ML19259B480

Ack 781206 Inquiry Re Incineration of Radioactive Waste at Univ of Iowa.Waste Consists of Paper & Liquid Counting Samples Containing Low Amounts of Radioactivity. Concentration Well Below NRC Stds.Copy of 10CFR20 Encl

ML19259B480
Person / Time
Issue date:	01/09/1979
From:	Hendrie J NRC COMMISSION (OCM)
To:	Leach J HOUSE OF REP.
References
NUDOCS 7902260024
Download: ML19259B480 (2)

Text

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UNITED STATES NUCLEAR REGULATORY COMMISSION y.

~

j ('g( : 2 WASHINGTON, D. C. 20555 COyh h

January 9,1979 CORR CH AIRMAN The Honorable James Leach United States House of Representatives Washington, D.

C.

-20515

Dear Congressman Leach:

We are pleased to respond to your inquiry of December 6, 1978 requesting information about incineration of radio-active waste at the University of Iowa, Iowa City, Iowa.

The University of Iowa was authorized to incinerate radio-active waste on May 10, 1977.

Mr. Neal G.

Berlin, City Manager, Iowa City, Iowa, is correct in his belief that radioactive material is dispersed during incineration of radioactive was..

However, maximum air concentration limits for radioactive materials in unre-stricted areas have been established by the Nuclear Regulatory Commission (NRC) at levels that assure the public health and safety.

These air concentration limits are stated in Appendix E,

Table II, Col. 1 of Title 10, Part 20, Code of Federal Regulations, and fom the basis for tur evaluation (under 10 CFR 820.106 (a) ) of a request to incinerate radioactive waste.

To determine compliance with NRC regulations, the staff requires the applicant to submit specific infomation, including the quantity of each radioisotope to be disposed of per da'y, characte"istics of the incinerator such as height of the stack and rated air. flow, distance to build-ings in the surrounding areas and their height.

The applicant is also required to demonstrate that the concentration in the air of radioactive materials in the effluent at the point where it leaves the incinerator stack confoms to NRC regulations.

Only after careful review of this information is approval.for disposal of radioactive waste by incineration granted.

All of the infomation that the staff required from the University of Iowa and the staff's attendant analyses of that information can be made available for Mr. Berlin's review if he should request it.

20/2 283 T% 22_co. cm M

Honorable James Leach The concentration of radioactive material in air as it leaves the stack of the University of Iowa incinerator will be only a fraction of that permitted by NRC regulations.

As an added safety factor, the University will refrain from incinerating radioactive waste when the wind is blowing towards the closest occupied areas.

The University will also periodically measure the radioactivity coming from the stack to confirm compliance with the regulati'-r.

We note that the newspaper article enclosed with Mr. Berlin's letter indicated that the University of Iowa may incinerate up to 17 tons a year of radioactive waste.

The waste to be incinerated consists of paper and liquid counting samples containing quite low amounts of radioactivity.

Therefore, even though the total volume of waste material may be considered large, the amount of radioactivity is small.

We appreciate your interest in these matters and would be glad to discuss them further with you cr your staff.

Sincerely,

(

s 3

h M.

Hendrie

Enclosure:

10 CFR Part 20 20/2 285L

UNITED STATES NUCLEAR REGULATORY COMMISSION RULES and REGULATIONS TITLE 10 CHAPTER 1, CODE OF FEDERAL REGULATIONS-ENERGY PART STANDARDS FOR PROTECTION AGAINST RADIATION 20 EXCEPTIONS AND ADDITION AL REQUIRF-GENERAL PROvid10NS ments set forth in this part, make every 20.501 Applications for exemptions.

rea.sonable effort to maintain radiation 20.5o2 Additional requirements.

exposures, and relesses of radioactive 20.2 Sco pe.

ENFORCEMENT materials in ei5uents to untestricted 20.3 Definitions.

O areas, as low as is reasonably achievable.

20.4 Units of radiation dose.

20.601 Wolations~

m The term "as low as is reasonably 20.5 Units of radioactivity.

$ achievable" means as low as is reason-oImu x b oncenYr t ons in air and water g ably achievable taking into account the o

6.

n state of technology, and the economics of above natural background.

gImprovements in relation to benefits to PERMISSIBLE DOSES, LEVELS, AND Appendit C.

CONCENTRATIONS Appendix D-United States Nuclear Reguta-the public health and safety, and other 2 0.101 Exposure of individuals to radia-r$ce etIe On o

o onomk consMera-ces tion in restncted areas.

tions, and in relation to the utilization

,T U

RiT

• P h s Part 2 20.102 De rmination of accumulated of atomic energy in the public interest.

d 53 3 8 03 9m, 68 Stat. 930,933,9 3 5,936,937,948, as 20.103 En s eo individuals to s'aIin amended: 42 U.iC. 2073,2093, 2095,2111, 9 20.2 Scope.

ma

$33J3j.229ga[a nded$2 l

restncted areas.

The regulations in this part apply to 3

g S C.-

,e 20.104 Exposure of minors.

20.105 Permissible levels of radiation in 2 273. Q 9 20.401-20.409, issued under sec.

R all persons who receive, possess, use, or 161 o.,68 Stat. 9 50, as amended : 42 U.S.C.

W transfer material licensed pursuant to 20.106 R oscti ty in eff uents to unre-9,,l.

4 6(42 S 8

0 8.88 5 the regulations in Parts 30 through 35, stricted areas.

o CD, or 70 of this 2hapter, including per-20.107 Medicat diagnosis and therapy.

g 20.1 Purpose.

sons licensed to operate a production or 2 0.10 s Orders requiring furniihing of bio.

(a) The regulations in this part estab.

utilization facility pursuant to Part 50 E lish standards for protection against ra.

of this chapter.

PRECAUTION ARY PROCEDURES

$ diation hazards arising out of activities

~

c under licenses issued by the Nuclear Reg.

6 20.3 Ih finitions.

!!202 eis'onTel rnonitoring.

$ ulatory Commission and are issued pur.

(a) As used in this part:

20.203 Caution sisns, labets, signals, and suant to the Atomic Energy Act of 1954, (1) "Act" means the Atomic Energy controts.

20.204 Sa me - exceptions.

as amended, and the Energy Reorganiza-Act of 1954 (68 Stat. 919) including any amendments thereto:

20.205 Procedures for picking up, receiv-tion Act of 1974.

ing, and openmg packages.

(2) " Airborne radioactive material" 20 206 Instruction of personnel, means any radioactive material dispersed (b) The m of radioactin material or 20 207 Storage and control of licensed materists in unrestricted areas.

other sources of radiation not licensed in the air in the form of dusts, fumes, WAST: DISPOSAL by the Commission is not subject to the mists, vapors, or gases; (3) " Byproduct material" means an; eg I t ai this pad Howenr, it is 20.302 Method for obtairiing approval of the purpose of the regulations in this radioactive, material (except special nu-20.301 General requirement clear material) rielded in or made ra-proposed disposal procedures.

5 part to control the possession, use, and dioactive by exposure to the radiation 20.303 Disposal by release into sanitary

$ trahsier of licensed material by any 11-incident to the process of producing or sewerage systems.

censee in such a manner that exposure u to such material and to radiation from utilizing special nuclear material-g 20.304 Disposal by burial in soil.

20.305 Tres ent or disposal by incinera-ggg to unlicensed radioactive material and than 12 consecutive weeks nor more than RECORDS, REPORTS, AND NOTIFICATION to other unlicensed sources of radiation 14 consecutive weeks. The first calendar in the possession of the licensee, and to s quarter of each year shall begin un Janu-

• Iro'rInf, s'nNs*/c's'aY. I " "

radiation therefrom, does not exceed the i ary and subsequent calendar quarters

"~

20.402 Reports of thef t or loss of bcensed standards of radiation protection pre-Q shall be such that no day is included in matenal.

scribed in the regulations in this part. e more than one calendar quarter or 20.403 14otirications of incidents.

' omitted from inclusion within a calendar (Reserved) oy,MsI*c"on'ce'nSratiIns., tions of the Federal Radiation Council,In accordance with re 20.404 (c) 20.405 e

so y lev

,n method observed by him of determining 20.406 l Reserved I w approved by the President, persons e -

calendar quarters except at the beginning h gaged in activities under licenses issued of a calendar year.

20.407 Personnel monitoring reports.

by th Nuclear Regulatory Commission 20.408 Reports of rerronnel monitoring on termination of emrinyment or work.E pursuant to the Atomic Energy Act of (5) o C.ommission, means the Nudear Regu-g 1954, as amended, and the Energy Re-20.409 Notifications and reports to indi.

t organization Act of 1974 should, in ad-Iatorf rnm n or its duly authonied vid uals.

l dition to complying with the require-

? 0 / /-

-) 8 5 g-A g

g'3~

h 201 A

November 10,1978 o

o.

a l

PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION ulations in this part, any of the follow *

(6) " Government agency" means any w eight one-twentieth of one percent h mMW M k M'hM M a executive department, commission, inde-

• ' " " I * "I" pendent establishment, corporation *

• g' dose of one rem:

wholly or partly owned by the United'i'g!*$ce m terIa1 does not in Ode $$ai (1) A dose of I r due to X-or gamma ou t

radiation-States of America which is an instru r-nuclear material.

(2) A dose of 1 rad due to X, gamma mentality of the United States, or anyn -

board, bureau, division, service, of5ce,'

or beta radiation; (16) "Special nuclear material" means (3) A dose of 0.1 rad due to neutrons of5cer, authority, administration, or other estabhshment in the executive (1) plutonium, uranium 233, uranium or high energy protons; branch of the Government;

, enriched in the isotope 233 or in the iso-(4) A dose of 0.05 rad due to particles (7) " Individual" means any humangtope 235, and any other material which heavier than protons and with su!5cient

-the Commission, pursuant to the.provi-energy to reach the lens of the eye;,

being:

" Licensed material" means source $ sions of section 51 of the act, determines If it is more consentent to measure the (8) material, special nuclear material, or by.,to be special nuclear material, but does neutron flux, or equivalent, than to de-g product material received. possessed.mnot include source material; or (11) anY termine the neutron dose in rads, as material artificially enriched by any of provided in subparagraph (3) of this

- used, or transferred under a general or the foregoing but does not include source paragraph, one tem of neutron radiation

[ specific license issued by the Commission may, for purposes of the regulations in this. material; this part, be assumed to be equivalent pursuant to the regulations in N chapter-g (17) " Unrestricted area" means any to 14 million neutrons per square centi-(3) "bicense" means a W ise issued area access to which is not controlled by meter incident upon the body; or, if under the regulations in r-30 40,or-the licensee for purposes of protection of there exists suf5clent information to esti.

the holder of such IIcense.ct' ae" means$ individuals from exposure to radiation mate with reasonable accuracy the ap-70 of this chapter "Li

~

" Occupational dose" includes ex

• and radioactive materials, and any area proximate distribution in energy of the neutrons, the incident number of neu-(10) posure of an individual to radiation (1)[used for residential quarters.

y trons per square cenWneter equMaled of employment in which the individual'sE" (18) " Administration means the En g to one rem may be estimated from the in a restricted area; or (1D in the course involve exposure to radiation;E ergy Research and Development Admin.; following table:

duties Narraos ytt: Doss zerrvdants provided, that " occupational dose" shallt istration or its duly authorized repre-m not be deemed to include any exposure", sentatives, g

Number of Average,

of an individual to radiation for the pur.*

pose of medical diagnosis or medicalD Eu*are *d deNer$co (b) Definitions of certain other words Neutron encru (Mev) umeter mmirem ti therapy of such individual.

and phrases as used in this part are set YmTP e[n7per seea equnntent a boars forth in other sections, including-

~~ (11) " Person" means (D any indi.

(1) " Airborne radioactivity area" de-tronna.

vidual, corporation, partnership, firm, fined in i 20.203; association, trust, estate, public or pri.

