d : x:,
i
=3 4
-4
__..... __- ___.. n,_,__ __
- u..
-5 752 lix :n :: x;i :in;: :h::: nad;;1 :sf : int:d;.u:::::
6.
- _..;ill xx :f lix;nd :: n;i:::nd nei::;tiv: =tni:1 th:t i; in.
.i: ;;t in :t:x;; = in ; p:ti:;t.
7 cxt::11:d :: xx:tri:t:d 2n: xxd tra
)
8 (t)
Thz x;icts:; 25211 n intzin :: :::1 f n dicti:n z hin:: that ::: -
9-in : x; n it:d = x x:::i:::d :::: :nd tra: ::: x:t ir ::;ng.. } (1) The j lican=== or reaintrant =hm11 macura linan=ad or reafstared radioactive materini 11-from un=uthnriano r==aval or aceaan.
- ) (2)
Tha lican=a.a or reafatrant ahmil maintain c<inatant murveillance. and
-13 uma devican or -d-in a trativa orne-duvaa to nravant un=uehnriand uma of lican=ad l
14 or reai5tarad radioactive material that in in an unrestricted arma -nd that in
-15 not in storama i.-
16 (3)
The raaiatrant
=h=11 nacure reafatared radiation machinas from 17-unauthorised r==aval-18 (4)
The reaintrant - shall - uma devices or ad-inistrative croceduras tg 19 nravant unauthorized uma of raciatered radiation machines.
20 r
21 R313 15 901.
caution signs, 22 (1)
Standard Radiation' Symbol.
Unless otherwise authorized by the 23 Executive Secretary, the symbol prescribed by 10 cra 20.1901, 199[6)2 ed., which
- 24 is incorporated by reference, shall use the colors magenta, or purple, or black
-25 on yellow; background.
The symbol prescribed is the three-bladed design as
-26 '
follows:-
=27 (a) cross. hatched area is-to be magenta, or purple, or black, and 28' (b)
The background is to be yellow.
37 L
1 (2) Exception to Color Requirements for Standard Radiation Symbol.
2 Notwithstanding the requirements of 10 CFR 20.1901a, 199(3))
ed.,
which is 3
incorporated by reference, licensees or registrants are authorized to label 4
sources, source holders, or device components containing sources of radiation 5
that are subjected to high temperatures, with conspicuously etched or stamped 6
radiation caution symbols and without a color requirement.
7 (3)
Additional Information on Signs and Labels.
In addition to the 8
contents of signs and labels prescribed in Rule R313-15, the licensee or 9
registrant shall provide, on or near the required signs and labels, additional 10 information, as appropriate, to make individuals aware of potential radiation 11 exposures and to minimize the exposures.
12 13 14 R313-15 902.
Posting Requirements.
15 (1)
Posting of Radiation Areas.
The licensee or registrant shall poat 16 each radiation area with a conspicuous sign or signs bearing the radi. 'un symbol 17 and the words " CAUTION, RADIATION AREA."
18 (2)
Posting of High Radiation Areas.
The licensee or registrant shall 19 post each high radiation area with a conspicuous sign or signs bearing the 20 radiation symbol and the words " CAUTION, HIGH RADIATION AREA" or " DANGER, HIGH 21 RADIATION AREA."
22 (3)
Posting of Very High Radiation Areas.
The licensee or registrant 23 shall post each very high radiation area with a conspicuous sign or signs bearing 24 the radiation symbol and words " GRAVE DANGER, VERY HIGH RADIATION AREA."
25 (4)
Posting of Airborne Radioactivity Areas. The licensee or registrant 26 shall post each airborne radioactivity area with a conspicuous sign or signe 27 bearing the radiation synd>ol and the words " CAUTION, AIRBORNE RADIOACTIVITY AREA" 28 or "DA'1GER, AIRDORNE RADIOACTIVITY AREA."
38 I
e 1
_(5)
Posting of Areas or Rooms in which Licensed or Registered Material is 2
Used or stored. The licensee or registrant chall post each area or room in which 3
there is used or stored an amount of licensed or registered material exceeding 4
ten times the quantity of such material specified in Appendix C of 10 CFR 20.1001 5
to 20.2402, 199[4]2 ed., which is incorporated by reference, with a conspicuous 6
sign or signs bearing the radiation symbol and the words " CAUTION, RADIOACTIVE-7 MATERIAL" or " DANGER, RADIOACTIVE MATERIAL."
8-9 m313-15-903. Exceptions to Posting mequirements.
{
l 10 (1)
A licensee or registrant is not required to post caution signs in 11 areas or rooms containing sources of radiation for periods of less than eight 12' hours, if each of the-following conditions is metr 13 (a) The sources of radiation are constantly attended during these periods 14 by an individual who takes the precautions necessary to prevent the exposurs of 15 individuals to sources of radiation in excess of the limits established in Rule
.16 R313-15; and 17-(b) The area or room is subject to the licensee's or registrantis control.
18 (2)
Rooms or other areas in hospitals that are occupied by patients are-19 not required to be posted with caution signe pursuant to Section R313-15-902 20 provided that the patient could be released from ( :afin;;;;;)licannee control-
'21 pursuant to Section R313-32 75.
22 (3)
A room or area is not required to be posted with a caution sign 23 because of the presence of a sealed source provided the radiation level at 30 24-centimeters from the surface of the sealed-source container or housing does not 25 exceed 0.05 mSv (0.005 rem) per hour, 26 (4)-
A room or area is not required to be posted with a caution sign-27 because of the presence of radiation machines used solely for diagnosis in the 28 healing arts.
39
1 R313 15 904.
Labeling Containers and Aadiation Machines.
2 (1)
The licensee or registrant shall ensure that each container of 3-
-licensed or registered material bears a durable, clearly visible label bearing 4
_the-radiation symbol and the words " CAUTION, RADIOACTIVE MATERIAL" or " DANGER,
-5 RADI0 ACTIVE-MATERIAL. " The label shall also provide-information, such as the 6
radionuclides present, an estimate of the quantity of radioactivity, the date for 7
which the activity is estimated, radiation levels, kinds of materials, and mass 8-
. enrichment, to permit individuals handling or using the containers, or working
'9
.in the vicinity of the containers, to take precautions to avoid or minimize 10 exposures.
11 (2)
Each licensee or registrant shall, prior to removal or dirposal of 12 empty uncontaminated containers to. unrestricted areas, remove or deface the 13 radioactive material label or otherwise clearly indicate that the container no 14 longer contains radioactive materials.
