ML20203F869

Offers No Comments Re Review of Proposed Regulations in Parts A,D & J of Suggested State Regulations, Drafted in October 1997.Pages D-59 & D-60 of Incoming Submittal Were Not Included

ML20203F869
Person / Time
Issue date:	02/04/1998
From:	Lohaus P NRC OFFICE OF STATE PROGRAMS (OSP)
To:	Bradley C ARKANSAS, STATE OF
References
NUDOCS 9803020075
Download: ML20203F869 (116)

Text

{{#Wiki_filter:.- j.,. s J_ FEB 0 41993 Ms. Cathy Bradley, SR 2 Csair Division of Radiation Control and Emergency Management Department of Heaith 4815 West Markham Street, Slot 30 i.ittle Rock, AR 72205-3867

Dear Ms.Bradley:

As requested, we have reviewed the proposed regulations in Parts A, D, and J of the Suggested State Regulations (SSR), drafted in October 1997. The regulations were reviewed by comparison to the equivalent NRC regulations in 10 CFR Parts 19, and 20. We also discussed our review of the regulations with you on January 15,1998. As a result of our review we have no comments. Under our current procedure, a finding that an SSR regulation meets the compatibility anc health and safety categories of the equivalent NRC regulation may only be made based on a review of the final SSR regulation. However, we have determined that if the proposed regulations were adopted without significant change, they would meet the compatibility and health and safety categories established in OSP Internal Procedure B.7. We request that when the proposed regulations are adopted and published as final regulatic.as, a copy cf the "as published

• regulations be provided to us for review. As requested in our All Agreement States Letter SP-96-027, *Reauest to Hiaoliaht Chanaes to Aareement State Reaulations Submitted to NRC for Comoatibility Review" (March 1,1996), please highlight the final changes and send one copy in a computer readable format, if possible.

) if you have any questions regarding the comments or any of the NRC regulations used in the review, please contact me or Mr. Richard Blanton of my staff at (301) 415-2322, or by Internet at RLB@NRC. GOV. Sincerely, U Od0lnalSigned By: F1 PAUL H.LCHAUS [$ Paul H. Lohaus, Deputy Director

• 1 Office of State Programs lt O?

cc: Bruce Hirschler, CRCPD

)3

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• See previous concurrence.

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• 03/p//98

~ 9003020075 980204 OSP FILE CODti: SP-C-7; SP-S-13 PDR STPRQ ESG

g' l At U0p t UNITED STATES p-f } NUCLEAR REGULATORY COMMISSION g WASHINGTON, D.C. 30666-0001 o %,,g # February 4, 1998 Ms. Cathy Bradley, SR 2 Chair Division of Radiation Control and Emergency Management Department of Health 4815 West Markham Street, Slot 30 1,ltile Rock, AR 72205 3867

Dear Ms. Bradley:

As requested, we have reviewed the propocad regulations in Parts A, D, and J of the Suggested State Regulations (SSR), drafted in October 1997. The regulations were reviewed by comparison to the equivalent NRC regulations in 10 CFR Parts 19, and 20. We also discussed our review of the regulations with you on January 15,1998. As a result of our review we have no comments. Under our current procedure, a finding that an SSR regulation meets the compatibility and health and safety categories of the equivalent NRC regulation may only be made based on a review of the final SSR regulation. However, we have determined that if the proposed regulations were adopted without significant change, they would meet the compatibility and health and safety categories established in OSP Internal Procedure B.7. We request that when the proposed regulations are adopted and published as final regulations, a copy of the 'as published' regulations % provided to us for review. As requested in our All Agreement States Letter SP 96-027,"Reauest to Hiahliaht Chanaes to Aareement State Reaulations Gubmitted to NRC for Comoatibility Review" (March 1,1996), please highlight the final changes and send one copy in a computer readable format, if possible. If you have any questions regarding the comments or any of the NRC regulations used in the review, please contact me or Mr. Richard Blenton of my staff at (301) 415-2322, or by Intemet at RLB@NRC. GOV.

rely,

[ i cx w we Paul H. Lohaus, Deputy Director Office of State Programs cc: Bruce Hirschler, CRCPD

4,_ Ms. Cathy Bradley, SR 2 Chair ' Division of Radiation Control and L Emergency Management - Departmeni of Health _4815 Wet Aarkham Street, Slot 30 Little Rock, AR 72205 3867

Dear Ms.Bradley:

- As requested, we have reviewed the proposed r ulations in Parts A, D, and J of the Suggnted State Regulations (SSR), drafted in ber 1997, The regulations were reviewed by comparison to the equivalent NRC regulations i 10 CFR Parts 19, and 20. We also discussed our review of the regulations with you on anuary 15,1998, p As a result of our review we have no comments. Un r our current procedure, a finding that an L SSR regulation meets the compatibility and health a safety categories of the equivalent NRC . regulation may only be made based on a review of the nel SSR regulation. However, we have Td.ormined that if the proposed regulations were adopt without significant change, they ild meet the compatibility and health and safety cat rios established in OSP Intemal o Prmdure B.7. t We request that when the proposed regulations are adopt and published as final regulations, a copy of the "as published" regulations be provided to us f review. As requested in our All Agreement States Letter SP-96-027,"Ran=st to Hiohlicht C anoes to Aoreement State Reaulations Submitted to NRC for Comnatibility Review" (Ma h 1,1996), please highlight the final changes and send one copy in a computer readable form t, if possible, if you have any questions regarding the comments or any of the NRC regulations used in the review, please contact me or Mr. Richard Blanton of my staff at ( 01) 415-2322, or by Intemet at RLBONRC. GOV. Sincerely, 4 Paul H. Lohaus, Deputy ' rector Office of State Programs cc: Bruce Hirschler, CRCPD E Distnbution: I' DIR RF (7S257) DCD (SP02 ) - SDroggitis _ PDR (YES./._,. O ) c SSalomon CRCPD File BUsilton SSR File DOCUMENT NAME: G:\\RLB\\97S257LT.WPD y.n.enm.n=h r ceen n.enm w.new. + ww. e mm e n.ni. woe.m m m. w c.: ^ : -4 . wo em OFFICE A00)iLy -lC O(1/$( -l OGC OSP:D h l NAME-RBiaWi@sh ) PHLday l FXCameron RLBangart i DATE' - 01/fA/98 61/l /98 01/ /98 - 01/ /98 - \\ a. p -{ 'fg OSP FILE COgE:: SP-C-7;. SP-S-13

i i AGREEMENT STATE REGULATIONS REVIEW RECORD Suggested State Regulations A, D, & J; October 1997 draft I l December 1997 i l l l t

= o Rule Package: 9SR 1997 draft Parts A, D, & J Qg Definition CFR Citation State Citation Comments '[A] Restricted area 49-3 [=]

[ States should 'use definition in 20.1003] '

C Worker 19.3 [A.2] I A Absorbed dose 20.1003 [A.2] A Activity. 20.1003 [A.2] A Adult. 20.1003 [A.2] A Airbome radioactive material 20.1003 [A.2] A Airbome radioactivity area 20.1003 [A.2] A ALARA 20.1003 [A.2] A Annuallimit on intake (ALI) 20.1003 [D.3] A Background radiation 20.1003 [A.2] A Bioassay 20.1003 [A.2] [A] Byproduct material 20.1003 '=]

[ States should use definition in 150.3]

A Class 20.1003 [D.3] OR: lung class [-] OR: Inhalation class [-] A Collective dose 20.1003 [A.2] } A Committed dose equivalent 20.1'V13 [A.2] i' A Committed effective dose equivalent 20.1003 [A.2] A Declared pregnant woman 20.1003 [D.3] A Deep dose equivaient 20.1003 [A.2] .A Derived air concentration (DAC) 20.1003 [D.3] A Derived air concentration-hour (DAC-hour) 20.1003 [D.3] t A Dose equivalent 20.10C3 [A.2] A Effective dose equivalent 20.1003 [A.2] A Embryo / fetus 20.1003 [A.2] C Entrance or access point 20.1003 [A.21 A Exposure 20.1003 [A.2] A External dose 20.1003 [A.21 A Extremity 20.1003 [A.2] A Eye dose equivalent 20.1003 [A.2] A/D Generally applicable environmental radiation 20.1003 [A.2] A for 11(e).2 States standards i A High radiation area 20.1003 [A.2] 1 -t 3

nole Package: SSR 1997 draft Parts A D, & J Gigt Definition CFR Citation State Citation Comments A Individual 20.1003 [A.2] A Individual monitoring - 20.1003 [A.2] C Individual monitoring devices 20.1003 -[A.2] A Internal dose - 20.1003 [A.2] A Limits - 20.1003 [-] OR: Dose limits [A.2] B Lost or missing licerised material 20.1003 [-] OR Lost or missing source of radiation [A.2] A Member of the public 20.1003 [A.2] 3

A Minor 20.1003

[A.2] A Monitoring 20.1003 [A.2] A Nonstochastic effect 20.1003 [D.3] A Occupational dose 20.1003 [A.2]

NOTE'

[C] Person 20.1003 [=]

[ States should use definition in 150.3]

l D_ Planned special exposure 20.1003 [A.2] A Pubiic dose 20.1003 [A.2] A Quality factor 20.1003 [A.2] A Radiation 20.1003 [A.2] -A Radiation area 20.1003 [A.2] A Reference Man 20.1003 [D.3] C Respiratory protective device 20.1003 [-] OR: Respiratory protective equipment [D.3] A Restricted area 20.1003 [A.2] A Sanitary sewerage 20.1003 [D.3] A Shallow dose equivalent 20.1003 [A.2] [A]. Source material 20.1003 [=]

[ States should use definition in 150.3]

[A]. Special nuclear material 204003 [=]

[ States should use definition in 150.3]

A Otochastic effect - 20.1003 [D.3] A Surve! 20.1003 [A.2] A Total effective dose equivalent (TEDE) 20.1003 [A.2] A Unrestricted area 20.1003 [A.2] A Very high radiation area 20.1003 [D.3] l 4 p 'A Weighting factor w 20.1003 [D.3] r A Whole body 20.1003 [A.2] A Working level (WL) 20.1003 [A.2] I 2

Rule Package: SSR 1997 draft Parts A. D, & J Cat Definition CFR Citation State Citation Comments A Working level month (WLM) 20.1003 [A.2] A Year 20.1003 [A.2] [A] Agreement State BOA [=3

[ States should use definition in 150.3] -

A Alert 30.4 0 [A] Byproduct material BOA [=]

[ States should use definition in 150.3]

[A] Curie 304 [=]

[ States should use definition in 20.1005]

C Decommission 30.4 0 l [A] Effective dose equivalent 304 [A.2]

[ States should use definition in 20.1003]

[C] Medical use 304 0

[ States should use definition in 35.2]

[C] Pe. son 30A [=]

[ States should use definition in 150.3]

[NRC] Production facility 30-4 [X]

[ States should use definition in 150.3]

[C] Radiographer BOA D

[ States should use definition in 34.2]

[B] Radiography 304 0

[ States should use definition in 34.2]

B Sealed source 50.4 [A.2]

NOTE 2 A

Site area emergency 30.4 0 [A] Source material 30-4 0

[ States should use definition in 150.3]

[A] Special nuclear material 30-4 0

[ States should use definition in 150.3]

[NRC] Utilization facility 304 [X]

[ States should use definition in 150.3]

i [A] Dose commitment 32-2 0

[ States should use definition of " committed dose equivalent"in 23.1003 ]

B Lot tolerance percent defective 32.2 0 l t I C Radiographer 34.2 0 B Radiographic exposure device 39.2 0 B Radiography (industrial radiography) 34.2 0 t [A] Sealed source 34-2 0

[ States should use definition in 30.4]

B Source changer 34.2 0 B Storage container 34.2 0 [A] ALARA 35-2 [-]

[ States should use definition in 20.1003]

t 3

Rule Package: SSR 1997 draft Parts A, D, & J Cat Definition CFR Citation State Citation Comments [B] Agreement State 35-2 [-]

[ States should use definition in 150.3]

G Authorized user 35.2 0 C Medical use 35.2 0 C Misadministration 35.2 0 C Prescribed dosage 35.1 0 C Prescribed dose 35.2 0 [B] Sealed source 35-2 0

[ States should use definition in 30.4]

C Written directive 35.2 D C frradiator 36.2 0 [B] Sealed source 36-2 D

[ States should use definition in 30.4]

L B Field station 39.2 0 C Logging supervisor 39.2 0 [B] Sealed source 39-2 0

[ States should use definition in 30.4]

C. Welllogging 39.2 0 [B] Agreement State 404 [-]

[ States should use definition in 150.3]

[A] Wrt. 40A D

[ States should use definition in 30.4]

[A] Byproduct material 40A 0

[ States should use definition in 150.3]

i [C] Decommission 404 0

[ States should use definition in 30.4]

A' Depleted uranium 40.4 [A.2] [C] Person 40A D

[ States should use definition in 150.3]

A/D Residual radioactive material 40.4 []

A for 11(e).2 States

[A] Site aree emergency 40-4 0

[ States should use definition in 30.4]

[A] Source material 40A []

[ States should use definition in 150.3]

[A] Special nuclear material 40A 0

[ States should use definition in 150.3]

B Unrefined and unprocessed ore 40.4 [A2] C/D Uranium milling 40.4 [A.2]

C for 11(e).2 States NOTE 8 D

Active maintenance 61.2 0

H&S 4

4

Rule Package: SSR 1997 draft Parts A, D, & J Cat Definition CFR Citation State Citation Comments C Disposal 61.2 [] C _ Disposal site 61.2 0 C Hazardous waste 61.2 0 C Inadvertent intruder 61.2 0 C Intruder barrier 61.2 0 C Monitoring 61.2 0 1 B . Waste 61.2 [A.2] 1 [B] Agreement State 70-4 [-]

[ States should use definition in 150.3]

[A] Alert 70-4 0

[ States should use definition in 30.4]

[C] Decommission 70-4 0

[ States should use definition in 30.4]

[A] Effective dose equivalent 70-4 0

[ States should use definition in 20.1003]

[C] Person - 70-4 0

[ States should use definition in 150.3]

[B] Sealed source 7 O-4 0

[ States should use definition in 30.4]

[A] Site area emergency 70-4 0

[ States should use definition in 30.4]

[A] Source material 70-4 0

[ States should use definition in 150.3]

[A] Special nuclear material 70-4 0

[ States should use definition in 150.3]

'NRC Special nuclear material of low strategic 70.4 [X] significar:/ NRC Strategic special nuclear material 70.4 [X] NRC Transient shipment 70.4 [X] NRC Unites States 70.4 [X] { NRC Uranium enrichment facility 70.4 [X] B A,A 71.4 [A.2] i 2 B Carrier 71.4 0 B Certificate holder 71.4 0 NRC Close reflection by water 71.4 [X] B Containment system 71.4 [] B Conveyance 71.4 0 B Exclusive use 71.4 0 B Fissile material 71.4 [] B Licensed malenal -71.4 0

D in 20.1003 5

1 Rule Package: SSR 1997 draft Parts A, D, & J . Cat Definition CFR Citation State Citation Comments B Low specific activity material 71.4 0 B Low toxicity alpha emitters 71.4 0 B Maximum normal operating pressure 71.4 0 B Naturalthorium 71.4 [] B Normal form radioactive material 71.4 0 NRC Optimum interspersed hydrogenous moderation 71.4 [X] B ' Package 71.4 [A.2] B Fissile material package 71.4 0 B Packaging 71.4 0 1' B Special form radioactive material 71.4 [A.2] B Specific activity ' 71.4 0 B Surface contaminated object (SCO) 71.4 0 B Transport index 71.4 0 B Type A quantity 71.4 [] B Type B quantity 71.4 0 B Natural uranium 71.4 [] B Depleted uranium 71.4 [] B Enriched uranium 71.4 0 l B Agreement state 150.3 [A.2] A Byproduct material 150.3 [A.2] B Offshore waters 150.3 0 C Person 150.3 [A.2] NRC Production facility 150.3 [X] A Source material 150.3 0 A Special nuclear material 150.3 [A.2] NRC Uranium enrichment facility 150.3 [X] NRC Utilization facility 150.3 [X] b 6 P

Rule Package: SSR 1997 draft Parts A. D, & J Category'and ' CFR citation Rule subject State citation Comments 10 CFR Part 19 NOTICES, INSTRUCTIONS AND REPORTS TO WORKERS: INSPECTION AND INVESTIGATION 19.3 Definitions [see list] C 19.11 Posting of notices to workers [J.11]

NOTE' C 19.12 Instructions to workers

[J.12]

NOTE 5 C 19.13 Notifications and reports to individuals

[J.13] C 19.14 Presence of representatives of licensee and [J.14] workers during inspections C 19.15 Consultation with workers during inspections [J.15] C 19.16 Requests by workers forinspection [J.16] C 19.17 Inspections not warranted; informal review [J.17] C 19.18 Sequestration of witnesses and exclusion of [-NONE-]

NOTE' counsel in interviews conducted under subpoena 10 CFR Part 20 STANDARDS FOR PROTECTION AGAINST RADIATION

- 20.1003 Definitions [see list] A 20.1004 Units of radiation dose [A.13] A 20.1005 Units of radioactivity [A.14] ( H&S 20.1101 Radiation protection programs [D.101] A 20.1201 Occupational drie limits for adults [D.201] 7 l 1 l

Rule Package: SSR 1997 draft Parts A, D, & J Category and CFR citation Rule subject State citation Comments A 20.1202 Compliance with requirements for summation [D.202] of extemal and intomal doses A 20.1203 Determination of extemal dose from airbome [D.203] radioactive mater al A 20.1204 Determination of intemal exposure [D.204] D 20.1206 Planned special exposures [D.206]

definition,20.2104, and 20.2202(e) become C if this rule is adopted A 20.1207 Occupational dose limits for minors

[D.207] A 20.1208 Dose to embryo / fetus [D.208] A 20.1301(a), Dose limits for individual members of the public [D.301] (b), (c), and (e) H&S 20.1302(a, b) Compliance with dose limits for individual [D.302] members of the public H&S 20.1501 Surveys and monitoring - general [D.501] H&S 20.1502 Conditions requiring individual monitoring of [D.502] extemal and intemal occupational dose H&S 20.1601 Control of access to high radiation areas [D.601] H&S 20.1602 Control of access to very high radiation areas [D.602] H&S 20.1701 Use of process or other engineering controls [D.701] H&S 20.1702 Use of other controls [D.702] 8

C ~ Rule Package: SSR 1997 draft Parts A. D, & J Category and CFR citation Rule subject State citatx>n Comments H&S ' 20.1703 Use of individual respiratory protectbn [D.703] equipment H&S 20.1801 Security of stored sources of radiation [D.801] i H&S 20.1802 - Control of material not in storage [D.801] A 20.1901 Caution signs [D.901] A ' 20.1902 Posting requirements [D.902] A 20.1904 Labeling containers [D.904] A 20.1905 . Exceptions to labeling requirements [D.905] H&S 20.1906 Procedures for receiving and opening packages [D.906] C 20.2001 Waste disposal - general requirements [D.1001] A 20.2003(a)(2), Disposal by release into sanitary sewerage [D.1003a.ii, a.iii) : (a)(3) H&S 20.2003(a)(1) Disposal by release into sanitary sewerage [D.1003a.i] C 20.2003(a)(4) Disposal by release into sanitary sewerage [D.1003a.iv) B 20.2006 Transfer for disposal and manifests [D.1006] i C 20.2101 Records-general provisions [D.1101] D 20.2104 Determination of prior occupational dose [D.205]

C if 20.1206 is adopted C. 20.2106 (a),

Records of individual monitoring results [D.1107a, d] (e) 9

Rule Package: SSR 1997 draft Parts A D.'& J ' Category and - CFR cdabon Rule subpH:t State citabon fdnDents 7, C ' 20.2201 Reports of Stolen Lost,' or Missing Licensed or [D.1201] (except c) Registered Sources of Radiation .C : 20.2202 Notification of incxients - [D.1202]

includes (e)if 20.1206 is adopted (except e)

C 20.2203(a), (b) - Reports of Exposures, Radiation Levels, and [D.1203] Conceduaikts of Radioactrve Material Exceeding the Limits NRC 20.2203(c) Reports of Exposures, Radiation Levels, and [X] Concentrations of Radicactive Material Exceeding the Limits I D 20.2204. [D.1204]

C if 20.1206 is adopted l

Reports of Planned Special Exposures C 20.2205 Reports to individuals of exceeding dose limits [D.1205] .j C. 20 Appendix A Protection Factors for Respirators [D App A) -g A. 20 Appendix B All's and DAC's; effluent concentrations; [D App B] concentrations for release to sewerage 'A 20 Appendix C Quantities of licensed mMerial requiring labeling [D App C] { States may. adopt Appendix F or Appendix G until 3f01/98, by wtuch a5 must adopt Appendix G} 'B 20 Appendix F LLW transfer for disposal and manifests [D App E] B -20 Appendix G Requirements for transfer of LLW for disposal. [D App G] uniform manifests i 'l 10 i

y -

Notes and Comments:

1. NOTEi Definsbons "Occupabonal dose

• and *pubhc dose"- add comma after
• received
• in new text.

2. NOTE ' Definsbon " Sealed source"- CFR 5perJc6 a " capsule

• wheie SSR speedies a " container. : Both defirubons requre the -

structure to gne.e.a the escape of material. It is determined that the definsbons are consistent. 3 L'

3. NOTE. Definsbon "Uraneum milling"- SSR defines " source matenal milling

• but the defir.itsons are the same. The defirubons are i

determined to be consistent. i, ' 4. NOTE: J.11d [equevalent to 19.11(e)] allows five worlung days, rather than two, for poshng of nobces of violabon. This di5erence is determined to be an 'admenestrative matter with no health and safety or compabbehty impiscahons, and is consistent with the competitwhty category "C" classdichbon. l

5. NOTE-J.12a.ii [ equivalent to 19.12(a)(2)] is more specdic with respect to the health protechon problems to be discussed.1 This '

g~ ' ddlerence is consistent with the compatibihty category "C" classificabon. ii

6. NOTE 10 CFR 19.18 [no SSR equivalent] addresses an administrative matter between the NRC and it's hcensees, the absence

'l of wtuch from Ayee.Tmid State proyerns does not ueste a conflict or gap. This sechon shouid be rWiad as"D." [ 4

i.

i l O t { t 11 - t r + l ,-_l,. '..O.1 -,f,. v

e u- =n EXECUTIVE TASK MANAGEMENT SYSTEM ~~~~~~ <<< PRIFT SCREEN UPDATE FORM >>> TASK #. - 7S257 5 DATE-10/01/97 EEEEEEEEEEE MAIL (TPL. - 1997 TASK STARTED - 10/01/97 TASK DUE - 11/30/97 TASK COMPLETED - / / TASK DESCRIPTION - REVIEW OF REVISED PARTS A, D AND J FROM SUGGESTED STATE REGULATIONS CRCPD REQUESTER - J. DAV'DSON WITS - 0 FYP - N REQUESTING SFF. a ~~........... PROG.- RLB PERSON - STAFF LEAD - RLB PROG. AREA - PROJECT STATUS - CRCPD DUE DATE: 11/30/97 PLANNED ACC. -N LEVEL CODE - 1

Suggested State. Regulations - Croup 2 of the Conference of Radiation Control Program Directors,'Inc. ~ A Partnership Dedicated to Radiation Protection MEMORANDUM enq TO:: Program Directors 9 a (n Agreement States -v v (y% Q iL x FROM: Joyce Davidson f Former Chair, SR-2 O a DATEt September 23,1997 RE: Peer review for revised Parts A, D & J As approvo by the Board of Directors of CRCPD, I would like to submit these revised versions of Par's A, D and J to all of the Program Directors in each of the agreement statca for peer review. The committee chose this group of reviewers c'ue to the particular relevance of these Parts ta the agreement states. Due to my new position within the Nebraska Department of llealth and Human Services, I will no longer be the chair of SR-2. All comments pertinent to any of these parts may be sent to Bruce Hirschler at the Office of the Executive Director: Bmcc Hirschler CRCPD 2-)5 Capital Ave. Frankfort, KY 40601 L Fax: (502) 227-7862 e-mail: Dhirschler@Aol.com Comments wH! be forwarded to the new committee chair once they are installed. We ask that all comments be forwarded in the next 30 days. I have enjoyed werking with all of you. cc: Chuck Hardin - Executive Director, CRCPD Paul Lohaus Deputy Director, NRC Office of the Committee Chairperson - Joyce Davidson Nebrasko HMS Regulation and Licensure e Regulatory Analysis and integration .O. Bos 95007. Lincoln, Nebraska 68509 5007 Telephone: 402/4710173. Fox: 402/471 -0820. E-mail: doh4139@vrnhost. cdp. state.ne.us

.%RC'R l'olumei. 7 25 97:-N: Dra)1 l - &A AA A.2 PART A GENERAL PROVISIONS Sec. A.1 Scope Except as otherw se specifically provided, these regulations apply to all persons aho receive, possess, use, transfer, e an, or acquire any source of radiation, provided, however, that nothirg in thes'e regulations shall apply to any person to the extent such person is subject to regulation by the Nuclear Regulatory Commission.1 Sec, A 2 - Definitions As used in these regulations, these teims have the definitions set forth below. Additional definitions used only in a certain part will be found in that part. >Ai means the maximum activity of special form radioactive material permitted in a Type A package. ,/A " means the maximum activity of radioactive material, other than special form radioactive material, pumitted in a Type A package. These values are either listed in Appendix A of Part T of these regulations, Table I, or may be derived in accordance with the procedure prescribed in Appendix A of 1Part T of these regulations. f" Absorbed dose" means the energy imparted by ionizing radiation per unit mass ofirradiated material. The units of absorbed dose are the gray (Gy) and the rad. " Accelerator" means any machine capable of accelerating electrons, protons, deuterons, or other charged particles in a vacuum and of discharging the resultant partic ilate or other radiation into a medium at e.ergies usually in excess of 1 MeV. For purposes of this definition, " particle accelerator" is an equivalent term. " Accelerator produced material" means any material made radioactive by a particle accelerator. . Act" means (cite State Radiation Control Act]. " Activity" means the rate of disintegration or transformation or decay of radioactive material. The units of activity are the becquerel (Bq) and the curie (Ci). r '" Adult" means an individual 18 or more years of age. " Agency" means (cite appropriate State agency] EAttention is directed to thefact that regulanen by the State ofsource matenal, byproduct material. coulspecialnuclear n'aterial in quartaies not sufcient tuform a enticalmass ts subject to the provnions of the agreen,ent between the State and the Nuclear Regulatory Commu sion <nni to IIH TR Part 130 cfthe l'ommnsion's regulanons. i l l . A l -l .-=

.%RCR INume I. September 1993 sec, A.2 / Agreement State" means any State with which the Nuclear Regulatory Commission or the Atomic Energy Commission has entered into an efTective agreement undei subsection 274b. of the Atomic Energy Act of 1954, as amended (73 Stat. 689). " Airborne radioactive material" means any radioactive material dispersed in the air in the form of dusts, g fumes, particulates, mists, vapors, or gases. g" Air orne radioactivity area" means a room, enclosure, or area in which airborne radioactive materials exist in concentrations: (1) In excess of the derived air concentrations (DACs) specified in Appendix B. Table 1 of Part D of these regulations or (2) To such a degree that an individual present in the area without respiratory protective equipment could exceed, during the hours an individual is present in a week, an intake of 0.6 percent of the annual limit on intake (All) or 12 DAC-hours. "As low as is reasonably achievable" (ALARA) means making every reasonable effon to maintain exposure to radiation as far below the dose limits in these regulations as is practical, consistent with the purpose for which the licensed or registered activity is undertaken, taking into account the state of technology, the economics ofimprovements in relation to state of technology, the economics of improvements in relation to benefits to the public health and safety, and other societal and socioeconomic considerations, and in relation to utilization of nuclear energy and licensed cr registered sources of radiation in the pub % interest. B'ackground radiation" means radiation from cosmic sources; naturally occurring radioactive materials, including radon, except as a decay product of source or special nuclear material, and including global fallout as it exists in the environment from the testing of nuclear explosive devices. " Background radiation" dces not include sources of radiation from radioactive materials regulated by the Agency. " Becquerel" (Bq) means the SI unit of activity. One becquerel is eqt.al to 1 disintegration or transformation per second (dps or tps). " Bioassay" means the determination of kinds, quantities or concentrations, and, in some cases, the locations of radioactive material in the human body, whether by direct measurement, in vivo counting, or by analysis and evaluation of materials excreted or removed from the human body. For purposes of these regulations, "radiobioassay" is an equivalent term. " Brachytherapy" means a method of radiation therapy in which sealed sources are utilized to deliver a radiation dose at a distance of up to a few centimeters, by surface, intracavitary, or interstitial application. " Byproduct material" means: (1) Any radioactive material, except special nuclear material, yielded in or made radioactive by exposure to the radiation incident to the process of producing or utilizing special nuclear matenal; and A22

8x A 2 SSRCR l'olume I. 2.2LglNW Drap l (2) The tailings or wastes prod. iced by the extraction or concentration of uranium or thorium from ore processed primarily for its source materia! content, including discrete surface wastes resulting from uranium or thorium solution extraction processes. Underground ore bodies depleted by these solution extraction operations do not constitute " byproduct niaterial" within this defmition. " Calendar quarter" mees not less than 12 consecutive weeks nor more than 14 consecutive weeks. The first calendar quarter of each year shall begin in January and subsequent calendar quarters shall be so arranged such that no day is inmiude 1 in more than one calendar quarter and no day in any one year is omitted from inclusion within a cAndar quarter. The method observed by the licensee or registrant for determining calendar quarters shall only be changed at the beginning of a year. " Calibration" means the determination of(l) the response or reading of an instrument relative to a series of known radiation values over the range of the instrument, or (2) the strength of a source of radiation relative to a standard L "CFR" means Code of Federal Regulations.

• Chelating agent" means amine polycarboxylic acids, hydroxycarboxylic acids, gluconic acid, and polycarboxylic acids.

" Collective dose" means the sum of the individual doses received in a given period of time by a specified population from exposure to a spechd source of radiation. " Committed dose equivalent" (lir.3o) means the dose equivalent to organs or tissues of reference (T) that will be receised from an intake of radioactive material by an individual during the 50-year period following the intake. " Committed effective cose equivalent" (fin 3o) is the sum of the products of the weighting factors (wr) applicable to each of the body organs or tissues that are irradiated and the committed dose equivalent to each of these organs or tissues (11uo = Ew lir.30). r " Curie" means a unit of quantity of activity. One curie (Ci) is that quantity of radioactive material which decays at the rate of 3.7E+10 disintegrations or transformations per second (dps or tps). _ " Deep dose equivalent" (lla), which applies to external whole body exposure, raeans the dose equivalent 2 at a tissue depth of I centimeter (1000 mg/cm ). "Dshieted uranium" means the source material uranium in which the isotope uranium-235 is less than 0.711 weight percent of the total uranium present. Depleted u.anium does not include special nuclear material. " Dose" is a generic term that means absorbed dose, dose equivalent, effective dose equivalent, committed dose equivalent, committed efTective dose equivalent, total organ dose equivalent, or total effective dose equivalent. For purposes of these regulatians, " radiation dose" is an equivalent term. A33 ___________-__________-___________________m

ssncR relume t. unnam /> raft sec. A.3 l Dose equivalent (Il )" means the product of the absorbed dose in tissue, quality factor, and a'l other i necessary modifying factors at the location ofintuest. The units of dose equivalent are the sievert (SV) and rem. ," Dose limits" means the permissible upper bounds of radiation doses established in accordance with these regulations. For purposes of these regulations, " limits" is an equivalent t-rn. " Effective dose equivalent (lit)" means the sum of the products of the dose equivalent to each organ or tissue (111) and the weighting factor (w ) applicable to each of the body organs or tisues that are r irradiated (lit = E w,1b) l " Embryo / fetus" means the developing human organism from conception until the time of birth. " Entrance or access point" means any opening through which an individual or extremity of an individual could gain access to radiation areas or to licensed or registered radioactive Inaterials. This includes entry or exit portals of suflicient size to permit human entry, irrespective of their ii. tended use. " Explosive material" means any chemical compound, mixture, or device which produces a substantial instantaneous release of gas and heat spontaneously or by contact with sparks or flame. " Exposure" means being exposed to ionizing radiation or to radioactive material. "Sposure" means the quotient of dQ by dm where "dQ" is the absolute value of the total charge of the ions of one sign produced in air when all the electrons (negatrons and positrons) liberated by photons in a volume element of air having mass "dm" are completely stopped in air. The SI unit of.npmuls is the coulomb per kilogram (C/kg) See A.13 Units of Exposure and Dose for the special unit? "Spgsu_r_c rate" means the caposure per unit of time, such as roentgen per minute and milliroentgen per hour. " External dose" means that portion of the dose equivalent received from any source of radiation outside the body. " Extremity" means hand, cibow, arm below the elbow, foot, knee, and leg below the knee. ', Eye dose equivalent" means the external dose equivalent to the lens of the eye at a tissue depth o centimeter (300 mg/cm') TStates may wish to desimpuish thronghout their regulations, and to include afootnote here specthing a shstmetion, between the Intern,awnalCommissmn on khatwn I ' nits wtJMeasurentenu definitwn ofexposure and the generaluse ofexposure. The footnote conkt be sinnlar to thefollowmg: 'llhen not mulerbned as above lor inshcoted as ' exposure'(X)]. the term ' exposure' has a more general mewung in these regnhatons.