(2) " Radiation area" and "high radi-

'rbermal

rox, co ation area" definedin i 20.202;

$1-E vate institution, group. Government agency other than the Commission or the (3) "Personne1 monitoring equipment, e.as..

wxis sso Administration (except that the Admin.

definedin f 20.202; g--

' Ig g

istration shall be considered a person (4) " Survey" t'efined in I e.01; si m io is within the meaning of the reculations in (5) Units of measurement of vee (rad, g.

g g

E this part to the extent that its facilities rem) definedin i 20.4; rf axim 1r e and activities are subject to the licensing (6) Units of measurement of ndio-g gij ly and related regulatory authority of the E Commission pursuant to section 202 of activity defined in i 20.5, the Energy Reorganization Act of 1974 9 20.4 Units of radiation dose.

(d) For determining exposures to X or (88 Stat.1244)), any State, any foreign g,),,

,, as used in this part is the gamma rays up to 3 Mev, the dose limits government or nation or any political quantity of radiation absorbed, per unit specified in 1120.101 to 20.104, inclusive, subdivision of any such government or g

may be assumed to be equivalent to the nation, or other entity; and (1D any bod'y en e us in th.s

" air dose'. For me purpose of mis part legal successor, r oresentative, agent, or part specify a dose during a period of

" air dose

• means that the dose is meas-a agency of the fc.:,70ing.

Y time, the dose means the total quantity

"#O "NOP'd7 C" "N

b "Radiatic>n" means any or all of of radiation absorbed, per unit of mass.

instrument in air at or near the body sur-U (12) face in me ugkn of pst @ sap rak the following: alpha rass, beta rays,E dur ng su p ri of time. Severa gamma rays, X-rays, neutrons, high g different units of dose are in current use.

0.5 Units of radioactivity.

g2

@ speed electrons, high-speed protons, and Definitions of units as used in this part (a) Radioactivity is commonly, and other atomic particles; but not sound are set forth in paragraphs (b) and (c) for purposes of the regulations in this g

or radio waves, or visible, infrared, or of is section.

part shall be, measured in terms of dis-u.

" ultraviolet Ifght, (b) The rad, as used in th!s part, is a 2 integrations per uni, time or in curies.

e (13) " Radioactive material" includes measure of the dose of any innWg radi-S One curie =3.7x10" disbtegrations per any such material whether or not subjecs ation to body tissues in terms of the N second (dps) =2.2x10" disintegrations to licensing control by the Commission; energy absorbed per unit inass of the E per rainute (dpm). Commonly used sub-O tissus. One rad is the dose correspond N multiples of the curie are the tn1111 curie (14) " Restricted area" means any and the microcurie:

area access to which is controlled by the ing to the absorption of 100 ergs per gram lice 'see for purphs of protection of of tissue. <One mmirad (mrad)=0.001 (1) One millicurie (mCD '=0.001 curie a

(CD 8=3.7x10' dps.

k indhiduals from exposure to radiation re d.)

- and radioactive materials. " Restricted (c) ' Die rem, as used in this part, is (2) One microcurie (uCD %0.000001

[ srea" shall not include any areas used a measure of the dose of any iontenr curie =3.7x10* dps.

as residential quarters, although a sepa-radiation to body tissue in terms of its eN rate room or rooms in a residential estimated biological effect relative to a building may be set apart as a restricted dose of one roentgen (r) of X-rays. (One

_ area; mmirem (mrem) =0.001 rem.) The rela-tion of the rem to other dose units de-cur $ea), Nits

=

pends upon the biological effect under sho I wrt ou ur n m t on r ny bm -

co? sideration and 1.pon the Conditions of curte(s)," or *microcurte(s)." and the abbre-tion thereof in any [hysical or chemical irradiation. For the purpose of the reg-vistions should not be used.

dit ores which contain by form; or

[}

}hh September 1,197 e

p 20-2 W

a

PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION column a column 2 section provided:

(b) IDeleted 40 FR 50704.]

(1) During any calendar quarter the assumed A ssume<t dose to the whole body from radioactive

• gigurg engr (c) [ Deleted 39 FR 23990.}

material and other sources of radiation 8, cakner en< tar in the licensee's possession shall not ex "

quarters marters ceed 3 rems; and i

gn'Y t$i "aNr'"

(2) The dose to the whole body, when uni,imi added to the accumulated occupational g dose to the whole body, shall not exceed whole tuE, d errninaenads, 3%

iu t

5 (N-18) rems where "N" equals the in-acuve dividual's age in years at his last birth +

E*"oI,7,f '"d """'

day: and The licensee has cetermined theg (2)

(3) accumulated occupational,

The licensee shall retain and pre-individual's dose to thc whole body on Form NRC-4, or - serve records used in preparing Form on a clear and legible record contain-g NRC-4 until the Commission authorizes ing all the information required in that, their oisposition.

form; and has otherwise complied with

• the requirements of I 20.102. As used in fIf calculation of the individual's ac-paragraph (b)," Dose to the whole bod? '

• cumulated occupational dose for all shall be (eemed to include any dose to g periods prior to January 1,1961 yields 6 20.6 Interpretations.

the whole body, gonads, active blood- - a result higher than the applicable ac-Except as specifically authorized by forming organs, head and trunk, or lens { cumulated dose value for the individual as of that date, as specified in paragraph Of 'Y'-

m g the Commission in writing, no interpreta-N (b) o Learo f I 20.101, the excess may be disre

- tion of the meaning of the regulations in 6 20.102 Determination of accumulated d.

cc this part by any officer or employee of do c,

' the Commission other than a written in-(a) This section contains require '0 i

@Po*um of n,ndividuals to ron.

R terpretation by the General Counsel will ments which must be satisfied by be recognized to be binding upon the licensees who propose, pursuant to para-

'[""[,"$[;

,'[* * * "' ' '"* I

• Commission.

graph (b) of I 20.101, to permit individ-(a)(1) No licensee shall possess, use, 2

uals in a restricted area to receive ex.

or transfer licensed material in such a 9 20,7 Communications.

posure to radiation in excess of the Itfnits Except where otherwise specified in, specified in paragraph (a) of I 20.101.

manner as to permit any individual in a this part, all communications and re -

(b) Before permitting aray individual restricted area to inhale a quantity of

, ports concerning the regulations in this in a restricted area to receive exposure radioactive material in any period of R part should be addressed to the Execu CC to radiation in excess of the limits spec-one calendar quarter greater than the

• tive Director for Operations, U.S. Nu ' ified in paragraph (a) of 6 20.101 each quantity which 5 )uld result from inha-

$ clear Regulatory Commission, Washing N licensee shall:

g lation for 401" as per week for 13 weeks c3 ton, D.C. 20555. Communications, re.

(!) Obtain a certificate on Form NRC-4, or ce at uniform concentrations of radioactive on a clear and legible remrd

• material in air speci containing all the information required u. T ble I, Column 1.,f, led in App ports, and applications may be delivered If the radioactive in person at the Commission's' offices at in that form, signed by the individual, material is of such form that intake by 1717 H Street NW., Washington, D.C.; or showing each period of time after the

• absorption through the skin is likely, in-at 7920 Norfolk Avenue, Bethesda, Mary-individual attained the age of 18 in which tvidual exposures to radioactive mate-land' the individual received an occupational rial shall be controlled so that the up-

' ~ Psamasists Doesa. tama. ano dose of radiation; and take of radioactive material by any or-

~~

C"C'"*""*

(2) Calculate on Form NRC-4 in accord-gan from either inhalation or absorption 6 20,101 Exposure of individuals to rs.

ance with the instructions appear.

or both routes of intake" in any calen-ing therein. or on a clear and legible dar quarter does not exceed that which distion in twtricted areas, i

record containing all the information w uld result from inhaling such radio-(a) Except as provided in paragraph required in that form, the previously ac-(b) of this section, no licensee shall cumulated occupational dose received by

, Since the concentration spec 1 Sed "or trit-possess, use, or transfer !! censed mate-the individual and the additional dose sum oxide vapor assumes equal int.tes by rial in such a manner as to cause any allowed for that individual under skin absorption and inhalation, the total individual in a restricted area to receive in any period of one calendar quarter i 20.101(b).

Intake permitted ts twice that which would (c)(1) in the preparation of Form NRC-4, result from Inhalation alone at the concen-5 from radioactive material and other or a clear and legible record con-tration spec 1 Sed for H 3 S in Appendix B g

Table Column 1 for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week for ssion a dose i excess f he i d taining all the information required in te g sperified in the following table:

"II ]g7o t tain r p rts of

P W m 322,the u= mar wantity is g;,

ha aa in & perbd el ene talendar tw Rems per calendar quarter individual's previously accumulated oc-

1. Whole body; head and trunk; acttre cupational dose. For each period for hf th blood-forming organs; lens of which the licensee obtains such reports, 9 **

• hM eyes; or gonads............._ _ _. 1%

the licensee shall use the dose shown in upon exposure to the material as an exter-

2. IIan and forearms; feet and the report in preparing the forri In nal radiat2n scune. inn w to o

s. skin of N S Ey--------- ~----- 7/:

any case Wm a he b gW % hse man may be amounted for as obtain reports of the individuals occu g part of the Ifmftation on individual dose in (b) A licensee may permit an indi-pational dose for a previous complett e 120.101. 'Ihese nucildes shall be subject to vidual in a restricted area to receive a Calendar quarter, it shall be assumed 6 the precantbnary prmdures eequired by dose to the whole body greater than that that the individual has received the oc r $20.103(bxD.

M

'd in appendia B, table L columna 1, try Multipty the concentration vahws spect-permitted under paragraph (a) of this cupational dose specified in whicheve De of the, following columns apply:

ao a

8.3x10' mi to obtain the quarterty quantity 5'=ft """'r'r th' omeentrati== veau

===o-D D

ifled in appendix B, table L column 1, by 2.5 x10' m1 to obtain

• manual quantity a

cw w

20/2

-)87

" " ~ ' "

' Amended 36 i R 1466.

Footnotes 4 and 5 on psge 20 4 20-3 September 1,1978

PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION active material for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week for limit concentrations of radioactive ma-1 20.101 lu po ure of mim rv 13 weeks at uniform concentrations spec-terial in air below those defined in ia i No licensee shall possess, use or ifled in Appendix B, Table I, Column 1.

I 20.203(d) (1) (ii), othe precautionary transfer licensed material in such a (2) No licensee shall possess, use, or procedures, such as inc reased surveil-manner as to cause any individual within transfer mixtures of U-234, U-235, and lance, limitation of wuwng times, or a restricted area who is under 18 years U-238 in roh.ble form in such a manner provision of respiratory protective equip-of age, to receive in any period of one as to pern it any individual in a restricted ment, shall be used to maintain intake calendar quarter irom radioactive ma-of radic ctive material by any individ-area to ir aale a quantity of such material ual withh. sny period of seven consec,ter!al and other sources of radiation in in excess of the intake limits specifled in the licensee's pcssession a dose in excess Appendix B, Table I, Column 1 of this utive days a far below that intake of hof 10 percerit of the limits specified in part. If such soluble uranium is of a form radioactive material which would result "the table in paragraph (a) of I 20.101.

such that absorption through the skin is from inhalation of such material for 40 K (b) No beensee shall possess, use or hours at the uniform concentrations u.

likely, individual exposures to such ma-t licensed material i su h terial shall be controlled so that the up-specified in Appendix B. Table 1. Col-R ransfer take of such material by any organ from umn I as is reasonably achievable.

within a restricted area, who is ur~ler 18 either inhalation,or absorption or both Whenever the intake of radioactive ma-years of age to be exposed to airborne routes of intake does not exceed that terial by any individual exceeds this 40-radioactive material possessed by the which would result from inhaling such hour control measure, the licensee shall licensee in an average concentration in material at the limits specified in Ap-make such evaluations and take such excess of the hmits spec: fled in Appendix ix B. Table I Column 1 and footnote actions as are necessary to assure IL Table II of this part. For purposes e.

against recurrence. The Ifcensee shall of this paragraph concentrations ma/

(3) For purposes of determining com-maintain records of such occurrences.

be averag.ed over periods not greater pliance with the requirements of this sec-evaluations. and actions taken in a clear than a week.

tion the licensee shad use suitable meas-and readily identifiable form suitable urements of concentrations of radioac-for summary review and evaluation.

alu ti g a rb rne radioactiv t

[ ion da as d on app -

N" d

i i the nh f irbo e radioactive mater 1 k sr ex pt t a te eferene in 1 0

p pursuant to paragraph b) 2) o cc (b) (2) and 20.103(c) to Appendix B.

cv b activity in the bodradioactivity excreted i o t e bod, o section, the licensee may make EUow-u; Table I, Column 1 shall be deemed to be

" #nces to Appendix B, Table II Col-at r als 'hmn 3.