15 (3)
Each registrant shall ensure that-each radiation machine is labeled
- 16 '
in a conspicuous manner which cautions individuals that radiation is produced 17 when it is energized.
118 19' R313 15'-905.
axeeptions to Labeling Requirements.
L20-A licensee or registrant is not required to label
-21 (1). Containers holding licensed or registered material in quantities less 22 than the quantities listed in Appendix C of 10 CFR 20.1001 to 20.2402, 199[4]2
-23
.ed., which is incorporated by reference; or (2) Containers holding licensed or registered material in concentrations 25 less than those specified in Table III of Appendix B of 10 CFR 20.1001 ' to l
-261 20.2402, 199(+12 ed., which is incorporated by reference; or l
27 (3)
' Containers attended by an individual who takes the precautions 28 necessary to prevent the exposure of individuals in excess of the limits e
40 l
(.
1
. established by Rule R313-15; or 2
(4)
Containers when they are in transport and packaged and labeled in 3
accordance with the rules of the U.S. Department of Transportation or 4
(5)
Containers that are accessible only to individuals authorized to 5
handle or use tham, or to work in the vicinity of the containers, if the contents 6
are identified to these individuals by a readily available written record.
7 Examples of containers of this type are containers in locations such as water-8 filled canals, storage vaults, or hot cells. The record shall we retained as long 9
as the containers are in use for the purpose indicated on the reccrd; or 10 (6)
Installed manuf acturing or process equipment, such as piping and 11 tanks.
12 13 R313-15-906.
Procedures for Receiving and Opening Packages.
14 (1)
Each licensee or registrant who expects to receive a package 15 containing quantities of radioactive material in excess of a Type A quantity, as 16 defined in Section R313-19-4 and Subsection R313 100 (19), shall make 17 arrangements to receive 18 (a) The package when the carrier offers it for delivery; or 19 (b)
The notification of the arrival of the package at the carrier's 20 terminal and to take possession of the package expeditiously.
21 (2)
Each licensee or registrant shall:
22 (a)
Monitor the external surf aces of a labeled package for radioactive 23 contamination unless the package contains only radioactive material in the form 24 of gas or in special form as defined in Section R313-12-3; and 25 (b)
Monitor the external surfaces of a labeled package for radiatiot.
26 levels unless the package contains quantities of radioactive material that are 27 less than or equal to the Type A quantity, as defined in Section R313-19-4 and 28 Subsection R313-19-100(19) ; and 41 i
L
4 1
(c)
Monitor all packages known to contain radioactive material for 2
radioactive contamination and radiation levels if there is evidence of 3
degradation of package integrity, such as-packages that are crushed, wet, or 4
damaged.
.5 (3)
The licensee or registrant shall perform the monitoring required by 6
Subsection R313-15 906 (2) as soon as (ps::ticabic) practical af ter receipt of the 7
package, but not later than three hours after the package is received at the 8
licensee's or registrant's facility if it is received during the licensee's or-9 registrant's normal working hours (,
er n:t 22ter th:2 tire; h;;r f;;; the 10-5:sirming cf the n::: ucrking day if it i ;;;;ived :f ter x:-hing h:urs.) or if 11 there is evidence of dearadation of nackman intearitv. auch as a nackmaa that in
-}c 12-crunhed. wet. or damaged.
If a nackmae is received after workina hours, and han
\\
13 no evidence of dearadation of nackman intearitv. the nackmae shall be monitored 14 no later than three hours from the bacinnina of the next workina dav.
15 (4) The licensee or registrant shall immediately notify the final delivery 16 carrier and, by telephone and telegram, mailgram, or facsimile, the Executive 17 Secretary when:
18 (a)
Removable radioactive surface contamination exceeds the limits of 19 Subsection R313-19-100 (13) (h) ; or 30 (b)
External radiation levels exceed the limits of Subsections R313 al 100(13)(i) and R313-19-100(13)d).
32 (5)
Each-licensee or registrant shall:
33 (a) Establish, maintain, and retain written procedures for safely opening 24
-packages in which radioactive material is received; and 2 5__
(b). Ensure that_the procedures are followed and that due consideration is 36 given to'special instructions for the type of package being opened.
2 1
37 (6) Licensees or registrants transferring special form sources in vehicles 42
~
~. -..
-.r
..,m..,.
-m.v
-,... ~ -
4 1-owned or operated by the licensee or registrant to and from a work site are 2
exempt f rom the contamination monitoring requirements of -Subsection R313 3 906 (2), but are not exempt from the monitoring requirement in Subsection R313 4 9n6 (2) for measuring radiation levels that ensures that the source is still SL properly-lodged in its shield.
6
~7 R313-15-1001. waste Disposal - seneral Requirements.
l
'S-(1)
A licensee or registrant shall dispose of licensed or registered -
9 material only 10 (a) By transfer to an authorized recipient as provided in Section R313 11 1006 or in Rules R313-21 R313-22, or R313-25, or to the U.S.
Department of 12
. Energy; or-13 (b)
By decay in storage; or 14 (c)
By release in effluents within the limits in Section R313-15-301; or 15 (d) As authorized pursuant to Sections R313-15-1002, R313-15-1003,_R313-16 15-1004, or R313-15-1005.
17 (2) A person shall be specifically licensed or registered to receive waste
.18 containing licensed or registered material from other persons for:
.19.
(a)
Treatment prior to disposali or 20 (b)
Treatment or disposal by incinerationi or 21-(c)
Decay in storages or 22 (d)- Disposal at a land disposal facility licensed pursuant to Rule R313-83 25; or 24-
. e) _ Storage until transferred to a storage or disposal facility authorized
(
25 to receive the waste.
- - 2 6 --- - - -
87 R313-15-1002. Method for obtaining Approval of Proposed Disposal Procedures.
'28 A ' licensee or registrant-or applicant for a license or registration may 43
1 apply to the Executive Secretary for approval of proposed procedures, not 2
otherwise authorized in these rules, to dispose of licensed or registered 3
material generated in the licensee's or registrant's operations.
Each 4
application shall include:
5 (1) A description of the waste containing licensed or registered material 6
to be disposed of, including the physical and chemical properties that have an 7
impact on tisk evaluation, and the proposed manner and conditions of waste 8
disposal; and 9
(2) An analysis and evaluation of pertinent information on the nature of 10 the environment; and 11 (3) The nature and location of other potentially affected facilities; and 13 (4) Analyses and procedures to ensure that doses are maintained ALARA and 13 within the dose limits in Rule R313-15.
14 15 R313-15-1003.
Disposal by Release into Sanitary Sewerage.