• A44

SSRCR IWaarI. 22&fyMN Draft l Sec. h2 " Eye dose equivaleni" means the external dose equivalent to the lens of the eye at a tissue depth of 0.3 centimeter (300 mg/cm'). "Former Atomic Energy Commission or Nuclear Regulatory Commission licensed facilities" means nuclear reactors, nuclear fuel reprocessing plants, uranium enrichment plants, or critical mass expenmental facilities where Atomic Energy Commission or Nuclear Regulatory Commission licenses have been terminated. ZGenerally applicable environmental radiation standards" means standards issued by the Environmental Protection Agency under the authority of the Atomic Energy Act of 1954, as amended, that impose limits on radiation exposures or levels, or concentrations or quantities of radwactive material, in the general environment outside the boundasies oflocations under the control of persons possessing or using radioactive material. Gray" (Gy) means the SI unit of absorbed dose. One gray is equal to an absorbed dose of 1 joule per kilogram (100 rad). "llazardous waste" means those wastes designated as hazardous by the Environmental Protection Agency segulations in 40 CFR Part 26!. "licating arts" means (cite appropriate State definition]. "lligh radiation area" means an area, accessible to indisiduals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 1 mSv (0.1 rem)in 1 hour at 30 centimeters from any source of radiation or from any surface that the radiation penetrates. "lluman use" means the internal or external administration of radiation or radioactive material to human beings. . " Individual" means any human t,eing. ~ r ," Individual monitoring" means the assessment o (1) Dose equivalent (a) by the use ofindividual monitoring devices or (b) by the use of survey data; or (2) Committed efTective dose equivalent (a) by bioassay or (b) by determination of the time-weighted air concentrations to which an individual has been exposed, that is, DAC-hours. [See the definition of DAC-hours in Part D.] " Individual monitoring devices" means devices designed to be worn by a single individual for the m assessment of dose equivalent. For purposes of these regulations, " personnel dosimeter" and " dosimeter" are equivalent terms. Exampks ofindividual monitoring devices are film badges, thermoluminescent dosimeters (TLDs), pocket ionization chambers, and personal air sampiing devices. A55 5

MRCRIWumeI ULypno?Drqft sec.A3 l " Inspection" means an cilicial examination or observation including, but not limited to, tests, surveys, and monitoring to determine compliance with rules, regulations, orders, requirements, and conditions of the Agency. " Instrument traceabil.ty" (for ionizing radiation measurements) means the ability to show that an instrument has been calibrated at specified time intervals using a national standard or a transfer standard. if a transfer standard is used, the calibration must be at a laboratory accredited by a program which requires continuing participation in measurement quality assurance with the National Institute of Standards and Technology or other equivalent national or international program. " Interlock" means a device arranged or connected such that the occurrence of an event or condition is required before a second event or condition can occur or continue to occur. " Internal dose" means that portion of the dose equivalent received from radioactive material taken into the body. " License" means a license issued by the Agency in accordance with the regulations adopted by the Agency. " Licensed [or registered] material" means radioactive material received, possessed, used, transferred or disposed of under a general or specific license [or registration] issued by the Agency. " Licensee" means any person who is licensed by the Agency in accordance with these regulations and the Act. " Licensing State" means any Sstate which.has.been.prarisionallyar_fmally designated.as suchtsthe Conference of Radiatic.n Control Program Directors. Inc whichfeyienstate regulations _to_ establish equivalency with the Suggested State Regulations and ascertains whether a State has an effective PI98tantfor_c00t rol ofBat ural _occutting.or.Ac.ccletatolpr.oduc.edladioac.tive_ma.ter.ialINABMLIhe Conference willdesignate_as. licensing States those statetwith.t.egulations foLcontrsLof.radiatica relating to, and an etTective prograni for..the regulatory. control _of NARM with4egulations-equivalenHo the4uggestedetate-Regulations-for-Gontrobof-Madiation+ elating-to-and-en-e!Teetive-program-for the r r egulatory-controbof-N A RM-and-which-has-been-granted-firiaWesignatioreby-t he-Gonferenc+of Radiation GontrobProgram-Directorsrine- " Limits" (See " Dose limits"]. . " Lost or missing source of radiation" means licensed [or registered] source of radiation whose location is t nknown. This defmition includes, but is not limited to, radioactive material that has been shipped but has not reached its planned destination and whose location cannot be readily traced in the transportation system. " Major processor" means a user processing, handling, or manufacturing radioactive material exceeding Type A quantities as unsealed sources or material, or exceeding 4 times Type B quantities as scaled sources, but does not include nuclear medicine programs, universities, industrial radiographers, or small i industrial programs. Type A and B quantities are defmed in T.2 of these regulatio - 1 A66

l SSRCR l'oluae I. l21234W Draft l sec. A : 1 " Member of the public" means an individual except when that individual is receiving an occupational ' dose. " Minor" means an individualless than 18 years of age, " Monitoring" means the measurement of radiation, radioactive material concentrations, surface area activities or quantities of radioactive material and the;n.e of the results of these measurements to evaluate potential exposures and doses. For purposes of these regulations, " radiation monitoring" and " radiation protection monitoring" are equivalent terms. "NARM" means any naturally occurring or accelerator-produced radioactive material. It does not include byproduct, source, or special nuclear material? " Natural radioactivity" means radioactivity of naturally occurring nuclides? " Nuclear Regulatory Commission" means the Nuclear Regulatory Commission or its duly authorized repic: ntatives. ,/ Occupational dose" means the dose received by an individual in the course of employment in which the individual's assigned duties for the licensee or registrant involve exposure to sources of radiation, whether or not the sources of radiation are in the possession of the licensee, registrant, or other person. Occupational dose does not include doses receivedt from background radiation, or-as# patient-from medicalpacticesror from any medical administration the individual.has received from voluntary participation in medical research programs, or as a member of the public. " Package" means the packaging together with its radioactive contents as presented for transport. " Particle accelerator" [See " Accelerator"). " Person" means any individual, corporation, partnership, firm, association, trust, estate, public or private institution, group, agency, political subdivision of this State, any other State or political subdivision or ager.cy thereof, and any legal successor, representative, agent, or agency of the foregoing (, but shall not include federal government agencies] " Personnel monitoring equipment" [See " Individual monitoring devices"]. " Pharmacist" means [an individual licensed by this State to compound and dispense drugs, prescriptions, and poisons or cite appropriate State defmition]. " Physician" means [ cite appropriate State defmition].

• Forpurposes ofmeetmg the deputwn ofa Licerning State by the Conference ofRahation Control Program Directors, Inc.,

MtRAI refers only to discrete sources of.V1RAl. Diffisse sources ofXtRAIare excludedfrom consideration by the Conference of Rahation Control Program Detectors, Inc.for Licensing State designation purposes. A77 i

.WRCR Ibice1 22Ly17 2MIDm/t Sec. A3 l

• Protective apron" means an apron maue of radiation-attenuating materials used to reduce exposure to radiation.

"Public dose" means the dose received by a member of the public from sources of radiatioa from licensed f or registered operations Public dose does not incluJe occupational dose, or doses received from background radiation, from any medical, administration the individual haucceived or4ose4eceiden patient-from-medicdptacticescer-dose 4eceived from voluntary participation in medical research programs. "Pyrophoric material" means any liquid that ignites spontaneously in dry or moist air at or below 130 EF (54.4 EC) or any solid material, other than one classed as an explosive, which under normal conditions is liable to cause Gres through friction, retained heat from manufacturing or processing, or which can be ignited readily and, when ignited, burns so vigorously and persistently as to create a serious transportation, handling, or disposal hazard. Included are spontaneously combustible and water-reactive materials. [" Qualified expert" means an individual having the knowMdge and training to measure ionizing radiation, to evaluate safety techniques, and to advise regarding radiation protection needs, for e. ample, individuals certified in the appropriate field by the American Board cf Radiology, or the American Board of Health Physics, or the American Board of Mecical Physics, or those having equivalent qualifications. With reference to the calibration of radiation therapy equipment, an individual having, in addition to the above qualifications, training and experience in the clinical applications of radiation physics to radiation therapy, for example, individuals certined in Therapeutic Radiological Physics or X-Ray and Radium Physics by the American Board of Radiology, or those having equivalent qualifications.] " Quality factor" (Q) means the modifying factor, listed in Tables 1 and 11 of A.13, that is used to derive " dose equivalent from absorbed dose. " Rad" means the special unit of absorbed dose. One rad is equal to un absorbed dose of 100 erg per gram /or 0.01 joule per kilogram (0.01 gray). " Radiation" means alpha particles, beta particles, gamma rays, x rays, neutrons, high speed electrons, high speed protons, and other particles capable of producing ions. For purposes of these regulations, ionizing radiation is an equivalent term Radiation, as used in these regulations, does not include non-ionizing radiation. such as radiowaves or microwaves, visible, infrared, or ultraviolet light. , Rsdiation area" means any area, accessible to individuals, in which radiation levels could result in an individual receiving a dose equivalent in excess of 0.05 mSv (0.005 rem) in I hour at 30 centimeters from the source of radiation or from any surface that the radiation penetrates. " Radiation do;e" [See " Dose"). " Radiation machine" means any device capable of producing radiation except, those devices with radioactive material as the only source of radiation. A88

Sec. A.3 SSRCR l'olume i. 2D.22Mk91 Drap l " Radiation safety officer" means an individuu who has the knowledge and responsibility to apply appropriate radiation protection regulations rad.has_heen. assigned such tdponsibility by the_litenste or tegistrant. " Radioactive material" means any solid, liquid, or gas which emits radiation spontaneously. " Radioactivity" means the transformation of unstable atomic nuclei by the emission of radiation. "Radiobioassay" [See " Bioassay"J. " Registrant" means any person who is registered with the Agency and is legally obligated to register with the Agency pursuant to these regu!ations anJ the Act. " Registration" means registration with the Agency in accordance with the regulations adopted by the Agency. " Regulations of the Department of Transportation" means the regulations in 49 CFR Parts 100-189. " Rem" means the special unit of any of the quantities expressed as dose equivalent. The dose equivalent in rem is equal to the absorbed dose in rad multiplied by the quality factor (I rem = 0.01 Sv). "Research and development" means (1) theoretical analysis, exploration, or experimentation or (2) the extension ofinvestigative findings and theories of a scientific or technical nature into practical application for experimental and demonstration purposes, including the experimental production and testing cf models, devices, equipment, materials, and processes. Research and devekpment does not include the internal or external administration of radiation or radioactive material to human beings. " Restricted area" means an area, access to which is limited by the licensee or registrant for the purpose of protecting individuals against undue risks from exposure to sources of radiation. Restricted area does not melude areas used as resMential quarters, but separate rooms in a residential building may be set apart as ~ a restricted area. " Roentgen" means the special unit of exposure. One roentgen (R) equals 2.58E.4 coulombs per kilogram of air (see " Exposure'.nd A.13)

3. " Sealed source" means any containes of radioactive material which has been cNstructed in such a manner as to prevent the escape of any radioactive material.

" Shallow dose equivalent" (11,), which applies to the external exposure of the skin or an extremity, means 2 the dose equivalent at a tissue depth of 0.007 centimeter (7 mg/cm ) averaged over an area of I square centimeter. "SI" means the abbreviation for the International System of Units. A99

.L SWu'R l'ohmeI UUy.i.s nthap see A.2 l " Sievert" means the Si unit of any of the quantities expre; sed as dcse equivalent. The dose equivalent in- - sievert is equal to the absorbed dose in gray multiplied by the quality factor (1 Sv = 100 rem). " Source material" means: f (1) - Uranium or thorium, or any combination thereof, in any physical or chemical form; or -(2) Orcs that contain by weight one-twentieth of 1 percent (0.05 percent) or more of uranium, thorit.m or any combination of uranium and thorium. Source material does not include' special nuclear material. l JSource material milling" means any activity that results in the production of byproduci material as . ' defined by definition (2) of byproduct material. " Source of radiation" means any radioactive material or any device or equipment emitting, or capable of producing, radiation. " Source traceability" means the ability to show that a radioactive source has been calibrated either by the national standards laboratory of the National Institute of Standards and Technology, or by a laboratory which participates in a continuing measurement quality assurance program with National Institute of Standards and Technology or other equivalent national or international program. ] "Special form radioactive material" means radioactive material that satisfies the following conditions: 7 (1) It is either a single solid piece or is contained in a seM capsule that can be opened only by destroying the capsule; (2) The piece or capsule has at least one dimension not less than 5 millimeters (0.2 inch); and l (3) It satisfies the test requirements specified by the Nuclear Regulatory Commission. A special form encapsulation designed in accordance with the Nuclear Regulatory Commission requirements in effect on June 30,1983, and constructed prior to July 1, l j 1985, may continue to be used. A special form encapsulation either designed or constructed aller June 30,1985, must meet requirements of this definition applicable at . the time ofits design or construction, "Special nuclear materia!" means: (1)

Plutonium, uranium-233, uranium enriched in the isotope 233 or in the isotope 235, and any other material that [the Agency declares by order to be special nuclear material aller)5 the Nuclear Regulatory Commission, pursuant to the provisions of section 51 of

- the Atomic Energy Act of 1954, as amended, determines to be special nuclear material, but does not include source material; or NThis wordmg n providedfor states that carmor automatically alopt changes made by the Nuclear Regulatory Commission. A10M

Sw A2 SSRCR INume I. Z@2ZZ.#91 Draft l the Atunic Energy Act of 1954, as amended, determines to be special nuclear material, but does not include source material, or (2) Any material artificially enriched by any of the foregoing but does not include source material. "Special nuclear material in quantities not sutTicient to form a critical mass" means uranium enriched in the isotope U-235 in quantities not exceeding 350 grams of contained U-235; uranium-233 in quantities not exceeding 200 grams, platonium in quantities not exceeding 200 grams; or any combination of them in accordance with the following formula: For s ich kind of special nuclear material, octermine the ratio between the quantity of that special nuclear material and the quantity specified above for the same kind of special nuclear material. The sum of such ratios for all of the kinds of special nucicar material in combination shall not exceed 1. For example, the following quantities in combination o ad not exceed the limitation and are within the formula: 175 (grams contained U-235),50 (grams U-233),50 (grams Pu) g 350 200 200 " Survey" means an evaluation of the radiological conditions and potential hazards incident to the producticn, use, transfer, release, disposal, or presence of sources of radiation. When appropriate, such evaluation includes, but is not limited to, tests, physical examinations, and measurements oflevels of radiation or concentrations of radioactive material present. " Test" means the process of verifying compliance with an applicable regulation. "These regulations" mean all parts of[ cite appropriate rules or regulations). " Total etTective dose equivalent" (TEDE) means the sum of the deep dose equivalent for external exposures and the committed etTective dose equivalent for internal exposures. " Total organ dose equivalent" (TODE) means the sum of the deep dose equivalent and the committed dose equivalent to the organ receiving the highest Jose as described in D.1107a.vi. of these regulations. " Traceable to a National Standard" (See " Instrument traceability" or " Source traceability"]. " Department of Energy" means the Department of Energy established by Public Law 95-91, August 4, 1977,91 Stat. 565,42 U.S.C. 7101 c/ wq., to the extent that the Deparunent exercises ftmcCons formerly vested in the Atomic Energy Commission, its Chairman, members, officers and components and transferred to the Energy Research and Development Administration and to the Administrator thereof pursuant to sections 104(b), (c) and (d) of the Energy Reorganization Act of 1974 (Public Law 93-438, October i1,1974,88 Stat.1233 at 1237,42 U.S.C. 5814, etTective January 19,1975) and retransferred to the Secretary of Energy pursuant to section 30)(a) of the Department of Energy Organization Act (Public Law 95-91, August 4,1977,91 Stat. 555 at 577-578,42 U.S.C. 7151, etrective October 1, 1977.) AllM

mRen Ike i.1 n n! 2. wit >np see A 2 , " Unrefined and unprocessed orc' means ore in its natural form prior to any processing, such as grinding, roasting, beneficiating, or refining-

• Unrestricted arca" means an area, access to which is neither limited nor controlled by the licensee or registrant. For purposes of these regulations, " uncontrolled area" is an equivalent term.

" Waste" means those low level radioactive wastes that are acceptable for disposal in a land disposal facility. I or the purposes of this definition, low level waste has the same meaning as in the Low Level Radioactive Waste Policy Act, P.L 96 573, as amended by P.L. 99 240, effectis e January l$,1986; that is, radioactive waste (a) not classified as high level radioactive waste, spent nuclear fuel, or byproduct material as defined in Section Ile (2) of the Atomic Energy Act (uranium or thorium tailings and was'e) and (b) classified as low level radioactive waste consistent with existing law and in accordance with (a) by the Nuclear Regulatory Commission. " Waste handling licensees" mean persons licensed to receive e' d stcre radioactive wastes prior to disposal and/or persons licensed to dispose of radioactive waste. " Week" means 7 consecutive days starting on Sunday. "_ hole body" means, for purposes of external exposure, head, tmnk including mak gonads, arms above W the elbow, or legs above the knee "WorLer" means an individual engaged in work under a license or registration issued by the Agency and controlled by a licenset or registrant, but does not include the licensee or registrant. " Working level" (WL) means any combination of short lived radon daughters in 1 liter of air that will result in the ultimate emission of 1.3E+5 MeV of potential alpha particle energy. The short lived radon daughters of radon 222 are polonium 218, lead 214, bismuth 214, and polonium 214; and those of radon 220 are polonium 216, lead 212, bismuth 212, and polonium 212. " Working level month" (WLM) means an exposure to I working level for 170 hours 2,000 working hours per year divided by 12 months per yer is approximately equal to 170 hours per month. " Year" means the period of time beginning in January used to determine compliance with the provisions of these regulations The licensee or registrant may change the starting dr.te of the year used to determine compliance by the licensee or registrant provHed that the.dni>ien to make the change is made ItollatetthaftDecember11 of.the previous at-thebeginningerthe year, IDLlisenses 0Ltesillant changesjtla. year..the. licensee.or.tegistrattt shallassute and-that no day is omitted or duplicated in consecutive years. Al242

( 1 Soc A 23 A 4 MRCR l'okDr /

• f 21g&J$.lu /hafi l l

l Esemptions from the Regulatory Requirements i Sid3 liitniptions. 4 i f2tatral Provisen The Agency may, upon application or upon its own initiative, grant such a. l exemptions or exceptions from the requirements of these regulations as it determines are i authorized by law and will not result in undue hazard to public health and safety or property. j b. Destment of Energy Contractors and Nuclear Regulatorv Commission Contractors. Any - Department of Energy contractor or subcontractor and any Nuclear Regulatory Commission i contractor or subcontractor of the following categories operating within this State is exempt from these regulations to the extent that such contractor or subcontractor under his contract receives, l possesses, uses, transfers, or acquires sources of radiation: 1 l 1. Prime contractors performind work for the Department of Energy at U.S. Government-owned o' controlled sites, including the transponation of sources of radiation to or from i such sites and the performance orcontract senices during temporary interruptions of such transponation; ii. Prime contractors of the Depanment of Energy performing research in, or development, manufacture, storahe, testinb or transportation of, atomic weapons or components thereof; ) iii. prime contractors of the Department of Energy using or operating nuclear reactors or other nuc! car devices in a United States Government owned vehicle or vessel; and - 4 iv. any other prime contractor or subcontractor of the Depanment of Energy or of the Nuclear Regulatory Commission when the State and the Nuclear Regulatory Commission jointly determine: 7 (1) That the exemption of the prime contractor or subcontractor is authorized by law; l and l (2) That, under the terms of the contract or subcontract, there is adequate assurance that the work thereunder can be accomplished without.adue risk to the public health and safety. General Regulatory Requirements Sec. A.4 ' _ Recordsc Each licensee and registrant shall maintain records showing the receipt, transfer, and disposal of all sources of radiation. - Additional record requirements are specified elsewhete in these regulations. 4 A130

r ,wRCR Iblume i. fDy73 2M3 Ibrup sec, A 3$. A Sy l

• l kc A3 Impfsflom.

Each licensee and registrant shall afford the Agency at all reasonable times opportunity to inspect a. sources of radiation and the premises and facilities wherein such sources of radiation are used or stored. f b. Each licensee and registrant shall make available to the Agency for inspection, upon reasonable notice, records maintained pursuant to these regulations. Sc A.6 Tests Each licensee and registrant shall perform upon instructions from the Agency, or shall permit the Agency to perform, such reasonable tests as the Agency deems appropriate or necessary including, but not limited to, tests of; l a. Sources of radiation, b. Facilities wherein sources of radiation are used or stored; c. Radiation detection and monitoring instruments; and d. Other equipment and devices used in connection with utilization or storage of ficensed or registered sources of radiation. Additional Regulatory Requirements Sic A.7 - Additional Requirements The Agency may, by rule, regulation, or order, impose upon any licensee or registrant such requirements in addition to those established in these regulations as it deems appropriate or necessary to minimize danger to public health and safety or property. Enforcement Requirements Sec. A 8 - Violations An injunction or other court order may be obtained prohibiting any violation of any provision of the Act or any regulation or order issued thereunder. Any person who willfully violates any provision of the Act or any regulation or order issued thereunder may be guilty of a [ felony, misdemeanor or crime) and, upon conviction, may be punished by fme or imprisonment or both, as provided by law. Sec. A 9 Impfundin.A Sources of radiation shall be subject to impoundment pursuant to (cite appropriate reference.] l A1414

Sw A 49 A6J) ,w< cit naune I. UL2p.n.n thanl kg A,10 Prohibited Usgs A hand held Ouoroscepic screen shall not be used with x ray equipment unless it has been listed in a. the Registry of Scaled Source and Dedces or accepted for certification by the Food and Drug Administration, Center for Devices and Radiological licalth. b. A shoe fitting fluoroscopic device shall not be used. [ Interpretations l ISec. A 11 - Interprrjatinnt Except as specifically authorized by the Agency in writing, no interpretation of these regulations by an omcer or employee of the Agency other than a written interpretation by the legal counsel will be recognized to be binding upon the Agency.] Communications htJLl2 - CornrnunitatierJL All communications and reports concerning these regulations, and applications filed thereunder, should be addressed to the Agency at its omce located at [insen appropriate address.] &c. A 13 - Units of Exposure and Doss. As used in these regulations, the unit of 93ppsure is the coulomb per kilogram (C/kg) of air. One a. roentgen is equal to 2.58E-4 coulomb per kilogram of air. b. As used in these regulations, the units of dose are: i. Gray (Gy)is the SI unit of absorbed dose. One gray is equal to an absorbed dose of 1 joule per kilogram (100 rad). ii. Rad is the special unit of absorbed dose. One rad is equal to an absorbed dose of 100 crg per gram or 0.01 joule per kilogram (0.01 Gy). iii. Rem is the special unit of any of the quantities expressed as dose equivalent. The dose equivalent in tem is equal to the absorbed dose in rad multiplied by the quality factor (I rem = 0.01 Sv). iv. Sieven is the SI unit of any of the quantities expressed as dose equivalent. The dose equivalent in sievert is equal to the absorbed dose in gray multiplied by the quality factor (1 Sv = 100 rem). A15M

i .WK'R IMunw I. (DJft.).L V1 thq/I &c. _ A,1) l c. As used in these regulations, the quality factors for converting absorbed dma to dose equivalent i are shown in Table 1. l I TABLEI l QUALITY F ACTORS AND ABSORBED DCE 30W/hl.IN W l 1 Type of Radiation Qu6t> Vmo. AsdM 6.. e Lqual to a Unit (Q) Dose Equivalent l X, gamma, or beta radiation and high speed i 1 electrons l Alpha particles, multiple charged 2 0.05 particles, fission fragments and l heavy panicles of unknown charge l Neutrons of unknown energy 1 0.1 liigh energy protons 1 0.1 l ' Ah tW anse in pa3 eqtml to i sun the absortal dose in rad cytml to I rem i d. Ifit is more convenient to measure the neutron fluence rate than to determine the neutron dose equivalent rate in sieven per hour or tem per hour, as provided in A.13c.,0.01 Sv (I rem) of neutron radiation of unknown energies may, for purposes of these regulations, be assumed to result from a total fluence of 25 million neutrons per square centimeter incident upon the body, if sufficient information exists to estimate the approximate energy distribution of the neutrons, the i licensee or registrant may use the fluence rate per unit dose equivalent or the appropriate Q value i from Table 11 to convert a measured tissue dose in gray or rad to dose equivalent in sievert or rem. d 1 h i 4 I n 4 is t A164 .- - ~. . ~.

s k ^ t3 ssken Ibluar).1n 9-2.aw orno l 1 TABLE il MEAN QUALITY FAC'lORS, Q, AND FLUENCE PER UNIT DOSE l EQUlVALENT FOR MONOENERGETIC NEUTRONS i i i i Neutron Quality Factor Fluence per Unit Fluence per Unit 8 h F Energy (Q) Dose Equivalent Dose Equivalent l d (McV) (Neutrons em rem ) (Neutrons em Sv ) (thermal) 2.5E 8 980E+ 980E+ l IE 7 980E+ 980E+ i lE 6 810E+ 810E+ ) IE 5 810E+ 810E+ IE 4 840E+ 840E+ 3 i 111 3 980E+ 980E+ IE-2 2. 1010E+ 1010E+ 4 lE l 7. 170E+ 170E+ $111 1 39E+ 39E+ i 1 27E+ 27E+ 2.5 29E+ 29E+ 23E+ 23E+ 7 24E+ 24E+ 10 6. 24E+ 24E+ 14 7, 17E+ 17E+ 20 16E+ 16E+ 4 40 14 E+ 14E+ I 60 5. 16E+ 16E+ IE+2 20E+ 20E+ 2E42 3. 19E+ 19E+ 3E+2 3. 16E+ 16E+ 411+2 3. 14E+ 14E+ l

• ' l'alue ofqualqfac tar <Q) at the potnt u here the shne equnnlent is inaumum in a 30 centimeter diameter cyltnJer tissue.

equimlentplumtom. 4 WA1anoenergetic neutrons inc Jent normally on a 30.centuneter diameter n ImJer ti< sue.rquimlent phantom i t i 1 4 A17M

.WH'll I himne I. [H.9714% V1Ikq/t Su AIH l fisc A 14 UnittoMeliyity, For purposes of these regulations, activity is expressed in the SI unit of becquerel (Bq) or in the special unit of eurie (Ci), or their multiples, or disintegrations or transfomiations per unit of time. a. One becquerel (11q) = 1 disintegration or transfortnation per second (dps or tps). b. One curie (Ci) - 3.7E+ 10 disintegrations or transformations per second (dps or tps) = 3.7E+ 10 becquerel (Ilq) = 2.22E+ 12 disintegrations or transformations per minute (dpm or tpm). ) A1818 4

i llMIEluly 29,199F) Drq/t Nationalefor Part A 1997 RATIONALE FOR REVISIONS ) PART A GENERAL PHOVISIONS Introduction The Nuclear Regulatory Commission continues to revise its Standards for Protection Against lonizing Radiation found in 10 CFR Part 20. This revision incorporated Changes in Part A of the SuggcatedState Regulationsfor Control of Radiation are as follows: Soccific Provisions &c A,2 D30nitions, " Licensing state" (revised). This definition of ficensing state was revised for additional clarification and had been recommended in the 1993 hiatters for Future Consideration. 1 J " Occupational dose" (revised). This defmition of occupational dose is consistent with the definition in the revised 10 CFR Part 20. "Public dose" (revised). This definition of public dose is consistent with the definition in the revised 10 CFR Part 20. " Radiation safety oflicer"(revised). This definition of radiation safety ofiicer was revised for additional clarification and had been recommended in the 1995 hiatters for Future Consideration. " Year" (revised). This definition of year was revised for additional clarification and had been f recommended in the 1995 hiatters for Future Consideration. Matters for Future Consideration 1. Presently, the Food and Drug Administration is considering replacing " exposure" with the term " air kerma" in the diagnostic x ray system performance standard (21 CFR, Sub-chapter J) Air kerma is currently in use by the National Council on Radiation Protection and hicasurements and international organizations. The Suggested State Regulations should be amended when the federal definition is amended, 2. The Working Group recommended that the definition of" waste" be referred to the Working Group for Part hi to consider inclusion of NARhi and NORhi waste. 3. When Part U has been approved, the Working Group will revise the definition of" byproduct material." 4 4. The Working Group has decided to consider the following changes during 1994: 4 " Exposure" means either:' 1

llM TKMe.'9, l VV7l lhan Ranonaltfor l' art, t the quotient of dQ divided by dm where "dQ" is the absoluts 'alue of the total charge of the ions of one sign produced in air when all the electrons (negatrons and positrons) liberated by photons in a volume element of air having mass "dm" are completely stopped in air. (See A.14 for the Si unit coulomb per kilogram (C/kg) and the special unit roentgen (R).); or irradiation by ioni,9g radiation or radioactive material.

• The context makes clear which is the appropriate definition.

5. The Working Group will consider new definitions for the following: indust:ial radiography, quali0ed expert (e g, Mammography Quality Standards Act of 1992 and American Association of Physicists in Medicine),

worker, manufacturing distribution commercial distribution processing 6.

The Working Group will consider the modi 0 cations to definitions, occupational dose and public dose when the Nuclear Regulatory Commission Gnalizes its rule on criteria for release of patients administered radioactivity. 7. The Working Group is considering the consolidation of the Qualified Expert definitions in various Parts into Part A. 8. The Working Group is considering revising Src A 1-Eteps. 2

fS. Conference of Radiotion Control Program Directors, Inc. I l Office of Executivo Director + 205 Capitol Avenue + Frankfort, KY 40601 Phone (502)227 4543 + Fox (502)227 7862 MIo N ca MEMORANDUM cn go e TO: Program Directors Agreement States FROM: Bruce Ilitschler Technical Assistant, CRCPD DATI: September 26,1997 RE: Peer review for revised Pans A, D & J Oue to my oversight, the Draft Rationale for Part D was not included in your original package. Please attach the following to Part D with my apologies. t 'A Partnership Dedicated to Radiation Protection

,e I997Drqft Rationalefor l' art D O 1997 RATIONALE FOR REVISIONS PART D STANDARDS FOR PROTECTION AGAINST RADIATION IntledRclino This revision to Part D 'ncorporates changes of the revised Part 20 into the Suggested State Regidations i for Control of Radiat/on, An accompanying revision to Part A incorporates many of the definitions to Pan 20 into the Suggested State Regadationsfor Control of Radiation. Definitions have been added, deleted or amended in Part D to be consistent with the revised Part A where the new or revised tenns were used throughout the regulations. Pan J was amended to be consistent with the revised 10 CFR Part 19. ComPAlihililylcQuitcmcDil hiost of the changes to Part D are compatibility requirements. Tiie following changes are addressed in this particular update: 10 CFR 20 per 60 FR 15649 (Low Level Waste Shipment hir lifest information and Reporting) with the effective date of hiarch 1,1998. 10 CFR 20 per 60 FR 36038 (Radiation -Protection Requirements Amended Definitions and Criteria) with the effective date of August 14,1995. 10 CFR 20 per 60 FR 48623 (hiedical Administration of Radiation and Radioactive hinterials) with the efTective date of October 20,1995.10 CFR 20 per 60 FR 7900 (Frequency of hiedical Examination for Use of Respiratory Protection Equipment) with the effective date of hiarch 13,1995. 10 CFR 20 per 60 FR 20183 (Standards for Protection Against Radiation; Clarification) with the effective date of April 25, 1995. OcBcutLlhusions in D.l.b.,"in an emergency" was deleted in the last line in order to be consistent with revised 10 CFR 20.100l b. In D 205a., the Working Group deleted reference about entering the restricted area per 10 CFR Part 20. In EMitiL the Working Group deleted " lifetime" per 10 CFR Part 20 and reformated 10 CFR 2104.C.ii to incorporate into D.205a ii. DJ,05c ii, was deleted because it was reformated into D.205a ii. D 205 c iii., was changed to D.205c.il as it was reformated due to the deletion of D.205c.ii. Additional wording was added to comply with 10 CFR 20.2104.C.3. RMid.], was reformated for editorial purposes. D.205d ii, was reformated for clarification purposes. Sec. D.701 - Use of Process of Other Engineering Controls. Changed for editorial purposes. I +.

199?I)rnft Rauonalefor l' art I) $ D.Enl ussWOdsiM Changed for editorial purposes. In D 703 a iii.$., the Working Group changed in order to be consistent with 10 CFR 20.1703a.(3)(v). In p.703 b i, the Working Group changed to be consistent with 10 CFR 20.1703.b.(1). Riihih06 s Transhifar DissisalM Mailtiii2 Revised due to new Appendix G to be consistent with 10 CFR Part 20.2006. See additional discussion in Appendix G Rationale explanation's Sss. D.1007 CompJians_e with Environmental and llealth Protection Regulations Changed for editional purposes. ILLt0 Lit, was added per 10 CFR 20.2101 and "special" was inserted for clarification. Dll.011t, was changed to D.1101.c Dl201, was changed to be more restnctive. Q129.$, clarined the title and changed to be consistent the 10 CFR 20.2205. The Wo king Group put brackets around [D.1206] due to D.1206 being bracketed. AppsmiiLILSectio1LilL(cK21 Deleted "Too Whom" to be consistent with 10 CFR 20 Appendix F, lile2. AppsndiLQ The working group decided to bracket this entire Appendix G because it is optional until March 1,1998 per 10 CFR Part 20.2006(a)(2), at that time Appendix G will supersede Appendix F in 10 CFR Pan 20 (Appendix D in Pan D). Editorial changes were made for clari0 cation. 2

~ ___ _ _ _ _ - _ _. i I99? Drqft Ranonaleforl' art D Matters for Future Considstall20 i 1. Provisions related to the National Emission Standards for llazardous Air Pollutants (40 CFR 61) Nre published as a final rule in the Federal Reghitt on February 6,1985 (50 FR 5190) by the Environmental protection Agency, pursuant to Section 112 of the Clean Air Act. The Part D ' Working Group should review these Clean Air Act standards for consideration in the next revision of the SSRCR. 2. The Working Group is considering changing the definition of hectsM pregnant woman as follows: Declared pregnant woman" means any woman who has voluntarily infonned her employer, in writing, of her pregnancy. 3. The Working Group is considering changing the dermition of calendar quaner as follows:

• Calendar quarter means not less than 12 consecutive weeks nor more than 14 consecutive weeks.