I any combination of such measurements ures of in i al to su as may be necessary for timely detection and assessment of individ lal intakes of kprovided that such equipment is used e

inas stipulated in Regulatory Guide 8.15.

-20.10 ~. Permi ible lescl* of radiation 8

radioactivity by exposed individuals. It g.* Acceptable... Programs for Respiratory in unrenrided aren is assumed that an individual inhalesu.

r ec W n.

(a) There may be included in any ap-radioactive material at the airborne con * (di Notwithstanding the provisions of plication for a license or for amendment centration in which he is present unless paragraphs ibi and (c) of this section, of a license proposed limits upon levels he uses respiratory protective equipment the Commission may impose further of radiation in unrestricted artas result-pursuant to paragraph (c) of this sec-restrictions:

ing from the applicant's possession or tion. When assessment of a particular individual's intake of radioactive ma-il) On the extent to which a heensee use of radioactive material and other terial is necessary, intakes less than those may make allowance for use of respira-sources of radiation. Such applications which would result from inhalation for tors in lieu of provision of process, con-should include mformaticn as to antici-2 hours in any one day or for 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> tainment, ventilation, or other engineer-pated average radiation levels and an-in any one week at uniform concentra-ing controls, if application of such con-ticipated occupancy times for each tions specifled in Appendix B. Table I, trols is found to be practicable; and unrestricted area involved. The Com-Column 1 need not be included in such (2) As might be necessary to assure mission will approve the proposed limits assessment. provided that for any assess-that the respiratory protective program if the applicant demonstrates that the ment in excess of these amounts the en-of the licensee is adequate in limiting, proposed limits are not likely to cause exposures of personnel to airborne ra-h any individual to receive a dose to the tire amount is included.

dioactive materials.

whole body in any pt iod of one cakndar (b)(1) The licensee shall, as a precau-tionary procedure, use process or other ie, The licensee shall notify. in writ m year in excess of 0 5 rem.

engineering controls, to the extent prac-ing, the Director of the appropriate Nu u.

(b) Except as authorind by the Com-ticable, to limit concentrations of radio-clear Regulatory Commission Inspection N mission pursuant to pararraph (a) of active materials in air to levels below and Enforcement Regional Of!1ce listed this section. no licensee shall possess, use those which delimit an airborne radio-in Appendix D at least 30 days before the or transfer licensed material in such a activity area as defined in i 20.203(d)(1) date that respiratory protective equip-mmner as to create in any unrestricted (11).

ment is first used under the provisions area from radioactive material and other (2) When it is impracticable ta apply of this section.

sources of radiation in his possession:

process or other engineering controls to (f) A licensee who was authorized to (1) Radiation levels which, if an indi-make allowance for use of respiratory vidual were contmuously present in the protective eautpment prior to Decem-area, could result in his rheelvmg a dose

' Significant intake by ingestion or injec-tion is presumed to occur only as a result of ber 29. 1976 sh,Il bring his respira-m excess of two millirems in any one circumstances such as accident, inadvertence, tory protective program into conform-hour, or poor procedu e. or stmtlar special condittons.

ance with the requirements of para-(2i Radiation levels which. If an indi-graph fc) of this section within one vidual were continuously present in the Such intakes must be evaluated and ac-area could result in h:s receiving a dose counted fer by techniques and procedures as may be appropriate to the circumstances of year of that date. and is exerr.pt from the occurrence. Exposures so evaluated shall the requirement of paragraph (e) of C nsecutive days be included tn determtntng whether the this section.

timitation on indtvtdual exposures in 120 -

h 20.106 Hadioactisity in effluents to 10Ha)(ll has been exceeded.

• This incornoratton by reference provi N unrestricted areas.

• Regulatory guidance on asessment of Individual intakes of radioactive material is slon was anproved by the Director of the Fed-I alven in Regulatory Guide 8 9. " Acceptable eral Register on October 19. 1976. Single

(at A licensee shall not possess, use, copies of Regulatory Guide 815 are available [ or transfer licensed material 50 as to re-Conce"ta. Models. Eountions and Assump-t!cns for a Bloan=av Prorram ' n'ngle copies from the Office of Standards Develoamen',

lease to an unrestricted area radioactive material in Concentrations which exceed Sad ds DeveloD P

.US uc ear M

s' u

i nr e

latory Commission. Washington. D C. 20555.

ry 7

v[D

' T )4fi'

/.0/2

~18 upon written request D"D d

September 1,1978

. b. J%'.n20'4 da

PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION the limits specified in Appendix "B",

reduce the concentration of radionuclides equipment by:

I1i Each mdividual who enters a re-Table II of this part, except as authorized in ecuents prior to their release.

pursuant to l 20.302 or paragraph (b) of (d) For the purposes of this section stricted area under such circumstances that he receives, or is likely to receive, this section. Por purposes of this sec.

the concentration limita in Appendix "B",

a dose in any calendar quarter in excess tion concentrations may be averaged over Table II cf this part shall apply at the f 25 percent of the applicable value a period not greater than one year.

boundary of the restricted ' area. The concentration of radioactive material specified in para;raph Ia) of I 20.101.

(2) Each 1"dividual under 18 years of (b) An a licati f

11 discharged through a stack, pipe or sim-age who enten a restricted area under amendment ay include r 11 ts Ilar conduit.may be determined with such circumstans a that he receives. or higher than those specified in para-respect to the point where the material leaves the conduit. If the conduit dis.

is likely to receive, iose in any calen-graph (a) of this section. The Coenmis-sion will approve the proposed limits charges within the restricted area, the dar quarter in exce-of 5 percent of if the applicant demonstrates; concentration at the boundary may be the applicable value sp cified in para-(1) That the applicant has made a determined by applying appropriate graph ian of 1 20.101.

reasonable effort to minimize the radio-(3i Each individual who s 'ters a high activity contained in ecuents to un-g factors for dilution, dispersion, or decay

, between the point of discharge and the radiation area.

restricted areas; and (b) As used in this part, (2) That it is not likely that radio. ' boundary.

(e) In addition to limiting concen-(1) " Personnel monitoring equipment" active materiaIdischarged in the ef5uent 'e trations in emuent streams, the Com-means devices Cesigned to be worn or would result in the exposure of an indl.

vidual to concentrations of radioactive R mission may limit quantities of radio-carried by an individual for the purpose material in air or water exceeding the active materials released in air or water *!of measur1ng the dose received (e.

g..

during a specified period of time if it g film badges, pocket chambers, pocket limits specified in Appendix "B", Table appears that the daily intake of radio-II of this part.

active material from air, water, or food e dosimeters, film rings, etc.);

(c) An application for higher limits pursuant to paragraph (b) of this sec.

by a suitable sample of an exposed pop-(2) " Radiation area" means any area, N

l accessible to personnel, in which ulation group, averaged over a period tion shall include information demon.

not exceeding one year, would otherwise exists radiation, originating in whole or strating that the applicant has made a exceed the daily intake resulting from in part within licensed material, at such reasonable effort to mMim% the radio.

continuous exposure to air or water con-a major porgon og y

activity dir> charged in emuents to unre.

amantnr one-third the concentration of stricted areas, and shall include, as could receive in any one hour a dose in F*dloactive materials specified in Ap.

pertinent:

pendiz "D", Table II of this part.

excess of 5 millirem, or in any 5 con-(1) Information as to flow rates, total (f) The provisions of this section do secutive days a dose in excess of 100 volume of emuent, peak concentration of not apply to disposal of radioactive ma-millirems; each radionuclide in the ecuent, and con.

terial into sanitary sewerage systems.

(3) "Iligh radiation area" means any centration of each radionuclide in the which is govemed by 5 20.303 area, accessible to personnel, in which emuent averaged over a period of one there exists radiation originating in year at the point where the emuent leaves S 20.107 Medical dingno in and therapy.

g a stack, tube, pipe, or similar condult; (2) A description of the properties of Nothing in the regulations in this part rial at such levels that a major portion

,* the emuents, including:

shall be interpreted as hmiting the in-of the body could receive in any one hour

'e (1) chemical composition; tentional exposure of patients to radia-a dose in excess of 100 millirem.

tid physical characterisucs,1ncluding tion for the purpose of medical diagnosis a

R suspended solida content in liquid emu-or medical therapy.

ents, and nature of gas or aerosol for air 2

$ C 708 Orders requiring furni hing of g cmuents:

bio-anaay nersca.

m 6 20.203 Caution signs, label., signals tiiD the hydrogen ion concentrations a

and controin.

(pH) of liquid emuents; and Where necessary or desirable in order (iv) the size range of particulates in to aid in determining the extent of an M emuents released into air.

individual's exposure to concentrations L (3) A description of the anticipated of radioactive material, the Commission

- ia) General (1) Except as otherwise human occupancy in the unrestricted may incorporate appropriate provisions area where the highest concentration of in any license, directing the licensee to authorized by the Commission, sym-radioactive material from the emuent is make available to the individual appro-bols prescribed by this section shall use expected, and, In the case of a river or priate bio-assay services and to furnish the conventional radiation caution colors stream, a description of water uses down-a copy of the reports of such services to

~(magenta or purple on yellow back-stream from the point of release of the, the Commission.

ground). The symbol prescribed by this s Clion is the conventional three-bleded lb' formation as to the highest con 5 PREcAtmoNARY PROCEDURES 4

centration of each radionuclide in an [" $ 20.201 Surveys.

unrestricted area, including anticipated ta) As used in the regulations in this concentrations averaged over a period of R part " survey" means an evaluation of the radiation hazards incident to the pro-DI air at any point of human oc-duction, use, release, disposal, or pres-eupancy; or ence of radioactive materials or other (1D In water at points of use down-sources of radiation under a specific set stream from the point of releasd of the of conditions. When appropriate, such emuent.

evaluation includes a physical survey of (5) The background concentration of the location of materials and equipment, radionuclides in the recelMng river or and measurements of levels of radiation stream prior to the release of liquid or concentrations of radioactive material emuent.

(6) A description of the environmental present.

(b) Each licensee shall make or cause monitoring equipment, including sensi.

f_ d / (_)

to be made such surveys as may be neces-

hh

)

tivity of the system, and procedures and sary for him to comply with the regula-calculations to determine concentrations tions in this part.

of radionuclides in the unrestricted area gnd possible reconcentrations of radio-

$ 20.202 9ersonnel monitoring, huclides-(a) Each licensee shall supply appro-(7) A description of the waste treat-priate personnel monitoring equipment ment facilitics and procedures used to to, and shall require the use of such D""D "D

~ T]!

September 1,1978 dd c.

j. J 20-5 a

D"D D 'T]

4

~

ocS b.