16 (1) A licensee or registrant may disch'arge licensed or registered material 17 into sanitary sewerage if each of the following conditions is satisfied:
18 (a) The material is readily soluble, or is readily dispersible biological 19 material, in water; and 20 (b) The quantity of licensed or registered radioactive material that the al licensee or registrant releases into the sewer in one month divided by the 33 average monthly volume of water released into the sewer by the licensee or 33 registrant does not exceed the concentration listed in Table III of Appendix B 24 of 10 CFR 20.1001 to 20.2402,199(G)2 ed., which is incorporated by reference; and 35 (c)
If more than one radionuclide is released, the following conditions 26 shall also be satisfied:
27 (i) The licensee or registrant shall determine the fraction of the limit 28 in Table III of Appendix B of 10 CFR 20.1001 to 20.2402, 199[G)2 ed.,
which is t
44
I i
1 incorporated by reference, represented by discharges into sanitary sewerage by l
2 2
dividing the actual monthly average concentration of each radionuclide released 3
by the licensee or registrant into the sewer by the concentration of that 4
radionuclide listed in Table 121 of Appendix B of 10 CFR 20.1001 to 20.2402, 5
199(412 ed., which is incorporated by references and 6
~ (11) The suoi of the fractions for each radionuclide required by subsection t
7 R313-15 1003 (1) (c) (i) does not exceed unity; and 8
(d) The total quantity of licensed or registered radioactive material that 9
the licensee or registrant releases into the sanitary sewerage system in a year 10 does not_ exceed les GBq (five ci) of hydrogen-3, 37 GBq (one ci) of carbon-14, 11 and 37 apq (one ci) of all other radioactive materials combined.
12 (2) Excreta from individuals undergoing medical diagnosis or therapy with 7
13 radioactive material-are not subject to the limitations contained in subsection 14 R313-15-1003(1).
l 15 16 m313 15 1004. Treatment or Disposal-by Incineration.
17-A licensee or registrant-may treat or dispose of licensed er registered 18 material by incineration only in the I: ::::: :nd f rs ) form and concentration 19-
_specified in section R313-15-1005 or as specifically. approved by the Executive 20 secretary pursuant to Section R313-15-1002, 21 22 R313 15-1005. Disposal of specific wastes.
2t (1)
A licensee or registrant may dispose of the following licensed or 24-registered material as if it were not radioactive:
25 (a) 1.85 kBq (0.05 uci), or less, of hydrogen-3 or carbon-14 per gram of 261-medium used for'11guid scintillation counting; and
~ 2 7_
(b) 1.95 kBq (0.05 uci) or less, of hydrogen 3 or carbon-14 per gram of 38 animal tissue averaged over the weight of the entire an; sal.
45
1 (2)
A licensee or registrant shall not dispose of tissue pursuant to 3
Subsection R313-15-1005 (1) (b) in a manner that would permit its use either as 3
food for humans or as animal feed.
4 (3) The licensee or registrant shall maintain records in accordance with 5
Section R313-15-1109.
6 7
R313-15 1006.
Transfer for Disposal and Manifests.
8 (1)
(8Fhe-e] Requirements of Section R313-15-1006 and Appendix F and a of 9
10 CFR 20.1001 to 20.2402, 199[3)2 ed.[, which i; ineerperated by referen c,)
10 la)
The requirements of section R313-15-1006 and Anoendix F and O of 10 11 CFR 20.1001 to 20.2402. 1997 ed.
which are incorporated into these rules by la reference. are designed toA 13 (1) control transfers of low-level radioactive was te [= int ended for 14 diepenal-et--e-14een;;d Icw 1 ^v 2 radicacti v w;.;t: dispc;;l f aci-lity, establich 15 a-ennif eet-+eeek ing ;, ate =, rad supple cat exi; ting requirements conecrains 16 tennefeve-en? recordk : ping f r th::: v;;tes,).bv any waste cenerator. wasta 17 collector. or waste processor licensee. as defined in Anpendix F or o in 10 CFR 18 20.1001 to 20.2402. 1997 ed.
who ships low-leve! waste either directiv. or 19 indirectiv through a waste collector or waste nrocessor. to a licensed low-level 30 waste land disposal facilitv an defined in section R313 2s-2, 31 (11) establish a manifest trackina system; and 33 (1111 supolement existina resuirements concernina transfers and 33 recordkeenino for those wastes.
34 (b)
Beginnina March 1.
1999. all affected licensees must use Anoendix G 25 of 10 CFR 20.1001 to 20.2402. 1997 ed.
which is incornorated into these rules 26 by ref erence.
Prior to March 1.
1998. a low-level waste disposal facility 9
37 ppgrator or its reculatory authority may recuire the shipner to use Anoendix F 38 or ADDendix 0 of 10 CFR 20.1001 to 20.2402. 1997 ed.
Licensees usino Appendis a
h 46 I
t
1 P ahall comniv with Subsection R313-15-1006(2)(a).
Licenneen usina Anoendix 0 2
shall comniv vith subsection R313-15-1006(2)(b).
3 (2)
Shipment of Radioactive Waste.
4 lal Each shipment of radioactive waste designated for disposal at a 5
licensed low-level radioactive waste disposal facility shall be cecompanied by 6
a shipment manifest as specified in section I of Appendix F of 10 CFR 20.1001 to l
l 7
20.2402, 199(a)2 ed., which is incorporated by reference.
l 8
ib) Any licennee chiteina radioactive waste intended for ultimate dinnonal 9
at a licenned land disnonal f acilit!' must document the information renuired on 10 the u.s. rinclear negulatory comminaion n uniform tow-Levei nadioactive Wante e
11 Manifent and trannfer this recorded information to the intended connionee in 12 accordance with Anoendix 0 to 10 cFR 20.1001 to 20.2402. 1997 ed.
which la 13 incorpoy_sted into these rulen by reference.
14 (3)
Each shipment manifest shall include a certification by the waste 15 generator as specified in section II of Appendix F or a. an annronriate. of 10 16 CFR 20.1001 to 20.2402, 199(4)2 ed., which is incorporated by reference.....See 17 S.ubsection n313-is-1006 (1) (b) to determine the anprocriate Annendix.
18 (4)
Each person involved in the transfer of waste for disposal or in the 19 disposal of waste, including the waste generator, waste collector, waste 30 processor, and disposal facility operator, shall comply with the requirements 21 specified in Section III of Appendix F or G.
an annropriate. of 10 CFR 20.1001 32 to 20.2402, 19 9 ] 2 ed., which is incorporated by reference.
See Subsection 23 R313-15-1006(1)(b) to determine the anpronriate Apnendix.