The first calendar quarter of each year shall begin in January and subsequent calendar quarters shall be so ananged such that no day is included in more than one calendar quarter and no day in any one year is omitted from inclusion within a calendar quaner. No licensee or registrant shall change the method observed by him for determining calendar quarters except at the beginning of a year " The change needed is to allow licensees or registrants to begin their year at times other than January as is allowed by the Nuclear Regu!atory Commission's defmit;on of" quarter." Note: The term quarter is used with residential quarters in the "SRCR. 4. The Working Group is considering changing the 0.3 multiplicative factor in the version of D 20lc.ii(2), which may be higher than necessary, to 0.2, which might be more appropriate, pending recommendations of the National Coimcil on Radiation Protection and Measurements. 5. The Working Group is considering the selection of an attenuation factor for use for pregnant fluoroscopists, for use in D.208. 6. The Working Group is cor.sidering a method for monitoring personnel eye doses when protective eyewear is worn for use in D 201, 7. The Working Group is considering revising D.205 as follows: 6205j DAenninsti6nhfPrior.0ccupsdikal bisEG E 57Q F6fsikidn3Mddil%liiy'eiiiiiidiifHsiEATWRiiiiiRiWe~tisidiii3Wiin3VEW) IoMyolLinia year,lan 'occupationhlM"soquirlag enor$oring pursijoil( ' ^ lhs ~

dom' W

penswtresistrant;shall, ca m n w orsar s k M;wKthisi, _ M 3a= . To accor.w ish this, a ~ licensee or registrant may use Agency Form Z. (Licensees and registrants also should attempt to obtain the records oflifetime cumulative occupational radiation dose.) 3 ,r,< _---n.-- e r e, -...m

e I99?Ikaft flanonalefor l' art I) h. Prior to permitting an individual to participate in a planned special exposure, the licensee or registrant shall: i. Determine the lifetime cumulative occupational radiation dose. (1)Ri(oiderycisiipifwis$M[g ^ p man. = tio mostat sq e M Penn % er pyen8ppfepsilkOSeidW.. I tadladosapesse.diqq '~ not employedlyAbehet (2) Obtain reports of the individual's dose equi,4ient for the time period subsequent to that included in Agency Forrr Y, or cquivalent, as specified in D.205.b.i.(1). Such reporta shall be signed by the individual and countersigned by an appropriate official (s) of the most recent employer (s) for work involving radiation exposure, or the individual's current employer (s)(if the individual is not employed by the licensee or registrant). - The information shall be recorded on Agency Form Z, or equivalent, ii. Determine the internal and external doses from all previous planned special exposuies lii. Determine all doses in excess of the limits received during the lifetime of the individual, including doses received during accidents and emergencies. The licensee or registrant shall record the exposure history, as required by D.205a. and c. D.205b., on Agency Form Y or Z, as applicable, or other clear and legible record containing all of the information required on that form. i. The form or record shall show each period in which the individual received occupational exposure to sources of radiation and shall be signed by the individual who received the exposure. For each peried for which the licensee or registrant obtains reports, the licensee or registrant shall use the dose shown in the report in preparing the exposure history. For any period in which the licensee or registrant does not obtain a report, the licensee or registrant shall place a notation on the exposure history indicating the periods of time for which data are not available. ii. For the purpose of complying with this requ,rement, licensees or registrants are not required to reevaluate the separate external dose equivalents and internal committed dose equivalents or intakes of radionuclides assessed before (the effective date of these regulations). Further, althcugh occupational exposure histories obtained and recorded before (the efTective date of these regulations) would not have included efTective dose equivalent, such histories rnay be used in the absence of specific information on the intake of radionuclides by the individual. 4

. _..= _ ~- . ~. 199?Drqft Rattonalefor Part D f d. If the licensee or registrant is unable to obtain a complete record of an individ9al's current and previously accumulated occupational

dose, the licensee or registrant:

1.?f 5 Whenistablishingidsinisifatisi"cinidiispiiiGe~ntThitil10iffEFaifrifiM shall assusw ths: the ellowableM almit Ibr Windividual.is saloose by; tr,s asi - (1,25 ~renQ for doch calender quaNarnwideh suponis;were'vasvaliabis"mid' tin 1,nsividual% ssensased:li;melvitisi%sitooiddleinneedboompitional redistion onposury, awl li. Shall not authorire the individual to receive any planned special exposures. c. Records shall bc retained in accordance with the requirements of D.1105a. 8. In reference to D Sole. on accreditation of dosimetry processors by the National Voluntary 1.aboratory Accreditation Program, the Working Group is considering the matters regarding accident level accreditation, electonic dosimetry and revising the text to eliminant pocket dosimeters per the previous version of the SSR. 9 The Working Group is considering clarifying the expression " proper visual, communication, and other special capabilitics" in D.703a vi. 10. The Working Group is considering revising D 1103, Records of Surveys, to specify records that should be transferred to the Agency. b should be noted that item 4 of the eighth edition of the SSRCR Part D Matters for Future Consideration also dealt with strengthening the D.407 " Vacating Premises to include decommissioning standards. It was recommended that such further revisions to Part D should be postponed until the decommissioning rule is placed in Part C; however, see D.1301 comments in this Matter for i uture Consideration. i 11. The Working Group is considering adding to D.1104 the specine information required to be in a leak test report. 12. When the c!Tective dose equivalent concept for exposure from external radiation sources is codined by the Nuclear Regulatory Commission, then the term efTective dose equivalent should be added to the list of terms in D.1107a.i. 13. The Working Group is considering revising D.1201a. as follows: Telephone Reports. Each licensee or registrant shall report to the Agency by telephone a. cach stoleri, lost, or missing source of radiation immediately aller its absence becomes known to the licensee or registrant. This requirement does not apply to sources of radiation that ire soQ6qhirjd t6Miiissidst registered. 14. The Working Group is considering a proposal to strengthen D.1301 " Vacating Premises" as follows-firsS1301 - Vacating Prcmises and Equipment. 5

.m I997I)r<$ Itatwnalefor l' art iJ s a. bcmhet IIach licensee or registrant, before vacating any premise or transferring the premises, shall perrnanently decontaminate such premise below or equal to the standards specified in Appendix G. A survey shall be made after such decontamination and the [ Director of Agency) and the landlord or subsequent tenant or transferee shall be provided with a copy of such survey no less than 30 days before vacating or relinquishing i possession or control of premise. No such premise shall be vacated, sold, or transferred until the decontamination survey has been accepted and approved by the (Director of Agency). b. Muipmentl)NdWMW"5"Sle66rssiryTgElpiiiiiiii[~eir^iiii'idiie~r ~'~ asill in coatset with, orLclose pmidetty tofssdionedvefmetastellatialliosaged;er; ' ' ~ ^ t Hw shall be melsned, sonCleeeed,iorLtranstemeto;asMiwor: person unless.such propertyMtufenfhhAbelowAequalMkslagderdi ipeci6ed in AppendixLO) A survey shall be made afler such decontamination and the [ Director of Agency) and subsequent owner or transferee shall be provided with a copy of such survey report No such equipment shall be assigned, sold, leased, or transferred until such decontamination survey has been accepted and approved by the (Director of Agency). 6

i i )99?()rqft Rottonalefor part D / APPENDIX G i Guidelines for Unrestricted Areas' (a) Surface contamination limits I (1) Alpha emitters q 31 dam average over I (i) Removable; O $55 Bq_,= 15 oCi = 100 cm' 100 cm' 100 cm' any one surface 100 dpm maxt:num 41pCJ 1.665 Ba = i 100 cm' 100 cm' 100 cm' L 1000 dpm average over (ii) Total 166.5 Bo = 450 oCi = 2 2 2 (fixed): 100 cm 100 cm 100 cm any one surface j 8325 Bg = 2250 oCi = 5000 dom maximum i 100 cm 100 cm 100 cm' 3 3 I 0.25 mism at I cm 2.5.ly at I cm = hr hr 1 (2) Beta Gamma emitters 4 100oCi average over (i) Removable: 3,7 B q = l (all beta. 100 cm' 100 cm' any one surface j gamma emitters 500oCi maximum except 185 Ba = 4 hydrogen 3) 100 cm' 100 cm' l 5 Removable: 37 Bq 109ap.Ci average over = (hydrogen 3) 100 cm' 100 cm' any one surface 5000 pC} maximum 185 Ba = 2 100 cm' 100 cm i 0.25 rnrem at I cm from (ii) Total 2.5_Sy = (b) Concentration in air and waterfM Table 11 of Part D. nuts Atywouin shallIt used only as a yukle. Hoe Agency mm require lower wlues in spec {fic Instances. Jeperuhng upon rahonuclules, hpe ofsurface, internicJpresent wulfuture use, etc. 7 ,c,w-- v.--ryye w w -. v, c-y- r -,4we-vv--en-v--w--e-+ +-i.e--v-.,--.--cc,.w,vrtver-tw,-*-~-,w~.-ev>v-re v---w.,,<-w.* +---r~.w,-c+-.e--~.. e.----w - e .r,-m----e----+--. .---~<

i 1997 l>rnft Rationalefor Part 1) s, (c) Concentrations in soil and oiher materials except water: (1) Radioactive material except source material and radiumEMMiiiilidi A, Column 11 of part C of these regulations; j (2) Source material and radiumRTM of radionuclides above background concentrations for total radium, averaged over areas of 100 square meters, shall not exceed: (i) $ picoeuries per gram of dry soil, averaged over the first 15 centimeters below the surface; and (ii) 5 picoeuries per gram of dry soil, averaged over layers of 15 centimeters thickness more than 15 centimeters below the surface. (d) The level of gamma radiation measured at a distance of 100 centimeters from the surface shall not exceed background. '15. The Working Group recommended that specific information required in the report oflost waste shipments in Section Ill.(c)(2) of Appendix D should be developed. t e -( t L 8 I ,c,, ,,,,-,,,,..,,-yn .-v.-.... ,_m -_4..,_,..w,.,-_,..., ,.v ,,p,e,.re-wrW "w* se--c-m--*--ie-++----+--w+w+m+

I99? DrqllRanooleforl'an D Attachment - Rationale for Proposed Changes to Regulaticas for Individuals Working in Medical Fluoroscopy (10/30/92) Medical Duoroscopic procedures involve exposures of operators and ancillary pmonnel to scatterei x rays and occuionally to primary beam x rays. Special Duoroscopic procedures m kurgical in nature and t than routine Ducroscopic frequently [ involve operator irradiation times an order of magnitude ~ %suisuipliisiGIoBii procedures Pssonnelho Meis&isalsfli; flu 6isisiipkgiicisF" iloesfoguivalentLvalues are. likely to be In"excesfofl55si(0AS nBaliddeep; dose equivalent values was in emoess%f diese W ^ Mgaildue eminnel i InterventionalistsWwrest their #r.onitMs properly l These values, under the present regulations, cause. frequent ' overexposure incidents," when in fact the associated efTective dose equivalent (llr) is much. lower. R'!#' /'ub//artion No. JJ (1982) states: In particular, the following advice applies in medical radiology, where the ue of lead aprons is common If a single dosimeter is used it should be worn outside the apror., usually high on the tmnk. The recorded result will provide information on tb dow equivalent to the skin, eye, and unshielded parts of the body (thsgh not necessarily to the hands) but will overestimate the effective dose equivalent. When the recorded values indicate annual totals approaching dose limits for efTective dose equivalent or when realistic estimates of effective dose equivalent are needed as in the optimization of protection, this over estimation may be unacceptable. Two dosimeters should then be used, one over and one under the protective apron. The interpretation of the combined results will have to depend on the local irradiation conditions and any *egulate:y requirements. The proposed changes to the SSRCR presented in D.20lc.ii defmc procedures by which lit can be determincd for special procedures Duoroscopists for whom the current method of overestimating ifr is unacceptable, while excluding personnel who may be working in routine fiuoroscopic or radiographic procedures. They also allow the current monitoring system to be used to estimate the eye dose equivalent in D502ah(1) and the ik for routine Quoroscopists in D.20lc ii(1). IlClimliMiiO11.of EtTectirc_Doselquitaient for Medical Fluoroscopuits Meinhold has presented the need for reporting personnel doses for external radiation in terms of Ilr pllleMilLEhysics (1989) M 4. 570). Alttuisipli ziewfaliisis?i4~C =qtip/CRp pi4//fgeidgyo ggtp?7 ?si&QtR AspirviN@p .ifbijthi detenniestioniof,He foripmonnellesposureMish)$$4sdistu@" ~ M~~ ~ /M' e posindselon misionWaat' ydincludeMd. - ?7 sewees,1beoeuse of a lackLoffspecillo. .tum diipeWaderal Raylanir (Mif 21EIM1)WG)W Nuclear Regulatory Commission regulations apply 3 to exposures from most licensed radioactive sources; but exposures to machine-produced x rays are not under purview of the Nuclear Regulatory Commission, therefore, such exposures were not expiicitly addressed in its rule making for amended Part 20. In the ene of the medical fluoroscopy work environment, the situation has been well dermed by Faulkner end Harrison in their paper " Estimation of EfTective Dose Equivalent to Staffin Diagnostic Radiology." 'ihis paper presents extensive data reisting 9 ~,. _ -

I In?I>rnft Rettwnalefor Part D the lit determined for a Rando phantom " operator" in fluoroscopy as a function ofindivic'ual monitoring devices worn at unshieMed collar and shialded waist locations, for various fluoroscopic peak tube potentials and apron thicknesses [byl cs in Medicine _and Diology (1988) 21:1,83 91). Although these i exiensive data are detemiined with the con 0guration of the x ray tube over the x ray table, a related paper by Wohni and Stranden [Healdithysics (M:1.7173)) allows comparisons between the x ray tube p6sitioned over and underneath the x ray table. The data of Faulkner and liarrison have been further analyzed and reduced by Webster, who has proposed a method of combining data from two individual monitoring devices as a good estimate oflit [UrAldLfhy1N1 (1989) M.4, 568 9] This method is given in proposed regulation D,3Mi%i) for fluoroscopists for whom the recorded deep dose equivalent values indicate annual totals approaching or exceeding the conservative regulation, as recommended by /CRP Publicalloir No. 35, quoted above. Speel0cally, Webster's equation requires the use of deep dose equivalent values for a shielded waist monitor (W) and an unshielded collar monitor (C) to determine lit with modifying factors which were desived from Faulkner and liarrison's paper: lit = 0.04C + 1.5W. The difference between 11, and the "whole body" deep dose equiva!cnt values currently required for fluoroscopios is given as an example. NCRP Repotl No. 37 states: Exposure of the face and neck will exceed the exposure recorded under the apron by factors between 6 and 25. 11sfefoie3n Eshielded collar Mdgelsiii'dosIssWiidiifitC*sjiial j6WsR10.0f S$165ffiEdili farge value for toWine fluoroscopists buf not neconneos fikspoolel piecedwee Suososispists)[sodd 9 seociated witlii.shioided saikbedadeepMoquivaleet#Xequal RA0sMDeiund0ER mSV)l Using Webster's equation, the lit for that month is calculated to be lit = 0.04 (1000) + 1.5 (40 to 167) mrem = 40 + (60 to 250) mrem = 100 to 290 mrem. This lit annualizes to 1.2. 3.48 rem (12--34.8 mSv), significantly below the limit of 5 rem (0.05 Sv). The annual dose equivalent to the eye is calculated to be 12 rem (0.12 Sv), also below the limit of 15 rem (0.15 Sv). A fluoroscopist with an annual collar monitor deep dose equivalent of 12 rem (0.12 Sv) would therefore be expected to have an annualli ofless than 3.5 rem (35 mSv). t It should be noted that wearing two personal monitoring devices has at least two drawbacks, i.e., the individual may confuse wearing the monitors and inconsistently wear them in the same locations'; and the cost of monitors is doubled. Fluoroscopy personnel who perform or assist in routine fluoroscopic or radiographic procedures do not rtecive doses sufficiently high to warrant the expense and potential confusion of wearing two badges in order to require a more accurate determination oflit. ' Color whng holders ts helpfulm minontzing this problem: *wilow bel &*for the waist balge is reasonaby straightforward! tiso u sing two Jferent t>pc.s ofmomsor.s. such asfilm and TLD. mm. be helpful. 10

4 I997 Drq/t Ranonalefor l' art D .C Consistent with R'RP Pubhcanon Na 33, quoted above, D.201c.ii(1) allows an overestimate oflit for some Dooroscopists to be determined from one individual monitoring device, because the overestimate is not burdensome. The criterion to allow calculation oflit based on the unshielded neck monitor by use of a 0.3 multiplication factor in D,20Si(1) is set at 25 percent of the dose limit for the purpose of separating personnel who work in special procedures from personnel who work in routine Quoroscopic or radiographic procedures The proposed methodology is derived from NCRP Ry>or/ Na 57 by using the most conservative value and setting W = C/6 in Webster's equation for Hr. lit then becomes approximately equal to the unshielded collar badge deep dose equivalent multiplied by 0.3. Comparison of this factor with the data presented in the papers of Faulkner and liarrison, and Wohni and Stranden indicate that this factor is conservatively low, however, the factor of 0.3 is not believed to be burdensome for the following two reasons: 1. When the collar monitor is used to monitor the dose to the lens of the eye, and the annual lens dose equivalent is limited to 15 rem (0.15 Sv), then the annual effective dose equivalent will not exceed 5 rem (0.05 Sv) annually. In this case, the lens dose equivalent becomes the limitation, rather than the effective dose equivalent. 2. The efroctive; dose equivalenfmayMstimatedly a singletoollaOnNdth, but a more accurate estimate is made with both the collar and waist monitors if a more accurate estimate oflit s desired, this second option should be used. Therefore, until the National i Council on Radiation Protection and Measurements provides definitive guidance for determining Ili, this conservative multiplicative factor of 0.3 may be used when a single collar monitor is worn Unlike routine Quoroscopists, special procedures fluoroscopists are likely to have annual collar badge values in excess of 5 rem (0 05 Sv) when they wear their monitors according to current regulations. Since the number ofindividuals who perform or assist in these types of procedures is much smaller than those in routine Huoroscopy, permitting better training and supervision, both the likelihood of confusing two monitors and the excess costs are minimized. Wearing two monitors has the added benefit of concurrently monitoring gonad dose as well as the dose to a potential embryo / fetus. If these data are needed for personnel in this higher dose work environment, they are readily available. liowever, it is proposed that wearing two monitors be requigd only for declared pregnant women in fluoroscopy so that actual meatsd values underneath the apron are documented, rather than coarse estimates (D502a M3)]. It is recognized that the monitor worn underneath the apron almost certainly provides an overestimate of the dose received by the embryo / fetus. Ilowever, a specine dose reduction factor depends on the individual and the work environment, and a universal dose reduction fattor is not recommended without the advice of a quali0ed expert Because nearly all personnel have monthly shielded waist monitor values ofless than 50 mrem (0.5 mSv), the embryo / fetus dose assessment for specine individuals will be required only in rare circumstances (Brateman L., Mth Annual National Confegnee on Radiation Control, CRCPD Publication 92 5 (1992) 277 9]. Proposed regulation D,20liiiM allows the cumulative lit for special 'sts to be dete,rmined,when data are available for only the collar monitor. ~ 74 y-m - ~ Willheir%enhlf pm er %,;disnWed h r%mu%w II

I99? Ikull Ranonalefor l'arr I) N N m, _ ~ ,_-_...s m~. 290 2 P +lN g ugr yrk %syk w na Es. biddose; In addition, since the current regulations are not burdensome for this group, this practice is consistent with rRP Publication No. 35. Protective aprons are worn to shield the gonads and a major portion of the trunk and bone marrow of the individual. Therefore, an individual assisting in fluoroscopic procedures with his/her back to the x ray beam needs to wear appropriate shielding to cover the back, as well as the front, of the chest, abdomen and pelvis, to limit the dose to these organs and tissues. This policy also ensures adequatcJrotection in the case of a declared pregnant woman. MiisiMMEGjiihmieEsflijidisqdtaleesj$EEEiiH ddedvMion5fEsMWebstel in his equation, because these aprons are in common usage. Therefore, F.3a i($b) is expanded to provide the appropriate monitoring conditions for the assumptions underlying D.201e li. Proposed modifications to Parts D and F address in particular the monitoring of occupational doses from medical fluoroscopy, and proposed modifications to Pan F include the relocation of personnel monitoring issues to Pan D. Therefore, F.3a i(10)is revised so as to include all of the appropriate sections of Part D, and F.3a l.(10)(a) is replaced by D.502a iv and D.20lc. SiindseW WWisia~Q r jifiaitikaptens'in fidsoscopy asiiricludid is pan F,ind ilisiproposed regulation lfor'iocating saaniaces fbr deiermining occupallonal doses 'Is included in Pa(D,(thejdelimitlopferpostinctivoiapses is'addedb Part! A,;in acconiance;with'the Conference of; Radiation Control Propeni Dinootors "Poliolesiand Procedures for the Preparition al Publication Athe SusseMSee AsswlW#rerJsyle Manuel'.5 ComhaionmLSummmy Physicians who perform special Cuoroscopic procedures frequently receive doses to the head and Eii Micli are greater than 5 rem (0.05 Sv) per year. Current regulations consider the largest of these values as the "whole b6dydio'e equivalent, even though the gonads and most of the trunk are shielded by s aprons which provide large protective factors. The incorporation of the recently revised 10 CFR Pan 20 into the SSRCR will exclude the present fallback position of allowing a 5(N 18) rem lifetime whole body dose equivalent for these individuals, and an untenable regulatory situation is likely to occur rapidly. It is already the case that, because the enforcement of current regulations requires frequent censure of personnel performing special Duoroscopic procedures, many personnel do not comply with existing Canisignisifuihigulati6ss t6'tliesefjiibfosiid3lllges which have values requirements (i.e., wearing unshielded collar bad rsiuliliiiiIisUsii"sisifactorais ~ s= " t supoiuritb radiation and Mll alloppersonnelf ~ ioMMaioneJuptodate laternational;Cessellso ' panglesi ftetension and Measuremsats eW telin ~ ~~ @hl80ittM stguistoryloveshoMthisjpecidgedp!dcise['f osk These proposed regulations are seen as an improvement over jIiiEtS x ray regulations and provide a conservative estimate of x-ray exposures in medical fluoroscopy without being unduly restrictive, burdensome and costly, it is extremely important that these changes be incorporated before unnecessary regulatory problems are created.. that is, incorporated concurrent with the revisions to the SSRCR which include the Nuclear Regulatory Commission Part 20 modifications. 12 ~

Sa U t. D.1 MRCR t duw I. lugust I99 Dntil PART D STANDARDS FOR PROTl:CTION AGAINST RADIATION General Provisions SSc D I - PunTm Part D establishes standards for protection against ionizing radiation resulting frota activities a. conducted pursuant to licenses or registrations issued by the Agency. These regulations are issued pursuant to the [ cite Radiation Control Act, as amended). b. The requirements of Part D are designed to control the receipt, possession, use, transfu, and disposal of sources of radiation by any licensee or registrant so the total dose to an individual, including doses resulting from all sources of radiation other than background radiation, does not exceed the standards for protection rgainst radiation prescribed in Part D. Ilowever, nothing in Part D shall be construed as limiting actions that may be necessary to protect health and safetyin an emergency-Ece D 2 - Scepse_ lheept as speci6cally provided in other Parts of these regulations. Part D applies to persons licensed or registered by the Agency to receive, possess, use, transfer, or dispose of sources of radiation. The limits in Part D do not apply to doses due to background radiation, to exposure of patients to radiation for the purpose of medical diagnosis or therapy, or to voluntary participation in medical research programs. See D 3 De6nitions As used in Part D: "Annuallimit on intake" (All) means the derived limit for the amount of radioactive material taken into the body of an adult worker by inhalation or ingestion in a year. All is the smaller value ofintake of a given radionuclide in a year by the reference man that would result in a committed efTective dose equivalent of 0.05 Sv (5 rem) or a committed dose equivalent of 0.5 Sv (50 rem) to any individual organ or tissue. All values for intake by ingestion and by inhalation of selected radionuclides are given in Table I, Columns I and 2, of Appendix It " Class" means a classi6 cation scheme for inhaled material according to its rate of clearance from the pulmonary region of the lung. Materials are classi6ed as D, W, or Y, which applies to a range of clearance half times for Class D, Days, ofless than 10 days, for Class W, Weeks, from 10 to 100 days, and for Class Y, Years, of greater than 100 days. For purposes of these regulations, lung class" and " inhalation class" are equivalent terms. beclared pregnant woman" means a woman who has voluntarily infoimed her employer, in writing, of her pregnancy and the estimat~i date of conception a " Derived air concentration" (DAC) means the concentrat' ion of a given radionuclide in air which, if ", breathed by,the reference man for a working year of 2,000 hours under conditions oflight work, results Dit i

SK 0 3

• SSRCit t bluxw I. Auguet iH1lhttil in an intake of one ALI. For purposes of these regulations, the condition oflight work is an inhalation rate of 1.2 cubic meters of air per hour for 2,000 hours in a sear. DAC values are given in Table 1.
• Column 3, of Appendix B

" Derived air concentration hour" (DAC hour) means the product of the concentration of radioactive materialin air, expressed as a fraction or multiple of the derived air concentration fo: each radionuclide, and the time of exposure to that radionuclide, in hours A licensee or registrant may take 2,000 DAC-hours to represent one All, equivalent to a committed etTectivo dose equivalent of 0.05 Sv (5 rem) " Dosimetry processor" meant an individual or an organization that processes and evaluates individual monitoring devices in order to determine the radiation dose blivered to the monitoring devices " Inhalation class" (see " Class"] " Lung class" (see " Class"J. "Nonstochastic cuect" means a health effect, the severity of which varies with the dose and for which a threshold is believed to exist. Radiation induced cataract formation is an example of a nonstochastic effect. For purposes of these regulations, " deterministic elTect"is an equivalent term " Planned special exposure" means an infrequent exposure to radiation, separate from and in addition to the annual occupational dose limits "Quaner" means a period of time equal to one founh of the year observed by the licensee, approximately 13 consecutive weeks, providing that the beginning of the first quarter in a year coincides with the staning date of the year and that no day is omitted or duplicated in consecutive quarters " Reference man" means a hypothetical aggregation of human physical and physiological characteristics determined by international consensus. These characteristics may be used by researchers and public health employees to standardize results of experiments and to relate biological insult to a common base. A description of the reference man is contained in the international Commission on Radiological protection repon, ICRp publication 23, "Repon of the Task Group on Reference Man " " Respiratory protective equipment" means an apparatus, such as a respirator, used to reduce an individuars intake of airborne radioactive materials " Sanitary sewerage" means a system of public sewers for carrying ott waste water and refuse, but excluding sewage treatment facilities, septic tanks, and leach fields owned or operated by the licensee or ., gistrant. " Stochastic clTect" means a health etTect that occurs randomly and for which the probability of the effect occurring, rather than its sescrity, is assumed to be a linear function of dose without threshold. Hereditary effects aad cancer incidence are examples of stochastic efTects-For purposes of these regulations, "probabilistic effect" is an equivalent term. D22

Sec. D ). D 4 SSRCR t'oluxor i.hgust 1997 DrctA "Very high radiation area" means an area, accessib!c to individuals, in which radiation levels could result in an individual receiving an abscrbed dose in excess of 5 Gy (500 rad)in I hour at I meter from a source of radiation or from any surface that the radiation penetrates.1 " Weighting factor" wt for an organ or tissue (T) means the proportion of the risk of stochastic elTects resulting from irradiation of that organ or tissue to the total risk of stochastic efTects when the whole body is irradiated uniformly. For calculating the effective dose equivalent, the values of wt are: Organ Dose Weighting Factors Organ or Tissue wt Gonads 0.25 Ilreast 0.15 Red bone marrow 0.12 Lung 0.12 Thyroid 0.03 Ilone surfaces 0.03 Remainder 0 30' Whole Body 1.00h

• OJU resuhs from 0 06for each of 3 'remamJer" organs. exchiding the sim and the lens of the eye, that reccht the highest Joses.

Y For the purpose of urightmg the extental whole body Jose,for aldmg at to the mternal Jose, a smgle urightmg factor, wt - I.O. has been specified. The use of other ue:ghtmg pctors pr esternal erposure will be approsrJ on a case,bpcase basis untd such tune as specolic gutJance is issued See D 4 Implementation Any existing license or registration condition that is more restrictive than Part D remains in force a. until there is an amendment or renewal of the license or registration. b. If a license or registration condition exempts a licensee or registrant from a provision of Part D in elTect on or before (c!Tective date of these regulations), it also exempts the licensee or registrant from the corresponding provision of Part D. If a license or registration condition cites provisions of Part D in effect prior to [efTective date of c. these regulations), which do not correspond to any provisions of Part D, the license or l hlI stry Ingh Joses recentJ at high Jose rates, umts of absorbedJose, gra and ral, are appropnate, rather than units ofdose equenden siesertandrem. D33

.%RCM iNuve I..tuper 19V1I)nf Sec. D 3. D l01. D 20t registration condition remains in force until there is an amendment or rerswal of the license or reglstration that modifies or removes this condition. Radiation Protection Programs Sec D 101 Radiati_on Protection Prourams. Each licensee or registrant shall deselop, document, and implement a radiatlon protection a. prograrn suflicient to ensure compliance with the provisions of part D. See D,1102 for recordkeeping requirements relating to these prograrns, b. The licensee or registrant shall use, to the extent practicable, procedures and engineering controls based upon sound radiation protection principles to achieve occupational doses and public doses that are as low as is reasonably achievable (ALARA). The licensee or registrant shall, at intervals not to exceed 12 months, review the radiation. c. protection program content and implementation. Occupational Dose Limits Src D 201 - Ocnipjtional Dose Littiits for AdultL The licensee or registrant shall control the occupational dose to individual adults, except for a, planned special exposures pursuant to D.206, to the following dose limits: i. An annual litnit, which is the more limiting of: (1) T he total effective dose equivalent being equal to 0.05 Sv (s rem), or (2) The sum of the deep dose equivalent and the committed dose equivalent to any individual organ or tissue other than the lens of the eye being equal to 0.5 Sv (50 rem). ii. The annual limits to the lens of the eye, to the skin, and to the extremities which are: (1) An eye dose equivalent of 0.15 Sv (15 rem), and (2) A shallow dose equivalent of 0.5 Sv (50 rem) to the skin or to any extremity. b. Doses received in excess _ of the annual limits, including doses received during accidents, emergencies, and planned special exposures, shall be subtracted from the limits for planned special exposures that the individual may receive during the current year and during the individual's lifetime. See D.206e.l. and 11. D44

r Sec. D 20t

• D 202 MRCR Ibluxw I..lugust i997 Drq/l

-The assigned deep dose equivalent and shallow dose equivalent shall be for the ponion of the c, body receising the highest exposure: l 1. The deep dose equivalent, eye dose equivalent and shallow dose equivalent may be assessed from surveys or other radiation measurements for the purpose of demonstrating i j compliance with the occupational dose limits, if the individual monitoring desice was not in the region of highest potential exposure, or the results of individual monitoring are unavailable; or ii. When a protective apron is worn while working with medical Auoroscopic equipment and monitoring is conducted as specified in D.502a.iv., the effective dose equivalent for external radiation shall be determined as follows: i (1) When only one individual monitoring device is used and it is located at the neck outside the protective apron, the reported deep dose equivalent shall be the effective dose equivalent for external radiation; or (2) When only one indi<idual monitoring device is used and it is located at the neck outside the protective apron, and the reported dm exceeds 25 percent of the limit specified in D.201a., the reported deep dose equivalent value multiplied by 0.3 shell be the effective dose equivalent for external radiation; or (3) When individual monitoring devices are worn, both under the protective apron at the waist and outside the protective apron at the neck, the effective dose equivalent for external radiation shall be assigned the value of the sum of the deep dose equivalent ter'1cd for the individual monitoring device located at the waist under the protec,..e apron multiplied by 1.5 and the deep dose equivalent reported for the individual monitoring device located at the neck outside the protective apron multiplied by 0.04. d. Derised air concentration (DAC) and annual limit on intake (ALI) values are specified in Table I of Appendix B and may be usca to determine the individual's dose and to demonstrate compliance with the occupational dose limits. See D 1107. Notwithstanding the annual dose limits, the licensee or registrant shall limit the soluble uranium c. intake by an individual to 10 milligrams in a week in consideration of chemical toxicity. See of Appendix B. footnote 5 f, The licensee or registrant shall reduce the dose that an individual may be allowed to receive in the current year by the amount of occupational dose received while employed by any other person during the current year. See D 205. Sec D 202 - CompJiance with Requirements for Summation of External and Imanal Doses, a: If the licensee or registrant is required to monitor pursuant to both D.502a. and b., the licensee or registrant shall demonstrate compliance with the dose limits by summing external and internal i D55

Sa:ti202 0:o) MRCR Ibluxw I. Aupal 1997 Draft doses. If the licensee or registrant is requiteci to monitor only pursuant to D.502a. or only pursuant to D.502b, then summation is not required to demonstrate compliance with the dose limits The licensee or registrant may demonstrate compliance with the requirements for summation of external and internal doses pursuant to D.202b, c. and d. The dose equivalen:s for the lens of the eye, the skin, and the extremities are not included in the summation, out are subject to separate limits. b. IntaldyJnhablipA If the only intake of radionuclides is by inhalation, the total effective dose equivalent limit is not exceeded if the sum of the deep dose equivalent divided by the tual elTective dose equivalent limit, and one of the following, does not exceed unity: i. The sum of the fractions of the inhalation All for each radionuclide; or 4 li. The total number of derived air concentration hours (DAC. hours) for all radionuclides divided by 2,000; or iii The sum of the calculated committed effective dose equivalents to all significantly irradiated organs or tissues (T) calculated from bioassay data using appropriate biological models and expressed as a fraction of the annuallimit. Fcr purposes of this requirement, an organ or tissue is deemcd to be significantly irradiated if, for that organ or tissue, the product of the weighting factors, w, and the committed dose equivalent,111.2 per unit r intake is greater than 10 percent of the maximum weighted value ofilt.30, that is, wilit.30, per unit intake for any organ or tissue. c. Intake by Oral Inessli.gA If the occupationally exposed individual receives an intake of radionuclides by oral ingestion greater than 10 percent of the applicable oral All, the licensee or registrant shall account for this intake and include it in demonstrating compliance with the limits. d. Lntake through Wounds or Abstrplitn through Skirt The licensee or registrant shall evaluate and, to the extent practical, account for intakes through wounds or skin absorption The intake through intact skin has been included in the calculation of DAC for hydrogen 3 and does not need to be evaluated or accounted for pursuant to D.202d Sec D 203 - Determination of External Dose from Airbome Radioactive Material Licensees or registrants shall, when determining the dose from airborne radioactive material, a. include the contribution to the deep dose equivalent, eye dose equivalent, and shallow dose b equivalent from external exposure io the radioactive cloud. See Appendix B, footnotes' and b. Airborne radioactivity measurements and DAC values shall not be used as the primary means to assess the deep dose equivalent when the airborne radioactive material includes radionuclides other than noble gases or if the cloud of airborne radioa:tive material is not relatively uniform. The determination of the deep dose equivalent to an individual shall be based upon measurements using instruments or individual monitoring devices. D%