2 PART 20 e ' TNDARDS FOR PROTECTION AGAINST RADIATION RADIAMON STMBot.

are& established for a period of 30 days trol devices such that upon failure of or less, direct surveillance to prevent un-the entry control devices to function as

1. creas-batched area is to be magenta or purpla.

authorized entry may be substituted for required by paragraph <c) # 6> (in of this

2. Background is to be yellow.

the controls required bT subparagraph section the radiation level within the (2) of this paragraph.

area, from the sealed source, shall be 0

(5) Any licensee, or applicant for a reduced below that at which it would be

[ (20 \\

R license, may apply to the Commission possible for an individual to receive a

~

8 for approval of methods not included in dose in excess of 100 mrem in one hour; a subparagraphs (2) and (4) of this para-and visible and audible alarTn signals w graph for controlhng access to high radi-shall be generated to make an individual s

areas. The Commission will attempting to enter the area aware of go $ ation approve the proposed alternatives if the the hazard and the licensee or at least licensee or applicant demonstrates that one other individual, who is familiar

'g; the alternative methods of control will with the activity and prepared to render s

prevent unauthorized entry into a high am me of M y

, % h

'N radiation area, and that the requirement f,

gg

- s e

subparagraph (3) of this paragraph is

( 111) Be equipped with control devices g

I such that upon failure or removal of u,,

~ (6) Each area in which there may exist physical radiation barriers other than U '$ l 1

the source's shielded storage container 1

radiation levels in excess of 500 rems in the radiation level from the source shall one hour at one meter from a sealed be reduced below that at which it would i

I radio-active source ' th,at is used to tr-be possible for an individual to receive radiate materials shall a dose in excess of 100 mrem in one I

(1) Have each entrance or access point hour; and visible and audible alarm sig-

.+gl A I

equipped with entry control devices nals shall be generated to make pot.n-AF

)

which shall function automatically to tially affected individuals aware of the prevent any individual from inadver-hazard and the licensee or at least one

[

tently entering the area when such ra-other individual, who is familiar with os diation levels exist; pc. tit deliberate the activity and prepared to render or (2) In addition to t.he contents of signs g entry into the area only after a controj and labels prescribed in this section,11.g device is actuated that shall cause the m e vd M h W M W h M m radiation level within the area, from the censees may provide on or near such cr the shield for the stored source is a signs and labels any additional informa-g sealed source, to be reduced below that at 3

Lion which may be appropriate in aiding,r which it would be pos4 Net for an in-gg g

g dividual to receive a dose in excess of individuals to minimize exposure to radt-nal, automatically, loss of adequate 100 mrem in one hour; and prevent op-ation or to radioactive material.

shielding. Physical radiation barriers eration of the source if the source would g

(b) Radiation areas. Each radiation produce radiation levels in the area that area shall be conspicuously posted with could result in a dose to an individual in a sign or signs bearing the radiation cau.

credible probability of failure or removal tion symbol and the words:

excess of 100 mrem in one hour. The en-Ein ordinary circumstances need not meet try control devices required by this para-graph tc)(6i shall be established in such y the requirements of this paragraph CAtTTION '

RAMATION NA a way that no individual will be pre-dv) Be equipped with devices that will (c) High radiation areas. (1) Each vented from leaving the area.

ma a generate visible and a di-high radiation area shall be conspicu-( til Be equipped with additional con-ously posted with a sign or signs bearing the area before the source can be put the radiation caution symbol and the into operation and in sufficient time for words;

' This paragraph (c)(6) does not apply to CAUTION s radioactne sources that are used in tele, any individual in the area to operate a therapy. in radiography, or in completely clearly identified control device which HIGH RADIATION AREA

• 1f-shielded irradiators in which the source shall be installed in the area and which is i th stored and operated within the same can prevent the source from being put

~

(2) Each entrance or access point to shielding radiation barrier and. in the de-into operation.

a high radiation area shall be:

signed configuration of the irradiator. is al-(v) Be controlled by use of such ad-(1) Equipped with a control device ways physteally inaccessible to any individual ministrative procedures

• anC such de-which shall cause the level of radiation and canrot create high levels of radiation in vices as are necessary to assure that the to be reduced bebw that at which an an area that is accessible to any individual.

area is cleared of personnel prior to each individual might receive a dose of 100 This paragraph iclie) also does not apply to millirems in I hour upon entry into the sources from which the radiation is inct.

use of the source preceding which use it dental to some other use nor to nuclear re-might have been possible for an indi-area; or actor generated radiation other than radia-vidual to have entered the area.

(11) Equipped with a control device tt n fr m byproduct. source. or special i vi) Be checked by a physical radia-which shall energize a conspicuous vis-nuclear materials that are used in sealed tion measurement t.o assure that prior to R ible or audible alarm signal in such a sources in non-self-shielded irradiators gle ggrst individuals entry into the area S manner that the individual entering the

These requirements apply af ter Mar.14.

af ter any use of the source, the radia-cc high radiation area and the licensee or 1978. Each person licensed to conduct activi-tion level from the source in the area is S a supervisor of the activity are made ties to which this paragraph (c)(6) applies

$ aware of the entry; or and w ho is not in compliance with the pro-below that at which it would be possible vis ns f this paragraph on Mar. 14. 1978, for an individual to receive a dose in ex-( 111 ) Maintained locked except during shal file with the Director. Office of Nuclear cess of 100 mrem in one hour.

periods when access to the area is re-Matertal Safety and Safeguards. U.S. Nuclear (v11) Ifare entry control devices re-quired, with positive control over each Regulatory Commission. Washington. D C.

quired in paragraph (c)(6)(1) of this individual entry.

20555. on or before June 14.1978. Information section whlen have been tested for (3) The controls required by suopara-describing in detail the actions taken or to proper functioning prior to initial graph (2) of this paragraph shall be be taken to achieve compliance with this operation with such source of radiation established in such a way that no indt-paragraph by Dec. 14.1978.and may continue vidual will be prevented from leaving a activities in conformance with present license on any day th1t operations are not un-c neons and the provisions of the pre-Interruptedly continued from the previ-high radiation area.

vi us!y effective 1 20203 until such comp!!-

ous day or before resuming operations (4) In the case of a high raalation ance is achieved For such persons compit-after any unintended interruption, and ance must be achieved not later than Dec 14 for which records are kept of the dates' or lucr 15a times. and results of such tests of fune-

\\ mended 43 i R 2161

. Amended

'U//.

?

~

~

~90 September 1.1978 20-6

A PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION tion. No operations other than those (e) Additionaltequirements. (1) Each (v11) For manufacturing or procesa necessary to place the source in safe area or roorn in which licensed material equipment, such a.s nuclear reactors, re-condition or to effect repairs on controls is used or stored and which contains any

_ actor components, piping. and tanks.

radioactive material (other than natural - (4) Each licensee shall, prior to dis-shall be conductsd with such source un-uranium or thorium) in an amount ex-l

/

less control devices are functioning ceeding 10 times the quanLity of such ; posal of an empty uncontaminated properly. The licensee shall submit an acceptable schedule for more complete material specilled in Appendix C of this g container to unrestricted areas, periodic tests of the entry control and part shall be conspicuously posted with N remove or ceface the radioactive mate-warning systems to be established and a sign or signs bearing the radiation i rial label or otherwise clearly indicate adhered to as a condition of the license.

caution symbol and the words:

m that the container no longe. contains oaMNe maw 8.

(v111) Have those entry and exit portals CAUTION,

that are used in transporting materials RADIOACTIVE MATERIAL (8) to and from the irradiation area, and that are not intended for use by individ-(2) Each area or room in which nat-uals, controlled by such devices and ad-ural uranium or thorium is used or ministrative procedures as are necessary stored in an amount exceeding one-to physically protect and warn against hundred times the quantity specified in inadvertent entry by any individual ANwmdiv C of this part be con-through such portals. Exit portals for sWcuously W with a m s@s processed materials shall be equipped to bearing the radiation caution symbol detect and signal the presence of loose radiation sources that are carried toward and the words:

such an exit and to automatically pre CAUTION 8 S vent such loose sources from being car-

• ried out of the area.

RADIOACTIVE MATERIAL (8)

(7) Licensees with, or applicants for, (f) Containers. (1) Except as pro-

[ licenses for radiation sources that are vided in subparagraph (3) of this para-N within the purview of paragraph (c)(6) graph, each container of licensed mate-of this section, and that must be used in a rial shall bear a durable, clearly visible variety of positions or :n peculiar loca-label identifying the radioactiva con-tions, such as open fields or forests, that tents.

make it impracticable to comply with (2) A label required pursuant to sub-certain requirements of paragraph (c:

paragraph (1) or this paragraph shall (6) of this section,such as those for the bear the radiation caution symbol and automatic control of radiation levels, the words " CAUTION, RADIOACTIVE MATERIAL" or " DANGER, RADIOAC-may apply to the Director, Of!!ce of Nu.

clear Material Safety and Safeguards.

TIVE MATERIAL", It shall also provide U.S. Nuclear Regulatory Commission, sufficient information ' to permit in-dividuals handling or using the con-Washington, D.C. 20555, for approval, tainers, or working in the vicinity there-prior to use of safety measures that are of, to takt precautions to avoid or mini-alternative to thwe specified*in paragraph mize exposures.

(c)(6) of this section, and that will pro-(3) Notwithstanding the provisions of vide at least an equivalent degree of per-subparagraph (1) of this paragraph, sonnel protection in the use of such labeling is not required:

sources. At least one of the alternative (1) For containers that do not con-measures must include an entry-prevent-ing interlock control based on a physical, tain licensed materials in quantities

.5 of radiation that assuresg greater than the applicable quantitles measureme the absence of high radiation levels be-S listedin Appendix C of this part.

(11) For containers containing only fore an individual can gain access to an cc ares where such sources are used.

I natural uranium or thorhm in quantities M no greater than 10 times the applicable

[ "(d) Afrborne radioactitfty areas.. (1) quantitles listed in Appendix C of this As used In the regulations in this part.

part.

" airborne radioactivity area" Ineans (D (11D For containers that do not con-any. room, enclosure, or operatingarelt tain licensed materials in concentrations in which airborne radioactive materials, greater than the applicable concentra-composed wholly or partly of licensed tions listed in Colamn 2, Table I, Ap-material, exist in concentrations in ex-xndix B of this part.

cess of the amounts specified in Appen-(iv) For containers when they are at-dix B, Table I, Column 1 of this part; or tended by an individual who takes the (11) any room, enclosure, or operating precautions necessary to prevent the area in which airborne radioactive mate-exposure of any individual to rr,diation or rial composed wholly or partly nf Itcensed radioactive materials in excess of the material exists in concentrations which, limits established by the regulations in avetaged over the number of hours in this part.

(v) For containers when they are in any week during which individuals are in the area, exceed 25 percent of-the transport and packaged and labeled in accordance with regulations of the amounts specified in Appendix B. Table I, Column 1 of this part.

Department of Transportation.

(2) Each airborne radioactivity area (vi) For containers which are acces.

8 As appro late, the information will in-shall be conspicuously posted with a sign sible' only to individuals authorized to clude radtauon levels, kinds of matertal, es-or signs bearing the radiation caution handle or use them, or to work in the timate of acurity, date for whien activity la estimated, mass enrichment. etc.

symbol and the words:

vicinity thereof, provided that the con-tents are identified to such individuals 4 s daMple, conmners an locations such CAITrION :

by a readily available written record, as water-Sued canals, storage vaulta, or hot AIRBORNE RADIOACrIVITY AREA Amended 34 FR 19546.

' Or " Danger

' Amended D "

• D "D'9'

~

C a

Septen ber 1,1978 20-7

s PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION l patients containing byproduct material days and a total quantity of no more Q provided that there are personnel in at-than 100 millicuries.

S tendance who will take the precautions The monitoring shall be performed as necessary to prevent the exposure of any soon as practicable after receipt, but no eu. individual to radiation or radioactive later than three hours after the pack-g material in excess of the limits estab-age is received at the licensee's facihty lished in the regulations in this part.

if received during the licensee's normal working hours, or eighteen hours if re-(c) Caution signs are not required tc ceived after normal working hours.

be posted at areas or rooms containMe (2) If removable radioactive contami-radioactive materials for periods of lea natfors in excess of 0.01 microcuries y than eight hours provided that (1) the (22,0' 0 disintegrations per minute) 'per 8 materials are constantly attended during 100,quare centimeters of package sur-

- such periods by an individual who shall face is found on the external surfaces of f take the precautions necessary to pre-the package, the licensee shall Immedi-m vent the exposure of any individual to ately notify the final delivering carrier

" radiation or radioactive materials in ex-and, by telephone and telegraph, mailgram, or cess of the limits established in the regu-facsimile,t the appropriate Nuclear Regulatory lations in this part and: (2) such area or Commission Inspection and I'nforcement Re-room is subject to the licensee's control.

S onal Office shown in Appendix D.

i 2

TAatz or Exxurr aNo TTrz A QhNTIMES (d) A room or other area is not re-quired to be posted with a caution sign.

g quantity k,mit quanuty bmit and control is not required for each en-

'tranmort anmp i n

U""""*

8 trance or access point to a room or other area which is a high radiation area solely because of the presence of radioactive n... _,

nt a mo u.

and fy -~.... _....

i a

I

-~ ----

g materials prepared for transport packaged and labeled in accordance with g.....-----

y 1

regulations of the Department of R vii:1.. '.' :

s. au wo Transportation.

R 8W N""

(c)(1) Each licensee, upon receipt of a 2

m 6 20.205 Procedures for picking up, re-u- package containing quantities of radio-ceiung, and opening packages.