24 25 R313-15-1007. Compliance with Envircnmental and Health Protection Rules.
26 Nothing in Sections R313-15-1001, R313-15-1002, R313-15-1003, R313-15 1004, 27 R313-15-1005, or R313-15-1006 relieves the licensee or registrant from complying 28 with other applicable Federal, State and local rules governing any other toxic 47
1 or hazardous properties e.,f materials that may be disposed of pursuant to Sections 3
R313-15 1001, R313-15 1002, R313 15-1003, R313-15-1004, R313-15-1005, or R313 3 1006.
4 5
R313-15-1008. Classification and Characteristics of 1,ow Level Radioactive Waste.
6 (1)
Classification of Radioactive Waste for Land Disposal 7
(a)
CM aiderations.
Determination of the classification of radioactive 8
waste involves two considerations.
First, consideration shall be given to the 9
concentration of long lived radionuclides (and their shorter-lived precursors) 10 whose potential hazard will persist long after such precautions as institutional 11 controls, improved waste form, and deeper disposal have ceased to be effective.
la These precautions delay the time when long-lived radionut..'.de s could cause 13 exposures.
In addition, the magnitude of the potential dose is limited by the 1
14 concentration and availability of the radionuclide at the time of exposure.
15 Second, consideration shall be given to the concentration of shorter-lived 16 radionuelides for whicts requirements on institutional controle, waste form, and 17 disposal methods are effective.
18 (b)
Classes of waste.
19 (i)
Class A waste is waste that is usually segregated trom other waste 30 classes at the disposal site. The physical form and characteristics of Class A 31 waste shall meet the minimum requirements set forth in Subsection R313 23 1000 (2) (a).
If Class A waste also meets the stability requirements set forth in 33 Subsection R313-15-1000 (2) (b), it is not necessary to segregate the waste for 24 disposal.
25 (ii) Class B waste is wa '.e that shall meet more rigorous requirements on 36 waste form to ensure stability
.'ter disposal.
The physical form and 27 characteristics of Class a waste shall meet both the minimum and stability i
38 requirements set forth in Subsectisn R313-15-1000(2).
48
1 (iii) class c waste is waste that not only shall meet more rigorous 2
requirements on waste form to ensure stability but also requires additional 3
measures at the disposal facility to protect against inadvertent intrusion. The 4
physical form and characteristics of class c waste shall meet both the minimum 5
and stability requirements set forth in subsection R313-15-1008 (2).
6 (c) classification determined by long-lived radionuclides.
If the 7
radioactive waste contains only radionuclides listed in Table I, classification 8
shall be determined as follows:
l-l 9
(i)
If the concentration does not exceed 0.1 times the value in Table I, 10 the waste is class A.
11 (ii) If the concentration exceeds 0.1 times the value in Table I, but does 12 not exceed the value in Table I, the waste is class C.
13 (iii)
If the concentration exceeds the value in Table I, the waste is not 14 generally acceptable for land disposal.
15 (iv)
For wastes containing mixtures of radionuclides. listed in Table I, 16 the total concentrat Aon shall be determined by the sum of fractions rule 17 described in Subsection R313-15-1008 (1) (g).
18 19 TABLE I 20 21 concentration 22 23 Radionuclide curie / cubic meter (1) nanocurie/ gram (2) 24 25 c-14 8
26 C 14 in activated metal 80 27 Ni-59 in activated metal 220 28 Nb-Si in activated metal 0.2 49
l t
1 Tc 99 3
21 I-129 0.0s 3
Alpha = emitting transuranic 4-radionuclides with half-5 life greater than five 6
years 100 7
Pu 241 3,500 8
Cm 242 20,000 9-Ra-226 100 10-11 NOTES.
_(1)
To convert _ the.Ci/m8 values to gigabecquerel (GBq)/ cubic metet 12 multijly the Ci/m$ value by 37. -
13
-(2) To convert the nci/g values to becquerel (Bq)/ gram, multiply the nCi/g value 14-
- by_37, 15
-16 (d). Classification' determined by short-lived radionuclides. If the waste
- _17 -
does not contain any of the radionuclides listed in Table I, classification shall 18 be - determined based - on the concentrations shown in Table II.
However,- as 19; specified in Subsection R313-15-1008 (1) (f), if radioactive waste does not contain.
20-any nuclides listed in'either Table I or II, it is.C.' ass A.
- 21; (i)
If the concentration does no exceed the value in Column 1, the waste
-12 3 is Class-A.
23 (ii)
If the concentration ' exceeds the value in Column 1 but does not
'24 exceed the value in Column 2, the waste is Class B.
- - - 2 5 - ---
-- (iii): If1the-concentration-exceeds-the-value-in Column 2 but does not 126 exceed the value in Column-3,-the waste is Class C.
27
_{iv) ;1f the concentration exceeds the value in Column 3, the waste is not L28 Jgen". rally. acceptable for near-surface disposal.
50
1 (v)
For wastes containing mixtures of the radionuclides listed in Table 2
II, the total concentration shall be determined by the sum of fractions rule 3
described in Subsection R313-15-1008 (1) (g).
4 5
TABLE II 6
7 8
Radionuclide Concentration, curie / cubic meter (1)
D Column 1 Column 2 Column 3 10 Total of all radio-11 nuclides with less 12 than 5-year half-13 life 700 (2)
(2) 14 H-3 40 (2)
(2) l l
15 Co-60 700 (2)
(2) 16 Ni-63 3.5 70 700 17 Ni-63 18 in activated ratal 35 700 7000 19 sr-90 0.04 150 7000 20 Cs-137 1
44 4600 21 22 NOTE:
(1)
To convert the Ci/m' value to gigabecquerel (GBq) / cubic meter,
. 83 multiply the Ci/m' value by 37.
24 (2)
There are no limits established for these radionuclides in Class B or C 25 wastes. Practical considerations such as the effects of external radiation and 26 internal heat generation on transportatio'4, handling, and disposal will limit the
~ 27 concentrations for these wastes.
These wastes shall be Class B unless the 88 concentrations of other radionuclides in Table II determine the waste to be class 51 I
v
1 C independent of these radionuclides.
2 3
(e) Classification determined by both long-and short-lived radionuclides.
4 If the radioactive waste contains a mixture of radionuclides, some of which are 5
listed in Table I and some of which are listed in Table II, classification shall 6
be determined as follows:
7 (i)
If the concentration of a radionuclide listed in Table I is less than 8
.0.1 times the value listed in Tablo I, the class shall be that determined by the 9
concentration of radionuclides listed in Table II.