Sec. D 204 SSRCR Iblume !. Aupist I997 Drap Sec. D 204 - Determinatlon of tnteinal Exposure, For purposes of assessing cose used to determine compliance with occupational dose equivalent a. limits, the licensee or registrant shall, when required pursuant to D.502, take suitable and timely measurements of; i. Concentrations of radioactive materials in air in work areat; or ii. Quantities of radionuclkles in the body; or iii. Quantities of radior.uclides excreted from the body; or iv. Combinations of these measurements. b. Unless respiratory protective equipment is used, as provided in D.703, or the assessment ofintake is based on bioassays, the licensee or registrant shall assume that an individual inhales radioactive material at the airborne concentration in which the individual is present, When specific information on the physical and biochemical properties of tlie radionuclides taken c. into the body or the behavior of the material in an individual is known, the licensee or registrant may: i. Use that information to calculate the committed effective dose equivalent, and, if used, the licensee or registrant shall document that information in the individual's record; and ii. Upon prior approval of the Agency, adjust the DAC or ALI values to reflect the actual physical and chemical characteristics of airborne radioactive material, for example, aerosol size distribution or density; and iii. Separately assess the contribution of fractional intakes of Class D, W, or Y compounds of a given radionuclide to the committed efTective dose equiva!'.at. See Appendix B. d. If the licensee or registrant chooses to assess intakes of Class Y material using the measurements given in D.204a.ii. or iii., the licensee or registrant may delay the recording and reporting of the assessments for periods up to 7 months, unless otherwise required by D.1202 or D.1203. This delay permits the licensee or registrant to make additional measurements basic to the assessments. If the identity and concentration of each radionuclide in a mixture are known, the fraction of the e. DAC applicable to the mixture for use in calculating DAC-hours shall be either: i. The sum of the ratios of the concentration to the appropriate DAC value, that is, D, W, or Y, from Appendix B for each radionuclide in the mixture; or ii. The ratio of the total concentration for all radionuclides in the mixture to the most restrictive DAC value for any radionuclide in the mixture. D77

Sec. D204 D 205 ,wRt'R l*olume I.. ingt.st s 997 ihaft l f. If the identity of each radionuclide in a mixture is known, but the concentration of one or more of the radionuclides in the mixture is not known, the DAC for the mixture shall be the most restrictive DAC of any radionuclide in the mixture. When a mixture of radionuclides in air exists, a licensee or registrant may disregard certain g. radionuclides in the mixture if: i. The licensee or registrant uses the total activity of the mixture in demonstrating compliance with the dose limits in D.201 and in complying with the monitoring requirements in D.502b.; and ii. The concentration of anj radionuclide disregarded is less than 10 percent ofits DAC; and iii. TI,e sum of these percentages for all of the radionuclides disregarded in the mixture does not exceed 30 percent. h. When determining the committed effective dose equivalent, the following information may be considered: i. In order to calculate the committed efTective dose equivalent, the licensee or registrant may assume that the inhalation of one ALI, or an exposure of 2,000 DAC-hours, results in a committed efTective dose equivalent of 0.05 Sv (5 rem) for radionuclides that have their ALis or DACs based on the committed efTective dose equivalent; ii. For an All and the associated DAC determined by the nonstochastic organ dose limit of 0.5 Sv (50 rem), the intake of radionuclides that would result in a committed effective dose equivalent of 0.05 Sv (5 rem), that is, the stochastic All, is listed in parentheses in Table 1 of Appendix B. The licensee or registrant may, as a simplifying assumption, use the stochastic ALI to determine committed efTective dose equivalent. However, if the licensee or registrant uses the stochastic All, the licensee or registrant shall also demonstrate that the limit in D.20la i(2)is met. Sec D 205 - Determination of Prior Occupational Dose. For each individual who-may-enter-the-licensee's-or-registrant's-restricted-area-and-is likely to a. receive,,, a year, an occupational dose requiring monitoring pursuant to D.502, the licensee or registrant shall: i. Determine the occupational radiation dose received during the current year; and ii. Attempt to obtain the records of lifetime cumulative occupational radiation dose. 6 lis.CasC2_ALLCgistrant may accept. as the record of cumulatise radiation dose. an uo-to-date_6gency_Eorml_oLcquinienuigned_by_the_indixiduaLanico.untenigneiby_an appropriate olTicial.of_the.mosLI.ccenternployer_foLwor}Linvolving. radiation _ exposure. or the individual's current emolover. if the individual is not emoloved by the licensee or Legistrant l l D88

Sec. D 20$ SSRCR Iblumeidugun 1997 Drap b. Prior to_ permitting an individual to participate in a planned special exposure, the licensee or registrant shall determine: i. The internal and external doses from all presious planned special exposures; and ii. All doses in excess of the limits, including doses received during accidents and emergencies, received during the lifetime of the individual. c. In complying with the requirements of D.205a., a licensee or registrant may: i. Accept, as a record of the occupational dose that the individualieceived during the current year, a written signed statement from the individual, or from the individual's most recent employer for work invohing radiatbn exposure, that discloses the nature and the amount of any occupational dose that the indisidual received during the current year; and; ii.- Acceptras the record oflifetime-cumulative-radiation-dose,-an-up-to-date-Agency-Form-Y or-equivalentr igned4>y-the4ndividual-and-countersigned-by-amappropriate-official-of-the s most-recent-employer-for-work-involvingsadiatiomexposure-or-the-individual's-current employerrif-thelndividual4sw>t employed 4>y4helicensee43r-registranti-and -iii.ii, Obtain reports of the individual's dose equivalent (s) from the most recent employer for work involving radiation exposure, or the individual's current employer, if the individual is not employed by the licensee or registrant, by telephone, telegram, facsimile, other ektttp.dc.nledia, or letter. The licensee or registrant shall request a written verification of the dose data if the authenticity of the transmitted report cannot be established. d:i: The licensee or registrant shall record the exposure history, as required by D.205a., on Agency Form Y, or other clear and legible record, of all the information required on that form i. The form or record shall show each period in which the individual received occupational exposure to radiation or radioactive material and shall be signed by the individual who received the exposure. For each period for which the licensee or registrant obtains reports, the licensee or registrant shall use the dose shown in the report in preparing Agency Form Y or equivalent. For any period in which the licensee or registrant does not obtain a report, the licensee or registrant shall place a notation on Agency Form Y or equivalent indicating the periods of time for which data are not available. ii. Jor the purpose of. complying 3vith_thiuequirement, blicensees or registrants are not required to partition historical dose between external dose equivalent (s) and internal committed dose equivalent (s). Further, occupational exposure histories obtained and recorded on Agency Form Y or equivalent before (the efTective date of these regu!*tions), might not have included efTective dose equivalent, but may be used in the absence of specific information on the intake of radionuclides by the individual. D99

Sm. D 205 D 206 SSRCR Iblu:w I. Aupat i997 I) raft. If the licensee or registrant is unable to obtain a complete record of an individual's current and e. previously accumulated occupational dose, the licensee or registrant shall assume: i. In establishing administrative controls pursuant to D.20lf. for the current year, that the allowable dose limit for the individualis reduced by 12.5 mSv (1.25 rem) for each quarter for which records were unavailable and the individual was engaged in activities that could have resulted in occupational radiation exposere; and ii. That the individual is not available for planned special exposures. f. The licensee or registrant shall retain the records on Agency Form Y or equivalent until the Agency terminates each pertinent license or registration requiring this record. The licensee or registrant shall retain records used in preparing Agency Form Y or equivalent for 3 years after the record is made. Sec D 206 - Planned Special Exposures. A licensee or registrant may authorize an adult worker to receive doses in addition to and accounted for separately from the doses received under the limits specified in D.201 provided that each of the following conditions is satisfied: The licensee or registrant authorizes a planned special exposure only in an exceptional situation a. when alternatives that might avoid the higher exposure are unavailable or impractical; b. The licensee or registrant, and employer if the employer is not the licensee or registrant, specifically authorizes the planned special exposure, in writing, before the exposure occurs; Before a planned special exposure, the licensee or registrant ensures that each individual involved c. is: i. Informed of the purpose of the picnned operation; and ii. Informed of the estimated doses and associated potential risks and specific radiation levels or other conditions that might be invo ved in performing the task; and l iii. Instructed in the measures to be taken to keer the dose ALARA considering other risks that may be present; d. Prior to permitting an individual to participate in a planned special exposure, the licensee or registrant ascertains prior doses as required by D.205b. during the lifetime of the individual for each individual involved; Subject to D.20lb., the licensee or registrant shall not authorize a planned special exposure that e. would cause an individual to receive a dose from all planned special exposures and all doses in excess of the limits to exceed: i. The numerical values of any of the dose limits in D.20la. in any b_:; and Dl010

-~. SSRCR l'olume i..tupat I99 Draft Sec D 206 0 2na ii. Five times the annual dose limits in D.20la. during the individual's lifetime; f. The licensee or registrant maintains records of the conduct of a planned special exposure in accordance wth D.1106 and submits a written report in accordance with D.1204; The licensee or registrant records the best estimate of the dose resulting from the planned special g. exposure in the individual's record and informs the individual, in writing, of the dose within 30 days from the date of the planned special exposure.; The dose from planned special exposures shall not be considered in controlling future occupational dose of the individual pursuant to D.201a. but shall be included in evaluations required by D.206d. and e. Sec D 207 - Occupational Dose Limits for Minors The annual occupational dose limits for minors are 10 percent of the annual occupational dose limits specified for adult workers in D.201. Sec D 208 - Dose to an Embryo / Fetus The licensee or registrant shall ensure that the dose to an embryo / fetus during the entire a. pregnancy, due to occupational exposure of a declared pregnant woman, does not exceed 5 mSv (0.5 rem). See D.I107 for recordkeeping requirements b. The licensee or registrant shall make elTorts to avoid substantial variation

• above a uniform monthly exposure rate to a declared pregnant woman so as to satisfy the limit in D.20Sa.

The dose to an embryo / fetus shall be taken as the sum of: c. i. The dose to e embryo / fetus from radionuclides in the embryo / fetus and radionuclides in the declared,.egnant woman; and ii. The dose that is most representative of the dose to the embryo / fetus from external radiation, that is, in the mother's lower torso region-(1) If multiple measurements have not been made, assignment of the highest deep dose equivalent for the declared pregnant woman shall be the dose to the embryo / fetus, in accordance with D.205c.; or (2) If multiple measurements have been made, assignment of the deep dose equivalent for the declared pregnant woman from the individual monitoring device which is most representative of the dose to the embryo / fetus shall be the dose to the embryoffetus. Assignment of the highest deep dose equivalent for the declared I 1he Nanonal Councilon Radianon l'rotectwn andMeawrement.s reconunended m NCRP Report No. 91 "RecommenJauons on 1.tnuts for Errosure to lom:mg Rahanon* (June I,1987) that no more than 0.3 mSv (0.05 rem) to the embryofetus be received m any one month Dil44

k D208. D30l SSRCR l'olume i..lugust I997 Draft pregnant woman to the embryo / fetus is not required unless that dose is also the most representative deep dose equivalent for the region of the embryo / fetus.' d. If by the time the woman declares pregnancy to the licensee or registrant, the dose to the embryo / fetus has exceeded 4.5 mSv (0.45 rem), the licensee or registrant shall be deemed to be in compliance with D.208a. if the additional dose to the embryo / fetus does not exceed 0.5 mSv (0.05 rem) during the remainder of the pregnancy. i l Radiation Dose Limits for Individual Members of'the Public q Sec D 301 - Dose Limits for Individual Members of the Public. Each licensee or registrant shall conduct operations so that: a. ^ i. Except as provided in D.301a.iii., the total effective dose equivalent to individual members i of the public from the licensed or registered operation does not exceed 1 mSv (0.1 rem)in a year, exclusive of the dose contribution from the licensee's or registrant's disposal of a radioactive materialinto sanitary sewerage in accordance with D.1003;" and ii. The dose in any unrestricted area from external sources does act exceed 0.02 mSv (0.002 rem)in any one hour; and i iii. The total effective dose equivalent to individual members of the public from infrequent exposure to radiation from radiation machines does not exceed 5 mSv (0.5 rem). b. If the licensee or registrant permits members of the public to have access to restricted areas, the limits for members of the public continue to apply to those individuals. A licensee, registrant, or an applicant for a license or registration may apply for prior Agency i c. authorization to operate up to an annual dose limit for an individual member of the public of 5 i mSv (0.5 rem). This application shallinclude the following information: i. Demonstration of the need for and the expected duration of operations in excess of the l limit in D.301a.; and 5 ii. The licensee's or registrant's program to assess and control dose within the 5 mSv (0.5 rem) annuallimit; and iii. The procedures to be followed to maintain the dose ALARA.

• Retraft shallnot be requiredfor locations withinfucihties where on& rahation machines existedprior so fthe effective date of these regulutmnsf und met the prevwns requirements of 3 mSv (DJ rem) in ayar.

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Sec. D 30l. D303, D.80t MRCR Iblume I.lupat 1997 Draft [d. In addition to the requirements of Part D, a licensee or registrant subject to the provisions of the Environmental Protection Agency's generally applicable environmental radiation standards in 40 CFR 190 shall comply with those standards.) (e. The Agency may impose additional restrictions on radiation levels in unrestricted areas and on the total quantity of radionuclides that a licensee or registrant may release in emuents in order to restrict the collective dose.] Sec. D.302 - Compliance with Dose Limits for Individual Members of the Public. The licensee or registrant shall make or cause to be made surveys of radiation levels in a. unrestricted areas and radioactive matvials in emuents released to unrestricted areas to demon-strate compliance with the dose limits for individual members of the public in D.301. b. A licensee or registrant shall show compliance with the annual dose limit in D.301 by: i. Demonstrating by measurement or calculation that the total effective dose equivalent to the individual likely to receive the highest dose from the licensed or registered operation does not exceed the annual dose limit; or ii. Demonstrating that: (1) The annual average concentrations of radioactive material released in gaseous and liquid em.icnts at the boundary of the unrestricted area do not exceed the values specified in Table 11 of Appendix B; and (2) If an individual were continuously present in an unrestricted area, the dose from external sources would not exceed 0.02 mSv (0.002 rem) in an hour and 0.5 mSv (0.05 rem)in a year. Upon approval from the Agency, the licensee or registrant may adjust the emuent concentration c. values in Appendix B, Table 11, for members of the public, to take into account the actual physical and chemical characteristics of the emuents, such as aerosol size distribution, solubility, density, radioactive decay equilibrium, and chemical form. (Testing for Leakage or Contamination of Scaled Sources Sec D 401 - Testine for Leakage or Contamination of Scaled Sources The licensee or registrant in possession of any sealed source shall assure that: a. i. Each sealed source, except as specified in D.40lb., is tested for leakage or contamination and the test results are received before the sealed source is put into use unless the licensee or registrant has a certificate from the transferor indicating that the sealed source was tested within 6 months before transfer to the licensee or registrant; D13G

= ~M U MI SSRCR IWume I..lugust 199? Draft ii. Each sealed source that is not designed to emit alpha particles is tested for leakage or contamination at intervals not to exceed 6 months or at alternative intervals approved by the Agency, aller evaluation of information specified by C.281.iv. and v. of these regulations, an Agreement State, a Licensing State, or the Nuclear Regulatory Commission; iii. Each sealed source that is designed to emit alpha particles is tested for leakage or contamination at intavals not to exceed 3 months or at alternative intervals approved by the Agency, after evaluation of information specificd by C.281.iv. and v. of these regulations, an Agreement State, a Licensing State, or the ' Nuclear Regulatory Commission; iv. For each scaled source that is required to be tested for leakage or contamination, at any other time there is reason to suspect that the sealed source might have been damaged or might be leaking, the licensee or registrant shall assure that the sealed source is tested for leakage or contamination before further use; Tests for leakage for all scaled sources, except brachytherapy sources manufactured to v. contain radium, shall be capable of detecting the presence of 185 Bq (0.005 pCi) of radioactive material on a test sample. Test samples shall be taken from the sealed source or from the surfaces of the container in which the sealed source is stored or mounted on which one might expect contamination to accumulate. For a sealed source contained in a device, test samples are obtained when the source is in the "off' position; vi. The test for leakage for brachytherapy sources manufactured to contain radium shall be capable of detecting an absolute leakage rate of 37 Bq (0.001 pCi) of radon 222 in a 24 hour period when the collection efficiency for radon-222 and its daughters has been determined with respect to collection method, volume and time; vii. Tests for contamination from radium daughters shall be taken on the interior surface of brachytherapy source storage containers and shall be capable of detecting the presence of 185 Bq (0.005 pCi) of a radium daughter which has a half-life greater than 4 days. b. A licensee or registrant need not perform test for leakage or contamination on the following sealed sources: i. Scaled sources containing only radioactive material with a half life ofless than 30 days; ii. Scaled sources containing only radioactive material as a gas; iii. Scaled sources containing 3.7 MBq (100 pCi) or less of beta or photon-emitting material or 370 k.Bq (10 pCi) or less of alpha emitting material; iv. Scaled sources containing only hydro' a-3; D1444

SSRCR l'oluae I.tugust I997 Dm)! Sec. D Ani. D $U \\ v. Seeds ofiridium 192 encased in nylon ribbon; and vi. Scaled sources, except teletherapy and brachytherapy sources, which are stored, not being used and identified as in storage. The licensee or registrant shall, however, test each such scaled source for leakage or contamination and receive the test resuhs before any use or transfer unless it has been tested for leakage or contamination within 6 months before the date of use or transfer. Tests for leakage or contamination from sealed sources shall be performed by persons specifically c. authorized by the Agency, an Agreement State, a Licensing State, or the Nuclear Regulatory Commission to perform such services. d. Test results shall be kept in units of becquerel or microcurie and maintained for inspection by the Agency. Records of test results for scaled sources shall be made pursuant to D.1104. The following shall be considered evidence that a sealed source is leaking: c. i. The presence of 185 Bq (0.005 pCi) or more of removable contamination on any test sample; ii. Leakage of 37 Bq (0.001 pCi) of radon-222 per 24 hours for brachytherapy sources manufactured to contain radium; iii. The presence of removable contamination resulting from the decay of 185 Bq (0.005 Ci) or more of radium. f. The licensee or registrant shall immediately withdraw a leaking sealed source from use and shall take action to prevent the spread of contamination. The leaking sealed source shall be repaired or disposed ofin accordance with this Part. g. Reports of test results for leaking or contaminated scaled sources shall be made pursuant to D.1208.] Suneys and Monitoring Sec D 501 - General a. Each licensee or registrant shall make, or cause to be made, surveys that: i. Are necessary for the licensee or registrant to comply with Part D; and ii. Are necessary under the circumstances to evaluate: (1) Radiation levels, and D15&5

5x D $0l. D $03 h5RCH l'olunw I..lugrat I997 Dnty (2) Concentrations or quantities of radioactive material; and (3) The potential radiological hazards that could be present. b. The licensee or registrant shall ensure that instruments and equipment used for quantitative radiation measurements, for example, dose rate and emuent monitoring, are calibrated at intervals not to exceed 12 months for the radiation measured, except when a more frequent interval is specified in another applicable Part of these regulations or a license condition. All personnel dosimeters, except for direct and indirect reading pocket ionization chambers and c. those dosimeters used to measure the dose to any extremity, that require processing to determine the radiation dose and that are used by licensees and registrants to comply with D.201, with other applicable provisions of these regulations, or with conditions specified in a license or registration shall be processed and evaluated by a dosimetry processor: i. Ilolding current personnel dosimetry accreditation from the National Voluntary Laboratory Accreditation Program of the National Institute of Standards and Technology; and ii. Approved in this accreditation process for the type of radiation or radiations included in the National Voluntary Laboratory Accreditation Program that most closely approximates the type of radiation or radiations for which the individual wearing the dosimeter is monitored. d. The licensee or registrant shall ensure that adequate precautions are taken to prevent a deceptive exposure of an individual monitoring device. Sec D 502 Conditions Requirinu individual Monitorine of External and internal Occupational Dose Each licensee or registrant shall monitor exposures from sources of radiation at levels sumcient to demonstrate compliance with the occupational dose limits of Part D As a minimum: Each licensee or registrant shall monitor occupational exposure to radiation and shall supply and a. require the use of individual monitoring devices by: i. Adults likely to receive, in 1 year from sources external to the body, a dose ir, ncess of 10 percent of the limits in D.201a.; and ii. Minors and declared pregnant women likely to receive, in 1 year from sources external to the body, a dose in excess of 10 percent of any of the applicable limits in D.207 or D.208; and iii. Individuals entering a high or very high radiation area; iv. Individuals wori;ing with medical fluoroscopic equipment. Dl6M

%RCR Iblume i..tugust 1997 Draft % n t)502.t)$03 (1) An individual monitoring desice used for the dose to an embryo / fetus of a declared pregnant woman, pursuant to D.208a., shall be located under the protective apron at the waist. 4 (2) An individual monitoring device used for eye dose equivalent shall be located at the neck, or an unshielded location closer to the eye, outside the protective apron. (3) When only 1 individual monitoring desice is used to determine the effective dose pquivalent for external radiation pursuant to D.201c.ii., it shall be located at the neck outside the protective apron. When a second individual monitoring device is used, for the same purpose, it shall be located under the protective apron at the waist. The second individual monitoring device is required for a declared pregnant woman. b. Each licensee or registrant shall monitor, to determine compliance with D.204, the occupational intake of radioactive material by and assess the committed effective dose equivalent to. i. Adults likely to receive, in 1 year, an intake in excess of 10 percent of the applicable ALI in Table 1, Columns I and 2, of Appendix B; and ii. hiinors and declared pregnant women likely to receive, in 1 year, a committed effective dose equivalent in excess of 0.5 mSv (0.05 rem). Sec D 503 - Location ofindividual N1onitorine Devices Each licensee or registrant shall ensure that individuals who are required to monitor occupational doses in accordance with D.502a wear individual monitoring devices as follows: An individual monitoring device used for monitoring the dose to the whole body shall be worn at a. the unshielded location of the whole body likely to receive the highest exposure. When a protective apron is worn, the location of the individual monitoring device is typically at the neck (collar), b. An individual monitoring device used for monitoring the dose to an embryo / fetus of a declared pregnant woman, pursuant to D.208a., shall be located at the waist under any protective apron being worn by the woman, An individual monitoring device used for monitoring the eye dose equivalent, to demonstrate c. compliance with D.201a.ii.(1), shall be located at the neck (collar), outside any protective apron being worn by the monitored individual, or at an unshielded location closer to the eye, d. An individual monitoring device used for monitoring the dose to the extremities, to demonstrate compliance with D.20la.ii.(2), shall be worn on the extremity likely to receive the highest exposure. Each individual monitoring device shall be oriented to measure the highest dose to the extremity being monitored. D17H

SN D $ t S%lh *R I Wume i.. In.enst IVV ?Drah Control of Exposure from External Sources in Restricted Areas Sec D 601 - Control of Access to liigh Radiation Areas The licensee or.'egistrant shall ensurg'that each entrance or access point to a high radiation area a. has one or more of the following featu'res: i. A control device that, upon entry into the area, causes the level of radiation to be reduced below that level at which anindividual might receive a deep dose equivalent of 1 mSv (0.1 rem)in I hour at 30 centimeters from the source of radiation or from any surface that the radiaticn penetrates; or ii. A control device that energizes a conspicuous visible or audible alarm signal so that the individual entering the high radiation area and the supervisor of the activity are made aware of the entry; or iii. Entryways that are locked, except during periods when access to the areas is required, with positive control over each individual entry. b. In place of the controls required by D.601a. for a high radiation area, the licensee or registrant may substitute continuous direct or electronic surveillance that is capable of preventing unauthorized entry. The licensee or registrant may apply to the Agency for approval of alternative methods for c. controlling access to high radiation areas. d. The licensee or registrant shall establish the controls required by D.601a and c. in a way that does not prevent individuals from leaving a high radiation area. The licensee or registrant is not required to control each entrance or access point to a room or c. other area that is a high radiation area solely because of the presence of radioactive materials prepared for transpon and packaged and labeled in accordance with the regulations of the Department of Transportation provided that: i. The packages do not remain in the area longer than 3 days; and ii The dose rate at I meter from the external surface of any package does not exceed 0.1 mSv (0.01 rem) per hour. f. The licensee or registrant is not required to control entrance or access to rooms or other areas in hospitals solely because of the presence of patients containing radioactive materia!, provided that there are personnel in attendance who sre taking the necessary precautions to prevent the exposure ofindi&als to radiation or radioactive neierial in excess of the established limits in Dl848

7 MRL*R Iblume I.lupat I997 Dmp Sec. D 60l. D 604 Pan D and to operate within the ALARA provisions of the licensce's or registrant's radiation protection program. j_ g. The registrant is not required to control entrance or access to rooms or other areas containing sources of radiation capable of producing a high radiation area as described in D.601 if the-registrant has met all the specific requirements for access and control specified in other applicable L Parts of these regulations, such as, Part E for industrial radiography, Pan F for x rays in the healing arts, and Part I for panicle accelerators. Sec D 602 - Control of Access to Very Hiuh Radiation Areas. In addition to the requirements in D.601, the licensee or registrant shall institute measures to a. ensure that an individual is not able to gain unauthorized or inadvenent access to areas in which radiation levels could be encountered at 5 Gy (500 rad) or more in I hour at I meter from a source of radiation or any surface through which the radiation penetrates. This requirement does not apply to rooms or areas in which diagnostic x ray systems are the only source of radiation, or to non-self shielded irradiators. ~ b. The registrant is not required to control entrance or access to rooms or other areas containing sources of rr Jiation capable of producing a very high radiation area as described in D.602a. if the registrant has met all the specific requirements for access and control specified in other applicable Parts of these regulations, such as, Part E for industrial radiography, Part F for x-rays in the healing arts, and Part i for particle accelerators. See D 603 - Control of Access to Very Hiuh Radiation Areas --Irradiators. Section D.603 applies to licensees or registrants with sources of radiation in non-self shielded a. irradiators. Section D.603 does not apply to sources of radiation that are used in teletherapy, in industrial radiography, or in completely self shielded irradiators in which the source of radiation is both stored and operated within the same shielding radiation barrier and, in the designed configuration of the irradiator, is always physically inaccessible to any individual and cannot create high levels of radiation in an area that is accessible to any individual.. b. Each area in which there may exist radiation levels in excess of 5 Gy (500 rad) in I hour at I meter from a source of radiation that is used to irradiate materials shall meet the following requirements: i. Each entrance or access point shall be equipped with entry control devices which: (1) Function automatically to prevent any individual from inadvertently entering a very high radiation area; and (2) Permit deliberate entry into the area only afler a control device is actuated that causes the radiation level within the area, from the source of radiation, to be reduced below that at which it would be possible for an individual to receive a deep dose equivalent in excess of 1 mSv (0.1 rem)in I hour; and Dl919

Sm.Dho4 . SSRCR l'ohwre I. Augun IV9? Draft (3) Prevent operation of the source of radiation ifit would produce radiation levels in. the area that could result in a deep dose equivalent to an individual in excess of 1 mSv (0.1 rem)in I hour. 3 ii. Additional control devices shall be provided so that, upon failure of the entry control devices to function as required by D.603b.i.: (1) The radiation level within the area, from the source of radiation, is reduced below that at which it would be possible for an individual to receive a deep dose equivalent in excess of 1 mSv (0.1 rem)in 1 hour; and (2) Conspicuous visible and audible alarm signals are generated to make an individual attempting to enter the area aware of the hazard and at least one other authorized individual, who is physically present, familiar with the activity, and prepared to render or summon assistance, aware of the failure of the entry control devices, iii. The licensee or registrant shall proside control desices so that, upon failure or removal of physical radiation barriers other than the scaled source's shielded storage container: (1) The radiation level from the source of radiation is reduced below that at which it would be possible for an individual to receive a deep dose equivalent in excess of 1 mSv (0.1 rem)in 1 hour; and (2) Conspicuous visible and audible alarm signals are generated to make potentially affected individuals aware of the hazard and the licensee or registrant or at least one other individual, who is familiar with the activity and prepared to render or summon assistance, aware of the failure or removal of the physical barrier. iv. When the shield for stored scaled sources is a liquid, the licensee or registrant shall provide means to monitor the integrity of the shield and to signal, automatically, loss of adequate shielding. Physical radiation barriers that comprise permanent structural components, such as walls, v. that have no credible probability of failure or removal in ordinary circumstances need not meet the requirements of D.603b iii. and iv. vi. Each area shall be equipped with devices that will automatically generate conspicuous visible and audible alarm signals to alert personnel in the area before the source of radiation can be put into operation and in time for any individual in the area to operate a clearly identified control device, which must be installed in the area and which can prevent the source of radiation from being put into operation. vii. Each area shall be controlled by use of such administrative procedures and such devices as are necessary to ensure that the area is cleared of personnel prior to each use of the source ofradiation. D2020

M D(dN. SVRCR t'olume i vlupal 1997 Dean sili. Each area shall be checked by a radiation measurement to ensure that, prior to the first individuafs entry into the area aner any use of the source of radiation, the radiation level from the source of radiation in the area is below that at which it would be possible for an individual to receive a deep dose equivalent in excess of I mSv (0.1 rem) in I hour, ix. The entry control devices required in D.603b.i. shall be tested for proper functioning. See D.1110 for recordkeeping requirementa (1) Testing shall be conducted prior to initial operation with the source of radiation on any day, unless operations were continued uninterrupted from the previous day; and (2) Testing shall be conducted prior to resumption of operation of the source of radiation afler any unintentional intermption; and (3) The licensee or registrant shall submit and adhere to a schedule for periodic tests of the entry control and warning systems. The licensee or registrant shall not conduct operations, other than those necessary to place x. the source of radiation in safe condition or to efTect repairs on controls, unless control devices are functioning properly, xi. Entry and exit portals that are used in transporting materials to and from the irradiation a;ea, and that are not intended for use by individuals, shall be controlled by such devices and administrative procedures as are necessary to physically protect and warn against inadvertent entry by any individual through these portals. Exit portals for irradiated materials shall be equipped to detect and signal the presence of any loose radioactive material that is carried toward such an exit and automatically to prevent loose radioactive material from being carried out of the area. Licensees, registrants, or applicants for licenses or registrations for sources of radiation within the c. pursiew of D.603b. which will be used in a variety of positions or in locations, such as open fields or forests, that make it impracticable to comply with certain requirements of D.603b., such as those for the automatic control of radiation levels, may apply to the Agency for approval of alternative safety measures. Alternative safety measures shall provide personnel protection at least equivalent to those specified in D.603b. At least one of the alternative measures shall include an entry-preventing interlock control based on a measurement of the radiation that ensures the absence of high radiation levels before an individual can gain access to the area where such sources of radiation are used, d. The entry control devices required by D.603b. and c. shall be established in such a way that no individual will be prevented from leaving the area. D21M

See D TOIA D 103 S%RCR Iblume i.,\\ugust I997 Drap Respiratory Pr tection and Contrcis to Restrict Internal Exposure in Restricted Areas Sec D 701 Use of Process or Other Enttineering Controls The licensee or registrant shall use, to the extent practicable practical, process or other engineering controls, such as, containment or ventilation, control the concentrations of radioactive material in air. Sec D 702 - Use of Other Controls, When it is not practicable practical to apply process or other engineering controls to control the concentrations of radioactive material in air to values below those de6ne an airborne radioactivity area, the licensee or registrant shall, consistent with maintaining the total efTective dose equivalent ALARA, increase monitoring and lirnit intakes by one or more of the following means: a. Control of access; or Limitation of exposure times; or Use of respiratory protection equipment; or c. d. Other controls Sec D 703 - Use ofIndividual Respiratory Protection F;gujipment. If the licensee or registrant uses respiratory protection equipment to limit intakes pursuant to a D.702: i-Except as provided in D.703aii., the licensee or registrant shall use only respiratory protection equipment that is tested and certi6ed or had certi6 cation extended by the National Institute for Occupational Safety and Health and the Mine Safety and Health Administration; ii The licensee or registrant may use equipment that has not been tested or certi6ed by the National Institute for Occupational Safety and Health and the Mine Safety and Health Administration has not had certi6 cation extended by the National Institute for Occupational Safety and Health and the Mine Safety and Health Administration, or for which there is no schedule for testing or certi6 cation, provided the licensee or registrant has submitted to the Agency and the Agency has approved an application for authorized use of that equipment, including a demonstration by testing, or a demonstration on the basis of test information, that the material and performance characteristics cf the equipment are capable of providing the proposed degree of protection under anticipated conditions of use, iii. The licensee or registrant shallimplement and maintain a respiratory protection program that includes: D22N l

SSRCR Iblume i..lu.eutt i997 I) tap See D 70.1 (1) Air sampling sufTicient to identify the potential hazard, permit proper equipment selection, and estimate exposures; and (2) Surveys and bioassays, as appropriate, to evaluate actual intakes; and (3) Testing of respirators for operability immediately prior to each use; and (4) Written procedures regarding selection, fitting, issuance, maintenance, and testing of respirators, including testing for operability immediately prior to each use; supersision and training of personnel; monitoring, including air sampling and bioassays; and recordkeeping; and (5) Determination by a physician prior to initial fitting of respirators, and-atleast-silher every 12 months thereafler or._pstiedisally at a frequency determined _ _by._a physician, that the individual user is physica!ly-ebb medicallyJit to use the respiratory protection equipment; iv. The licensee or registrant shall issue a written pe icy statement on respirator usage r covering: (1) The use of process or other engineering controls, instead of respirators; and (2) The routine, nonroutine, and emergency use of respirators; and (3) The length of periods of respirator use and relief from respirator use; The licensee or registrant shall advise each respirator user that the user may leave the area v. at any time for relief from respirator use in the event of equipment malfunction, physical or psychological distress, procedural or communication failure, significant deterioration of operating conditions, or any other conditions that might require such relief, vi. The licensee or registrant shall use respiratory protection equipment within the equipment manufacturer's expressed limitations for type and mode of use and shall provide proper visual, communication, and other special capabilities, such as adequate skin protection, when needed. b. When estimating exposure of individuals to airborne radioactive materials, the licensee or registrant may make allowance for respiratory protectica equipment used to limit intakes pursuant to D 702, provided that the following conditions, in addition to those in D.703a., are satisfied: i The licensee or registrant selccts respiratory protection equipment that provides a protection factor, specified in Appendix A, greater than the multiple by which peak concentrations of airborne radioactive materials in the working area are expected to exceed the values specified in Appendix B, Table I, Column 3. However, if the selection of respiratory protection equipment with a protection factor greater than the peak concentration-muhiplc_defmed_in_the_pIssedmg.sentcace is inconsistent with the goal D23M