8 active material in excess of the Type A (a) (1) Each licensee who expects to quantities specified in paragraph (b) of receive a package containing quantitles this section, other than those transported of radioactive material in excess of the by exclustre use vehicle, shall monitor D

7D,3 A

Type A quantities specified in paragraph the radiation levels external to the pack-O

^

d (b) of this section shall:

age. The package shall be monitored as D (J D dj~

a (1) If the package is to be delivered soon as practicable after receipt, but no to the licensee's facility by the carrier, later than three hours after the package make arrangements to receive the pack-is received at the licensee's fEcility if age when it is offered for delivery by the received during the licensee's normal carrier; or working hours, or 18 hours2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> if received (11) 1.f the package is so be picked up af ter normal working hours.

by the licensee at the carrier's terminal, (2) If radiation levels are fcund on the Inake arrangements to receive notifica-external surface of the package in excess tion from the carrier of the arrival of the of 200 millirem per hour, or at three feet package, at the time of arrival.

from the external surface of the package (2) Each licensee who picks up a in excess of 10 millirem per hour, package of radioactive material from a e the licensee carrier's terminal shall pick up the pack I shall immediately notify by telephone

-620.201 Sarne: c c cnione.

p age expeditiously upon ruelpt of-notifi-R and telegraph. mails; ram, or facsimile.

R cation from the carrier of its arrival. e the director of the appropriate NRC Re-Notwithstanding the provisions of (b)(1) Each !!censee, upon receipt of a package of radioactive material, shall; gional Office listed in Appendix D, and

?

8. # 20 203' C

the final delivering carrier.

(a) A room or area is not required to a monitor the external surfaces of the (d) Each licensee shall establish and r

c be posted with a caution sign because of 8 package for radioactive contaminationRcaused by leakage of th the presence of a sealed source provided packages in which licensed material is s

,n the radiation level twelve inches from Packages containing no more than [ received, and shall assure that such pro-tents, except:

the surface of the source container or (1) cedures are followed and that due con-housing does not exceed five millirem the exempt quantity specified in the g sideration is given to special instructions

, er hour.

table in this paragraph; for the type of package being opened.

p (11) Packages containing no more than 10 millicuries of radioactive mate-f@ 20.206 Instruction of permnnel.

(b) Rooms or other.reas in hospitals are not required to be posted with cau' rial consisting solely of tritium, carbon, g tion signs, and control of entrance or

14. sulfur-35, or lodine-125; R

Instructions required for individualo access thereto pursuant to i 20.203(c) is (iii) Packages containing only radio c working in or frequenting any portion of not required, because of the presence of active material as gases or in special ' a restricted area are specified in i 19.12 Packsges containing only radio $8 of this chapter.

form; (iv) 6 active matrialin other than liquid form (includng Mo-99/Tc-99m generators) ano not exceeding the Type A quantity limit specified in the table in this para-graph; and (v) Packages containing only radio-y..

r.n p,y a y a

,,,w,y, nuclides with half-lives of less than 30 t,,nc m ne.Ianfanmim.

t Amended 41 l R 1644L September 1,1978 20-8

,D) c m D D @

)? : L a

Too oASLLAh 4

PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION

$ 20.297 Storage and controf of liccused day does not exceed the larger of sub-which must be maintained pursuant to rnaterials in unrestricted arcas.

paragraphs (1) or (2) of this paragraph:

the provisions of paragraph ia t of this R

(a) IJcensed materials stored in an (1) The quantity which. if diluted by section and records of bioassays, includ-8 unrestricted area shall be secured from the average daily quantity of sewage re-ing results of whole body counting ex-unauthorized removal from the place of leased into the sewer by the licensee, aminat,ons made pursuant to ! 20.108.

shall be preserved until the Commission 3 storage.

will result in an average concentration suthorizes disposition.

(b) Licensed materials in an unre-equal to the limits specified in Appendix (2i Records of the results of surveys o' stricted area and not in storage shall be B. Table I, Column 2 of this part; or and monitoring which must be main-tended under the constant surveillance (2) Ten times the quantity of such Jnd immediate control of tt}e licensee.

material spectfled in Appendix C of this taind pumant m paragap y %e%

section shall be preserved for two 3 ars

~

WASTE DISPOSAL part; and af ter completion of the survey except (c) The quantity of any !! censed or that the followmg records shall be mam-6 20.301 Cencral requirement.

other radioactive material released in tained until the Commission authorizes No licensee shall dispose of licensed any one month,if diluted by the average their disposition: sit records of the re-material except:

monthly quantity of water released b) sults of surveys to determine compli-(a) By transfer to an authorized re-the licensee, will not result in an average ance with t 20.103 < a > ; til> in the ab-c!pient as provided in the regulations in concentration exceeding the limits spec-sence of personnel monitoring data, rec-ords of the results of surveys to deter-Part 30,40. or 70 of this chapter, which-died in Appendix B. Table I, Column 2 mine external radiation dose; and diill ever may be applicable; or of thfs part; and records of the results of surveys used to (b) As author 1 zed pursuant t (d) The gross quanuty of licensed and evaluate the release of radioactive edlu-120.302; or other radioactive material released into 8 ents to the environment.

(c) As provided in 1 20.303 or I 20.304, applicable respectively to the the sewerage system by the licensee does Q i31 Records of disposal of licensed ma-disposal of licensed material by release not exceed one curie per year.

- terial made pursuant to !! 20.302, 20.303, into sanitary sewerage systems or burial Excreta from individuals undergoing [ or 20.304 shall be maintained until the on soil, or in i 20.106 ( Radioactivity in medical diagnosis or therapy with radio Commission authorizes their disposition.

v d4) Records which must be maintained EfSuents to Unrestricted Areas) active material shall be exempt from pursuant to this part may be the orig-9 20.302 Method for obtaining approsal any limitations contained in this inal or a reproduced copy or microform of proposed diaposal procedures.

section.

if such reproduced copy or microform is (a) Any licensee or applicant for a 5 20.30% Dispoaal by burial in noil.

duly authenticated by authorized person-g *icense may apply to the Commission for 'r

-l nel and the microform is capable of pro-c approval of proposed procedures to dis. 5 No licensee shall dispose of licensed ducing a clear and legible copy after

• pose of licensed materialin a manner not material by burial in soil unless:

storage for the period specified by Com-N otherwise authorized in the regulations $ (a) The total quantity of Ilcensed and mission regulations.

in this chapter. Each application should mother radioactive materials buried at any W If there is a connict between the Include a description of the licensed ma "one location and time does not exceed, at Commission s regulations in this part.

terial and any other radioactive material the time of burial,1,000 times the amount license condition, or technical specifi-involved, including the quantitles and specified in Appendix C of this part; and cation. or other written Commission ap-Irinds of such material and the levels of (b) Burial is at a minimurn depth of proval or authorization pertaining to the radioactivity involved, and the proposed four feet; and p ication should al eude a

e regu at o s t1 i pr for sue n 12 a a en ysis and evaluation of pertinentinforma-records shall apply unless the Commis-tion as to the nature of the environment, 6 20.305 Treatment or disposal by incin-sion pursuant to 1 20.501, has granted a erstion.

specific exemption from the record re-including topographical, geological, me.

teorological and hydrological character-No licensee shall treat or dispose of tention requirements specified in the istics; usage of ground and surface licensed material by incineration except _ regulations in this part, as specincally approved by the Commis E 2"$",,j

[,;"!

waters in the general areal the nature sion pursuant to Ii 20.106tb) and 20.302.

~

and t cation of other potentially affected facilities; and procedures to be observed arconos, arronts, AND NOTIFICATION W _a.cn.Ica:Im

.11 repo:t by to minim 17e the risk of unexpected or

@ 20.101 Iterord of mrsen radiatom clephonet to the Dirt of the appropriate hazardous exposures.

monitoring, and d.o p<,.d.

8 sutlear Regulatory Co ssion Inspection and

[* (b) The Commission will not approve va) Each licensee shall maintain rec. N I ntorcernent Regional Umce listed g any application for a license to receive ords s!'or.ng the radiation exp3sures of e licensed material from other persons for all indmduals for whom personnel mon. m in. ap.w.W. < D.. Au.tely cher its oc-g disposal on land not owned by the itormg is required under ! 20 202 of the g emnce h u mwn to the licensee, u

c c.

la. cr aci. of heenned material in sucla m g Federal government or by a State regulations in this part. Such records shall Jcs ;mn unde such circum-(government.

be kept on l'orrn NRC-5. in accord.

C "CUS

' 31 " E r.s tc the hcensee ance with the instructions contained m nd may result to g-tc) The Commission will not approve that form or on clear and lecible rec _

t c

t.o P"

M N

O any application for a license for disposal ords containing all the information re- - ibi Each licensee who is required to g of licensed material at sea unless the quired by I:orrn NRC-5. The doses entered applicant shows that sea disposal offers on the forrns or records shall be for make a report pursuant to paragraph g less harm to man or the environment periods of time not exceedme one calen-u t of this section shall, within thirty p ' 30' days af ter he learns of the loss 01 g than other practical alternative methods -dar quarter.

3' gof disposal.

Each licensee shall maintain rec - thef t make a report m writing to the n

(b) ppropriate NRC Regional OHice lis"

-6 20.303 Dispo al by relcane into sani-S ords in the same units used in this part, [ in Appendix D with copies to the Paec-tary sewerage systerrm.

O showing the results of surveys required tor of Inspection and Enforcemen U.S.

3 No licensee shall discharge licensed c by 120.201 t b ), monitoring required by 'r Nuclear Regulatory Commt aon. Wash-8 ' materialinto a sanitary sewerage system ' i120.205tb) and 20.205(c), and disposals ington. D C. 20555. setting forth the fol.

It is readily soluble or dispersible 'made under iI 20.302,20.303, and 20.304.

_ lowing information.

' unless:

[

(a) in water: and (c)(1) Records of individual exposure e"

(b) The quantity of any licensed or to radiation and to radioactive material other radioactive material released into Wnended 42 i R 4 3M the system by the licensee in any one

)

)

• Redesignated 36 i R 2 3138.

L 20-9 September 1,1978

PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION

~

(1) A description of the licensed materir.1 involved, including kind, quan-tity, chemical, and physical form; (2) A description of the circum-stances under which the loss.oy theft occurred (3) A statement of disposition er probable disposition of the licensed material involved; (4) Radiation exposures to individ-uals, circumstances under which the ex-posures occurred, and the extent of pos--

sible hazard to persons in unrestricted arcas; g

ll be taken, to recover the material; (5) Actions which have been taken, or wi 3

and e

(G) Procedures or measures which M have becn or will be adopted to prevent a recurrence of the loss or theft of 11-censed mattrial.

(c) Subsequent to filing the written report the licensee shall also report any substantive additional information on the loss or theft which becomes available to the heensee, witi m 30 days alter he learns of such information.

(d) Any report filed with.le Com-Inission pursuant to this sectu.i shall be 30 pr,epared that names of Individuals who may have received ex,x sure to radiation are stated in a e;, urate part ed 2.e report m $ 20.103 Notificatiim. of incidenta.

h (a) Immediate notification. Each 11-

" censee shall.immediately notify by tele-E phone and telegraph, ma11 gram, or fac-

,. simile, the Director of the appropriatt i NRC Regional Omce listed in Appendix o~o gn 3

skv=

20/2 294 September 1,1178 2 0-10

s-D dau a

mm o

D D

w e

_f a

e PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION D of any incident involving byproduct, diation or concentrations of radioactive (a)(2) of this section. If personnel source, or special nuclear material pos-material (whether or not involving ex-monitoring was not required to be pro-sessed by him and which may have cessive exposure of any individual) in vided to any indhidual by the licensee

,,_ caused or threatens to cause:

an unrestricted area in excess of ten under 1120.202(a) or 34.33(a) of this times any applicable limit set forth in chapter during the calendar year, the individua 25 rems or r or of di this part or in the license. Each report licensee shall submit a negative report required under this paragra, a 5ali desenbe indicating that such personnel moni-tion; exposute of the skin of the whole body of any individual of 150 rems or Q.the extent of exposure of individuals" toring was not required.