10 (ii)
If the concentration of a radionuclide listed in Table I exceeds 0.1 la times the value listed in Table I, but does not exceed the value in Table I, the la waste shall be Class C, provided the concentration of radionuclides listed in 13 Table II does 'ot exceed the value shown in Column 3 of Table II, 14 (f)
Classification of wastes with radionuclides other than those listed 15 in Tables I and II.
If the waste dor 1 not contain any radionuclides listed in 16 either Table I or II, it is Class A.
17 (g)
The sum of the fractions rule for mixtures of radionuclides.
For 18 determining classification for waste that contains a mixture of radionuclides, 19 it is necessary to determine the sum of fractions by dividing each radionuclide's 30 concentration by the appropriate limit and adding the resulting values.
The 31 appropriate limits shall all be taken from the same column of the same table.
22 The sum of the fractions for the column shall be less than 1.0 if the waste class 23 is to be determined by that column.
Example:
A waste contains Sr-90 in a 24 co'scentration of 1.85 TBq/m (50 C1/nf ) and Cs-137 in a concentration of 814 3
35 GBq/m* (22 Ci/m'). since the concentrations both exceed the values in Column 1, 26 Table II, they shall be compared to Column 2 values. For Sr-90 fraction, 50/150
[
27 0.33.,
for Cs-137 fraction, 22/44 0.83.
{
0.5; the sum of the fractions
=
i 28 Since'the sum is less than 1.0, the waste is Class B.
j 52 t
o 0
1 (h)
Determination of concentrations in wastes.
The concentration of a 2
radionuclide may be determined by indirect methods such as use of scaling factors 3
which relate the inferred concentration of one radionuclide to another that is 4
measured, or radionuclide material accountability,. if there is reasonable 5-assurance that the indirect methods can be correlated with actual measutaments, 6
The concentration of a radionuclide may be averaged over the volume of the waste, 7
or weight of the waste if the units are expressed as becquerel (nanocurie) per 8
gram.
9 (2)
Radioactive Waste characteristics 10 (a)
The following are minimum requirements for all classes of waste and 11 are intended to facilitate handling and provide protection of health and safety 13
-of personnel at the disposal site.
13 (1)
Wastes shall be packaged in conformance with the conditions of the 14 licerse insued to the site operator to which the waste will be shipped.
Where-15 the conditions of the site license are more restrictive than the provisions of 16 (Peet-ejnula R313-is, the site license conditions shall govern.
17' (ii)- Wastes shall not be packaged for disposal-in cardboard or fiberboard 18
. boxes.
19 (iii). Liquid waste shall be packaged in suffic'ient absorbent material to 20
-absorb twice the volume of the liquid.
21 (iv)
Solid waste containing liquid shall contain as little free-standing 22 and non-corrosive liquid as is reasonably achievable, but in no case shall the 23
. liquid exceed one percent of the volume.
24 (v)
Waste shall not be readily capable of detonation or of explosive 25-decomposition or reaction at normal pressures and temperatures, or of explosive 26 reaction with water.
-27 (vi) Waste shall not contain, or be capable of generating, quantities of
-38 toxic gases, vapors, oor fumes harmful to persons transporting, handling, or.
53 4
1 disposing of the vaste.
To a does not apply to radioactive gaseous waste J2
_ packaged in accordance with Subsection R313 15-1008 (2) (a) (viii).
~
-3 (vii)
Waste shall not be pyrophoric.
pyrophoric materials contained in
-4 wastes shall be treated, prepared, and packaged to be nonflammable.
5 (viii) Wastes in a gaseous form shall be packaged at an absolute pressure
-6 that does not exceed 1.5 atmospheres at 20 degrees celsius. Total activity shall 7
not exceed 3.7 TBq (100 C1) per container.
8 (ix) Wastes containing hazardous, biological, pathogenic, or infectious 9
material shall be treated to reduce to the maximum extent [p ;= i d i:) practical 10 the potential hazard from the non radiological materials.
11 (b) Tr 3 follow'ing requirements are intended to provide stability of the 12 waste.
Stability is intended to ensure that the waste does not degrade and 13 affect overall stability of the site through slumping, collapse, or other failure 14 of the disposal unit and thereby lead to water infiltration.
Stability is also 15 a factor in limiting exposure to an inadvertent intruder, since it provides a 16 recognizable and nondispersible waste.
17 (1) Waste shall have structural stability. A structurally stable waute 18-form will generally maintain its physical dimensions and its form, under the 19_
expected disposal conditions such as weight of overburden and compaction
- 20 equipment, the preeence of moisture, and microbial activity, and internal factors 21 such as radiation effects and chemical changes.
Structural stability can be 22 provided by the waste form itself, processing the waste to a stable form, or 23
_ placing the waste in a disposal container or structure that provides stability 24 after disposal.
25 (ii) Notwithstanding the provisions in Subsections R313-15-1008(2) (a) (iii)
-26 and R313-15-1000 (2) (a) (iv), liquid wastes, or wastes containing liquid, shall be 27 converted into a form that contains as little free-standing and non-corrosive 28 liquid as is reasonably achievable,-but in no case shall the liquid exceed one 54 g
1
e 1
percent of the volume of the waste when the waste is in a disposal containar 2
- designed to ensure stability, or 0.5 percent of the volume of the waste for waste 3
processed to a stable form.
4 (iii) Void spaces within the waste and between the waste and its package 5-shall be reduced to the extent (;;;;;i:151:19 tactical.
6 (3) Labeling. Each package of waste shall be clearly labeled to identify 7
whether it is class A, class B, or class C waste, in accordance with subsection 8
. R313 15-100B (1).
9 9
10' R313-15-1101. Records - seneral Provisions.
11 (1)
Rach licensee or registrant shall use the SI units becquerel, gray, 12 sievert and coulomb per kilogram, ior the special units, curie, rad, rem, and 13' roentgen, including multiples and subdivisions, and shall clearly indicate the 14 units of'all quantities on records' required by Rule R333-15.
15 (2)
Notwithat=ndina the ramuir---nts of Buhmaction R313-15-1101(1). when 16 recording information on =hia--at==nifants. as resuired in suhmaction nai3-is-17
.1006(2). information must be recordad in 97 units or in af units and the mencini 18
_ units anecified in submaction R313-15-liO1(1).
19 (44+1J21 The licensee or registrant shall make a clear distinction among 20 the quantities entered on the records required by Rule R313-15, such so, total 21 ef fective dose equivalent, total organ dose equivalent, 9 hallow dose equivalent, 22 eye-dose -equivalent, deep dose equivalent, or committed effective dose 23 equivalent.