Sec. D.10.1, D t(O l SSRCR IblxwI iupalI999 Draft specified in D.702 of keeping the total effective dose equivalent ALARA, the licensee or registrant may select respiratory protection equipment with a lower protection factor provided that such a selection would result in a total effective dose equivalent that is ALARA. The concentration of radioactive material in the air that is inhaled when respirators are worn may be initially estimated by dividing the average concentration in air, during each period of unintermpted use, by the protection factor. If the exposure is later found to be greater than initially estimated, the corrected value shall be used; if the exposure is later found to be less than initially estimated, the corrected value may be used; ii. The licensee or registrant shall obtain authorization from the Agency before assigning respiratory protection factors in excess of those specified in Appendix A. The Agency may authorize a licensee or registrant to use higher protection factors on receipt of an application that: (1) Describes the situation for which a teed exists for higher protection factors; and (2) Demonstrates that the respiratory protection equipment provides these higher protection factors under the proposed conditions of use. In an emergency, the licensee or registrant shall use as emergency equipment only respiratory c. protection equipment that has been specifically certified or had certification extended for emergency use by the National Institute for Occupational Safety and Health and the Mine Safety and llealth Administration. d. The licensee or registrant shall notify the Agency in writing at least 30 days before the date that respiratory protection equipment is first used pursuant to either D.703a. or b. Storage and Control of Licensed or Registered Sources of Radiation Sec. D 801 - Security and Control of Licensed or Registered Sources of Radiation. a. The licensee or registrant shall secure licensed or registered radioactive material from unauthorized removal or access. b. The licensee or registrant shall maintain constant surveillance, and use devices or administrative procedures to prevent unauthorized use oflicensed or registered radioactive material that is in an unrestricted area and that is not in storage. The registrant shall secure registered radiation machircs from unauthorized removal. c. d. The registrant shall use devices or administrative procedures to prevent unauthorized use of registered radiMion machines. D2424

~ ___ _.-..._..__._. ~._.___ _ -. _ _. _ _ - __-._ __ _ _.. _ - Sec.'D 90l. l} 9u: SSRCR l'olume i. Aupnt I997 Drqll Precautionary Procedures Sec D 001 - Caution Siuns. e 'a. - Standard Radiation Symbol. ' Unless otherwise authorized by the Agency, the symbol' prescribed by D.901 shall use the colors magenta, or purple, or black on yellow background. The symbol prescribed is the three bladed design as follows: , r 60' a a! 4-l l $ $$I I. Cross. hatched area is to be magenta, or purple, or black, and 2. 'the background is to be 3cllow. Figure 1. Radiation Symbol. b. Exception to Color Requirements for Standard Radiation Symbol Notwithstanding the requirements of D.901a., licensees or registrants are authorized to label sources, source holders, _ device components containing sources of radiation that are subjected to high temperatures, with conspicuously etched or stamped radiation caution symbols and without a color requirement. c. Additional Information on Siuns and Labels in addition to the contents of signs and labels prescribed in Part D, the licensee or registrant may provide, on or near the required signs and labels, additional information, as appropriate, to make individuals aware of potential radiation exposures and to minimize the exposures. Sec. D 902 - Postinu Reauirements . a. Postinu of Radiation Areas. The licensee or registrant shall post each radiation area with a - conspicuous sign or signs bearing the radiation symbol and the words " CAUTION, RADIATION ARE A." . b. Postine of Hiuh Radiation Areas-The licensee or registrant shall post each high radiation area i with a conspicuous sign or signs bearing the radiation symbol and the words " CAUTION, HIGH --ERADIATION AREA" or " DANGER, HIGH RADIATION AREA." D2526

~ A D509di .%RL*R l'olume i..hogust IV97 Uraft Postinu of Very 1lich Radiation Areas The licensee or registrant shall post each very high c. radiation area with a conspicuous sign or signs bearing the radiation symbol and words " GRAVE DANGER, VERY lilGH RADIATION AREA." d. Postinu of Airborne 13adioacdvity Attal The licensee or registrant shall post each airborne radioactivity area with a conspicuous sign or signs bearing the radStion symbol and the words " CAUTION, AlRBORNE RADIOACTIVITY AREA" or " DANGER, AIRBORNd RADIOACTIVITY AREA " The listjne of Areas or Rooms in which Licsawd or Reulstered Matedal is Used or Storeds e. licensee or iegistrant shall post each arra or room in which there is used or stored an amount of licensed or registered material exceediag 10 times the quantity of such material specified in Appendix C with a conspicutus sign or signs bearing the radiation symbol and the words " CAUTION, RADIOACTIVE MATERIAL (S)" or " DANGER, RADIOACTIVE M ATERI AL(S) " Sec_p 903 - Exceptions to Postinu Requirement A licensee or registrant is not required to post caution signs in areas or rooms containing sources a. of radiation for periods ofless than 8 hours, if each of the following conditions is met: i. The sources of radiation are constantly attended during these periods by an individual who takes the precautions necessary to prevent the exposure of individuals to sources of radiation in excess of the limits established in Part D, and ii. The area or room is subject to the licensee's or registrant's control. b. Rooms or other area 3 in hospitals that are occupied by patients are not required to be posted with caution signs pursuant to D 902 provided that the requirements of G 38a.ii. or G 44a ii. of these regulations are met. Rooms or other areas in hospitals that are occupied by patients are not required to be posted with c. caution signs, provided that: i. A patient being treated with a permanent implant could be released from confinement pursuant to G 26 of these regulations, or ii A patient being treated with a therapeutic radiopharmaceutical could be released from confinement pursuant to G 38c. of these regulations d. A room or area is not required to be posted with a caution sign because of the presence of a scaled source provided the radiation kvel at 30 centimeters from the surface of the sealed source container or housing does not exceed 0.05 mSv (0.005 rem) per hour. D2626

I SSRCR l'olurne i..lugust I997 Draj) Sec (W0 i)40$ A room or area is not required to be posted with a caution sign because of the presence of c. radiation machines used solely for diagnosis in the healing arts. S_ge D 004 - Labeling Containers and Radiation Machines The licensee or registrant shall ensure that each container oflicensed or registered material bears a a. durable, clearly visible label bearing the radiation symbol and the words " CAUTION, RADIOACTIVE MATERIAL" or " DANGER, RADIOACTIVE MATERIAL." The label shall also provide information, such as the radionuclides present, an estimate of the quantity of radioactivity, the date for which the activity is estimated, radiation levels, kinds of materials, and mass enrichment, to permit individuals handling or using the containers, or working in the vicinity of the containers, to take precautions to avoid or minimize exposures. b. Each licensee or registrant shall, prior to removal or disposal of empty uncontaminated containers to unrestricted areas, remove or deface the radioactive material label or otherwise clearly indicate that the container no longer contains radioactive materials. Each registrant shall ensure that each radiation machine is labeled in a conspicuous manner which c. cautions individuals that radiation is produced when it is energized. lig.q_D 905 - Exemptions to Labeling Requirements A licensee or registrant is not required to label: Containers holding licensed or registered material in quantities less than the quantities listed in a. Appendix C; or b. Containers holding litensed or registered material in concentrations less than those specified in Table III of Appendix B; or Containers attended by an individual who takes the precautions necessary to prevent the exposure c. of;ndividuals in excess of the limits established by Part D, or d. Containers when they are in transport and packaged and labeled in accordance with the regulations of the Department of Transportation;l or Containers that are accessible only to individuals authorized to handle or use them, or to work in c. the vicinity of the containers, if the contents are identified to these individuals by a readily available written record. Examples of containers of this type are containers in locations such as water filled canals, storage vaults, or hot cells. The record shall be retained as long as the containers are in use for the purpose indicated on the record; or f. Installed manufacturing or process equipment, such as piping and tanks. helmg ofpadages wnianung rahoaasve matersah a s regnared by the uepartment of Transportation f the amount and nye of radioactive materia: ds the lunas jhr an eucpted quanton or artale as defined wsJ lunned by Department of Transportatwn regulatwns 49 CFR 173.403tm) and tw> an 21.J N D27N

^ SA D 906 .wn rohnne I..tugrat 1997 orap Sec D 906 - Procedures for Receivinu and Openine Packanet Each licensee or registrant who :xpects to receive a package containing quantities of radioactive a. material in excess of a Type A quantity, as defmed in T.2 and Appendix A of Part T of these regulations, shall make arrangements to receive: i. The package when the carrier otters it for delivery; or i ii. The notification of the arrival of the package at the carrier's terminal and to take possession of the package expeditiously. b. Each licensee or registrant shall: Monitor the external surfaces of a labeled package for radioactive contamination unless f i. the package contains only radioactive material in the form of gas or in special form as defmed in A.2 of these regulations; and Monitor the external surfaces of a labeled package for radiation levels unless the package F ii. contains quantities of radioactive material that are less than or equal to the Type A quantity, as defined in T.2 and Appendix A of Part T of these regulations; and iii. Nionitor all packages known to contain radioactive material for radioactive contamination and radiation levels if there is evidence of degradation of package integrity, such as packages that are crushed, wet, or damaged. The licensee or registrant shall perform the monitoring required by D.906b. as soon as practicable c. afler receipt of the package, but not later than 3 hours after the package is received at the licensee's or registrant's facility ifit is received during the licensee's or registrant's normal working hours or if there is evidence of degradation of package integrity, such as a package that is crushed, wet, or damaged. If a package is received after working hours, and has no evidence of degradation of package integrity, the package shall be monitored no later than 3 hours from the beginning of the next working day. d. The licensee or registrant shall immediately notify the fmal delivery carrier and, by telephone and either telegram, mailgram, or facsimile, the Agency when: i. Removable radioactive surface contamination exceeds the limits of T.15h. of these regulations; or ii. External radiation levels exceed the limits of T.15i. and j. of these regulations. beled means labeled wah a IMhoactne lihae I, Yellow II. or Yellow Ill label as specJied in Department of Transportation regulations 49 CFR 172 73.436-440. D2828

_._.. ~.. _ -. _ _ _ _ _ _ _ _ SNRCR \\ *olume i.hipal I997 Dra)1. Sec. D.906, ty tou t c. Each licensee or registrant shall: 1. Establish, maintain, and retain written procedures for safely opening packages in which_ radioactive material is received; and ii. Ensure that the procedures are followed and that due consideration is given to special instructions for the type of package being opened. f. Licensees or registrants transferring special form sources in vehicles owned or operated by the licensee or registrant to and from a work site are exempt from the contamination monitoring requirements of D.906b., but are not exempt from the monitoring requirement in D.906b. for nicasuring radiation levels that ensures that the source is still properly lodged in its shield. Waste Disposal Sec D 1001 General Requirement 1. A licensee or registrant shall dispose of ficensed or registered material only: a. 4 S of i. By transfer to an authorized recipient as provided in D.1006 or in Parts C, M, or U these regulations, or to the Depa.. ment of Energy; or ii. By decay in storage; or iii. By release in emuents within the limits in D.301; or iv. As authorized pursuant to D.1002, D.1003, D.1004, or D.1005. -b. A person shall be specifically licensed or registered to receive waste containing licensed or registered material from other persons for: i. Treatment prior to disposal; or ' ii. Treatment or disposal by incineration; or iii. Decay in storage, or iv. Disposal at a land disposal facility licensed pursuant to Part M of these regulations; or Storage until transferred to a storage or disposal facility autherized to receive the waste. v. ? l' art U h on draftfonn. D2929 =.

Sec. D.t000 DIt003 ^ l %RCR Iblume I.,tugust 199? Draft Method for Obtaining Accroval of Proposed Discosal Procedures A licensee or Sec. D 1002 registrant or applicant for a license or registration may apply to the Agency for ap procedures, not otherwise authorized in these regulations, to dispose oflicensed generated in the licensee's or registrant's operations. Each application shall include: A description of the waste containing licensed or registered material to be dispose the physical and chemical properties that have an impact on risk evaluation, and the a. manner and conditions of waste disposal; and An analysis and evaluation of pertinent information on the nature of the environment; an b. The nature and location of other potentially affected facilities; and c. Analyses and procedures to ensure that doses are maintained ALARA and within d. in Part D. Sec D.1003 Disposal by Release into Sanitary Sewerage-A licensee or registrant may discharge licensed or registered material into sanitary sewer a. each of the following conditions is satisfied: The material is readily soluble, or is readily dispersible biological material, in water; and i. The quantity oflicensed or registered radioactive material that the licensee or reg ii. releases into the sewer in 1 month divided by the average monthly solume of water released into the sewer by the licensee or registrant does not exceed the concentration listed in Table ill of Appendix B; and If more than one radionuclide is released, the following conditions must also be satisfied: iii. The licensee or registrant shall determine the fraction of the limit in Table Ill of (1) Appendix B represented by discharges into sanitary sewerage by dividing the actual monthly average concentration of each radionuclide released by the licensee or registrant into the sewer by the concentration of that radionuclide listed in Table 111 of Appendix B; and (2) The sum of the fractions for each radionuclide required by D 1003a.iii.(1) does not exceed unity; and iv. The total quantity of licensed or registered radioactive material that the licensee or registrant releases into the sanitary sewerage in a year does not exceed 185 GBq hydrogen-3,37 GBq (1 Ci) of carbon 14, and 37 GBq (I Ci) of all other radioactive materials combined, b. Excreta from individuals undergoing medical diagnosis or therapy with radioactive material are not subject to the limitations contained in D.1003a. D30M

WRCR l'olume i. August IV97 Draft -i \\ &c. D l004. U. t006 S_ec. D 1004 JTreatment or Disposal by incinerationi A licensee or registrant may treat or dispose of-- licensed or registered material by incineration only in the form and concentration specified in D.1005 or as specifically approved by the Agency pursuant to D.1002. o I Sec. DIl005 - Disposal of Specific Wastes. A licensee or registrant may dispose of the following licensed or registered material as ifit were a. not radioactive: i. 1,85 kBq (0,05 FCi), or less, of hydrogen 3 or carbon-14 per gram of medium used for liquid scintillation counting; and ii. 1.85 kDq (0.05 FCi), or less, of hydrogen 3 or carbon 14 per gram of animal tissue, averaged over the weight of the entire animal. b. A licensee or registrant shall not dispose of tissue pursuant to D.1005a.ii. in a manner that would permit its use either as food for humans or as animal feed. 4 c; The licensee or registrant shall maintain records in accordance with D.] 109. Sec D.1006 - Transfer for Disposal a.nd Manifests.

a. _.. _ Requirements of D.1006.and Appendix D and G.

i. The requirements of D.1006 and Appendix D and_G are designed to; L (1) cControl transfers oflow level radioactive waste 4atended-for-disposal-at-a4ic+nsed J [ low-level 4adioactive-waste-disposal-facilityr tablish-aananifest-tracking-system; es and-supplement-existing requirements-concerning-transfers and recordkceping for those-wastes-by any_ waste _ generator..ayaste_collectormor_ waste _ptocessor licensee, as defmed inAppenditR..or_Gjn.this_section.3yho_ ships.Jow-lcreLwaste cither_dit.cstly._or indireelly through a waste collector or waste procestofm.to_a liccasedjow-level waste land disposal facility as defined in Part A. Section A 2. _ (2) _. Establish a manifest tracking system; and (3) SupplemenLesistiDgaquirements concerning transfen and recordkeeoing for those wastes, L ___ii. _ ReginningMarsh 1.1998 (effective date of these regulationst all affected licensees must - useAppendiLG_hioI.lo March I.1998 (effective date of these regulations)_ a low level waste disposal facility _ operator otjtslegulatory. authority _mayJequir.c_the. shipper._to_use Appendix D.or Appendix..G._ Licensees _using.Appcodix_D shallcomply withA1006b.i. liciniciusi_ngfpp.cudix G shall comolv with D 1006b.il D3134

Sec, D.1006 D t001, D t10I SSRCR l'olocw I.hogent IVVP Draft hm S.bipillenlofBadioxtiYcMMie Each shipment of radioactive waste designated for disposal at a licensed low level i. radioactive waste disposal facility shall be accompanied by a shipment manifest as specified in Appendix D.I. _ _. ii Any. licensee _ shipping radioactive _wasteintended_focultimate_disposaLalajiccus disposal. facility must do.cument.thejnformation.tequired.on.the_ Agency =s.Uniformlow Litc.LRad!01cliYslastcJJanifest and transfer this recorded information to c.onsigneeja.acc0Idance with AppendjLQ, Each shipment manifest shall include a cenification by the waste generator as specified in c. Appendix D.ll oLApp.cndiLQmAs_appipatiatt. S.te D 1006a.ii. to__dttermine thcappIppf Appendix. Each person involved in the transfer of waste for disposal or in the disposal of waste, inclu d. the waste generator, waste collector, waste processor, and disposal facility operator, shall com with the requirements specified in Appendix D 111 otApp.endisf as apptopriate. Sce__D,10 to determine the appropriate Appendit Sec D 1007 - Compliance with Environmental and Health Protection Reculations Noua a in D.1001, D.1002, D.1003, D.1004. D.1005, or D.1006 relieves the licensee or registrant from complying with other applicable Federal, State and local regulations goveming any other toxic or hazardous p materials that may be disposed of twin accordance with D.1001, D.1002, D.1003, D.1004, D.1005, or D.1006. Records See D.1101 - General Provisions Each licensee or registrant shall use the SI units becquerel, gray, sievert and coulomb per a. kilogram, or the special units curie, rad, rem and roentgen, including multiples and subdisisions and shall clearly indicate the units of all quantities on records required by Part D. b. Not_ withstanding the requirements _of DJ10La.. when recording _information. on_ shipment IMnifeltLAslequiredjrLD 1006b. information must be recorded in_the Intematio. pal System of UnitslSILotiaSland specialunits as_spesi&d in D. I 101a. cb. The licensee or registrant shall make a clear distinction among the quantities entered on the records required by Part D, such as, total etTective dose equivrient, total organ dose equivalent, shallow dose equivalent, eye dose equivalent, deep dose equiv, ant, or committed effective dose equivalent. D32M

MRCR Iblume I,hipal 1997 Ikajl &w D \\ \\02 U tl05 Sec D 1102 - Records of Radiation Protection Programsf ~ Each licensee or registrant shall maintain records of the radiation protection program, including: a. i. The provisions of the program; and ii. Audits and other reviews of program content and implementation. b. The licensee or registrant shall retain the records required by D.1102a.i. until the Agency terminates each pertinent license or registration requiring the record. The licensee or registrant shall retain the records required by D.1102a.ii. for 3 years aner the record is made. Ecg_D 1103 - Records of Surveys Each licensee or registrant shall maintain records showing the results of surveys and calibrations a. required by D.501 and D.906b. The licensee or registrant shall retain these records for 3 years aRet the record is made. b. The licensee or registrant shall retain each of the following records until the Agency terminates each pertinent license or registration requiring the record: i. Records of the results of surveys to determine the dose from external sources of radiation used. in the absence of or in combination with individual monitoring data, in the assessment ofindividual dose equivalents; and ii. Records of the results of measurcments anl calculations used to determine indisidual intakes of radioactive material and used in ihe assessment afinternal dose; and iii. Records showing the results of air sampling, surveys, and bioassays required pursuant to D.703a.iii-(l) and (2); and iv. Records of the results of measurements and calculations used to evaluate the release of radioactive c0luents to the environment. [c. Upon termination of the license or registration, the licensee or registrant shall permanently store records on Agency Form Y or equivalent, or shall make provision with tne Agency for transfer to the Agency.] See D 1104 - Records of Tests for Leakage or Contzninstion of Sealed Sources P.ecords of tests for leakage or contamination of scaled sources [ required by D.401] shall be kept in units of becquerel or microcurie and maintained for inspcction by the Agency for 5 years aner the records are made. Sec. D.1105 - Records of Prior Occupational Dose Toe licensee or registrant shall retain the records of prior occupational dose and exposure history u. as specified in D.205 on Agency Form Y or equivalent until the Agency terminates each pertinent D3313

SSRCR l'olume1.lbgnst !997 Umft ; Sec, D.l103 D.)101 7 license or registration requiring this record. The licensee or registrant shall retain records used in preparing Agency Form Y or equivalent for 3 years after the record is made. (b. Upon termination of the license or registration, the licensee or registrant shall permanently store records on Agency For.n Y or equivalent, or shall make provision with the Agency for transfer to the Agency.] Sec D 1105 -- Records of Planned Special Exposures. For each use of the provisions of D.206 for planned special exposures, the licensee or registrant. af shall maintain records that describe: i.' The exceptional circumstances requiring the use of a planned special exposure; and. ii. The name of the management official who authorized the planned special exposure and a copy of the signed authorization; and lii. What actions were necessary; and iv. Why the actions were necessary; and What precautions were taken to assure that doses were maintained ALARA; and v. vi. What individual and collective doses were expected to result; and vii. The doses actually received in the planned special exposure. bc The licensee or registrant shall retain the records until the Agency terminates each pertinent license or registration requiring these records. [c. Upon termination of the license or registration, f e licensee or registrant shall permanently store records on Agency Form Y or equimlent, or shall make provision with the Agency for transfer to the Agency.] Sec. D 1107 - Records cfIndividual Monitorina Results a. - Recordkeepinu Reauirement: Each licensee or registrant shall maintain records of doses received by all individuals for whom monitoring was required pursuant to D.502, and records of doses received during planned special exposures, accidents, and emergency conditions.' Assessments of dose equivalent and records made using units in etTect before [the effective date of Part D) need not be changed. These records shall include, when applicable: i. The deep dose equivalent to the whole body, eye dose equivalent, shallow dose equivalent to the skin, and shallow dose equivalent to the extremities; and ii. The estimated intake of radionuclides, see D.202; and D34M

&v l)lin7.l)llu9 SSRCA lblume /..fugust /991 Drq// iii. The committed effective dose equivalent assigned to the intake of radionuclides; and iv. The specine information used to calculate the committed effective dose equivalent pursuant to D.204c.; and The total effective dose equivalent when required by D.202; and v. vi. The total of the deep dose equivalent and the committed dose to the organ receiving the highest total dose. b. Renudfr.rpinu Fremtency The licensee or registrant shall make entries of the records specified in D.1107a. at intervals not to exceed 1 year. Repmdicemngfqrmat The licensee or registrant shall maintain the records specified in D.1107a. c. on Agency Form Z, in accordance with the instructions for Agency Form Z, or in clear and legible records containing all the information required by Agency Form Z. d= The licensee or registrant shall maintain the records of dose to an embryo / fetus with the records of dose to the declared pregnant woman. The declaration of pregnancy, including the estimated date of conception, shall also be kept on file, but may be maintained separatelv Gom the dose records. The licensee or registrant shall retain each required form or record until the Agency terminates c. each pertinent license or registration requiring the record. [f. Upon termination of the license or registration, the licensee or registrant shall permanently store records on Agency Form Y or equivalent, or shall make provision with the Agency for transfer to the Agency.] Ses_p 1108_ _J1ecords of Doselo Individual Members of the Publig, ach licensee or registrant shall maintain records sufficient to demonstrate compliance with the a. r dose limit for indiv; dual members of the public. See D.301. b. The licensee or registrant shall retain the records required by D.I108a. until the Agency terminates each pertinent license or registration requiring the record. See D 1109 - R_gcoids of Weste Disposal Each licensee or registrant shall maintain records of the disposal oflicensed or registered materials a. made pursuant to D.1002, D.1003, D.1004, D.1005, Part M of these regulations, and disposal by _ _ ~ _ _ D3SM

xvnw alunA,iugu i /nr thun Elil159DIllt.D1:01 burial in soil, including burials authorized before [ insert effective date of rule that removed the authorization]I b. The licensee or registrant shall retain the records required by D.1109a. until the Agency terminates each peitinent license or registration requiring the record &LD 1110 - Records of Testing Entry Control Devices for Very High Radiation Aisat Each licensee or registrant shall maintain records of tests made pursuant to D.603b.ix. on entry a. control devices for very high radiation areas. These records mest include the date, time, and results of each such test of function. b. The licensee or registrant shall retain the records required by D.llloa. for 3 years aller the record is made. F91mnfln0Ldi Each record required by Part D shall be legible throughout the kc_llull specified retention period. The record shall be the original or a reproduced copy or a microform, provided that the copy or microform is authenticated by authorized personrcel and that the rnicro capable of producing a clear copy throughout the required retention period or the record may also stored in electronic media with the capability for producing legible, accurate, and complete records during the required retention period. Records, such as letters, drawings, and specifications, shall include all pertinent information, such as stamps, initials, and signatures The licensee shall maintain adequate safeguards against tampering with and loss of records Heports kg_D 1201 Reports of Stolen. l.ost. or MissingLicensed or Regbtered Somtes of Radiation. a Ielephone Reports Each licensee or registrant shall report to the Agency by telephone cash stolen, lost, or missing source.of radiation _immediately afler its_ absence _becomes known to the licensee er registrant,.This. require:nent_does.not apply to_ sources.of radiation..that are_not tequited.tp..b.cJicenscipuegi>Jctsi as follows> i If nmediately-aller-ils-occurf ence becomes-know!Ho-the4icensee-of-f egistrant;-stolendost; or-missinglicensed or-f egisteved4adioactive-material 4n-an+ggregate-quantity-equal-to-or greateHhan-l.,000 times the quantity-specified-in-Appendis&under-such-circumstances that-it appeals-tolhelicenseeot-fegistianilhatan-egposure<ould-resulHo4ndividualvin unrestricted afeasr r o previous D 304 perunned bursal ofsnoall quantates ofhcensed ntateroals on walbefore lJarc ofrule that rensoveJ authors:ationj, wa piration D30%

_. - ~ -.. - -. - i i Sw D l20l. 0 l202 WRr *R l'olume I. Aupal 1997 Drqll l _._. jj.----Within-30 days aRef-its-occurrence-becomes4nown-to the-licensee-or-fegiMf ant-lostr Molen,-of-tni6 sing-licensed-of-fegiMeted-fedic;ctive malefiel-4ft-ett-egg;;50t: q=tity l gecater-than-to timesihe4pantittspeci6 edin-AppendsC-thaHatin nsg i iii-I mmedia t ely-a ner -it s-occu r renc e-becomes-k now n-t o-t he -regiu r ant,- a-st olen,-lost ror missing radiation machine-i j b Written Bsports. Each licensee or registrant required to make a repon pursuant to D.1201a. shall, within 30 days aRer making the telephone report, make a written report to the Agency setting forth the following information: 1. A description of the licensed or registered source of radiation involved, including, for radioactive material, the kind, quantity, and chemical and physical form; and, for radiation machines, the manufacturer, model and serial number, type and maximum energy of 1 radiation emitted; ii. A description of the circumstances under which the loss or then occurred; and

iii, A statement of disposition, or probable disposition, of the licensed or registered source of radiation involved, and iv.

Exposures ofindividuals to radiation, circumstances under which the exposures occurred, and the possible total effective dose equivalent to persons in unrestricted areas; and v. Actions that have been taken, or will be taken, to recover the source of radiation; and vi. Nocedures or measures that have been, or will be, adopted to ensure against a recurrence of the loss or then of ficensed or registered sources of radiation. Subsequent to Cling the written report, the licensee or registrant shall also report additional c. substantive information on the loss or then within 30 days aner the licensee or registrant learns of such information d. The licensee or registrant shall prepare any report Gled with the Agency pursuant to D.1201 so that names ofindividuals who may have received exposure to radiation are stated in a separate and detachable portion of the report. Sec. D 1202 - Noti 0 cation ofincidents a. Immediate Noti 0 cation. Notwithstanding other requirements for notification, each licensee or registrant shall immediately report each event involving a source of radiation possessed by the licensee or registrant that may have caused or threatens to cause any of the following conditions: 1. An individual to receive: (1) A total effective dose equivalent of 0.25 Sv (25 rem) or more; or D37M

S k U l202 * .WRCR IdunwI.tugust I991Drqll (2) An eye dose equivalent of 0.75 Sv (75 rem) or more; or (3) A shallow dose equivalent to the skin or extremities or a total organ dose equivalent of 2.5 Gy (250 rad) or more; or ii. The release of radioactive material, inside or outside of a restricted area, so that, had an individual been present for 24 hours, the individual could have received an intake five times the occupational All. This provision does not apply to locations where personnel are not normally stationed during routine operations, such as hot cells or process enclosures. Twenty Four llour Notincalgn. Each licensee or registrant shall, within 24 hours of discovery of i b. the event, report to the AEency each event involving loss of control of a licensed or registered source of radiation possessed by the licensee or registrant that may have caused, or threatens to cause, any of the following conditions: i. An individual to receive, in a period of 24 hours: (1) A total effective dose equivalent exceeding 0.05 Sv (5 rem); or (2) An eye dose equivalent exceeding 0.15 Sv (15 rem); or (3) A shallow dose equivalent to the skin or extremities or a total organ uose equivalent exceeding 0.5 Sv (50 rem); or ii. The release of radioactive material, inside or outside of a restricted area, so that, had an individual been present for 24 hours, the individual could have received an intake in excess of one occupational All. This provision does not apply to locations where personnel are not normally stationed during routine operations, such as hot cells or process enclosures. Licensees or registrants shall make the reports required by D.1202a. and b. by initial contact by c. telephone to the Agency and shall confirm the initial contact by telegram, mailgram, or facsimile to the Agency. d. The licensee or registrant shall prepare each report filed with the Agency pursuant to D.1202 so that names of individuals who have received exposure to sources of radiation aie stated in a separate and detachable portion of the report. The provisions of D.1202 do not apply to doses that result from planned special exposures, c. provided such doses are within the limits for planned special exposures and are reported pursuant to D.1204. 4 D3818

.wRCl! l'olume i.4 pat 1997 l)nt/l kst)l20.t htD.1203 Ikpm1L9f_E3nclures. Radiation Levels. and Concentrations of Radioactive Material lixceedinu Ihe 1.imits, Esportahle lhents In addition to the notification required by D 1202, each licensee or registrant a. shall submit a written report within 30 days aller learning of any of the following occurrences: i. Incidents for w hich notification is required by D.1202; or ii. Doses in excess of any of the following: (1) The occupational dose limits for adults in D.201; or (2) The occupational dose limits for a minor in D.207; er (3) The limits for an embryo / fetus of a declared pregnant woman in D.208; or (4) The limits for an individual member of the public in D 301; or (5) Any applicabic limit in the license or registration, or iii. l.evels of radiation or concentrations of radioactive material in: (l) A restricted area in excess of applicable linuts in the license or registration; or (2) An unrestricted area in excess of 10 times the applicable limit set forth in Pan D or in the license or registration, whether or not involving exposure of any indisidual in excess of the limits in D.301; or iv. For licensees subject to the provisions of the Environmental Protection Agency's generally applicable environmental radiation standards in 40 CFR 190, levels of radiation or releases of radioactive material in excess of those standards, or of license conditions related to those standards. Conlegs of Reports b. on i. Each report required by D.1203a. shall describe the extent of exposure ofindividuals to radiation and radioactive niaterial, including, as appropriate: (1) Estimates of each individual's dose; and (2) The levels of radiation and concentrations of radioactive material involved; and (3) The cause of the elevated exposures, dose rates, or concentrations; and D3939

Sec. D 1:0s. D 1201 - Sslu'It IWewI. 6.j12th4rm I)run (4) Corrective steps taken or planned to ensure against a recurrenc], including the schedule for achieving conformance with applicable limits, generally applicable

• environmental standards, and associated license or registration conditions.

ii. Each report Gled pursuant to D.1203a. shall include for each individual exposed: the name, Social Security account number, and date of birth. With respect to the limit for the embryo / fetus in D.208, the identiners should be those of the declared pregnant woman. The report shall be prepared so that this information is stated in a separate and detachable portion of the report. ~ All licensees or registrants who make reports pursuant to D.1203a shall submit the report in c. writing to the Agency. Sge D 1204 - Reports of Plann.csLSp.cgiallhpmmc1 The licensee or registrant shall submit a written report to the Agency within 30 days following any planned special exposure conducted in accordance with D 206, informing the Agency that a planned special exposure was conducted and indicating ti._ Jate the planned special exposure occurred and the information required by Sec. D.I106. Ste_!11205 Jjiomnij_ Reports to individuals.When. Dose Limits archceeded When,ajicensee.or tegistrant is required, pursuant to the provisions.of D 1203..D.1204...orJD.1206)._to_ report _to_the Agency.pny.csppsure.of artidenti0ed_oc.cupAlio.nallymnosed..individuaknLN1identifttd mtmhetnf_tbe publicJo.souices..ofiadiationJhcJitensec ourgisitantahallatso_pto. tide.a. copy of.ibcleportsubmitted to the. Agency to the individual This report.must bc. transmitted at.a time no laterJharLthcJransmittaljo the Agency, [Sec D 1206 - Repens ofIniividual Monitoring, t This section applies to each person licensed or registered by the Agency to: a. 1. Possess or use sources of radiation for purposes of industrial radiography pursuant to Parts C and E of these regulations; or ii. Receive radioactive waste from other persons for disposal pursuant to Part M of these regulations; or l D4040

&c l) l (s. l) l201 h5R(*R l'oluone i. 4ugust I997 Drall iii. Possess or use at any time, for processing or marc.facturing for distribution pursuant to Part C or G of these regulations, radioactive materialin quantities exceeding any one of the following quantities: Radionuclide Activity' Ci GBq Cesium 137 1 37 Cobalt.60 1 37 Gold.198 100 3,700 lodine.131 1 37 Iridium.192 10 370 Krypton.85 1,000 37,000 Promethium 147 10 370 Technetium.99m 1,000 37,000 ' The.lgency mac requur as a hcense conJotwn or by rule. regulanon. or order pursuwst to.4.7 of these regulanons. reports froin hccruces or regatrants uho are hcenscJ or regtstered to use oa.honus hJes not on tins Int, in quanunes sotficient to cau. e comparable rashanon levels. f b. Each licensee or registrant in a category listed in D.1206a. shall submit an annual repon of the results ofindividual monitoring carcied out by the licensee or registrant for each individual for whom monitoring was required by D,502 during that year. The licensee or registrant may include additional data for individuals for whom monitoring was provided but not required. The licensee or registrant shall use Agency Form Z or equivalent or electronic media containing all the information :equired by Agency Form Z. The licensee or registrant shall file the report required by D.1206b., covering the preceding year, c. on or before April 30 of each year. The licensee er registrant shall submit the report to the Agency.] Ecc D 1207 Notincations_and RepoJ1 slo Individuals. Requirements for notification and reports to individuals of exposure to radiation or radioactive a. material are specined in J 13 of these regulations, b. When a licensee or ree!strant is required pursuant to D.1203 to report to the Agency any exposure of an individual to radiation or radioactive material, the licensee or registrant si.all also notify the individual. Such notice shall be transmitted at a time not later than the transmittal to the Agency, and shall comply with the provisions of J.13a. of these regulations. D4144

Sec D t20R.D t.0l 1 .%RCR l'ohar I *.tupst I999 thq/l he D 1208. Repons of Laking or ContaminatriSoled Sources The licensee or registrant shall file a report within 5 days with the Agency if the test for leakage or contamination (required pursuant to D.401) indicates a sealed source is leaking or contaminated The report shall include the equipment involved. the test results and the corrective action taken. Additional Requirements he D 1301 Vacating Premises Each specific licensee or registrant shall, no less than 30 days before vacating or relinquishing possession or control of premises which may have been contaminated with radioactive material as a result of his activities, notify the Agency in writing ofintent to vacate. When deemed necessary by the Agency, the licensee shall decontaminate the premises in such a manner as th Agency may specify. .1 D4242 j 1

SWR t'olume i..tugust 1V97 Draft Apgenda A i PART D APPENDIN A PROTITTION FACTORS FOR RESPIRATORS' j 4 Tested & Cenified Protection Factors Equipment Description hiodes' Panicu. Panicu-NationalInstitute for S lates

lates, Occupational Safety &

only

gases, rkalth & Mine Safety &

vapors' liealth Administration tests for permissibility I 1. AIR PURIFYING RESPIRATORS Facepiece, half mask 8 NP 10 30 CFR I1 Facepiece, full NP 50 Subpan K. Facepiece, half mask PP 1000 full, or hood i

11. ATMOSPilERE SUPP131NG RESPIRATORS 1.

Air line respirator I acepiece, half mask CF 1000 Facepiece, half mask D 5 Facepiece, full CF 2000 Facepiece, full D 5 30 CFR 11, Facepiece, full PD 2000 Subpart J. b-Ilood CF i i Suit CF 2 Self contained breathing apparatus (SCB A) Facepiece, full D 50 4 Facepiece, full PD 10,000 30 CFR 11, Facepiece, full RD 50 Subpart 11. 3 Facepiece, full RP 5,000 111. COMBINATION RESPIRATORS Any combination of Protection factor air purifying and for type and mode 30 CFR 11, atmosphere supplying of operation as Sec. I1.63(b). respirators listed above See Ihefollowing prgesforfootnotes. D4345

AMenda A SNRCR l'el=or !..lngu st 1997 I)rqft Footles:

• For use ht the scin tton of renparatory protnHsr equtpment to be used ordy uhere the contannnants hast been identl ed wul fl the concentratwns, or possable concentratwns, are known.