(b) A statistical summary report of more of radiation: or exposure of the c to radiation or to radioactive material.

the personnel monitoring Information io feet, ankles. hands or forearms of any ' including estimates of each individual's reccrded by the licensee for individ.

gid Adual to 375 rems or more of radia. E exposure as required by paragraph (b) ua!s for whom personnel monitoring of this section; levels of radiation and was either required or provided, as de-E t21 The release of radioacJve r it '.

concentrations of radioactive material S s tal in concentrations which. if avet i

scribad in paragraph (a) of this sec-

@ over a period of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, would exce d involved; the cause of the exoosure.

tion,1.7dicating the number of individ-c 5.000 times the limits specined for such levels or concentrations; and corrective uals wh,se total shole body exposure steps taken or planned to assure against materials in Appendix D. Tab!e !!: or recorded during the previous calendar (3) A loss of one workintr week or a recurrence.

year was in each of the following esti-

' more of the operation of any facintics (b) Any report filed with the Commis-mated exposure ranges:

g sion pursuant to this section shall in-4 an ace to propet:v in excess of 5200,000.t g clude for each individual exposed the

- name, social security number, and date numan.o ahole body N umber of indiudoals

- (b) Twenty-four hour notification E of birth; and an estimate of the indi-esposure ransc <remse m each ranse Each licensee shall within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> no ' vidual's exposure. The report shall be tify by telephone and telegraph. mail-N this information is No mensurable enpowe.

gram, or facsimile, the Director of the { prepared so that stated in a separate part of the report.

M *"o2s '. " W"' k" "" 8 3 '

M oit appropriate NRC Regional Omce listed g

(c) (Deleted 38 FR 222201 y5,tay m in Appendix D of any incident involving us a n_

- licensed material possessed by him and g 20.4% IDeleted 38 FR 22220.1 192_

which may have caused or threatens to

!ok h 20.407 Personnel monitoring eeports.

cause:

j[C f1) Exposure of the whole body of any Each person described in 120.408 of

[

individual to 5 rems or more of radia-this part shall, within the first quarter ea tion; exposure of the skin of the whole of each calendar year, submit to the 7 to s ame_

body of any individual to 30 rems or Director of Management and Program fo"o!.

I more of radiation; or exposure of the Analysis.

U.S Nuclear Regulatory g feet, ankles hands, or forearms to 75 Commission. Washington. D.C. 20555, 2 12+-

u a 12 rems or more of radiation; or the reports specified in parRgraphs (a)

,o (2) 'Ite release of radioactive mate.

and (b) of this section covering the Z - - - --

g rial in concentrations which, if aver-preceding calendar year ' All other $ Q,8,,' [u e rangM

'Indmdual vanes exactly equal to the vanes sep a

sha:t be reported in the e ceed 500 times the lir ts sp cihi persons specifically licensed by the.

N r

r Commission shall. within the first such materials in Appendix B. Table II; 1979 and ;

quarter of calendar years The low exposure range data are re-or (3) A loss of one day or more of the 1980, submit to the Director of Man-quired in order to obtain better infor-operation of any facilities a!Tected; or agement and Program Analysis. U.S.

mation about the exposures 'actually (4) Damage to property in excess of % Nuclear Regulatory Commission, recorded. This section does not requi:e

$ 2,000.t

Washington D.C. 20555..he reports improved measurements.

specified in paragraphs (a) and (b) of n"

[ this section covering the precedmg cal-5>l 20.40M fleports of personnel monitoring endar years 1978 and 19793 '

~

on termination of employ ment or 8 su(c) Any report filed with the Comminion pur,,

N ant to this section shall be prepared so that (a) A report of either (1) thg total work.

E names of individuals who have received exposure number of individuals for whom per-(a) This section applies to each

• to radiation will be stated in a separate part of sonnel monitoring was required under person licensed by the Commission to:

R the report. 20,202(a) or 34.33(a) of this chapter pna e a nudear reactor de-during tha calendar year; or (2) the signed to produce electrical or heat 620.404 IDeleted 38 FR 22220.] total number of indaiduals far whorn energy pursuant to 150.21(b) or $ 50.22 g 20.40*> Heport. of oserespo ures and personnel monitoring was provided ~~ fef

• D "

esecesive Ictets and concentrations. durmg the calendar year-Pm rided, i )50 br) of th ch p, g (a) In addition to any notification re-hatceter, That such total includes Rt (2) Pt SES or use byproduct m.teri-g quired by 8 20.403, each licensee shall least the numbe r of mdividuals re-al for purposes of radiography pursu-quire d to be repo!ted u..dtr paragraph ant to Parts 30 r.id 34 of this chapter; N make a report in writing withh2 30 dayd ( a )( 1 ) ! this secwn. The repo t shall d) Process o-use at any one time, E to the appropriate NRC Regional Ofice D a

• M for purposes of fuel processing, fabri-listed in Appendix D with a copy to the e rde Cth pm m ph m l) or cation, or reprocessing. special nuclear N

Director of Inspection and Enforcement, material in a qantity exceeding 5,000 U.S. Nuclear Regulatory Commission, grams of contained uranium 235, ura- _ Washington. D.C. 20555. of; ' A hee nsee mhose beense expires or teimi-nium-233, or plutonium or any combi-(1) each exposure of an nates prior to or on the last day ut the cal nation thereof pursuant to Part 70 cf individual to radiation in excess of the endar Sear. shat! submit rerorts at the expi. applicable !!mf ts in il 20101 or 20.104 rauon or terminanon of the ucense, coser this chapter; or rg that part of the Sear durms which the (4) Possess or use at any one time, or the license; (2) each exposure k o(a) f an individual to radioactive material h7.(( *Q$I[ vi:1 esahitte the data for processing or manufacturing for y in excess of the applicable limits in obtained for 1978 and 1979 purwant to thw distribution pursuant to part 30,32. or Il 20.103(a) (1), 20.103 (a ) ( 2), 20.104 (b) paracraph. and the benefits dertved the" 33 of this chapter, byproduct material g S or the license; (3) levels of radiation or from and may take action. includ:na puuh-in quantitles exceeding any one of the E conet strations of radioactive material cation of notice of orwd rulemakirit to in a restricted area in excess of any extend or othersiv inetly thm reportiiig following quantities: other applicable hmit in the license: (4) req uitru n t

• A mended 4 3 I R 29 2 70.

any incident for which notification is re-t \\menJed 42 i R 43M outred by 120 403; and (5) levels of ra-20/2 295 "e ~8erio.ie78 20-Il

PART 20 e STANDARDS FOR PROTECTION AGAINST RADIATION b

• I "" " " " ' "
• Radionuct2de
• Quanuty an The Commission may, by rule, regula-curwa E tion, or order, impose upon any licensee C"i"*' 3 37 1

~ such requirements, in addition to those f;ja*."g 9I 3d [ established in the regulations in this todine-t 3 t. t e part. as it deems appropriate or necessary Irtdtum 192. 10

• to protect health or to minimize danger to life r property.

hroYe um' 14 7 Technetium 99m.. 1.000 f6 20.601 Violations, t

• The Comminanon may require, as a 1kense condt-An injunction or other court order uon. or ey rune. resuiauon or order cursuant to i 20 %2. reports from ticensees uno are imenwd to may be obtained prohibiting any viola-use radionuchdes not on this hat. !n quanuties suf-tion of any provision of the Atomic nesent to cause comparata, ramanon aescis.

Energy Act of 1954. as amended, or Title II of the Energy Reorganization Act of (b) When an individual terminates r any rWamn or der WW employment with r licensee described thereunder. A court order may be ob-in paragraph (a) of this section, or an tained for the payment of a civil penalty

individual assigned to work in such a, imposed pursuant to section 234 of the 53,57,62,63,

licensee's facility but not employed by 2 Act for violation of section

• the licensee, completes the work as. " 81, 82,101,103,104,107, er 109 of the signment in the Ilcensee's facility, the ' Act, or section 206 of the Energy Reorga-

" licensee shall furnish to the Director ; n zau n Act of M or any rule, Ma-tion, or order issued thereunder, or any

• of Management and Program Analysis.

term, condition, or limitation of any U.S. Nuclear Regulatory Commission, license issued thereunder, or for any Washington, D.C, 20555, a report of violation for which a license may be re-v ked under section 186 of the Act. Any the individual's exposures to radiation person wno willfully violates any pro-and radioactive material, incurred vision of the Act or any regulation or during the p(riod of employment or order issued thereunder may be guilty of work assignment in the licensee's fa-a crime and, upon conviction, may be cility, containing information recorded punished by fine or imprisonment or by the licensee pursuant to both, as provided by law. (( 20.401(a) and 20.108. Such report ~ shall be furnished within 30 days after the exposure of the individual has been determined by the licensee or 90 days after the date of termination of employment or work assignment-D*P D D 9~Vi ~ whichever is earlier, t; y O d .I ~ $20,109 Notifications and reports to individuals. (a) Requirements for notincations and reports to individuals of exposure to radiation or radioactive material are % specified in i 19.13 of this chapter. (b) When a licensee is required pur-suant to il 20.405 or 20.408 to report to a [ the Commission any exposure of an in-dividual to radiation or radioactive ma- " terial, the licensee shall also notify the individual. Such notice shall be trans-mitted at a time not later than the transmittal to the Commission, and shall comply with the provisions of i 19.13(a) of this chapter, EXCEPTIONS AND ADDITIONAL REQUIREMENTS

• 6 20.501 Applications for exernptions,

$ The Commission may, upon application ~ by any licensee or upon its own initiative, w grant such exemptions from the require-a ments of the regulations in this part as " it determines are authorized by law and will not result in undue hazard to life or property. Nort -The reporting and record keeping requirernents contained in this part have been approved by the General Accounting O*ke under B-180225 tRoo43), (Roo44), and iRoo84l-2072 ?96 November 10,1978 20-12

APPENDIX B APPENDIX B Concentretiens in Air and Water Above Naturel Bechground-Centinued Concentretiens in Air end Water Above Natural Berkground (see footnotes on page 20-18) (See footnotes on page 20-18) T Table i Table if Table i Table 11 m Element (etemic number) Isotope ' Column 1 Ce16 mn 2 Colven 1 Column 2 Elemens (stemic number) isetepe ' Calven I Colven 2 Celven 1 Colven 2 d h3 t (pcifml);( ci517(pci)ml)(pit /ml). tKpcifml)(pc1[ml)(pc )mi) (pIi)ml) ^ ^ M Actinium (89). Ac 227 5 2 x 10-" 6 x10-s s x t o-'* 2 x 10-* Bromine (35).. Br 82 5 1 x10-8 8 x10-8 4 x10 8 3 x10-* d 1 3 x 10-" 9 x 10-8 9 x 10-88 3 x10-8 1 2 x 10-F 1 x10-8 6 x 10-' 4 x10-s Ac 228 5 8 x 10 ' 8 3 x 10 -8 3 x 10' 9 x10-s Cedmium (4 8).. Cd 109 5 5 x 10 5 x10-8 2 x 10

• 2 x 10-
• 2 8

3 x10-s 6 x 10 - 9 x 10 -8 1 7 x 10 5 x 10 '8 3 x 10 ' 2 x10 '* Q Americium (95).. Am 241 5 6 x 10-'8 1 x10 ~8 2 x 1018 4 x10 4 Cd 115m 5 4 x10 8 7 x 10-* 1x101 3 x10-8 p 1 2 x10

• I Ix1018 8 x 10 -
• 4 x 10 -"