'24
-25 R313 15 1103. Records of Radiation Protection Programs.
26-(1)
Each licensee or registrant shall maintain records of the radiation 27 protection program, including:
28 (a) The provisions of-the program; and 55 i
1 (b)
Audits and other reviews of program content and implementation.
2 (2)
The licensee or registrant shall retain a records required by 3
Subsection R313 15-1102 (1) (a) until the Executive Secretary terminates each 4
pertinent license or registration requiring the record.
The licensee or 5
registrant nhall retain the records required by Subsection R313-15-1102 (1) (b) for 6
three years after the record is made.
7 8
R313-15-1103. Records of Surveys.
9 (1) Each licensee or registrant shall maintain records showing the results 10 of surveys and calibrations required by Section R313-15-501 and Subsection R313-11 15-906(2). The licenoee or registrant shall retain these records for three years 12 after the record is made.
13 (2) The licensee or registrant shall retain each of the following records 14 until the Executive Pecretary terminates each pertinent license or registration 15 requiring the record 16 (a) Records of the results of surveys to determine the dose from external 17 sources of radiation used, in the absence of or in combination with individual 18 mo:1.itoring data, in the assessment of individual dose equivalents; and 19 (b)
Records of the results of measurements and calculations used to 20 determine individual intakes of radioactive material and used in the assessment 21 of internal dose; and 22 (c)
Records showing the results of air sampling, surveys, and bioassays 23 required pursuant to Subsections R313-15 703 (1) (c) (i) and R313-15-703 (1) (c) (ii) ;
24 and 25 (d)
Records of the results of measureme ts and calculations used to 26 evaluate the release of radioactive offluents to the environment.
I 37 28 R313-15-1104. Records of Tests for Leakage or Contandnation of Sealed Sources.
56 t
1o 0
1 Records of tests for leakage or contaminatien of sealed sources required
-- 2 by Section R313-15-401 shall be kept in units. of becquerel or microcurie and 3.
maintained for inspect ion by the Executive Seexetary for five years af ter the 4
records are made.
5 i
6 R313-15-1105. Records of Prior Occupational Dose.
-/
For each individuni whn im likely to receive in a year an occunatinnal dong 8
reauirina mnnitorina nursuant to Section R313-15-502.
(8P) the licensee or 9
registrant shall retain the records of prior occupational dose and exposure 10_
history as specified in Section R313-15-205 on form DRC-05 or equivalent until 11 the Executive Secretary terminatos each pertinent license requiring this record, 12 The licenses or registrant-shall retain records used in preparing form DRC-05 or l-13 equivalent for thres years af ter the record is made.
14 i
15 R313-15-1106.
Records of Planned Spanial Exposures.
16 (1)
For each use of the provisions of Section R313-15-206 for planned 17 specfal exposures, the licensee or registrant shall maintain-records that 18 describe:
19 (a)
The exceptional circumstances requiring the use of a planned special 20 exposure; and 31 (b) The name of the management official who authorized the planned special 32 exposure and a copy of the signed authorization; end 23 (c)
What actions were necessary; and 24 td) 'Why the actions were.ecessary; and 25 (e)
What precautions were taken to assure that doses were maintained 26-ALA4 and 37 (f)
What individual and collective doses were expected to result; and 28 (g)
The doses actually received 1.4 ;;he planned special exposure.
57 i....
i 1
(2)-
The licensee or registrant shall retain-the records until the 2
Executive Secretary terminates each. pertinent license or registration requiring i
3 these records.
4 5
R313-15-1107.
Records of Individual Monitoring Results.
6
-(1)
Recordkeeping Requirement. Each licensee or registrant shall maintain 7
records of doses received by all individuals for whom monitoring was required 8
pursuant to Section R313-15-502, and records of doses received during planned 9
special exposures, accidents, and emergency cenditions.
Assessments of dose 10 equivalent and records made using units in effect before January 1, 1994, need 11 not be changed. These records shall include, when applicable:
12' (a)
The deep dose equivalent to the whole body, eye dose equivalent, 13 hallow dose equivalent to the skin, and shallow dose equivalent to the s
14 extremities; and 15 (b)
The estimated intake of-radionuclides, see Section R313-15-202; and 16' (c)
The committed effective dose equivalent assigned to the intake of 17 radionuclides and 18 (d)
The specific information-used to calculate the committed effective 19 done equivalent pursuant to Subsection R313-15-204 (3) and 20 (e) The total effective dose equivalent when required by Section R313 21 202; and 22 (f)
The total of the deep dose equivalent and the committed dose to the p
23 organ receiving the highest total dose.
'24 (2) Recordkeeping Frequency. The licensee or registrant shall make entries
'25' of the records specified in Subsection R313-15-1107 (1) at intervals not to exceed f
26 one year.
.27 (3) Recordkeeping Format. The licensee or registrant shall maintain the i
l l'
28 records specified in Subsection R313-15-1107 (1) on form DRC-06, in accordance I
i l
58 i
.-i
I with the instructions for form DRC-06, or in clear and legibic records containing 2
all the information required by form DRC-06.
3 (4) The licensee or registrast shall maintain the records of dose to an i
4 embryo / fetus with the records of dose to the declared pregnant woman.
The 1
5 declaration of pregnancy, including the estimated date of conception, shall also 6
be kept on file, but may be maintained separately from the dose records.
7 (5) The licensee or registrant shall retain each required form or record 8
until th( 4xecutive Secretary terminates each pertinent license or registration 9
requiring the record.
10 11 R313-15-1108.
Records of Dose to Individua; Aembers of the Public.
12 (1)
Each licensee or registrant chall maintain records sufficient to 13 demonstrate compliance with the dose limit for individual membera of the public.
14 See Section R313-15-301.
15 (2)
The licensee or registran; shall retain the records r-tred by 16 Subsection R313 1108 (1) until the Executive Secretary terminates each 17 pertinent license or registration requiring the record, Recuirements for 18 dinnosition of these records. nrior to licenne termination. are 19eated in 19 Section R313-12-51 for activities licenned under these rules.
20 21 R313-15-1109.
Records of to Disposal.
4 22 (1) Each licensee or registrant shall maintain records of the disposal of 23 licensed or registered materials made pursuant to Sections R313-15-1002, R313 24 1003, R313-15-1004, R313-15-1005, Rule R313-25, and disposal by burial in soil, 25 including burials authorized before January 28, 1981, 26 (2)
The licensee or registrant shall retain the records required by 27 Subsection R313 1109 (1) until the Executive Secretary terminates each 28 pertinent lice.ase or registration requiring the record.