> Onlefor shasen f<wes wul uhe're nodung noterferes unds llor seal of sigla.fottingfsxeporces agamst the sLm floals wul su are etccpled

• 1he made synboh me definedasfollous:

contunwusflow CF ~ dennuki l} = NP - negaint pressure, that us, negause phase during inhalation pressure demwul. that is. always posant pressure PI) PP posant pressure Jennnul. rectrculatmg or < losed circuit RI) pressure dentwul. rce arculating or closed circuit RP = A the protalwnfactor n a measure of the degree ofprotection afforJed by a respirator Jejined as the ratio of I the wncentranon of wrburne nnhoactnr matenal ouniJe the respiratory protectnr equipment to that instJe the eyrnpnoent, usually untJe the facetone, muler condawns of use. It is upphed to t'se ambient wrborne e oncentratwn to estunate the wncentratwns mhaleJby the u cater accordmg to thefollowmgfannula. Cons entratwn mhaled - Ambient arrborne concentranon Protecitonfactor h The protec toonfactors apply: Ili Onlefor nuherJuals tramedin usmg resperators and uranng properlyfitted resperators that are used and mamtamed under supervnton in a u elbplamred respiratoryprotectar program. (21 For air pur#mg respnators. onlyyhen high efficiency parucuhar filters, abost 99.97 percent renwval eff)ciemy by thennallygenerated DJ l'rn dwctsIphthalate flXJP) test or equivalent, are used {j m alnwsphern not deficient m ongen and not contatmng rahoactne gas or vapor restnratory ha:arJs f 13J No adjustment n to be malefor the use of sorbents agannt rahoacuve matenal m theform ofgases or vapors. Ih For annosphere supplymy resp >rators only uhen supphed wah alequate resporable wr. Resporable wr shall be pun oded of the quahty and quwaity requoted m accorJance wah Ihe NanonalInstaure for Ustupsawnal Safere wul llealth and the Ahne Safe and Heahh Admnustranon cernficanon dest nbed m 30 Cl R I1. Cnyen and wr shall not br used m the same apparatus.

• Ftt hoJmg nnhom snr comannnams that present an absorptwn or stabmerswn ha:ard. For trasum ostJr. opproumately one-third of the mtale va urs by ah.sorptwn through the sim so that an overallprotectwnfactor ofless than 2 is appropnate uhen alnwsphere wppipng respirators are uscJ to protect agamst trawm ouJr. If the protectwnfactorfor respiratory protective equotunera os 3, the effa tne protectwn)&tarfor tranan is about 1.4; unh protectwnfactors of 10, the effectarfactorfor tretmm oude o ohara lJ; wul u udt protecuon factors of 100 or more, the efectatfactorfor trotnam ortJe is about 1.9. Air punfymg respirators are not suitablefor protectwn agamst annum ottJr. See ahofootnote concermng suppheJ air suits.

Y I Cwnsters wklcartnJges shallnot be nsed beyvoulservoce-hfe hmaations. D4444

Aprenda A %RCR l'olume I. August 199? Until Urder-<hm tspe wJy, lins Ope of respnator n twt satufactoryfor use uhere a nught be possoble, such as, of as accdent es emetyency urre la occur, for the wnhwnt <urborne concentranora to reach instarnaneous udues greater thws 10 nmes the penment sabres m lable I, Colunm ) of.I ycuhe B of Part D. Tlus Ope of respirator is not sunable for protecnon agaunt t phnanann or other hrgh.coauty materrats. The masa n to be testedforp pnor to use, each ume 11is donned b Equipmera shall be operated in a manner that ensures that proper wrflowrotes are maunamed A protecnon o. factor ofno more than 1000 mm. be utdacJJor testeJ wd-cernfed supphed-asr hoods uhen a minimum air flow of 6 cubstfeet per minute to 17 m'.rnin) is mamtained wul cabbrated air hne pressure gaiges orflow measunny devices are used, \\ protectionfactor ofup to 2000 mm be usedfor tested wd centfled hoods only u hen the wrflow n manaamed at the inanufacturer's recommeruled maumum ratefor the equipment, this rate o< gr rater than 6 cubicfeet per numar (0.17 m' mm) ad cahbrated att hne pressure gauges orflow rneasurmg Jences are used The design of the suppheJ-air hood or hehnet. u ah a mmemumflow of 6 cubicfeet per onmute (0.17 m* rnm) of n. nor, mm Jetermine as metall epiciency wid the protectwn a proudes. For example, some hoods aspirate contaminatedwr into the breathmg tone uhen the wearer works u ah hands over heat. This aspiranon may be usercome tf a short cape ble extension to the hood ts wons unJer a coat or ostrails. Other hmaations specified by the approval agency shall be constJered before usmg a hood in certain Opes of atmospheres. Set footnote I.typrornate protecnon factors shall be deternaned. talmg mio account the design of the sua ad as permeabthry to the unnammant under condatons of use. There shall be a standby rescue person equipped unh a respirator or other apparatus appn>priatefor the potennallucards wdcommumcanons equa[ ment u heneser supphed ast suas are used U No approval sehed:Jes are <urrentiv availablefor this rytapment. Equipment u to be evaluated by testmg or on the basis of rehable test mfonnalwn 1 hts Qpc of respuator Inav proude greater protection wd be used as an ernergency Jevtce in unknown concentranons for protecnon agamst tr*halanon ha:ards, Esternal rahanon ha:ards wd other hmaakons to pennated exposure, such as skm absorptmn. must be taken inta account in such con umstances. I Quwaaalnrfit testmp shall be perjonned on each mJaviJual, wd no more than 0.02 percent leakage ts aHou rd wah this Ope of apparatus, percepuble outuard leakage of gas from tins or wry posauve pressure self-coraamed breathmg apparatus is unacceptable because sernce hfe wdl be reduced substannally. Special trammg in the use of thu Qpe of apparatus shall be pronJed to the u carer. Note 1: Protecnonfaaors for resporators apprmsJ by the Bureau of.\\hnes and the NationalInstautefor Occupanonal Safen-wdlleahh, accordmg to apphcable approvah far respiratorsfor Ope anJ mode of use to protect agaunt atrborne rahonuchJes, may be used to the ertent that they da not escccJ the protecnonfactors lated in alus table. The protecnonfactors hsted in thn table may not be appropnate to conmnuames uhere chenucal or other resporatory ha:ards exnt in aldawn to rahoactive ha:ards. The selecnon wd use of resporators for such circumstances should take mio account apphcable approvals of the Bureau of.\\hnes wd the NutwnalInstantefor OccupanonalSafen. wdlleahh Note 2: Rahoactnr cosaannnants.for uInch the conceraration values m Table I, Column 3 ofApperdix B of part D are based on Intenud Jose due to what.stmn, mm pre <ent esternal esposure ha:ards at higher concentranons. Under these circumstances, hwaatwon on o< aapuncy nury base to be governcJ by extensalJose hmus. (0E'O

ArTenkt il .WK'R ( Mume I.. tuynu 19971)np PART D APPENDIXH ANNilAI,l.lMITS ON INTAKE (AI.1) AND DERIVED AIR CONCENTRATIONS t (D AC) OF R A DIONtlCLIDES FOR OCCilPATIONAL EXPOSilRE: EFFLif ENT CONCENTR ATIONS: CONCENTRATIONS FOR RELEASE TO SANITARY SEWERAGE Introduction i For each radionuclide, Table I indicates the chemical form which is to be used for selecting the appropriate ALI or DAC value. The ALis and DACs for inhalation are given for an acrosol with an activity median aerodynamic diameter (AMAD) of 1 pm, micron, and for three classes (D,W,Y) of radioactive rnaterial, which refer to their retention (approximately days, weeks or years) in the pulmonary regwn of the lung. This classification applies to a range of clearance half times for D ifless than 10 days, for W from 10 to 100 days, and for Y greater than 100 days. The class (D, W, or Y) given in the coluran headed ' Class" applies only to the inhalation ALis and DACs given in Table 1, column 2 and 3. Table 11 provides concentration limits for airborne and liquid efiluents released to the general emironment. Tabic ill provides concentration limits for discharges to sanitary sewerage. Note: The values in Tables I,11, and 111 are presented in the computer "E" notation. In this notation a 2 value of 6E 02 represents a value of 6 x 102 or 0.06, 6E+2 represents 6 x 10 or 600, and 6E+0 represents 6 x 10" or 6-Table i " Occupational Values" Note that the columns in Table I of this appendix captioned " Oral Ingestion All," " Inhalation All," and "DAC " are applicable to occupational exposure to radioactive material. The ALis in this appendix are the annual intakes of given radionuclide by " reference man" which would result in either (1) a committed efTective dose equivalent of 0.05 Sv (5 rem), stochastic All, or (2) a committed dose equivalent of 0.5 Sv (50 rem) to an organ or tissue, non stochastic All. The stochastic ALis were derived to result in a risk, due to irradiation of organs and tissues, comparable to the risk associated with deep dose equivalent to the whole body of 0.05 Sv (5 rem). The derivation includes multiplying the committed dose equivalent to an organ or tissue by a weighting factor, wr. This weighting factor is the proportion of the risk of stochastic effects resulting from irradiation of the organ or tissue, T, to the total risk of stochastic effects when the whole body is irradiated uniformly. The values of wt are listed under the defmition of weighting factor in D.3. The non stochastic ALis were derived to avoid non stochastic effects, such as prompt damage to tissue or reduction in organ function. A value of w = 0.06 is applicable to each of the 5 organs or tissues in the " remainder" category receiving r the highest dose equivalents, and the dose equivalents of all other remaining tissues may be disregarded. The following portions of the GI tract - stomach, small intestine, upper large intestine, and lower large intestine -- are to be treated as 4 separate organs. D4654

- - _ _ - - _ _ _ - ~ _ _ _. - MRCR IWunw I. August I997 Drqll Appenda ll Note that the dose equivalents for an extremity, skin and lens of the eye are not considered in computing the committed c0'cetive dose equivalent, but are subject to limits that must be met separately. s l When an ALI is defmed by the stochastic dose limit, this value alone is given. When an ALI is deterrnined by the non stochastic dose limit to an organ, the organ or tissue to which the limit applies is shown, and the All for the stochastic limit is shown in parentheses. Abbreviated organ or tissue desig. 1 natiors are used: LLI wall = lower latge intestine wall, St wall = stomach wall; illad wall = bladder wall, and llone surf = bonc surface. The use of the ALis listed first, the more limiting of the stochastic and non stochastic Alls, will ensure that non $tochastic clTects are avoided and that the risk of stochastic c0'ects is limited to an acceptably low value. If, in a particular situation involving a radionuclide for which the non stochastic ALI is 1 limiting, use of that non stochastic All is considered unduly conservative, the licensee may use the - stochastic All to determine the committed effective dose equivalent. Ilowever, the licensee shall also ensure that the 0.5 Sv (50 rem) dose equivalent limit for any organ or tissue is not exceeded by the sum of the external deep dose equivalent plus the internal committed dose equivalent to that organ, not the effective dose For the case where there is no external dose contribution, this would be demonstrated if the sum of the fractions of the nonstochastic ALis (Alin,) that contribute to the committed dose equivalent to the organ receiving the highest dose does not exceed unity, that is, 3 (intake (in FCi) of each radionuclide/Alin.) # 1.0 If there is an external deep dose equivaient contribution oflia, then this sum must be less than 1. (11/50) instead of # 1.0. 4 Note that the dose equivalents for an extremity, skin, and lens of the eye are not considered in computing the committed e0'ective dose equivalent, but are subject to limits that must be met separately. The derived air concentration (DAC) values are derived limits intended to control chronic occupational exposures The relationship between the DAC and the ALIis given by: DAC = All(in :Ci)/(2000 hours per working year x 60 minutes / hour x 2 x 10' ml per minute) = [All/2.4 x 10'] pCi/ml, where 2 x 10' ml is the volume of air breathed per minute at work by reference man under working conditions oflight work. The DAC values relate to I of 2 modes of exposure: either external submersion or the internal committed dose equivalents resulting from inhalation of radioactive materials DACs based upon submersion are for immersion in a semi infmite cloud of uniform concentration and apply to each radionuclide separately. The ALI and DAC values include contributions to exposure by the single radionuclide named and any in-growth of daughter radionuclides produced in the body by decay of the parent. However, intakes that D47f9

_ ~ - - - - Atynda l) S%)u'R t bloww I..tomtat IVV7 Draft include both the parent and daughter radionuclides should be treated by the general method appropr for mixtures. The values of All and DAC do not apply directly when the individual both ingests and inhales a radionuclide, when the individual is exposed to a mixture of radionuclides by either inhalation or ingestion or both, or when the individualis exposed to both internal and externalirradiation. See D 202. When an individual is exposed to radioactive materials which fall under several of the translocation classifications of the same radionuclide, such as, Class D, Class W, or Class Y, the exposure may be evaluated as ifit were a mixture of different rad.onuclides it should be noted that the classification of a compound as Class D. W, or Y is based on the chemical form of the compound and does not take into account the radiological halflife of different radionuclides For this reason, values are given for Class D, W, and Y compounds, even for very short lived radionuclides Tnble 11 "l:muent Concentrations" The columns in Table 11 of this appendix captioned "Elliuents," " Air" and " Water" are applicable to the assessment and control of dose to the public, particularly in the implementation of the provisions of DJ02. The concentration values given in Columns 1 and 2 of Table 11 are equivalent to the radionuclide concentrations which, ifinhaled or ingested continuously over the course of a year, would produce a total efTective dose equivalent of 0 5 mSv (0.05 rem). Consideration of non stochastic limits has not been included in deriving the air and water eflluent concentration limits because non stochastic effects are presumed not to occur at or below the dose levels established for individual members of the public. For radionuclides, where the non stochastic limit was governing in deriving the occupational DAC, the stochistic All was used in deriving the corresponding airborne ellluent limit in Table Il For this reason, the DAC and airborne ellluent limits are not always proponional as was the case in Appendix A of Part D of the eighth edition of Volume i of the Suggested State Regulatunnfor Gmuni of Radianon. The air concentration values listed in Table 11, Column I were derived by one of two methods. For those radionuclides for which the stochastic limit is governing, the occupational stochastic inhalation All was divided by 2.4 x 10'(ml), relating the inhalation ALI to the DAC, as explained above, and then divided by a factor of 300. The fact ~ of 300 includes the following components: a factor of 50 to relate the 0.05 Sv (5 rem) annual ocommonal dose limit to the 1 mSv (0.1 tem) limit for members of the public, a factor of 3 to adjust for the difference in exposure time and the inhalation rate for a worker and that for members of the public, and a factor of 2 to adjust the occupational values, derived for adults, so that they are applicable to other age groups. For those radionuclides for which submersion, that is external dose, is limiting, the occupatienal DAC in Table I, Column 3 was divided by 219. The factor of 219 is composed of a factor of 50, as described above, and a factor of 4 38 relating occupational exposure for 2,000 hours per year to full time exposure (8,760 hours per year) Note that an additional factor of 2 for age considerations is not warranted in the submersion case. D4850

hgptsta tl MRCR I bhame I..hopal 1997 Dutil The water concentrations were derived by taking the most restrictive occupational stochastic oral ingestion ALI and dividing by 7 3 x 10' The factor of 7.3 x 10'(ml) includes the following components: the factors of 50 and 2 described above and a factor of 7.3 x 10'(ml) which is the annual water intake of reference man Note 2 of this appendix provides groupings of radionuclides which are applicable to unknown mixtures of ) radionuclides These groupings. including occupationalinhalation ALis and DACs, air and water efiluent concentrations and releases to sewer, require demonstrating that the most limiting radionuclides in successive classes are absent The limit for the uriknown mixture is defined when the presence of one of the listed radionuclides cannot be defmitely excluded as being present either from knowledge of the radionuclide composition of the source or from actual measurements. Table ill " Releases to Sewers" The monthly aserage concentrations for release to sanitary sewerage are applicable to the prosisions in 111003 The concentration values were derived by taking the most restrictive occupational stochastic oralingestion All and dividing by 7 3 x 10(ml) The factor of 7.3 x 10'(ml)is composed of a factor of 7 3 x 10'(ml), the annual water intake by reference rnan, and a factor of 10, such that the concentrations, if the sewage released by the licensee were the only source of water ingested by a reference man during a year, would result in a committed etrective dose equivalent of 5 mSv (0 $ rem), l.ist of Elements Atomic Atomic Name Symbol Number Name Symbol Number Actinium Ac 89 Chromium Cr 24 Aluminum A 13 Cobalt Co 27 Americium Am 95 Copper Cu 29 Antimony Sb 51 Curium Cm 96 Argon Ar 18 Dysprosium Dy 66 Arsenic As 33 Einsteinium Es 99 Astatine At 85 Erbium Er 68 Ilarium lla 56 Europium Eu 63 llerkelium Ilk 97 Fermium Fm 100 lleryllium lie 4 Fluorine F 9 llismuth fli 83 Francium Fr 87 Ilromine llr 35 Gadolinium Gd 64 Cadmium Cd 48 Gallium Ga 31 Calcium Ca 20 Germanium Ge 32 Californium Cf 98 Gold Au 79 Carbon C 6 11afnium lif 72 Cerium Ce 58 llolmium llo 67 Cesium Cs 55 11ydrogen 11 1 Chlorine Cl 17 Indium in 49 TM92

Anusdn tl .WH *ll I hlunw I.. luyunt I991 I)talt List Cf LltmCts (Cottliittied) Atomic Atomic Name Symbol Number Name Syn bol Number lodine 1 53 Technetium Tc 43 Iridium ir 77 Tellurium Te 52 fron Fe 26 Terbium Tb 65 Krypton Kr 36 Thallium Tl 81 Lanthanum La 57 Thorium Th 90 Lead Pb 82 Thulium Tm 69 Lutetium Lu 71 Tin Sn 50 Magnesium Mg 12 Titanium Ti 22 Manganese hin 25 Tungsten W 74 Mendelevium Md 101 Uranium U 92 Mercury Ilg 80 Vanadium V 23 Molybdenum Mo di Xenon Xe 54 Neodymium Nd 60 Ytterbium Yb 70 Neptunium Np 93 Yttrium Y 39 Nickel Ni 28 Zine Zn 30 Niobium Nb 41 Zirconium Zr 40 Osmium Os 76 Palladium Pd 46 Phosphoms P 15 Platinum Pt 78 Plutonium Pu 94 Polonium Po 84 Potassium K 19 Praseodymium Pr 59 Promethium Pm 61 Protactinium Pa 91 Radium Ra 88 Radon Rn 86 Rhenium Re 75 Rhodium Rh 45 Rubidium Rb 37 Ruthenium Ru 44 Samarium Sm 62 Scandium Sc 21 S-lenium Se 34 Silicon Si 14 Silver Ag 47 Sodium Na 11 Strontium Sr 38 Sulfur S 16 Tantalum Ta 73 D5050

SW'R IWume /..lurust /PP1 thq/t Argenda 11 Annual I.imiliun intale ( AlJ) and Demed Air Concentratmns (1)AC)omadmnuclides fo acuiutmnal Estmure r ulluent C meentratons Coinentrations for Releaw to Samt.v) ScWerage (t'ontusued) 2 1sh.e i lame !! table int tscusee.ms1 Lilleeni Releaws to Values Gruncatans Semers Col l Col ! Cal ) Col I Col ! Oral %miW tr$v*

• _lW t'NfL.

Amap Abwmc li aJ*eminic rimes All All DAC Ad u nie, Carnevitrauan i e n mli 46aH (en mh (pr*, mit Ne a pN tura e f l lhdtt p) % alef !)di' trillihic4 din atowstre Fled IE*J Il $ I&-7 10-) IL 2 Oas s til <v 1 ) Kuhmrraum* t'u alm =4 values as ifT and 1eaudae in ad and in de l==h to ifl0 i e llentinam t W. ali c.wnpaurids ewept 40*4 L*4 9t4 3L 8 6td 6E.) 14mc gnen f v Y ).mniet hal6deit and neueici 0 3+4 80 4 )F 8 C C J Lieniinmid u. we b li.. ) 2E : 6L 8

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C 1.01 wal!

1. it.1)

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b6 70 4 lL4 C

C t hnude r 21 + 9 44 3E.7 C C r.wno wide !! +) Il+)

11. 4

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L4 E9 SE 3

$EJ ll Madrievum.'R D all ownpunk curpt thme gn en t,w % 7L

• 2

!!.* ) 70 1 E.9 SL4 9E 5 a % nudet hgJanuks tartudci. halides and nittees C IL+) $t 1 N. 9 C r 1) Aiurninum-lh O alls.vnpiunda cuest theme pen t w W' JE*2 6E*l El VL il 60 4 6E 5 % nuJet hulamidct wtwies hatedn.and aiu4ies c 9E*1 4L 4 IL.its C C le Silisreal D all$innemmJe ewere thme pen f e W and Y 9t') 3L*4 IE 5 4L 8 10 4 10.) %. mnh hsJrmidet 4tudes anJ ndswei O )L*4 LEA Et C C Y, alumirmailsew elet C JE*4 IEd al..I C C iimtonan euptwar.n sloe end uit)ww clorst tabla D5199

Apperklis 11 .um'R l'ohoc l..hipttt 19FF Ih<$ Altntuil I.imda a lutas ( Al.1) and Dettied Air Consoittatio.is (DAC) of Radiantalldes for Owupational Espture l@ueist Coswoitrations Con 44 littattutil l'uf Releanc 10 $Attitar) $cucf 0gd f pilarmnh T d4e i 1abw 11 f able til Owgesel Ein.ura Etwano 6i 1 aims Cawerwsure sewers Cut 1 C4 Col 3 Col 1 Col 3 kkrahh W irg. stem hWet_ Aterep Asen k ok.malade riens All AEl DAC Ag % stet C sverweimri s t*,-mn (pn mn (un mn s e.) s pe, mn u

1. p *.s u

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E * )

OE+2 IE.? )E.10 C C 1.ll s all I tt s)) C C C 4E.3 4E 4 %.we"N r IE+2

• E.8 lE.10 C

C L we "% C $E o E.9 TE.l! C C 19 1%ghnw12 O alls.vnpardscueri (Warhaien gnen tsv W f.E + 2 9E *! JE.7 lE.9 9E4 9E.) F tbmphets rd /n". 8".Og"fe*,hi " armilamharuare c 4E* lE.7 SL.80 C C 14 thr6eunal l) we *P f4 + 1 IE+1 JE 4 it.8 $E.S $14 %. nee "P O 3Ed if 4 dl.9 C C 16 Buite 14 \\ apr P 1[ +4 6E4 OE.8 C C D sulhden ami nulimes curri thw 8n en t v u t t' +4 lL*4 71 4

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( * ) '

fE4 JE.9 lE.! E.4 % shkedn eu lamha-ni Ac. lie My ra se lia Ra Al.Os 1411. De $st l'b. At $b tio Ie ku on Co.kAli. No IN1 l't Cu Ag Aa l#L rd lig 56 ). T i< h Ill. E \\b Ta re. Ma, %~ Mn is anJ ke C lE : I E.7 3E.10 C C 11 Chl. wine. ns" (1 w, *rl IE*d 4E*4 OE.! 6E -8 C C 51 mall ill*d) C C C 3E4 3E.3 %. we 't l c SE*4 lEA 6E.8 C C ti chevme l# l) we 'cl

t' + 4 SE*4 1E.5 7E-8 C

C St mall I4E*d) C C C SE4 SE.3 % we *cl C 6E 4 lE.3 IE 4 C C it Ary.m 11 Naimerie.e* O C IE*o 6E.3 C C 18 Ary*. l9 Nuhmsru.c' C C

• E 4 8E.T C

C 18 A9 c.41 %ubmeewe' C C 3f.4 IE.8 C C 19 Iwawum-ei D allsevnpnadt Ste: 4E*: E.1 60 10 4E 4 40.$ 19 1%anaeum42 fl all siurpanda SE*) St+) E4 7E.9 6E.S 6E4 19 P unsourn4) D. all s.vnenado ties t 90 0 4E 4 IE.8 90 5 9E4 Footnotes appear at the end qf these three table.t. D5298

Agstenda ll .WlCR Iblume I..tugust 1997 Ikqft Arviual ljnuts mlIntale ( Al.1) and Iktned Air Coiwenttstioris (i' AC) of Radionuelides for Oautational thrunue limuent Corwentrations Cosuntralmns for Releasic to Salutar) Sewerop (Confutunh TeMei f aNe il TaNe 111 tuurearial I.fNeni kelemas la Valuse vivantiswve Semm Col I Cid 2 Cal ) C4 i Col ; Me#Jv (mal Ingestaan JWen.,, Anetage A6 unes R adovelide Clan All ALI DAC Aa u set Caruntratum Nn tyca i ge.) spc. mn tpci nin (pci mn (pre mn 19 hamniurn4' (>sils4epiunda

• E.4 7E*4 JEJ 9[ 8 C

C 86 e all (4E*4) C C C 40 4 SE4 19 l'oiantende D allsewnpumJn JE*4 lE+)

• E,3
• E ?

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• 2 Ilo?

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1. E 4 IE 8 C

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Aggwnda D .wRCM l'obar !.,ingust 199? Ihtgl Asunuil1.iinit iniInt.it.c(Al.1)and ikmoj Air Coruntrauons(DAC)of Radiouchdes for Oaupauonal bposure I'muent Cotuntrabons Comentratiotis for Releau to Sarutari ewetage It'ontinued) S 1aede i TeNe il TeNe !!! newemeal f&ers Releanes to Yalues Crearntstiers seoves Cut 1 Col : Cd 3 Col I Cd ManiPJv Oral Average Irgesteun jnh,$,ttity Avems RadveiinliJe Claen AEl AE! DAC As W eser Ct.4entratnin iu e mn iuce mn apc mn c Na apr'it t pei) ori =t t maks ernlindroudes C 7E. )

37. 4 IE.8 C

C y 24 CM euum4# D ae, "ce JE.4 IE.4 4E $ IE.7 4E 4 4E.) % we "P C IE+! JE4 IE.7 C C ), we "cf c 9E+4 4E.) lE.7 C C 24 (Vimiwn41 D. ore "et 4E+4 4E 4 35 6E-4 $E4

• E.)

%. ore "Of C 3+4 If.1 JE 8 C C V. are "Cr C 3+4 IE4 St 8 C C 6 24 Manerne 41 D ar t. npunik euen sh.= gn en i e n 3 +4 ts+J 3.$ 7E.8 JE4 3EJ % maks M4rnuJn haliJet arminiomes C 6t*4 If.4 IE.8 C C ,E+4 9E+4 40 4 IE.7 C C 24 M c crrw 42m' O. wv un t si mall (4E+4) C C C SE4 SE4 %. we "Mn c IE $ 4E.4 10 4 C C 24 MeganewA: D are %ln 7E : If+) SE 7 lE.9 lE-! lE4 % we %tn C 9E*: 4E.7 IE-9 C C 24 Manganne 41 D we"Mn 4E+4 IE*4 4F4 C 7E 4 7E.) thme awrf C (3+4) C JE4 C C %. we "un C IE*4 SE4 Of,8 C C 25 M agsww 44 D we Sin

!. * )

9E+ 4E.7 IE.9 30.$ JE4 % we %)n C IE+2 3E.7 f f.9 C C 24 Manpane r D we %)n ?E+) E *4 6E4 38 7E.$ 71 4 k we %ln C lE*4 9E4 JE 8 C C 26 tr+4 O eli sepun.a euce ihme snen tre W &E+ 3E*) IE4 4E 9 IE 4 IE4 W. nvJes bJrnte.s. and halides P lE*) lE 4 3E.9 C C 26 tron 43 D we "l e UE*) E+) IE.7 3E.9 IE4 IE.) %. we "I e C 4E+) E4 6E.9 C C 26 Ir+ *9 D we "I s SE+ 3E* IE.7 $E.14 IE S lEJ % we "I e C SE 34 E10 C C 26 Irwei D we "le JE+1 6E*o 30 9 9E.12 4EJ 4E4 % we "te C lE +1 St.9 JE.Il C C 27 P.hlt 44 %.a;lpesemnJovuce iW pven t.e V IE+) JE+) IE4 AE.9 E.S 2E4 V. m.Jn. InJrmedet hahdet armi niumn C 3E+) IE4 4E.9 C C I enhent.46 %. we "On 4E* st+; 10 7 4E.lu LE4 6E.5 ), we "Ce 4E+2 2E+ 8E.8 SE.10 C C 27 C+ht:Af %. ice "en sE.) 3E+) lE4 4E.9 6E4 6E 4 V. we "Ce 4E*) 7E+ 3E.7 9E.10 C C lindendes appear at Ilw coulof these three tables D5498

Argendail SSRCH l'olune f. 4ugust 1997 Unt/l A:uiualI.iinit oriintole;Al.1)and Derited Air Cuentrations(DAC)of Radionuclides for Oxupational Esposure Elliuent Concentrations Comentratnnis for Releaw to Sarutar) Sacrage fontmunl/ taMei Tab.e 11 1aMe ill t enurewesi EtNere Re wswi ki \\ alust formenaratavis &esat Col i Col 2 Col ) Cid i Col ! Oral Mresihh tryestem Jehigo Awaye Ahvna RaluviuclJe Cima All All DAC Aaf M alef Cornereration t u i mi) v tu *. mit rpri mh Ipri m1) No (36) (pr.) c 27 Cetell t&m %. ere "Co 6l+4 9E*4 46 $ IE 7 $IJ IE4 i. are "Co C M *4 3E.) 9E.8 C C 27 Coheit 48 %, are "Co 2L*) li *) 40 7 39 2E.$ 2EJ L aev "Ca IE+) fL

• 2 3E 7 lE.9 C

C 27 Coeelia en* %. are "Ce iL+6 4E*4 IL.) 6L4 C C Si nall (I E *61 C C C 32

• L l L we "Ce C

JL*6 IL.1 JL4 C C

• 7 Cohili.re e

% we "i'n ti e! 'f 4 2 7F s 3 10 jf 4 3E 4 t we "C.i 2L+2 JL*1 IL.8 4E 11 C C 27 Ceball e.I' %. we "Co 21-

• 4 61 + 4 3L.4 9E 8 3E4 JL-)

Y we"Ca

L.4 R4 34 IL.s C

C 27 nball A.'.m' %. we "Co 4E+4 L4 49 37 C C 81 mall (tr+4) C C C 7E4 7E.)

4. nee "Ca C

lI. 5 e4 J 3-7 C C

E NnkelA.