3 x101 1 4 x 10' 8 7 x 10

• 1 X 10' 3 x10-s Am 242m 5

6 x 10-" 1 X IO-* 2 x 10-" 4 x 10-* Cd 115 5 2 x 10 - 7 1 x 10 '8 8 x 10' 3 x 10 -s 1 3 x 10 ' 3 x10-3 9 xio-n 9 x yo-s g 3 x 30-7 3 xio ^8 6 x 10 -' 4 x 10 -8 E Am 242 5 4 x10 e 4 x 30-3 1 x 10 -' 1 x 10-* Calcium (20).. Ce45 5 3 x 10 8 3 x10 -8 1 x 10 ' 9 x 10- 8 1 5 x10-s 4 xio-3 2 x IO -' i xt0-8 8 1 x10-F 5 x 10 8 4 x10 -' 2 x10' "T1 Q Am 243 5 6 x 1018 1 x 10 ' 2 x1018 4 X 10-* Ce47 5 2 x10-7 1x10a 6 x 10 5 x10 8 I I x IO 8 x t0 -* 4 x lo -" 3 x10-s g y xio-F g xio a 6 X10-' 3 x10 8 1 1 x 10 - 7 5 X 10-8 Californive (98). Cf249 5 2 x 10-" 1x10-* 5 x10-" 4 x10-s i 2 x 10-8 I XIO1 8 x 10" 5 x10-8 1 1 x 10 - 7 x 10 -* 3 X 10 -" 2 x10-s T Am 244 5 4 x 101 1x10 Antim Sb 122 5 2 x 10 ~ F 8 x 10-* 6 x 10' 3 x10-s Cf 250 5 5 x 10 -" 4 x10' 2 x 10 -'8 1 x 10 - s 2 T I 1 x IO'F S X IO-* 5x10' 3 x to-s Y g i xio-so 7 x 10-4 3 x 10 '" 3 x10-s Q 8 Sb 124 5 2 x 10'F 7 x 10' 5x10' 2 x10-8 $ Cf 251 5 2 x 10 -" 1 x 10- 8 6 x10 '* 4 x 10 - * "I i 2 X f 0 7 x10-8 7 x 101' 2 X 10-s 1 1 x 10 ~ 8x10-* 3 x 10 '" 3 x 10 s fTl N (4 u. Sb 125 5 5 x 10' F 3 x 10 8 2 x10^8 1x10-* u. Cf 252 45 6 x 10 u 2 x10' 2 x10-" 7 x 10' O 3h y 8 3 x 10-8 9 x 10"' 1 x 10'* m 41 3 x 10 - n 2 x to-* ix10-" 7 x 10

• d

" Argon (18) A 37 Sub8 6 x 10 '8 3 x 10 ' 8 Cf 253 5 8x10-E 4 x10 8 3 x 10 " 1 x 10 ' * ~ m I 3 x10 Q A 48 Sub 2 x 10 '* 4 x101 1 8 x 10 - '8 4 x 10 8 3 x 10 " 1 X 10

• g Arsenic (33)

As73 5 2 x10-8 1 x 10 -8 7 x10-a 5 x 10 '

• Cf 254 5

5 x 10 - " 4 x 101 2 x 10 " 1 x 10 ~ 7 I 4 x IO F I xlO'8 1 x10 e 5 X 10 '

• I 5 x 10 "

4 x 10-* 2 x 10 -" 1 x10-7 ) F S x 10

• Q 7

2 x10-8 1x10s 5 x10-s Corben (6). C 14 5 4 x 10 -

• 2 x 10 8 1 x 10 As 74 5

3 x 10 e f I xfo-F 2 x 10 8 4 x 10

• 5 x 10- s (COz)

Sub 5 x10-s y xio

p-1 9 x 10 - s C

As 76 5 1 x10-F 6 x10-8 4 x 104 2 x10-s Cerium (5 8).. Co 141 5 4 x10'F 3 x10 s 2 x 10 N I I x 10 'F 6 x t0-* 3 x 10 ' 2 X10-s 1 2 x10'F 3 x 10 8 5 x 10 ' 9 x10 8 2 As 77 5 5x10-7 2 x10-8 2 x101 8 XIO-s Co143 5 3 x 10' F 1 X 10 8 9 x 10

• 4 x10 s g

i 4 x 10 - 7 2 x 10 - 8 1x10e g xyo-s i 2 x 10 ' F 1 x 10 8 7 x 10 ' 4 x 10 - 8 . -{ 8 3 x 10 -

• 3 x 10 ea 1 xto-s 1

5 x10-s 2 x 10 "8 2 x 10 Ce 144 5 1 x10 i 3 x 10 a 2 x 10 - 8 1 x 10 ' 7,'10-s a 6 x 10 3 x 10 ' 8 2 x 10 " 1 x 10 s 3 Astatine (8 5) At211 5 7 x 10 4 Barium (56) Be131 5 1 x 10-* 5x10-8 4 x10 8 2 x '0-* Cesium (55). Cs 131 5 1 x10-s 7 xyo-: 4 xgo-r 2 x10~8 M sy I 4 x 10 - 7 5 x 10' 3 1 x10-e 2x1r* I 3 x 10 '

• 3 x10 -a y xio-F 9 x yo
• Q-g 1

1 x 10 8 6 x 10 8 N Be140 5 1 x 10 - 7 8 x 10-4 4 x 10 3 x10-s Cs 134m 5 4 x 10 s 2 x 10 F e x 10 8 4 xIO e 7 x 10 -4 1 x 10-' 2 x 10 i I 6 x10-* 3 X10 8 2 x 10 Berkelium (97) Bk249 5 9 x 10

• 2 x 10-8 3 x 10-"

6 x 10-8 Cs 134 5 4 x 10 3 x10~8 1 x 10 ' ' 9 x 10

• d i

1 x10-F 2 x 10-8 4 x 10 -' 6 x10-8 l 1xW8 1 xm-8 4 M 0 ' 4xm-s O Sk250 5 1x10-7 6 x10-8 5 x 10 ' 2 x 10-* Cs135 5 5 x 10- F 3 X 10 8 2 x 10 ' 1 x 10 -

• g i

I x 10

• 6 x 10 ~ 8 4 x101 2 x 10-*

I 9 x10 8 7 xio 8 3 x 10-' 2 x 10

• 8 9 x10-s Beryllivm (4)

Be 7 5 6 x 10-* 5 x10-8 2 x10-7 2 x10-s Cs136 5 4 x10-F 2 x10-8 1x10 i I x 10

• 5 x10-8 4 x10-8 2 x10-s i

2 x10-F 2 x 10 8 6 x 10 6 x10-s l Bismuth (8 3) Bi206 5 2 x10-F 1 x10-8 6 x101 4 x10-8 Cs 137 5 6 x 10- 8 4 x 10

• 2 x 10
• 2 x10-s o

i I x 10 ' F 1 x 10-8 5 x10-' 4 X10-s 1 1 x10-a 1 x 10 - 8 5 x 10- 4 X10 s Bi207 5 2 x 10-7 2 x10 -8 6 x 10-' 6 x10-s Chlorine (17). C136 5 4 x 10- 7 2 y LO'8 1WO' 8 x10-s cr 1 2 x 10 'J 8x10"' 6 x 10 8 1' 6 x10-s i 2 x 10 I 1x10 8 2 x10-s 5x10 h 84210 5 6 x104 1 x10-3 2 x 10 '" 4 x10-8 CI38 5 3 x 10~* 1 x 101 9 x 10 8 4 < 10 *. to I 6 x104 1 x10-8 2 x 10- 4 X10-8 3 2 x 10-* 1 x 10 - 8 7 x 10 a

• (10
• 01 84 212 5

I xio-F 1 x10-8 3 x 10-* 4 X 10' Chromium (24). Cr 51 5 1 x10-s 5 x 10 ~8 4 x 10~ F 2 x10 8 5 x 10 -8 8 x10 8 2 x10-s 1 2 x10-F 1 x10-s 7 x104 4 x 10-* l 2 X10-* i

PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION e4
• =a

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PART 20

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PART 20

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o n n eh e-Ls ie vt n e oo A oe e v p '* e vt C im 0 eed o" t db es was a it c ie iel s i sd e d e' ) db b i-aed o "r l r is eyP e e r r r e 4 t ( r e e meh e ledeme nt e ledb ed s*' e em-e m lgts i s i. gt i f ( ) u f . gt n i yw " d ll e iniyetewl sn l a"* t c vs l ah n ei is s y t 0 i n s l a f-3 i f podl vs e n c te e I' t c ( m e yoeIP'naeyoel pnaey o le i i n nd - ' hh nd es ahh n nd' c n n r E Z Z A A A W rCxT. vCF. eD ) ) N N Y8- [ N hQg7* *7 _W C m2" D e

PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION

~ NOTE TO APPE NDIX B

3. If any of the conditions spec 16ed below Nots In any case where there is a misture in air or are met, the corresponding values specified

~ u ster of more than one radionuclide, the limitir. value, below may be used in lieu of those spec 1 Sed for purposes of this AppendlE should be determined an in paragraph 2 above. 10D0**

a. If the identity of each radionuclide in the mixture is known but the concentration el de in the en tur re own the 11 n nr alu should be derived as follon s-Determine, for each ra.

of one or more of the radionuclides in the I dionuclide m the misture, t he ratio t.et u een t he quantit v 0 mitture is not known, the concentration @ lished in Appendts Il for the specine ratonuclide w hen = 1n Appendix "B" for the radionuclide in thepresent in the misture and the 'e kr C mixture having the lowest concentration i ucli s ir the m tt a ot c 4 1 '11mit; or N " unity").Esaurts' If radionuclides A. II. and r are present @

b. If the identity of each radlonuclide in in concentrations Ca C s, and Cc. and if the appl aible "the m12ture is not known, but it is known i

M PC s, are %f PCa. and %f PCs, and %t PCc rewe that certain radionuclides spectaed in Ap-titelv, then the conantrations shall be limited w tha' pendix "B" are not present in the m12ture, the followini telationshm esists the concentration limit for the m11ture is . Ca C# Cr the lowest concentration limit specified in g, y _tPCs#StPCr Appendiz "B" for any radionuclide which is ~ $1PCa S not known to be absent from the mixture;

2. If either the identity nr the concentration of any or O

$ ra.11onuclide in the misture is not known. the Itmiting " n fd Q values for purpmca e' Appendts 11 shall be: {

a. For purposes of Table 1. Col.1-4 x 10as y

n p j $q

b. For purpotes of Table 1. Col. 2-4 X 10-'

ld; Jj l g ]i 1 U o C. For purposes of Table II, Col.1-2 X 1048 d,J m f1

d. For purposes of Table II, Co!,2-3 X 104 L.-

A Toble 1 Table II

e. Element (atomic number) and tsotope Column 1 Column 2 Column 1 Column 2 Air b,C1/ml)

R ater Air (nCt/ml) W ater GCi/mi) GC1/ml) If It In known that $r 90, I 125. I 126. I 119. I 131, (I 133, table 11 only), Pb 210. Po 210, At 211, ha 71.3, ka t4, Ra 226, Ac 227. Ra 22M, Th 230, Pa 31. Th 232. Th. nat, Cm 248, Ci 254, and Fm no are not present... 9Xlti 3X104 3 If 18 ts k noen that 6r Wu,=l 125. I 126, i 1.'9, ti 131,1 B33,- cg table !! only), Pb 210, Po 210, Ra 223. Ha 226, Ra 228, m_ Pa 231. Tb-nat, Cm 248, Cf ut, and Fm 256 are not ~~~~ E If k noir n'tWaiBr 90',} I29,il'I'23,'i'156'. t"th,~tabie' II ' " ~ ~ ~ ~ only). Pb 210, Ra r6, Rs 228, Cm 244, au Cf ne are 2X10-e 4X104 notpresent........_............................... g If it is known that iI 129, table II only). Ra 226, and Rs If it is known (bat alpheremitters and Fr 90. I 129. Pb..... 3 X 10-8 IX104 228 are not prement..,................. 210. Ac 227. Ra 228, ra 230,Pu 241, and lit 249 are not If it is known that alphumitters and Pb 210, Ae 222...... ~............ 3X104 IX104 preent. ~... -........ If it la known that alphumitters and Ae 227 are not.... 3X10-8 IX10-H Ra 228. and Pu 241 are not present............ 3 X 10-8 IX10-8 !!present.It is known the..... _Ae 227 Th 230. Pa 23I. Pu 23R, Pu 239. Pu 240, Pu 2=2, Pu 244, Cm 248, Cf 249 and Cf 251 are not present.,.... 3X1048 1X10-8

4. If a mixture of radionuclides consists of

=r O dranium and its daughters in ore dust prior o to chemical separation of the uranium from the ore, the values specified below may be [ used for uranium and its daughters through radium.226,instead of those from paragraphe 0 1,2,or3above. a-I

a. For purposes of Table I, Col.1-1X104' f SC1, ml grome alpha activity; or 6X10-u act/

m1 natural uranium; or 75 micrograms per co cubic meter of air natural uranium. N E

b. For purposes of Table II. Col.1-3 X 1048 act/ml groes alpha activity; or 2X104'asC1/

@ ml natural uranium; or 8 mieregrams per cubic meter of air natural uranium.