59
e i
1 R313-15-1110. Records of Testing Entry Control Devices for Very High Radiation 2
Areas.
3 (1)
Each licensee or registrant shall maintain records of tests made 4
pursuant to subsection R313-15-603 (2) (1) on entry control devices for very high 5
radiation areas. These records shall include the date, time, and results of each 6
such test of function.
7 (2)
The licensee or registrant shall retain the records required by 8
Subsection R313-15-1110 (1) for three years after the record is made.
9 10 R313-15-1111.
Form of Records.
11 Each record required by Rule R313-15 shall be legible throughout the
'i2 specified retention period. The record shall be the original or a reproduced copy 13 or a mieraform, provided that the copy or microform is authenticated by 11 authorized personnel and that the microform is capable of producing a clear copy 15 throughout the required retention period or the record may also be stored in 16 electronic media with the capability for producing legible, accurate, and 17 complete records during the required retention period. Records, such as letters, 18 drawings, and specifications, shall inr:lude all pertinent information, such as 19
- stamps, initials, and signatures.
The licensee shall maintain adequate 20 safeguards against tampering with and loss of records.
C#yd 21
" f'
( t'M 22 R313-15-1201. Reports of Stolen, Lost, or Missing Licensed or Registered Sources 23 of Radiation.
r 24 (1)
Telephone Reports.
Each licensee or registrant shall report to the 25 Executive Secretary by telephone each stolen.
lost.
or missina source of
,}q p&
f 26 Igdiation immediatelv after its absence becomen swn to the licensee or t h r 0 f*r-y l )
27 registrant. This recuirement does not anply to sources of radiation that are not 28 recuired to be licensed or recistered.( : f ellc;;;. ]
N i
60 y
e e
1
[i:):. adi::cly : tu it 2xurren : Ex ;;;; kas n :: the licen::: cr 2
r egistr:.nt, ;;;1:n, 1;;t, or mi::ing-lic n :0 : r;;ict:r:d radica:tiv
- teri:1 3
in n
ggr: gat: s ntity :T :1
- cr grc:::
than 1,0:0 tim;; th; q::ntity 4
7... n...a.
.77....o_..,-
,.., a.
.s
,m.m..
e m...,
- m.,,
.mm.
,,,2..
. 1. 2. _. t..
v.
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~
5 in==rp;r;ted by r:f :=n :, und:r ::;b L::==::=n :: th=t it ;&&;;r
- th:
6
-41:n.:::.cr
- gi:: ant th t :n
- r;;;;; ;;;ld I;;;10 t; individ;;10 in 7
unr :tricted :::::,
8 th; i:itri 30 day after it: ::curr:n:: b;s c
'ncur. to th; licen;;; cr 9
regi;;r
.t, 12:t, :::le., :: mi :ing lic;. :.d :: ::;ist ::.d ::.di;;;tiv; :t ri:1 10 ir :-
ggr: gat: 7:=tity 5::.a t e r than ta time; th: q::ntity sp :ified in 11
____m..._
77-...
s.
,,m.
,m.
m.m.,
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.2
. 1..1 _ u.
2_________
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u.y
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~~
.r...
12 ref r:n:, th: i: still mi::ing, 13
- = dict:17 after its c ; urn.:: h:::::: 'n=n t: th:
- sistrant, a l
l r
l 14 at:1:n, 1;,t,
- mining ::. diction :::hinc.)
1 15 (2) written Reports.
Each licensee or registrant required to make a 16 report pursuant to Subsection R313-15-1201(1) shall, within 30 days after making 17 the telephone report, make a written report to the Executive Secretary se.t.ing 18 forth the following information 19 (a)
A description of the licensed or. registered source of radiation 20 involved, including, for radioactive material, the kind, quantity, and chemical 21 and physical form; and, for radiation machines, the manufacturer, model and 22 serial number, type and maximum energy of radiation emitted; 23 (b)
A description of the circumstances under which the loss or thef t 24 occurred; and 25 (c) A statement of disposition, or probable disposition, of the licensed 4
26 or registered source of radiation involved; and 27 (d)
Exposures of individuals to radiation, circumstances under which the 28 exposures occurred, and the possible total effective dose equivalent to persons l
61
e 1
in unrestricted areas; and 2
(e) Actions that have been taken, or will be taken, tn recover the source 3
of radiation; and 4
(f)
Procedures or measures that have been, or will be, adopted to ensure 5
against a recurrence of the loss or theft of licensed or registered sources'of i
6-radiation.
7 (3) subsequent to filing the written report, the licensee or registrant 8
_shall also report additional substantive information on the loss or theft within 9
30 days after the licensee or registrant learns of suen information.
10 (4)
The licensee or registrant shall prepare any report filed with the 11 Executive Secretary pursuant to Section R313-15-1201 so that names of in9.Aviduals 12 who may have received exposure to radiation are stated in a separate and 13 detachable portion of the report.
14 15 R313-15-1202.
Notification of Incidents.
16 (1)
Immediate Notification.
Notwithstanding other requirements for 17 notification, each licensee or registrant shall immediately report each event 18 involving a source of radiation possessed by the licensee or registrant that may 19 bave caused or threatens to cause any of the following conditions:
20 (a)
An individual to receives 21 (i)
A total effective dose equivalent of 0.25 Sv (25 rem) or more; or 22 (ii)
An eye dose equivalent of 0.75 Sv (75 rem) or more; or 23 (iii)
A shallow dose equivalent to the skin or extremities or a total 24 organ dose equivalent of 2.5 Gy (250 rad) or more; or 25 (b) The release of radioactive material, inside or outside of a restricted 26 area, so that, had an individual been p esent for 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the individual could 27 have received an intake five times the occupational ALI.
This provision does not 28 apply to locations where personnel are not normally stationed during routine 62 F
Y g
l' oper9tions,-such as hot-cells or process enclosures.
2 (2)
Twenty-Four Hour Notification.
Each licensee or registrant shall, 3
'within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of al.covery of the event, report to the Executive Secretary each 4
event / involving loss of control of a licensed or registered source of radiaEion i
5; possessed by'the licensee or registrant that may have caused, or threatens to G.
cause,:any of the following conditions:
17
- (a)
An individual to receive, in a period'of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s:
8
-(i). ' A total effective dose equivalent exceeding 0,05 Sv (five rem); or
-9 (ii)
An eye dose equivalent exceeding 0.15 Sv (15 rem); or
- 10 (iii)
A. shallow dose equivalent to the skin or extcomities or a. total
.11 d
organ 1 oes equivalent exceeding- 0.5 Sv (50 rem); or
'12
.(b)
The release of radioaccive material, inside or outside of a restricted L
113-;
area, so that, had an individual'been present for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, the individual could 14:
have received an intake in excess.of one occupational ALI.