D alltompiunJa ewee lhe gneriliv %' 11.*3 lL.) IL.? 3L.9 00 5

E4

% nudet IndrouJet and cartwJen C lla) 51.7 E.9 C C \\ sov C IE.) SE.1 39 C C

s

%th cM i D we *N L.) 50.) 34 7E-9

L 5 34 i

% we*% C 3E-3 lE4 di. 9 C C \\ ap e C tiL*) JF 4 90 9 C C

l

%5kal $9 D =ce *M 3+4 4E.) 34 SE 9 JE4 3E.) %. es e *N C TE 3 30 4 If 8 C C \\ apv c 33 st.7 3L.9 C C lt Nukele) D iev 'N 9E.)

l+3 E7 L -9 led IE 3

% we'Ni C JE*) 10 4 4E-9 C C \\ep, C 8E.2 10 7 IE 9 C C 28 NnLel ot D. we 'M sEe) 3+4 IE.S 3E.8 IE4 IE.) % we *N C 3E.4 IE.S 4E.8 C C \\ ape 'E*4 7E4

• E.B C

C 28

Nukelse, D we 'M 4E 2 L*)

70 7 39 C C t LI wall (5fie ) C C C 6E 4 6E i % we 'N P 6E*! 3E 7

• E.Iti C

C hos C JE*3 IE4 4L 9 C C 29 t'ggwr ee P O all eiwnewl= ewes tMw pnen tie % and ) 11 +4 9E+4 49 IE 7 C C As wall (IE 4) C C C 4E4 4E.) % oultiJes halides. and n irews C IE+$

• E4

L 7 C

L asales eW hJrnudes C lE+$ 4Ed IE 7 C

9 Cyp,41 l} we*0s lE.4 3E*4 it.S 48 N4 3.)

w we*Ce C 4E.4

E 3 6E-8 C

C y we "Ce C 4E*4 IE.$ SE 8 C C l'ovnwe.s appear at ole emiqf these three tables D5599

Apre>Jn 11 +witCit \\ *e>Iam I + + lugnsi I991 htaff Annual 1.iinits on inl+ih ( Al.1) and ikmal Air Concentrations (DAC) cf Radionuclides for Occupatiold Espomre Lilluent Cuentrations Cthentiations (of Relc4W to $anitwy $cuct9(c (bimped) Table i T able il Table til thmurieweial i gnewes Releassa to % alues C,rnerstatmns Eemm t'ni i cui ! Col ) Col l Col 2 Manthly 4 kal Astrare legeene _Jrtett L Ab we.ic kajumus liJv th AE1 Au DAC Aif % ster C wsonantson f u i mh f uf's mn (pr*s mh fier*i mn r ip M t pr*i) f Mi '9 rig 5=v4 D we're IE+4 JE +4 IEJ 40 8 21 4 3-) % w *rv C 3 *4 ILJ JE.8 C C Y. m "rv C E+4 9E4 JE.8 C C 09 Cmrve? D. we *Cu sea) SE+1 af4 IE.8 (EJ 6EJ W.we're C SE*) 34 E9 C C i. we *cv C SE+) 2E4 6L.9 C C m linc e:

1. all evnp aund.

IE*) JE+) IE4 JE.9 2LJ 2E4 $1 tim 4# ) alltivnpuds E*4 7E + 4 JEJ 9F.8 C C si n ail (JE*4) C C C 30 4 JE.) . E.9 /mc et ). all siunpeds 4L*: JE+2 1E.7 JE.10 ff 4 lim **n i. all s4enewe 4E*) 7E * ) R4 IL.8 6E.9 6F 4 18 lins d ). ali s4impuds 60 4 lE+5 6E4 37 80 4

• E )

bl lou.71m ). ail sinnewe 6t*) lt +4 7E 4

• E.8 8E.)

1. E4

.in ter.7

1. all enenowds IE*)

1E+) !E.7

• E.9 IEJ IE4 31 Galliumet*

D allownewaeven wne pnen tie % SE44 E+5 ES ZE.7 C C 54 mall (bb+4) C C C 9E4 9E.) %.nuJes hsJrmdes satt.eJes halides. and fupates C 3+$ IEJ JE.7 C C )) Gallivm u. D w Ga IE+1 4E+) IE4 $E-9 IEJ IE4 W. we "04 C JE*) IL4 JE.9 C C ll Gallium 47 0 ice da 70+) IE*4 6E 4 lF 5 IE4 IEJ W. we Ga C IE+4 JE4 IE.8 C C }l t. allium +a* O m o n E+4 4E*4 E4 60 8 34 E.) W w '*na C SE*4 2E.5 E8 C C 11 Oali.um # D. m d.

• E*4

E+4 7E 5 ZE-7 C

C 54 mall (7E+4) C C C IE.) 1E.: % we da C lE+) 8E.5 JE.7 C C 31 Gallef: D we ila IE*) 4E*) lE4 SE.9 2E.5 lE4 W.weda C 3E+) lE4 4E.9 C C al natt e 71 D we G4 SE*) E*4 6E4 E.8 7E.! 7E4 %. we Ca C M*4 6E4 lE.8 C C + ): Germeruuma D. all enmpwnds suce thme gnen fu % 2E*4 3E*4 lE.$ 4h.8 )E4 3E.) % m Jes intte.s anJ halides C ZE*4 8E4 3E.8 C C i 3 Ocemaruum4f D. w "Cs .1E

• 4 9E*4 4E.S 1E.7 C

C 54 mell (4E*4) t' C C 6E4 6E.) W. we *0e C 10 5 JEJ t r..? C C fearsinott.1 uppewt at Ilw cust o{tlese tinrre table.1 D5698

SSRCH l'olume 1..tlipst 1997 Drqtt Anm.la in e Arviusi Linuts on intale ( Al.1) and Iktn ed Air coisentrations (1)AC) of Radionuclides for acupational Espurc l Elliuent Concentrations Concentrations for Relcaw to Sarutar) Sewerage (Cairniml> 1aNei TaNe !! T able !!! Oscwemeial Efilusta Relraws to Values Caenummre Se. m Cid 1 Col : Col ) Col 1 Col hkihly ID at Ingestum _ WlyfL Aterage kivms Rajensinle Clana ALI All DAC As M aies Carmentatmn c f u ima fu emn f pt'i mh f et* mn r Nn s pee) d pca I 12 Afmanwmed D we'lk $E*) JL*) OL4 $E.9 6E.) 6E4 % an "de C lE*2 41.8 lE !O C C 12 Germamuma.9 D we "de ll *4 IL*J 6E4 IL 8 OE4 lE.) W. we "De C IE*) 3E4 IE 8 C C l' Gennamum 71 D aes *de SL*$ J'i + 9 IE 4 6E.7 7L.) 7E.: n we "as C JE+4 00 4 6f -4 C C ): Germamum 75' D we "tk 4E*4 80+4 3E.3 IE 7 C C Si esil 17L '4 C C C 9E 4 9E.) %, we "ik C BL*4 40 4 IE.7 C C M Gefmanmm-77 D we "de 9L*) IL*4 4Le IE 8 lE4 IL.) %; ace "(k C 6E*) 36 IE.9 C C 3: Germamum 78* D we *oe E4 OE*4 96 + JE-8 C C 56 mall ( E*4) C C C JE4 JL.) % we "de C E*4 90 s. )I -4 C C .13 kwnue# % all papend. M *4 10 5 SL.4 lE.7 C C St mall (40 4# C (* C 6E4 6E.) 11 kwms. hf %, eli ssnpunda IE*4 !E*4 20 9 7E.8 IE4 OI.) 14 kwnn fl n. ell sepwnds 4t*1 SE*) 21 4 6E.9 ?L.3 $E4 il kwnis 72 n. all evnp unds 9E* IE ) 6E 7 lE.9 IE $ IE4 31 Anena 73 % all 6.vnpunJi sta) 0E-3 7E.7 lE.9 IE4 IE.; 31 kwms 74 %. all usmp ends IE*) BE*: JE.7 IE.9 F.9 lE4 1,1 kwmc M %. all evneve IE*) IE*) 6E.7 lE 9 IE 3 IE4 )) Arwnis 77 n allstenpunds 4L*l SL*)

E4 Tr9 C

C 1 L1 onl6 ($ E * )) C C C 6E.$ 6E4 3% ,\\rvric. 7E' W. ali penpunds EE*)

• E*J 9E 4 3E 8 IE4 IE.1 14 5elemum.h 8 D silvenpends ewpt

- th.*w gnen he % lL*4 4E*4 20 5 SE.8 IE4 IE.1 % mih bdemidn sar%h anJ clementd 5e IE*4 4E*4 20 4 6L.A C C 14 Sciemum 71m' 11 we he 6E.4 Et 6E. 4 lE.7 4E 4 4E.1 %. we is 3E*4 I[*$ 60 9 2E.7 C C 14 Se6emum.7 t in we % )L*) IE*4 $E4 l0 8 4E.S 4E4 %,we % C lE+4 7E4 OE.8 C C 14 se temum-74

13. we %

$E*: 7E*: IE.7 I F. 9 7E4 7E-5 %.we % C 6E* 3E.7 IE.10 C C bumes artwar a* IIw end ofilww thets tabla DS799

.W'R l'ohoe i.* lugust I99? I)rqft Amnda 11 Annual I inuts on intale ( AlJ) and IktncJ Air Corwentrations (DAC) of ReJionu6l ides for Occupational Lyusurc Emuent Coruntrations Cmuntrations for Release to Sarutary Senetage ICoramni) Tatae I f.Ne 11 1aba til t uurwimal thers Krieance ta i alues Comenersuons Sewers Cd l Cd : Cd ) Cd i Cd 2 l umwe usi thgesimn _jtibelegt.,, Astrage Atems k adi. val Je Pica All All DAC Air % ster Carmentrotne Nn t pr%) r u(M turs enn a p('s mn r90$ mn t p(* inh 14 f.evemurn 79 D ace he 6L*2 IE*: )E.7 IE.9 8E4

• E !

%. nee he C 6E+2 17

1. E 10 0

C 44 '.elemurn Atm* D we he 4E*4 7E*4 JEJ 9E.8 li d IE.1 n' we he

L*4 7E*4 JEA 1E.7 C

C 34 Kelernum sl* D.we %e 61 4 9EA 3E.7 C C Sa mall (SE*4) C C C lE-) li.: % we he C lE** IE4 31 7 C C 44 % mum s i' D we he 40*4 (L*!

• E 4 26 7 did 4E l

% we hv JE*J (E*4

• E.$

OF 7 C C 39 fir emne.74m' D hr4eeJen ie ll i t \\a L kh. ra arW i r IE*4 4L.4 14 (E.8 C C 5: well (;f*4) C C C JE 4 JL.) % t+eides e4 laruha. rudet its Mg Ca Sv fia Ra Al. Ua let it. roe Sri Pb Aa % ili l e ku i n ra kh. Ir, N l'd li. Ca Ag Au. 14 Cd 14 Sc Y. It h.10 %, Nh it Mit Tc. and ke C 4E*4 2E 3 6E 8 C C 3% liteme 74* D we *Dr L*4 UsJ 31 4 lE 7 C C 8t mall (JE*d) C C C 30 4 $E 3 % tet *lls C IE 4

41. A IL.7 C

C )) litnamne-73' D,we *ltr 3L+4 SE*4 14 70 4 C C 51 mall

1. 40*4)

C C C 50 4 !F.) %. we *hs C SL*4 EA 7E 't C C li lisormne ?te D we *llt 4Etj $E*)

E4 TE.9

$E.1 SE4 W. net *nt C af*) E4 6L.9 C C li Inromitw.77 D we *Hr

1. e 4 E *4 tE $

JE.8 E4 Of.) %. we *Hr C lE*4 8E4 IE.8 C C 34 tireine.num D we **n, E*4

E*4 n.4 E.s JE4 36.J

% we

• Tis C

IE*4 oE 4 28 4 C C 34 henemne a# D we *lte 3L*4 2E*4 st.$ 3E.7 C C Si m all (9t*4) C C C IF.) IE-A we *be C lE*4 WEA 3E.7 C C 39 Dreine a:

1) we "nr 3L el 4E*)

E4 6L.9 4E $ 4E 4 % we *ne C 4L*)

E4 3E.9 C

C 35 informnc-41 D we *Dr SE*4 6E*4 JE.S 9F.8 C C 54 =all (7E

• 4)

C C C 90 4 9E.) W. we *"Dr C 6E*4 )E S 9L 8 C C lina **acs arrear at the end ofslocse there tables l D5898

• %Rt'R l'olume ! + + tugust 196 Drqll Anundts ll i

Alituuil 1,linits on intale ( Al.1) and Iktned Air Coinentrations (DAC) ol' Radionudides for (hupational Es}osure I;tiluent Coswentrations Conwntratmns for Relcase to Sanitary Sewcrage (smtmurd) 7 able i iaNe il T aNe lit t uursweial

iINerit iteicaws in 4 alues Caenuamns f,m ers Oni 1 Col

Col ) C4 I col kkwohly ( sal Aware legention _trihttswL., Alivmc RaJovim hde Class A1.1 ALI DAC An u sier Cornentration t u. mi) r r rit r i.rit t re mn r r, mn (wr, mn u w Nn I i .tv itinum v % w, **) 3F +) vf' + 1 dL4 IL-8 dLJ 4L 4 ), we ** Y C 8L+) JL4 IL.8 C C Je i sirium.ul % we "*Y ll: * ) JI +3 IL4 4L-9 34 34 Y.we"") C M e) IL4 JE.9 C C 10 i ttreurd 4 we "*)

• L*4 8t+4 30.$

IL.7 C C r.: esil (3 L

• 4)

C C C 4LJ 4L.) ). we ** Y C

1. L*4 Sta ll 7 t'

C 39 ituiurnu'* % we **) 40 4 lL** 61 3 21 7 C C si e all (ti +4) C C C 7L 4 70.) ). ws **) C IL*$ 6t J 20.1 C C 4) /w mium ar. [1411 c.enowna ewes th ar gn en lev % 4tW ) lb) el*) 2L e 6L.9 'f. 8 34 % oud. hs Jr.iudn halides and nitrees C 3061 IL4 41 9 C C i urNJe C 20*) IE 4 .1f.9 C C .LJ 4 41 /pe mium na D we "h 4L*) lL*: 9L 8 16.f o HJ % we"h C

• L+

If.? Elo C C ).we"h C JE*: IL.7 4L.10 C C 4) Inveium 84 D we "/r !!

• 1 d!! * )

lle 5L.9 lL $

• L 4

% we"h C 21 * ) IL4 3L.9 C C ) we"h C

• L*3 1L4 1L.9 C

C 4i lersanium Wl D we "h IL*) f.L *0 JL.9 C C C lbrw surf Ibes nerf 13L*3) (2L + 1) C 20 11 4L J

41. 4

%, we "h C L*l it 8 C C C lbme surt I f f>F

• l)

C 9E 11 C C ). we "h C 6 Lei 20 8 C C C lbme surf C (7E*l) C E li C C es hecrvuum vi O we"h II'

• 1 iL*:

4L 8 C 3$ 2L4 Ikme surf C ()L4 2) C

41..in r

C % we"/ C 4t*: 20 7 St.la C C i we "h I' JL*: II..? 40 10 C C el / mmium47 0 we"h (A * : 2L+) 8L.7 IL,9 9L4 9L.i % we"h C IL*) 6L.?

• L 9 C

C ),ws"h C llal it.? 31 C C 4 di N.iNum-an' % alle vnew ouen ibar gnen 14, ) 40 4 L*) 904 El C C 3: 4 411 (70 4) C C C it.) 10 2 Y. as.Jn anJ hsdroudes (* Otel VL.

• 11;. 7 C

C 41 Nemium E# % w,"% (Lad 4L*4 lL4 4.8 I r..t it.) vs. man, ), we "o C 4r.e 4

ta St 8 C

C femhmtra alTear at the end of thew shree IaMe.s D6199

I AMenda U MlWR l'oloor I.loign<l IVVP Ikq/I Asunwl 1.inuts oillntaLe ( Al.l) and iktned Air Conemtrations (DAC) of Radiomwlides for Occuptioci l'\\1cm l'.nluent "oiwentratums Coinentratums for Release to Nmtary Seuctore W4msmun0 t38.. i t.* u T.m in w 4*.,' t Iflured keleames i*i islurt Ciwisemtastus $eo e*t Cal l Col I fel ) 00l l Col hkuuhh (rel trycatsun hWomL Anetagt Abens k.Ji.eul le Cima Att ALI DAC Air H aier C*vuentation a c mh

1. pri mn ta en iuca f c mh rpei nin u

r Na 41 b hwn49 % net "% ti e) 3*4 60 4 3E.8 7E J 70 4 61 : mini E we"W C 3*4 6L 4 38 C C 41 % Awn se % we "W IL4) ll ) It4 40.9 IL.) IE4 L we "9 C 3.) II.4 31r9 C C Ji M6um mm W we "w vt ) 3.) St.7 JL.9 C C til e all (10 4) C C C 34 31 ). we %b c

• f.:

7[. A 3 10 C C 41 b6wm u % we "w 90 2 3+ 5L.8 JL-la ti.4 IL4 i we "W C 31 6f 0 'f. Il C C 41 M 4.ium em W we "W l*) )! * ) IL4 40.9 C C t i l mall ( t. )) C C C AL 4 ILJ t we "% C

Lej vl.1 JL.9 C

C al % Awn 94 % e "% !! e i 1L*)

• E.7 2L-9 JE 4

)E 4 ) we "% C IL+1

• F 7
• L 9 C

C 41 %+<um e. %. ws "W 10+) Al ) IF 4 4f. 9 '04 'L 4 twe"W C 33 If4 ll.9 C C 41 MAum vf W we "W 3 +4 BL.4 )L t 1L.7 JI 4 3b) ), we "2 C 7L.4 31 4 1L.7 C C Ji %.Num*F' W. we "W ll *4

• E*4 Oi 4

1. L.8 34 20 1

4. are "W C

'f. + 4 31 48 C C 4 % % knen

• D all e.vntenene eum tNae gnen i.e i 41 4

?! l if 4 IL.4 )f 4 JE4 ). medes hveme,s and kl4 OL*) St.1 34 60 0 C C 4: W htenwnwim D we %b 9L') lL*4 70 4 35 60 4 604 ). we *\\lo 4L*) IL 4 61 4

f f C

r' 4 kbhNenum44 D we h b 4 Lei SE*) 34 11 -9 SIA 50 4 Y wv *%s 2L*4

L*

4L.8 3 10 C C 42 A W Menwn W D we *\\b 3.) JL.) IL 4 4L.9 C C L l.1 mall t \\ L

• 1)

C C C

L.S 34 i.wv*\\b ll.. )

II.) 6L.7 20-9 C C 4: \\bhwenwn lut* O we *\\b 4E*4 1L.4 60 4

E.7 C

C 51 m all 14t*4i t' C C 7E 4 7E.) i ve *W C IL*4 6E.4 MJ C C el T eshrwtiwn 9 tm" O all c.vngmM suc iMee gnen (.v % 7h

• 4 3*)

60 4

fi.7 10 3 1L.2

% me.sMemes halect. and neu Wes C 10 e t It 4 40.7 C C 43 f ecterown el il nee"Ts 3E*4 7L.4 )E-3 IE.f 4E 4 4E.) % we'*rc C it.$ 4E.s 10 7 c c l'omsonnes appear at Ilw enJ golww thru taMa D6298

. ~.. - -. -. A;pndn il XW'R IWume /.,tupal I991 Drg/l 9 i Astinial 1.s' sts ivi Intalc ( Al.1).tud lkrised Att Corintitratioris (DAC) of Ra&onuclides for Acupatuvial INuure I filuent Concentrations Cothetitfut40 fin for Release to Sarutan Scuerop s*smtmurch i 14w. 14hle !! tew III (44unen mal 0liluent LeWaws u ) alues cementretents Sete4 r c.4 1 e4 : c,4 ) Cai i col : Wnthh t aal livesi m. _trM et o Aseinte venis Ital. m i.de claw All ALI DAC Av u sef c aravaxe Nn (pf'il ( pt'd (u(* mh f uf*e mh (p(*i mh disf*t mit 4A I nhneuumen' f) we'*fe

L+4 4F 4 ltA tt 8 JE.

1EJ W we'*ts c 6L.4

1 A 11 8 e

c 41 inhrvtium48 t) we '*f s 91 1

t 4 tL4 JL.8 10 4 IL4

%, we '*f s c

E 4 ifA JE s e

c di Techneteum-94m l) we '*f t 4L+)

• E*)

34 81 9 81 d

• t 4

% us **h c

t.)

30 1 AfA (* c di Tc hacown44 (1 we **f s 11 4

1 4 9L 4 48 Il d if4

% we '*fs c E*J $04 10 8 0 C el Inhr.coume' i) we'*f s 3+$ JL 4 16 4 4F.1 lL4 3* % we'*h c

t

• 10 4 JL 7 C

C al fettvwum.+ D we **f s IF+1 H.) li 4 $L 9 JL. )E4 %. ce '*f t c L.t JL.,1 JF 9 e c 44 lethacouma'im f) we '*f s 4t *) 71' * ) )L4 c 6f d 6F J si e all c 17t n c it -6 e c %. we '*!t c II.)

• !.7 Of 9 c

c el le6hneimmat D we'*is at+4

• E-4 LJ 71 4
• i d
• Ed

% we '*h c t,1; - )

ta stav c

c 41 T ec hncoun,. Ja () we'*f s IL+)

L+)

7L 7 39 Ilb 4 10 4 %, we *Te c M.: 11 1 4L 10 C C JI Inhnenum nn D ve **f s 51 *4 L5 66 A .t. 7 IL4 10-2 % we '*Tt c f* IF 4 IE.7 C C 41 f emimmm I we *1: 40.) st-)

L4 c

GA na Staed r W.,o e al,9 e c % we '*Is c 7}. *

• ll.7 9h,li t e

f' di f echnsoum istl' D we **f s VI. ' 4 JL** 10 4

• F. 7 C

C 9.en utm e e c 3-)

t a

% we '*f s e 4L 4 E4

• F.1 c

t' 41 leghnium las' D we **Ts L*4 70 4 1LA 1[.4 f* 4"' 9 e a.1 iQ*4) f* f' f* dl J

4).)

% we **;s e vi. 4 4 H.1 e t' M kwh,% m *$ i)... v *P <d% %qt ^ is,e p enev n 4nd )

E.4 4t.4

tA e,t.a

E 4 Na W. Miides e

ht.4 3r A Sa e r* \\ w ea hsar.wie, c 6t.4

tA st.:

t-r- 44 flwilwmum>J) D we *% XL*) lI. 4 the 1L.5 l[4 IE.) t It 4 %E 4 3R (' % we'% ), we *h il+4

41. 4 41

(' C M kwNmum-Oil D. ee '% 3*l lL*) E7 L 'd ilA IF A W we *% e IF+) 4E.7 IL,9 C e ) we *% (' bE*! 10 7 90 40 (' c lknarnes apyw at siw roost o>f there there tables D6399

• WK'R I We,mc /.. luguit /991/>roft Apper. dis !!

Aluwl Lients on intae ( All) and Iktned Alt Coinentrations (DAC) of Rcdionuclides for Occupational bposure IMlluent Corwentration: {0lwcillr3llolla for SeleaW to Saluuu) Se% etape d'ontmpeJ) Table i f etue ll T able ll1 a4urexre tillunt Relemas ta \\ aime Civuerwaanes Sews t al l Col ! Col.1 C4 I CM ! h Lm.hh (mal Ingestum irit+416.tL,,,, Awage Ahens kedamsh.it Clans All A1.8 DAC As M aier Carmenrauan r (u rmn ho sN (90. < pn en 'wri mh v 6 mn u 44 kuihenium.14 D. wv **k u 3F e) 1[ +4 6E 4

• [.0 70 9 7E 4

%..es k u C 1L+4 ef d IL I C C ),act"kw C ILad ?L 4 'l - 8 C C 44 kuthe um let. (1 we ku

L*2 WEel 4L A IL lo C

C 4.1.1 e all (2L+;) (* C C )[4 JF.S % we"ku C

• t*l 11 8 10-81 C

C ) we Ru C IL*1 SL 9 lL.11 C C 49 khahum 4*n l) 4116 wnfasmd.euert thme gnan irv % stuj i 'l e d t.E 4

• l. 3 IL 8 OL4 2[ d

%. hahees C 8L.4 JL 4 10 7 C C i. esake anJ h*udre C 71 +4 31.e gt.3 C C J4 kh.shumet

1) we **kh

!! *) JL*) lie 4L 9 JL 9 if 4 % we *kh C lL l 9I 7 3I 9 C C t we **kh t' 'L-) BL 7 11 9 C C .f.) Ole fl u 2L.4 IF 4 44 khshum-Im D we 'kh Olel % me *kh C 4f l hl.9 C C ), we **kh C 4L+3

• L +

$L.9 C C 49 khsh m inlm D we 'kh 01.I It 4 SL4 IE 8 flo 8L4 % uv *kh C IL-) df 4 ll.8 C C ). we 'kh C IL-) 3f + 10 8 C C 44 kh shum. lut b we *kh 2L.) St

• 21 7 0

)Lo )L 4 % we 'kh C Bl

• 2

)f.7 J.9 C C \\.cv *kh C 10-2 of 4 lL40 C C 44 khshum lo;m D we 'kh 11.* ) SL=* 'l 7 7F.10 C C L1 I e all (10.)) C C C 't 9 lL-4 % we **Kh C 41 + :

l f

$L 10 C C li. *

• E 4 2L.19 C

C i we**Kh 44 kbih a lo: D we 'Kh OL*; 9L.I 4f 4 1L.10 6E4 BLA % we *kh C

• L*2 7L 8 2L.10 C

C ) we**Rh C t.E * ;

f -t

$L.ll C C 44 kheslium loim' D weRh di * $ 10 6 5L4

• L 4 6L.)

6L.2 % tse 'kh d' l[*6 SE4 Of e C C ). we **kh C IL 6 Si 4

E4 C

C 44 kh shum-lut D we *Rh 41.* ) ll 4 (I e lE A C C Lt.] e all s al. e in C C C st.9 3L4 % are**Rh t' 6t+1 4E A VE.9 C C t we 'kh C el.1

t.6 L.9 C

C 44 kheum bem D we 'kh El' * ) 3E+4 l[ 9 4L-4 IF4 IL.) % we"Kh C 4E*4 !E 9 SL-4 C C ) we*kh dL*4 10 4

• L s C

C 49 khahum-lof 11 we *kh M. + 4

L+1 lla 3L.7 C

C 34 eall (9Eed) C C C lt 1 1[.4 %. we 'idi C JE+l IE4 4L 7 C C ) we **kh C 3E*l IE4 3E.7 C C hentwks surpear at the endofalwse three sahles D6498

Alp:nda il SSRCR l'olume I

• dugtest i997 Draft Annual 1.iimts on intale ( A!.1) and Ikrised Au Coswentratres (DAC) of Radionuclides for Oxuptional thposure I:lliuent Concentrations Concelltrations for RclcaW to SamtMy Se%erage fo##tursted)

Tahoe t T able 11 Table !!! acemal if!)uent Releancs to Values concentrations Seners Cd l Cd : CA 3 Cd 1 Cd : Mmthlv Oral In8eSham _lfhia100._ Asernige Abenes Rai.ieulate riau AEl AEl DAC Aar Water C mcenusuari Nn turn) t ur*\\ t sers mn t uri mn lursen turs mn e Palladium-lisi D all siengvundw ruem tw gnen s<e W an44 Y IE*3 IE*) 6E 7 Eo 34 E4 W eius'en C IE*) !E.7 3-9 C C i a* 4 and hidmvan C IE*3 6E 7 1E.9 C C e Pallatium lol Dr Td IE 4 3E 4 IE 5 SE-8 ZE4 OE-3 W. we '*N C 3E.4 IEd SE-a C C L wv *N C 3E+4 IEJ 4E t C C 46 Palladium.ini D. we *N riE

• 3 6E*3 JE4 9E-9 C

C LLI well ( 7E

• 31 C

C C IE4 1E 3 W.weN P 4E*3 E4 6E 9 C C 1, we "N r JE 3 IE4

• E 9 C

C e Palladium-l"7 D we #Td 3E 4 !!'

• 4
• E 4 C

C C Lil mail L.Jnew (4E 41 i:E 4) C 3E-2 SE4

• E 3

% we '*N P .4 3E4 I E.s C r i, we *N C IE 7 6E.10 C C e Pallatium im D we*N E3 oE ) 3E4 9E 9 3E 3 3E4 % we *N r SE 3 OE4

1. E.9 C

C i. we *N C SE*)

E4 6E 9 C

C 47 Li*ee in.* D all siimp=nda nces th.ne gnen be W and Y

• E-4 E5 8E 5 OE 7 C

C Stwa9 (6E 4, C C C 9E 4 9E 3 %. niuaies and sulliws r OE 5 9E4 3E 7 C C i. nudes and hurwdes C OE-SE4 3E 7 C C 47 Lher.'u? D we Ag 4E.4 IE 5 4E 9 I F-7 .'E4 SEJ W.we *Ag C IE 9 SE 5 lE 7 C C Y,we *Ag r IE-5 SF 5

E 7 C

C 47 Lhev,I%n* D.we "Ag it 4 9E 4 4E t IE 7 ci. 4E 3 % we

• Ag C

IE 5 SE4 E7 C L we *Ag C IE 5 SE 5 OE 7 C 3E 3 47 Sher l*# D wv *As OE 4 7E 4 3E4 IE ? % we

• Ag C

IE 4 6E.5 lE 7 C C L we "Ag C IE*5 6E.5 lE 7 C C 47 5.h er.lus D we "8Ag 3E.3 IE-3 4E 7 IE 9 4E 5 4E.4 %. we

• Ag r

OE*) 7E 7 lE 9 C C L we *Ag e E3 7E 7 OE 9 C C 47 Lher. lire D.we *Ag RE*: 7E*: 3E 7 IE 9 IE 5 IE4 %.we *Ag C 9E 4E 7 IE 9 C C l' we"As C 9E*: 4E 7 IE 9 C C 47 Lher liv >' D we *Ag 6E*4 OE*$ SE 5 3E*7 C C Sq uail (6E*4) C r C 9E4 9E.) % we

• As e

OE*5 vE 3 3E 7 C C L we "As (* OE 5 RE.5 3E 7 C C 47 S.her lusm D,we "Ag 6E*2 2E *.' 8E.8 3E.lu 9E4 9E 3 W. we " Ad C 3E*: IE 7 4E 10 C C Y.we "As C ZE * ) lE a 3E Il C C Fuornata appear at the end ofofww three tabla D6599

App:ndn 11 bSRCh l'oluae I..lugu3t I997 I) raft Annual 1 imita on Intale ( A1.1) and I)enved Air Colwentrations (DAC) of RadionucliJes for Occuptiod Expaure Efiluent Concentrat'.)ns Concentrations for Release to Sarutary Sewerage (Cormnutti) Tabie i f able il Tah6e !!! (Wasal Etflues Releases to s sues C=erumions se.m Cd i Ca : Cd 3 CW l Cai : Akirelv ( ksi Anmge Irpstem J## met Atomic Rahiemchde Class All All DAC Aar Was Ceuwestum <u. ci mn r Io i mn iuc.i iuri) < uc mn r uct mn w of Ethe i t e D. we * \\g 8E*: IE*: SE4 2E 10 6E4 6E 3 %. we "Ag C E.: SE 8 JE 10 C C Y,we *Ag C 9 Eel 4E 4 IE la C C 47 F ih...t a l u.cAs 9E*: E+3 60 7 C C C 1.Li mall Lner (1E+33 (;E* 3) C OE-9 IEJ E4 W we *Ag C 9E 42 7 IE 9 C C ),we *Ag C 9E.: 4E 7 IE 9 C C 47 Silwr-II: D.we*Ag 3E+3 8E 3 JE4 IE.8 4E 3 4E4 u.we *As C IE*4 JE4 lE 8 C C i wv *Ag C 9E+3 4E4 1E 8 C C 47 Sib er.' i d D we *As 3E+4 9E-4 4Ed IE 7 C C St mall n3E 4) C C C .sE4 4E-3 n we *Ag C 9E 4 4E 4 IE 7 C C ), we

• Ag C

RE*4 3E 4 IE T C C 4s cadmmm D# D all crmp=na vue thine snen im W ard i E *4 7E 4 3E 5 9E.8 JE4 JEJ W. sultides. hahdes and mttmes C IE+5 SE 5

C 7 c

c h miJes and hsaroudes C IE.5 SE-5

I ?

C C 4 Padmmm-In7 D we "CJ E.4 SE-4 2E !

1. E 8 3E4 JEJ

%. we *CJ C 6E 4 OE.5 8E4 C C Y. we *CJ C SE+4 lE 3 7E 3 C C 3 Cadmmm liH D.we *CJ 3E.; 4L.I IE4 C C C Lidnm LJ%n HE * ) (SE 1) C 7E411 6E4 6E 5 %. wv *CJ C IE : SE 8 C C C LJres C (IE 2) C

E-10 C

C 1, we "CJ C IE 2 SE 8 E lo C C 44 Chium-Il 3m D.we *CJ E.1 E *u IE 9 C C C knincys LJneys (4E+1) (4E *0) C SE l: SEJ SE4 %.we "CJ C AE*0 4E 9 C C C LJnm (iE*l) C OE Il C C \\.we "CJ C IE*l S E,9 lE Il C C a Palmmm lli 0 we CJ

E+1 OE 0 9E 10 0

C C Lianm kidnm ale *l) ( 3E-u) C SE 12 4E 7 4E4 w. we *CJ C tE 9 JE4 C C C Ednm C (IE.1) C lE.l l C C Y. we *t'd C IE 1 6E 9 2E ll C C M i "almie l l *m I). we *CJ JE*: SE 1 Ea C 4E4 4E 3 LW C (IE + l) C IE 10 C C w we *CJ C IE*: SE s E 14 C C Y se *CJ C IE*: 6E 8 E lu C C da Cahimi t t (1 we *CJ %+: IE*3 6E 7 lE 9 C C Lt l eaJi Femtnt>tes appear at the errd of these three tahlt.s. D6698

e Appendlx 11 SSRCR l'olume I + August i997 Drall Annual 1,uluts on intake ( Al.1) and I)emed Air Concentrations (DAC) of Radionuclides for Occupational thposure D11uent Concentrations Concentrations for Release to Sarutary Seucrase groenmmh TaNe i Table il Tabic ill tkcuswiunal EINent Releases to Valdes Cencentrauons Semers Col I Col : Col.1 Col I Col : real umihh ingesuon _InMation Aserage Ahumt Railumisrlale Cl.as /,[,i AEj DAC As u sier Cancentrainin Nn turd 19C0 furi mh s uci mh (p'i mb rpri mh (I E.31 C C C IEA IE4 % we *CJ C IE*3 SE 7 2E-9 C C Y we "rd C IE+3 6E.7 E9 C C 48 Caam. m-Il7m D.we'**CJ SE ? IE+4 SE4 E8 6EJ 6E4 % we "CJ C E4 7E4 E8 C C i. see "CJ C IE*4 6E4 E8 C C 48 Cadmeum-I l 7 D.ce "rJ SE+1 lE 4 SE4 E.8 6E4 6E4 %,we "CJ C lE *4 7E4 E8 C C 1 we *CJ C IE.4 oE4 E8 C C Ju indium-lw D all ownp unds cw. ;g

ti. w gnens,w %

E-4 4E*4 lE 3 6E 8 3E4 3EJ %. imJn in JrmiA a. Maides and mitteles C 6E 4 3E 5 9E-4 C C 49 Indium Ild D we '*in lE 4 4E -4 OE 5 6E-8 OE4 2E 3 gu I mini n we '*In C oE 4 lE 5 8E 8 C C 49 Indium-l in D we"In SE+3

E*4 7E4 E-8 7E 5 7E4 (4 4 hi

%. we '*In C OE

• 4 8E4 3E 8 C

C 49 Indium-l il D we"In 4E*3 6E*) JE4 9E 9 6E4 6E4 % we'*In C 6E+3 3E4 9E-9 C C j 49 Indium-I I ? D we **In lE*5 6E.5 3E4 9E 7 lEJ OE W.we'*In C 7E+5 3E4 104 C C 49 Indium-l) Im' D we "in SE*4 If +4 6EA E7 7E4 7E-3 u. we '*In C E+5 8E 5 3E 7 C C 49 Indium-I lam D we '*In 3E+ f,E 1 3E 8 9E-Il C C 1.Ll mail HE 2) C C C SE4 SE 5 % we *In r IE 2 4E 8 IE-lo C C 49 Indium Il5m D.we*In IE-4 4E 4 OE 5 6E 8 OE4 'E-3 % we '*In r SE 4

E 3 7E 8 C

C t 49 trJium-l li D. we '*in 4E+1 lE+n eE.lo OE-12 aE-7 SE4 A. we '*In r SE a OE 9 IE 12 C C 49 Indium Ilun' D we'*in E*4 8E 4 3E-S IE 1 1E d 3E 3

3. wv '*In C

IE 5 SE 5 OE 7 r C 49 Indium I t 7m' O we '*ln IE 4 3E 4 IE 5 5E 8 OE4 OE 3 %. we '*In P 4E 4 E3 6E 8 C C 4'8 Indium lif D we '*la 6E 4

E*5 7E 5 2E 7 8E4 8E 3

%. we *In F E.5 9EA 3E 7 C C 49 Indium-Il%' f 7 we ""in 4h*4 IE.5 SE 5 E7 C C 5 mill (5E 4) C C C 72 4 7E 3 w we '*In C IE+9 6E 5 2E 7 C C Foxnmacs appear su ohe end ofthese three tables D6799

Appenas B ' +%RCR l'olume i..lugust 1997 Draft Almual I.nmts on intule ( Al.1) cnd Denved Air Concentrations (DAC) of Ra&onuclides for Occupational Enosure Elliuent Concentrations Concentrations for Release to Sanitary Se%erage Amtmued) Tet41 TaNe11 Table !!! Cacupammal Effluent Rewanes to Values Civisaremmns Semera Cd i Cd : ed 3 Cd i Cd : %mtNv Oral Amage Iri8cstion ,, 10helaott,,,, Atarnia Raluvialale Class ALI ALI DAC Air % ser Cannasuan i w i) vi mn

1. .C. mn vi mi) vi.ini) e (uca Na

%) Intlo D alicernpsals esept One gwen lot W 4E+3 IE*4 SE4 E.8 SE.5 5E4 W. sulhact ovdes bdnmdes. halides. niuma and stannis thschate C IE *4 5E4

• E.8 C

C So Te Ill* D we "*5n 7E+4

E+5 9E.5 3E.7 IE 3 IE.