8. For purposes of this flote, a radio-nuclide may be cons.dered as not present in a mixture if (a) the ratto of the concentra-tion' of that radionuellde in the m12ture (Ca). to the concentratics limit for that v3 radionuclide spectaed in Table II of Ap-c pendix B (NPCa) does not exceed he

= (i.e. p Q ) and (D) the ettm of such /b/ /ny L. U / c) j(}j ratios fog all the radienuclides considered ** N not gesent in the mixture does nos eued Ca Ce 6%h (l.a. yg + y+ 20-19 September 1,1978

PART 20

• STANDARDS FOR PROTECTION AGAINST RADIATION Any a a em ng radonuch daterial Microcuries not listed atxive or mtxturen of

~ Ae n wett C Osmiu m.191 rn'.............-.. _ 100 alpha emitters of unknown com. Meterial Microcurfes 100 position .01 Osmium.191 Americtum-241 --..-........---- .01 Ommlum.193 100 Any radionuclide other than alpha Antimony-122...........---_._ 100 Pallsdl uin-103...... _ - -. - - - -.. 100 emittmg radionucitdes, not listed Antimony _124.............-..... 10 Palladiu m - 109... -. -.... - - - - - - 100 above or mixtures of beta emit-Phosphorus.32........ - -- - - - - - - - 10 ters of unknown compmition._. 1 A ntimon y.125 _. _ _ _.............. 10 A rse nic 73....................... I Platinum 191 3 Notz: For purposes of Il 20 203 and 20 304, rsen Platin um-193 m......... -... - - - -- 00 where there is involved a combination of 110 A rae nic-76 _................. _ _ _. 10 Platinum-193...._- -.. ----.. 100 Plat in um 197m _ _ _ _ - --. ---- -- IM topes in known amounts the limit for the Arsenic.77.......... ____.____. 100 m combination should be dertsed as follows: Battum.131.................... 10 Platinum-197 100 c4 Determine. for each 1sotope in the combina. 'Ibnum133 10 Plutonium.239 tion, the ratto between the quantity present Banum.140 10 I [0 a in the combination and the Itmit otherwise Polottlum-210 Etamuth.210..............._....._.. __...__....... 10 1 Pot assi um-4 2.. -.... -- - - - - - -- -

u. estabushed for the specific isotope when not 13romine-82 Pr aseod y miu m-14 2.... -.... ---- - -

100 n combination. The num of such ratios for Cadmium.109......... --....... 10 Praseodymium-143 100 all t.he isotiopes in the combination may not 10 Promethi um-147.. - -. _ -. --- -- 10 Cadmium 115m exceed "1" (1 e.. " unity"). Example: For pur. Cad m tu m-I I 5....... - _ - _ -. - - -. 100 Promet hi u m-14 9...... -... - - - - -.. 10 es of I 20 304, if a particular batch con-Calciu m-45......... _ _ _. ---.. -... 10 P.adi u m -226 _...... -.... -. --- - -. .01 ns 20.000 po + of Aul98 and 50.000 pCi t Cal ci um.4 7. _ _ _......... -.... -. 10 R h e n t u m.186, _........ - - - -..... 100 gg gi4 it mn aim mtluJe not more than Ca r bon.14....... _ - - _ _ - - -..... _. 100 Rh en i um.188... --.. - - -. - -- ---.. 100 300 ub t i,f 1 13 8 Ihis linut w.is determmeJ Ce rt u m-141 100 Rhodiu m-103 m.. _ _ -... - _. -..... 100 Certum.143............--.-..... 100 as follows: Rhodi u m-105........ - -... - -- - - 100 14 til , JhooogcLad. MNQL + W W C.1 Ceri u m.144............... - - _ - - 1 Ru b i di u m - 86..... _ _.. -. - -- - -. 10 .........__.. _ 1.000 R u bi di u m.87 _ _ _.... _..... -- --- 10 1Acoo da MM* Cent um.131 100 R u t he niu m -97.............. -..-. 100 The denominator in each of the above Cest u m-134m Ceslum - 13 4.. _ _. _. _.. - _ -..... - - I Ru t henium.103 -. _ _ _.. -....------ 10 ratios war, obtained by multiplying the figure Cesium.135 10 R uthenium-105.................. 10 in t.tle table by 1.000 as provided in i 20.304. Ce nt u m - 13 6..... _ _........ -...... 10 R u thenium.106. _............_. -- 1 Sam arium - 151........._.....- -. 10 Cesi u m - 137 _..... -........_ _ _ _ 10 Chlori n e -3 6......... - - _ _........ 10 Samart um-153...... _....... - --. 100 Chlorine -3 8...... - _ _............. 10 Scandium-46 10 Chrom 1um.51.._.....__....... 1,000 Sca n d i u m.4 7..... _ _...... _ _..... 100 Cobal t.5 8m..................... 10 Scandium.48 10 Oubal t-5 8.. _ _.......... _ _...... - 10 scie n t u m.75 _ _ _.................. 10 Cobalt-60 1 Silicon-31 100 Cop pe r.64... _ _ _.... _ _....... _.. 100 811rer-105 __..........___........ 10 mp3 p D D .,3 10 S11ver.110m........... _ _ _..... _ _. 1 Dysprostum.165...__........_.. 100 Sil v e r - 1 1 1... _. _ _ _.... _... _ _..... 100 i h p' Dysproalum 166...__..__......._ 100 Sodt um-24 10 gg D O Erbium-169 _....___.__........ 100 St ro n t i u m - R5 _.......... _ _ _... _ _. 10 Erbium-171 __................__. 100 S t.ron t i um - o9... _...... _. _ _ _. _ _ _ 1 Europiu m-152 9 2 h......._ __.... N t3 S tron ti um-90..... _. _ _ _ _ _ _ _ _.... 01 e4 Europium-152 13 yr......_ _ _ _.... 1 $ Europium-154 _ _..... __....__ 1 8 St ron tiu m-91.. _ _ _........... _ _. 10 Euruptum-155....._.........._ 10 g St rontiu m. 92.... _...... _ _ _ _ _ _ _ _. 10 g

u. Fluortne-18 __..___..._ ___.. 1.000 u.

S u l ph ur.35. _...... _ _............ 100 10 Ge dolinium.153 _ _ _.. _ _ _..... -- 10 g Tantalum 182 g Ondolinium.159......._.___...-- 100 Technetium-96 10 Oa111 u m 72..................... 10 Technetium-97m 100 100 Germantum-71.........__...... 100 Technet tum-97.. ___________.. 100 Gold - 198......... _ _ _... _ _ _ _ _ _ _ _ 100 Technetium-09m Gold.199........___............ 100 Technet tum _99 _ _. _ _ _ _ _ _ _ _... 10 It ai n t um-181....... _........... 10 Tellurtum-125m. _ _ _ _ _....... 10 10 IIol m i um - 16 6 _ _ _...... _ _ _ _....... 100 Tellurtum-127m __....._____.... 100 Ilydrogen-3..............___... 1.000 Tell urt um - 127...... _ _...... _ _ _ _ I n d i u m - 1 13 m _ _ _................. 100 Tellurtum-129m. __.___... __ 10 Indiu m-114 m.................... 10 Tellurium.129... _....__.... 100 In diu m 115m....... _........ _ _ _ _ 100 Tell urt u m-131 m..... _.. _ _ _... 10 Indium.I!5 __..____..._......___ 10 Tell u rt u m-13 2............... _. 10 10 fodine-125........___......._... 1 Terblum-160 _._....._....____ 100 1 Thallium-200... __.....__.. __. Iodine-!26......._______...... 0.1 Tha lli um-201.........._.____ 100 ledine-129........______...___. 1 Thallium-202 _ _ _..___...... 100 Iodine-131..................... 10 Thallium 204..... ___.... 100 10 Iodine-132 1

• *Ihorium (natural)1...............

lodtne.133 10 Thu11um.170........___....... 10 lodine-134... __.____._________ 10 Thultum-171 10 Iodme.135 ___...............___. I rt d t um-192 _ _................... 10 Tm-l l3.__.___ 10 Irtd t u m.194.... _ _ _ _ _ _ _ _... _ _ _ 100 Tin-125....._...._______ _ 10 Iron.55 100 Tu ngst en-181.. _...... _... - 10 Iron 53 __..................... 10 Tungsten 1HS.... 10 100 Krypton-85.._.___..____...... 100 Tu n gste n_187 _ _. 100 Krypton.87... __......__..... 10

• Uranium ( natural ) '.......... _ _..

01 Lanthanum-140.._............. 10 Uranium-233 .01 Lutet tu m-177 100 Urantum-234-Uranium.235... h!an g a nese-5 2 _ _ _........ _ _ _. _ _.. 10 Va nadium-48..._ _ _ __ 10 hiang ane se-54... _ _ _ _ _ _ _......... 10 Xenon-131 m 1.000 hf a n g e n ene-56... _ _ _ _.......... 10 Xenon.133. _....... __.... 100 htercury-197m.._ _ _ _ _..___.. 100 Xe non-135 100 h!crcury-197. ___................ 100 Y t t e rbiu m-175 lou Klerc u ry -203............... _ _. _ to Yt trium-90. 10 htolybdenum-99 __.. __.....__ 100 Y t t riu m.91 _ _ 10 Neodymium-147 _ _. 100 Ytt rium-02 100 Neodymtum-149............... 100 Yttrium-03 IN ' llased on alph a disintegration rate of Nickel-59. 100 Zmc-65 Lj Nic kel-63. __.... 10 Z nc-Om 1u9 Th-232. Th-230 and their daughter products ' Based on alpha disintegration rate of N ic k el-65 _ _.. _ _ _.......... 100 Zi n c - tM. 1.004 U 238. U-234. and U-235. Ntobtum-93m._ _ 10 Zirmnium-93. 10 Zircontum-95 !o A"'enkl h I H IW s Niobtum-95 10 \\"*"*d D IR I M O Niobium-97........ 10 Zarrontum-97, lo t \\mena J 1% l H N tia Os miu m -185...... 10 September 1,1978 -$04 20 20

PART 20 m STANDARDS FOR PROTECTION AGAINST RADIATION Append 6m D UNITED STATES NUCLEAR REGULATORY COMMtSSION INSPEC110N AND ENFORCEMENT REGION AL OFFICES Telephone Region Address Daytime $8y 4 Retoni USNRC Connecticut, Delaware, 06 strict of Co-Office of Inspect 6on and lumD6a, Maine, Marytar. ;, Mast.hu-Enforcement (215 ) 3 3 7-5 0 0 f (215)337-5000 % setts, Vtw Hampshire, New Jersey. 6 31 Park Avenue New York Pennsylvania, Rhode 15-King of Prussia Pa. 19406 land, and hermont (I t Re on 11. USN RC E (4 4)22 503 (404)2214503 M s pl rt h na Pana CanalYone Puerto Rico. South I e a t et Carolina, Tennessee, Virgenta, Virgin Suite 3100 Islands, and West Virginia Atlanta, Georg's 3 0 3 0 3 141 Region I!!, USNRC Office of Inspection and illinals, Indiana, Iowa, Michigan, M6nne-Enforcement (312) 858 2660 (312)858 2660 tota, Missourt, Ohio, and Wisconsin 799 Roosevelt Road Geen Ellyn, Ill. 60137 R lon IV, USN RC O ice of Inspection and Arkansas, Colorado, Idaho,1(ansas. Enforcement LAulslana, Montana, Nebraska, New Me xico North Dakota Oksanoma,

61) Ryan Plaza Drive (817) 334 2841 (817) 334-2841 South bkota, Texas, l%h, and Suite 1000 Arlington, Texas 76012 Wyoming V

Region V, USN RC Of fice of Inspection and Alaska, Astrona California. Hawaii. Enforcement Neva da Oregon, Washington, and U.S. eq9 0 N. California Blvd. (435) 486 3541 (4I5)486 3141 territories and possessions in the Su6t e 20 2 PaClfic Walnut Creek, Calif. 44596 S FR 42557 ' Amended di FR 55851. tAmended 43 FR 32743, $ Amended 43 FR 52201. 20/2 $05 20-21 November 10,1978}}