This provision-does 15 not apply to locations where' personnel are not normally stationed during routity 16 operations, such as hot-cells or process enclosures.
17:
-(3)
The licensee or registrant shall prepare each report filed with the j
18L Executive Secretary pursuant to Section R313-15-1202 so that names of individuals 19 who-have received exposure to. sources of radiation are stated in a separate and
~20 detachable portion of the report.
1 721 (4)
Licensees. or registrants shall make the reports required by 22
- Subsections R313-15-1202 (1) and R313-15-1202 (2) to the Executive Secretary by
- 23-telephone, telegram, mailgram, or facsimile to the Executive Secretary.
24-(5)
The provisions of Section R313-15-1202 do not apply to doses that 25 result from planned special exposures, provided such doses are within the limits
- 26 for planned special saposures and are reported pursuant to Section R313-15-1204.
27 28
-R313-15-1203.- Reports of Exposures, Radiation Levels, and Concentrations of 63 i
e 1
F,adioactive Material Exceeding the ea==traints or Limits.
- 2, (1)
Reportable Events.
In addition = to the notification required by
-3 Section R313-15-1202, each licensee or registrant shall submit a written report 4
within 30 days af ter learning of any of the following occurrences:
5 (a)
Incidents for which notification is required by Section R313-15-1202;
-6 or 7
(b)
Doses in excess of any of the'following:
_ i)' The occupational dose limits for adults in Section R313-15-201; or 8
(
9 (ii) The
.upational dose limits for a minor in Section R313-15-207; or 10 (iii)
The limits for an embryo / fetus of a declared pregnant woman.in 11 Section R313-15-208; or 12 (iv) The limits for an individual member of the public in Section R313 13 301; or 14 (v)
Any applicable limit in the license or registration; or i15 (vi) The ALARA ennstraints for,gir am4 malann estab11mhed imder Subsection 16 R313-15-101f4)? or 17-(c)
Levels of radiation or concentrations of radioactive material in:
18 (1)
A restricted area'in excess of applicable limits in the' license or 19 regietration; or 20 (ii) An unrestricted area in excess of ten times the applicable limit set 21 forth in Rule R313-15 or in the license or registration, whether or not involving 22 Eexposure of any individual in excess of the limits in Section R313-15-301; or 23 (d)
For licensees subject to the provisions of U.S.
Environmental 24 Protection Agency's generally applicable environmental radiation standards in 40 e
25 CFR 190, levels of radiation or releases of radioactive material in excess of 26 those standards, or of license conditions related to those standards.
27 (2)
Contents of Reports.
tr 28 (a) Each report required by Subsection R313-15-1203 (1) shall describe the 64
0 o
1:
extent of -. exposure of individuals to radiation and radioactive material,
- 2
' including, as appropriate:
3-(1)
Estimates of each individual's dose; and 4
(ii)
The levels of rs.diation and concentrations of radioactive material 5
involved; and 6
'(iii) The cause of the elevated expcaures, dose rates, or concentrations; 7
and 8
(iv)
Corrective steps taken or planned to ensure against a recurrence, 9
including the schedule for achieving conformance with applicable limits, ALARA 10 enn=traints. generally applicable environmental standards, and associated license 11 or registration conditiono.
12 (b) Each report filed pursuant to Subsection R313-15-1203 (1) shall include 13 for each occunatinn=11y overavnomed individual ( exp;;;d): the name, Social 14 Security account number, and date of birth. With respect to the limit for the 15-embryo / fetus in Section R313-15-208, che idnintifiers should be those of the 16 declared pregnant woman. The report shall be prepared so that this information 17 is stated in a separate and detachable portion of the report.
18 (3) All licensees or registrants who make reports pursuant to Subsection 19 R313-15-1203(1) shall submit the report in writing to the Executive Secretary.
~ 20-21 R313-15-1204.
Reports of Planned Special Exposures.
22 The licensee or registrant shall submit a written report to the Executive 23 Secretary within 30 days following any planned special exposure conducted in
'24 accordance with section R313-15-206, informing the Executive Secretary that a 25 planned special exposure was conducted and indicating the date the planned 26 special exposure occurred and the information required by Section R313-15-1106.
27 28 R313-15-1205.
Renorts to Individu=1m of Rxceedine Dome L4mits.
65
1 9
~
o I
1 When a licennee or recistrant is reaufred. nursuant to the nrovisions of 2
-Sectinnn R313-15-1203 or R313-15-1204. to renort to the Executive Secretary any
'3 ernomure of an identified occunationally ernosed individual. or an identified 4
mamher of the oublic, to sources of radiation, the licennee or racistrant shall 5
also nrovide a cony of the renort submitted to the Executive Secretarv to the 6
individital.
This renort shall be trannmitted at a time no later than the 7
-trannmittal to the Executive Secretary.
8 9
R313-15-1207.
Notifications and Reports to Individuals.
10 (1) Requirements for notification and reports to individuals of exposure 11 to radiation or radioactive material are specified in Rule R313-18.
12 (2) When a licensee or registrant is required pursuant to Section R313 13 1203 to report to the Executive Secretary any exposure of an individual to 14 radiation or radioactive material, the licensee or registrant shall also notify 15 the individual.
Such notice shall be transmitted at a time noc later than the 16 transmittal to the Executive Secretary, and shall comply with the provisions of 17 Rule R313-18.
18 19
.R313-15-1208.
Reports of Leaking or Contaminated Sealed Sources.
--20 If the test for leakage or contamination required pursuant to Section R313-21 401 indicates a sealed source is leaking or contaminated, a report of the test 22 shall be filed within five days with the Executive Secretary describing the 23 equipment involved, the test results and the corrective action taken.
24 25 R313-15-1301. Vacating Premises.
26 Each specific licensee or registrant shall, no less than 30 days before 27 vacating or relinquishing possession or control of premises which may have been 28 contaminated with radioactive material as a result of his activities, notify the 66 a
h m
9 x,-
1 --
Executive secretary in writing of intent to vacate. When deemed necessary by the -
-2 Executive secretary, the -licensee shall' decontaminate the - premises in such a 3
manner as the Executive Secretary may specify.
4
-5 KEY:
radioactive material, contamination,-waste' disposal, safety 6
(&M4}1SSR 19-3-104 7 3-los 8'
9 10 i
i I
i 67
..