W, we '*5n C JE+5 1E4 4E.7 C C N Tell) D we "*3n OE*3 IE 3 SF 7 E.9 C C LLI mall CE

• 3)

C C C 3E 5 JE 4 %. we '*Sn C

• E ;

E.7 IE 10 C

C Tm il?m D we "*5n

E 3 IE*3 SE 7 C

C C !.LI mall ihme surt 1:E*h ( E*3) C 3Ed 3L-5 3E4 %.we"*5n C 11 + 3 6E 7 E.9 C C Sn r+1!= 0 we"*5n 3E*?

Eal IE4 3E4 C

C LLi mall (4E*3) C C C 6E-5 6E-a %,we"*$n C IE.) 4E.7 IE.9 C C Sn l in-l

• l m D. we "*5n 3E*)

9E*' 4E 7 IE.9 C C 1.11 mall (4E+3) C C C SE.5 SE4 W we '*Sn C 5E+ E.7 8E 10 C C Tin.l:1 D. we "*5n 6E*3

E 4 6E4 ZE 8 C

C LLi mall (6Et3) C C C 8E.5 8E4 W. we '*Sn C IE 4 5E4 E.8 C C M Tml:3m' D. we "'Sn 9E+4 IE 3 $E 5

E.7 TE4 7E 3

%. we "*Sn C IE-3 oE 5 2E.7 C C M Tel.) D.we'*Sn SE*: 6E 3E 7 9E.lo C C LLI mall (6F + 2) C C C 9E4 9E.5 %, we "*5n C OE* 7E.8 lE 10 C C M T+1:5 D. we '*Sn 4E 2 9E 2 4E.7 IE-9 C C LLImaa iE*) C C C 6E 4 6E 5 4 W.we"*5n e 4E*: IE.7 5E-10 C C So im 126 0 we"*%n JE. 6E*l E.8 aE.i t 4E e 4E 5 W.we"*Sn C 7E 1 3E-8 90 11 C C N Tin-107 D. we "*Sn 7h*3

E*4 8E4 3E.8 9E 3 9E4 W. we "*5n C

E*4 8E4 3E 8 C

C 9 Tel t* D. we "'Sn 9E*3 3E*4 IE.S 4E-8 I E -l IE.3 W.we"'Sn C 4E 4 IE4 S E-8 C C SI Aruint ow-I l t' D, all s.wnrunh euert ilne snen f s W 8E*4 E+5 IE4 3E.7 IE.1 IE.2 W, swudes. Insirmaks. halnies sulfules wifates and nittmes C 3E*5 IE4 4E.7 C C Fourmstes appear at the crut ofshe.se there rahlex D6898

App:nda ii SSRCR l'olume I *.4ugust i997 Draft Aruuul 1. units oii Intale ( Al.1) and l Amed Air Concentrations (DAC) of Radionuchdes for Occupational Exposurc [0luent ConGcntfallofts CotRentfutions for Rcleasc to Sanitary SCWcragC $'onfuthed) Table i Table 11 Table 111 (kcupsi. mal E&ent Releases to \\ wuss Cmemrataans sewm Col 1 Col C4 3 Col i Col l Oral hinnihly Ingeston ktnaison Asernge Atmus kadneul.Je Clama All ALI DAC Air W ater Consercaban f u i mn (pComh (uci mh r . Nn Ipen (ped f ura mh 41 Animon ll(en' D. we "'5b

E+4 7E*4 JE 3 IE 7 JE4 JE 3 W we "'5h C

IE*$ 6E 5 E7 C C 91 Mmm lin* 11 ws "'5h 7E*4 3E*$ 1E4 JE 7 C C Si wall (vE*4) C C C IE 3 IE : %'we"*5b C JE*5 IE4 5E 7 C C St Anim m-l l ? D. we "'Sb 7E *4

E

• 3 9E 5 JE 7 9E4 9E 3 4 we"'Sb C

3E*3 IE4 4E.7 C C 51 Anim on -l l#m D see "'5h 6E*) 2E*J lie E8 7E-3 14 %. we "'5b ?E+3 OE*4 9E4 3E-8 C C 41 Amm milu D we "'5b lE*4

• E 4 21 A (E.s E4 OE 1

% we "'5h lE 4 3E 4 tE 4 4E-8 C C 51 ,Wmem t # D we "*5b it + 5 4E 3 E4 6E 7 C C g in mm i Si wall ( E*3) C C C OE 3 OE. W. we "'5b c ?E+$ E4 7E 7 C C SI Wi-pm-1:n D, we "'Sb IE*) 2E 3 9E 7 E9 IE 5 IE4 (97tdi %. we "'Sb 9E*: IE*3

• E 7 lE-9 C

C 91 Anime -l:0 D we "'Sh IE*: 2E*) IE-o 3E-9 C C 1.Li *4ll (sE*:) C C C IE-3 IE4 % we "'5h 7E* lE*3 4E 7 lE 9 C C 41 4timel:4m' D we'"Sh 3E*$ IE * $ 4E4 IE4 JE-3 3E ; W we "'Sb OE*% tE*5 OE4 EE 7 C C 41 Amme-l:4 D we "'Sb (40 2 9E*: 4E 7 I E.9 7E4 7E $ % we "'Sh SE OE*:

E.7 3E 10 C

C $1 Antem-l:S D we "'Sh 2E*3 2E*3 1E4 3E 9 3E 5 3E4 W. we "'5h C 5E*:

E 1 7E.10 C

C 51 Anime -l >m' D wv "'5h SE*4 2E 5 tE t 3E 7 C C 5t wall (7E *4) C C C 9E 4 9E 3 %. we "'5b C OE*3 IE $ 3E 7 C C $1 Ammen l*f. i3 wv "ih 61 IE 3 !E 7 lE 9 7E4 7E 5 %. we "'5b SE*: SE*: E7 7E 10 C C 51 Am m mvI:7 11 we "'$b ME*2 lE*) 9E 7 JE 9 C C LLi m ail (AE*:) C C (* IE 3 IE4 W,we"'Sh 7E*: 9E*: 4E 7 IE 9 C C Si An'mm 1 4* D we"'Sh RE*4 AE*S E4 %7 C C (lu 4 mins as wall (IE

• 3)

C C C IE 3 IE ; % we "**h e 4E*9 OE4 47 C C 91 Ante m l:4 (1 wv "'Sh IE*) 4E*3 OE4

• ,E 9 OE.5
• E 4 (Unl hl W.we"'5h C

3E*3 IE4 SE 9 C C Fourrartes appear at the end of the.w thriv tables D6999

Ap'tvlls 11 o .%RCR l'alunw I *.ingust 1997 Draft Annual 1.inuts on lutake ( Al.1) and Iktned Air Concentrations (DAC) of Radionuchdes for Occupational Exposurc Elliuent Concentratioin Concentrations for Release to Sanitars Sewerage Woenmmh IaNeI taNe Il Tebbe !!! (keupatamal Estluent Releases to Values C*wweritratews $eutrs Col I Col : Col ) Col I Col 2 Monthly oral Astrage Ingestne _InhenrL._ At vene Rade mud.Jr Clm AEl Al.1 DAC Ad W ater Ca centratum a ci mn euci mh t uci mb rpermn

1. _uci) f uci) u 41 Asuma l>8 D. we "'6b JE.)

9E*) 4E m I E -8 4E J 4E4 n. we "'sb C oE*3 4E4 IE.s C C 41 Antim.m lhe D we "'Kh IE*4 6E4 3E 5

• E -s 3E4 3E )

W. we "'5h C 8E*4 3EJ IE 7 C C 51 Animvn.13I* D. see "'5b IE*4 OE

• 4 IE 3 C

C C Thymid Thnmd ( 3 4) (4E*4) C oE 8 24 El u.sw "'$b C 2E*4 lE4 C C Thwmd C (4E+4) C oE 8 C C 3: Tel!wium 116 D all seemnJ* cwcri thow g.nen 1,v u st.) M *4 9E e 3E 8 IE4 IE 3 %. oudn husroudet end anraies C 3E.4 IE,5 48 C C 5 Tellunum l:Im D see "*f e 5E*: E*: RE 8 C C C bee swt ikwie surf (7E* ) (4E *:) C 5E 10 IE 9 IE4 % we "*le C 4E*: E7 6E-io C C 5 Tcliunum 101 D we "*Te 3E+) 4E+3 OE + f+ 4 4E 5 4E4 W we "*Te C 3E*3 IEm af 4 C C 42 lellunum 1:Im D. we "*Te et*: 3*: 9E.8 C C C Em swr one surf (IE*3) (SE* ) C IE 10 1E4 IE4 %. we "*te C SE.2 OE.7 IE lo C C 5 Teilwel:3 D we "*ie SE*: M*: tE 8 C C C Nee surt &me surt (IE

• 3)

(SE.2) C 7E 10 34 OE4 W, we "*Te C 4E *: IE 7 C C C Em surf t E 3i C lE 9 C C l C 5: 1ellwium-l *m D..er "*!e IF ) 4E.: E7 C C C Smcswt Ame swt (I E * )) (IE.) C IF A

E 4 lE 4 W. we "' Te C

7E ': 3E 7 IE 9 C C 4: Tellunum-1:?m 11 we "*Te 6E.2 3E*: IE 7 C 9E4 9E4 Sme surt C (4E*:) C 6E.10 C C n.we"*!e C 3E*: IE 7 4E 10 C C 5 f eilunwn 127 D. we "*Te 7E * ) lE*4 9E 4 3E 8 IE4 IE 3 % we"'Te C IE*4 7E4 OE f C C $2 Tellur e ttim D we "*Te SE+ 6E*: IE 7 9E lo 'E 4 7E.5 % wv "*Te C IE*: IE 7 3E in C C 5: Tellurium l?f D we "'Te 3E=4 6E+4 3E 4 ?E-8 4E4 4E.3 n we "*Te C 7E *4 IE-5 IE T C C 143rsnorde.1 appear at Ilw em)af thew three table.s. D7098

App:nda I) .%RCR l'olume I

• August i997 Draft Asuiual Limits on intake t ALI) and Iktned Alt Concentrations (DAC) of Radionuclides for Oxupational Exposure Ellluent Concentrations Concentrations for Release to Sanitary Sc%crage (Contmml>

TaNe i TaNe 11 Table til occupaumal EINent Rekanes to Values emcercata.s Sews Col I Col : Col 3 Cal I Col : Momhlv nel Ingestaan Jrgem,__, Amage Atiems Ral*euclide Clau AEl AEl DAC Air %'ater Cant.entrauon f u il fufM (ui mh ' uri mh (ucrmh auremn c N.* 4: reilunwwlilm D w "*Te JE*: 4E*:

E 7 C

C C Thm.J Thwmd (6I. + 2) (IE 3) C IE.9

• E4 IE 5

% we "*t e C 4E*: 37 C C C Thm d C (9E*:) C IE 9 C C 4: T eilunum-I tl* D w "*Te 3E+3 ?E+3 E4 C C C Thwmd Thwad (6E*3) (IE+4) C IE-8 SE-5 8E4 % we ' *ie C $E+3 E4 C C C Thmud C (IE*4) C OE 8 C C 4: Tellunum-I t: D w "*T e E.2 lE*: 9E 8 C C C Dwmd Dwmd (7E+ ) (86 *:) C I E.9 9E4 44 %. w "*i C lE*: 9E-8 C C C nomd C (6E* ) C 9E 10 C C 52 Tellunum 111m' D we "*Te 3E*3 ?E*l 14 C C C Thnmd Thmid (6E+3) (IE.4j C

E I 9E 3 9E 4

% we "*Te C SE+3 34 C C C D3rmd C (IE +4) C OE 8 C C 3: Tettunum-131* D.cc "*Te IE+4 14 9E 4 C C C Thwand Thvemd (1E*4) (6E *4) C 8E 8 4E4 4E 3 W. we "*T e C 24 9E4 C C C Thumd O (6F +4) C 8E 8 C C 42 Teilunum 134' D, we "*Ts E*4

E*4 IE4 C

C C Thwmd Thwmd ( E 41 (SE 4: C 7E-B 3E4 3E 3 %. m "*Te r 3 +4 IE4 C C C Thomd C (5E 4) C 7E 8 C C 43 1 dme-id e' D alivenw4s 1r+4

E.4 9E 4 IE-8 C

C Dwmd flE 4 C C C OE4 E3 43 1.ent-l > P I) att uepwai 4F.3 9E=3 4E4 C C C thomd Thwmd t NE.1, tlL 4) C JE 8 IE4 IE 3 ti lidme 121 D, all uvrpwds IE.4 lE*4 NE4 r C C 1humd thwood (3E.4! (SE 4) C m.a 4E 4 4E 3 ti lidme-121 II. all o epwds 3E=3 6E*) 3E4 C C thwmd Thyroid (IE*4) ( E*4) C 38 IE4 IE 3 53 imime 124 l). all oepeds SE+1 8E+1 3E-3 P C C Thwmd Thwmd (;E

• 2)

(3E*2) C 4E 10

E4 E3 Foonu>tes uppear at the enJafthex three rahla D7199

AppendisD a SSRCR Ii>lunre i..lupust I997 Drall Annual I.inuts on intale ( Al.1) and lamed Air Concentrauons (DAC) of Radionuclides for Occupational Exposure Ell 19ent Concentrauons Concentsations for Release to Sanitary Sewerage (Contarved) TaNei Tat 4e 11 Tahle I!! rkcestamai E& ens Iteleases to Va4ues C.nerarsuva $ew m Cni i Col : Col 3 Col I Col kkuuhlv Oral Astrage Irgestum _hiMlstigt, ,wwmc Rademu6lule Clas All ALI DAC Aar W ater Conocrursuem tu ima c f u i mn c scima f ure mn ,u_cA iuc A u N.i il 14ne.114

0. all ownp nh 4E*l 6E+1 3E 8 C

C C Thnd Tbmd (IE+ ) (:E *:) C JE 10 E4 ES 33 liene-l:6 0 alls 4vnpunds E*l 4E*l IE-8 C C C Thtmd Tbmd '7Eal) (IE+:) C OE 10 IE4 IE 5 SJ 1 ahne i t* O all uenpunds 4F 4 IE+$ $Ed IE 7 C C 34 mall not+4) C C C IE4 IE 3 St Indme 109 0 alloependa

• E*d 9Eul 4E.9 C

C C Nmd Thnd (;i l) (3E l) C 4E-il 2E.7 ZE4 41 Imline llu D. nat uepuds 4E. 7E *: 3E 7 C C C Tbmd Thed ilE 3) (;E 3) C JE 9 lE $ E4 St I.orw 111 D Mi ovnpunds 3E *1 SE l 20-8 C C C ThwoW Tbmd (9E.1) (:E. ) C E to IE4 IE 5 93 kene 13 m' D. ali cunnmnds 4E*) 8E*) JE4 C C C lbtmd Thm4 (IE*4) (:E-4) C 3E 8 IE4 IE 3 SJ 1.une-II: D MI cepends 4F+3 ff -1 JE4 C C C Thw nd Thnd (CE+3) (IE 4) C lE-4 IE4 IE 3 31 lene Ill D all s.epmnds IF : 3E*: IE-7 C C C Tbmd Thund 1 F 2) (9E-l) C 1E 9 7E4 7E-S 5 33 !=hne-I tt' D. all siepends t4 ?E 4 E3 (EJ C C Thw.wd OE.4i C C C 4E4 4E 3 53 14ne 135 D allownemnds

• E*:

E 3 7E 7 C

C C Thvenid Thmd LIE + 1 (4E + 1s C 6E 9 3E 5 3E4 54 Nenin l?if %hmerwm' C C IE-1 JE 4 C C u Xcom 12t* hbmenam* C C E4 IE s C C M X m m l:2 submermn* C C 7E-3 JE 7 C C 4 Xcom l:3 Suteerwm' C C 6E4 3E 8 C C 4 Xennn-l:4 %hmsnam' C C lE 3 7E 4 C C M XmWl:7 %bfTWfw e' C C lE-$ 6E I C C M XetW4el '%n hiTfWrw1R' C C E4 '/E

• I C

C 4 %nw l.ilm htenerwm' C 4E4 lE4 C C 54 Xemm-111m %hmm.m' C C IE4 6E 7 C C hmenvues appear at alw end nf alwse thr>>e tables D7298

.%RCR l'olume i. iugun 1997 Dran Appendnil Annual 1.ilnita nei Intake ( Al.li and 11erised Air Corwentrations (DAC) of Radionuclides for Occupational Exposure Emuent Concentrations Coiwentrations for Release to Sanitary Sewerage (Cixstmued) i Table i TaNe !! Tele !!! ac4atamal E fUwefit Reicanes to Values (* mcefitratwrit $cuers Col I Col Col 3 Col 1 Cai : Wnthly feel Ingestge Au1L.,,, Astrage Ahng R alvmuchde th All AEl DAC Aa % sier Cancentrauen f o s) o ut'i mli (uri mil (uri mf1 furimD r hen f utM 84 Xemm-131 krecrwe' C C IE4 'E 7 C C 54 Xeme 134m' Levnerwe' C C uE4 4EJ C C 44 Xemwl35 ht'mmne' C C lE.4 7E 8 C C 9 Nenic-138' Submmum' C C 4E 4 OE-8 C C $3 Cenium-l:t* D allownpiune 'E*4 IE*9 60 3 Of 7 C C 5t mall (9E *41 C C C IE-3 IE : 43 Ceuum-l'7 D di evnnmnds 6E*4 9E*4 4E 3 IE 7 9E4 9E 3 Cesium l u D allsepiurus OE*4 3E*4 1E 3 $E4 JE4 3E 3 45 rewm-l W* D d vepune 6E*4 lE*4 8E t 3E 7 C F si aai! (IE * *) C C C IE 3 iE 2 4 59 Ceuum Ill D ait sepune OE*4 3E*4 IE 3 4E a 3E4 3E 3 it resium-I I: D alicepmne JE*) 4E*3 IE 6 6E 9 4E-5 JE4 95 reuum lum D cluepmne IE*5 IE*? 6E 3 OE 7 C C Si ma;l (IE*?) C C C IL 3 IE 45 revum,i t4 D aa sepwne 7E

• l LE*:

4E 8 E 10 9E 7 9E4 St revum-13 9m' D allovnnmous IE*3 lE-9 ilf S 3E 7 IE 3 IE ; 54 remum-I t' D mi cepiune 7E 0 IE*3 'E 7 E9 IE-3 IE4 35 rewm-l b D else pmne 4E*: 7E - 3E 7 9E 10 6E4 (E 3 it reuum 117 D allsompmne IE*:

E*

6E A lE.iu 10 4 IE-3 39 Cemum-13E" D W oppends OE 4 6E*4 OE t 8E.8 C C 54 mall 13E 41 C F C 4E 4 4E 3 to Hanum-1:5* O dise pene 6E*1 lE *4 6E a

E-4 RE-5

• E4 56 Banum 10lt D aaltepmne SE*

E*3 7E 7 lEA 14 7E 3 to Hanum 131m' D all umpmn*

4E** IE 6 6E4 lE 4 C C St mail (SE

• S)

C C r 7E-3 7E

l lunum Ill O a.lwwne w e 3E*3 IE*3 3E4 IE a 4E.5 4E4 ILvmm l11m U ail sepur h lE*)

9E*) 4E4 IE 4 C C l El a n!! ( 3E * )) C C C 4E 9 4E-4 to itenum-111 D diowpune OE*J 7E 2 3E 7 9E lis E3 E4 So lunum 415m Il an unpurds JE*) IE*4 SE4 Es 4E S 4E4 46 Danum. i te lxallce pune IE*4 3E** IE 3 4La

E4

E.3 1%tuntn appear at the end ofihne three taMa D7399

Appends % 13 .%Rt *R l'oluent i.. lugust I991 I)raf Annual Linuts on IntaLe ( Al.!) and Ikrived Air Concentrations (DAC) of Radionuclides for Occuptional thposure 1:111uent Concentrations Concentrations for Relenw to Sanitary Sewcrage (Contoturd) Table i TaNe 11 iable ill Occupumal EtNent Releases to s aiues Coniews.ns se. m Ca i Ca : Cd 3 Ca i ce : Monthiv Oral Aserage ingestion _Jfigin A1wmc R4Jusul k Flass All All DAC Air % ster Concentrauen ipre) (ufs) iW's mi) iu0 mh (afi mh e ufs mh Nn Danwn-len D all eenpunih $E*: IE*l 6E.7 OE 9 C C LLI mall (6E* ) C C C 8E4 IE4 So Danura l41' [3 all s.orf wdn E4 7E 4 3E.! lE-7 JE4 3E 3 46 Danwn 14:* D. aii sienpanh SE 4 IE*! 6E.4 2E.7 7E4 7Ed $7 Lantheum-lii* D ali cionpiunds cuept th ac gnen f.e % SE*4 lE*3 SE.* lE 7 6E4 6E4

n. mides and hsJroudes C

OEa! 7E 9

E 7 C

C 47 lanthanum 132 D we "'I a 3E*) 10 4 4E e I E.8 4E.4 4E4 n we"'la C IE+4 sE4 E-a C C 37 Lantheum Iti O we "'t a 4E+4 IEd 4E 4 lE.7 SE4 ?E4 % ove "'t.4 C 9L 4 JE

• 10 7 C

C 57 Lanthanum 437 () we "'l a IE*4 (E+1 JE 8 C OE4

E 3 Le,er C

(7E+1) C IE lo C C n we "'t a C 3E+2 IE 7 C C C Lner C (3E+ ) C 4E lu C C 37 1 anthanum 138 D. we "'l.a OE+: 4E+0 10-9 SE.12 IE4 IE4 W. ws "'L a r IE+1 6E 9 OE Il C C 47 Lethanum len D. we "'l a oL*: IE+1 6E 7 OE 9 9E4 9E4 %. we "'La C IE*) ?E 7 OE.9 C C 37 ( anirmum 141 D we "'t.a 4E+3 90 3 4E 4 IE.A SE 5

• E 4

%. we "'l.a C IE *4 SE4 IE 8 C C 37 I antranum l4:* D we "'I a ILE 3 lE*4 4E 4 .lE 8 IE4 IE4 % we "'La e 3E 4 IE 3 ?E.8 C C 47 l anuunum 14 4' O m "'l a 4E*4 IE 4 4E 3 I E.7 C C 54 mall (4E 4) C C C 5E4

• E 3 n we "'I a C

9E 4 4E 3 IE 7 C C 4A t'enum 4 44 W'. all sepunus eucpt th.w gnen hr ) SE*: 7E*: 3E.7 IE 9 C C LLl usil (6E*:) C C C IE4 EE-3 L.mJn hswwM and tlu.vides c 7E.: ]E 7 9E.10 C C 54 Penum IIS W we'"Fe OE*3 4E 3 lE4 SE-9 ZE4 E4 ).we'"ve c 4E 3 (E4 ?E.9 C C

• 2 t'enum 117m

%.we'"Pe

E+1 40a)

E +

• L 9 C

C LLl wa41 ( E a l) C C P 3E 3 3E4 Y.we'"Pe C 4E 3 2E 4

• E -9 C

C - Sa renwn-ll? W. we '"Ce 5E.4 IE+5 6E4 lE 7 7Ed 7E.3 ) we'"ce C IE6 5E.5 OE.7 C C l 1 l 14mtonstes appear at alw eminf these three tables D7498 f I l l

I .';5R('R I hiume I +.hopost IV97 Drap Ag y rds%l} Annual 1.nnits on lutake ( Al.1) and iktned Alt Concentradons (DAC) of Radwnuclides for Cxcupauonal bposure litlluent Concentrations Coswentrations for Release to Sanitary Sewerage fontumed) Table i Tab 6e 11 tatu 111 e (keuremai EINent Rekases ic Va;ues C.nuemrations Sewers 1%I I C4 : C.51 3 Cal l Col Oral Monthh Inte$him .,_l@e 492_ A"fase Al.wmc INemucNw 4 %ns ALI ALI D AC Ast % aict Ccwwentraum r c.) fue) .uci mh (pci mn (utemn (uci mh - u w

• a renum-lN u. we '"ve SE+3 sE :

$E ? IE 9 7E 3 7E 4 L we'"re C 7E*: 3E.7 9E 10 C C 5s cen.vn.141 n.we'"Ce

E +)

7E 3E 7 IF 9 C C LEI wall (:E* l) C C C JE S 3E4 4.we'"Ce C 6E*:

E 7 8E.10 C

C in twel41 n, we '*ce IE+3 E*3 IE 7 3E.9 C C LLl mall (IE*3) C C C OE 3 OE4 1.we'"Ce C E3 7E 7 E9 C C sa renum-144 % we'"ve OE+ 3E i lE A 4E lt C C LL! mall ( JE *.) C C C 3E 6 3E 3 T..re'"ce C IE -l 6E 9 3,11 C C 49 F uc.ewel b' W.4I comneds cueri ttune gnen tW Y SE 4 E.* IE4 3E 7 C C Mt mall (7E 4) C C C IE 3 IE ), mdes twdiwJes carddes and itevides P . E.- 5 9F J 3E ? C C 59 hwetmum. I nf n we'*h 4E 4

E i

+1 4 25.,7 .' E 4 4E 3 L we'*h C IE

• 6E 5 lE.7 C

C 59 Nwe emium lism u. we ' *P IE.4 SE-4 OEJ IE t IE 4 I E.3 ), we *W r 4E 4 E4 6E t C C 59 hwemielw n, we ' *W 4E 4 IE-5 SE.9 OE 7 eE.4 eE. 3 L we *W c IE 9 SEJ 20 7 C C So hwemum l4:m' % we "h WE-4 E4 E' 20 7 IE 3 IE Y. we *N O lE 3 eFJ OE-7 C C 44 Pawemium 44: W. wc "W IE 3 lE 3 sE 7 JE.9 IEJ IE4 t we'*N P E3 AE 7 3E 9 C C 49 hwemium-141 n we'*N CE.; IE 30 7 IE-9 C C LLI wall (IE *3) C C C EJ OE4 1,weW C 7L 4 3E 7 9E 10 C C 49 F w unmium. i.W' W we '*h 1lO4 IL 4 SEJ E7 r C St wall (4E 4) C C C (E 4 6E.1 L we '*h C IE 3 5E-5 20 7 C C $9 er womie t 44 a we '*S 3E 3 vE*) 4E.e IE.8 JE.5 JF4 ).we'*W r 8E 3 3Ee I E.4 C C t's b wemium-14 P w we'*W

• E.4

E.5

• E S 3E.7 e

C 5 eall inE*4) C t' IE.) 1L 2 ), we '*h c

E 5 SE.9 1E.7 C

C 1 eo womie I w* w.salc.ime wa euen owne snen be y IE.4 6E 4

Ea sE t

E4 lE.3 L.e. hvdrwdct tartudes. anJ 11 wales C

SE*4 lL-3 RE.s C C limtwares uppear at the enJ<>fthese three tablet I D7599

Appendix B. .WRCR Ibluar / *,lugust /997 /hn/t Annual Limits on intake ( Al.1) and Ikrwed Air Concentrations (DAC) of Radionnelides for occuptional Esposure Efiluent Concentrations Contentrations for RCIc0W to Sanitary Sc%erage (Ccxitimse<// TaNe ll TaNe ill iaNei E!! bent Reiemes u (kcurwaval Values Correntratums Stam Cd I Cd : Col 3 Cd i Cd klenttJv Oral As ernge Ingreatne .,,_Jrgggl_ Aksme Italwmu6 tale N All All DAC Asr % ster Cimantrauen (u i mh (ufemD c (u e el) c r rii (ge )

1. uc, mh u

No ev) Neshmium.lis % w '*NJ

E*3 6E*)

31 4 9E o JE 5 IE4 Y.weNJ C SE*3 OE.i 7E-9 C fut Neshnum 139m %.avNJ SE*3 E*4 7E4 E8 7E-! 34

1. see NJ C

IE+4 6E4 El C C 61 Ncshm..am-13# %.wv**NJ 9E+4 3E.5 IE4 SE 7 IE 3 IE.: ).we'*NJ C JE 5 lE4 4E 7 C C to Ncshmium.141 W we '*NJ OE 3 7E** )E4 IE4 OE 3 OE-2 4.we'*NJ C 6E 4 3E4 9E.7 C C ee n Ncomium-147 %. see '*NJ IL+3 9E* 4E.7 I E.9 C C Lt.1 mall (IE*3) C C C OE 5 Of 4 i we'*NJ P IE-4E 1 IE.9 C C to Neemum 14# %. we '* NJ IE*4 3E-4 IDS 4E-8 IE4 IE 3 ). we NJ C

E *4 IE.5 3E 8 C

C 63 Neishmsum 19 ? %. we NJ 7E*4 IE*5 8E.3 3E.7 9E4 9E 3 i.weNJ C JE*3 SE 3 3E.7 C C 61 Pr'vnet hnei-141' % *i mr*mb naTt ihime gnen I v i SE*4 E5 8E.5 3E.7 C C 5t weil (6E*J) C C C 8E4 fE 3 I Y was hJr %3 cartsdes andlbedes C lE 3 7E.5 OE 7 C C 61 Pmenewum-143 %,we'"Pm SE*3 6E 2E.7 8E.10 7E-5 7E4 i we '"f% C 7E 3E.7 IE-9 C C 61 f%methium44 %. we "'Pm I E *.1 lE+ SE 8 E lo lE.5 OE4 1.we'"tw C IE 2 SE.8 26 10 C C 61 l'erowtruum-145 %. we '*l% lE 4 lE*: 7E.8 C IE4 IE.3 Isone surt C ( E* ) C 3E.10 C C Y. we '"l% C 2E*: 8E 8 3E 10 0 C of fYwethium i ki % we '*lw E3 SE+1 E.8 7E ll 20 5 lE4 ).we'*l% C 4E l 2E.8 6E-Il f' C 61 Promewum 147 %.we'"lw 4E 3 IE : SE 8 C C C 1.LI aall Done surf (5E 3) ( E 2) C 3E-10 7E 5 7E4 ).we'"Pm C IE 6E.8 lE In C C 61 IWwthium-148m % we '"lw 7E + 3E IE.7 4E 10 lE 5 lE4 1.we'"l% 3E IE 7 SE 16 C C 61 Promethium 14x % we '"Pm 4L*: SE : E7 8E lo C e LLI wall (SE* ) C C P 7E4 7E-5 ). we'"tw C SE= 17 7E.14 - C C al l't.wncthium-149 w we '"Pm IE*3 OE*) 8E.7 3E 9 C C LLl wall (IE

• 3)

C C C E-5 lE4 Y. we '"lw C 2E*3 8h 7 E.9 C C l'uornutes appear at the endofthew slurs e tahl s D7698

Appendst3 MRCR l'olume !..lupasi I997 Drqtl Asuiual 1.lliuts uti Intake ( ALI) and Derised Air Concentsations (DAC) of Radionuchdes l'or Occupational thposure Elliuent Concentrations C0110Ulitrallolis for Release to Sarutary Seuerage (Conimuch f *6e I tarwe !! TaNe !!! Occupesamni EINent fielcows to Velves thenvetinre sewers col 1 - Col

• Cd 3 C41 col :

Oral klimthh insestam _LrM er3L-_ herase Atams Radumucinic Cim ALI All DAC Air W ater Concentra1mn eu M i u(M i#imh e#,mh

#i mi" (uri enh Na r

el Pnence,e i m u. we "'Pm St.) E*4 8E4 3E-8 7E4 7E4 L ace '"Pm C

• E+4 7E4 OE-8 C

C f.I Precthie l ti %.we"'lw E*) 4E*) IE4

• E 9 E4 E4 1.we "Pm C

JE*) IE4 4E.9 C C 6 5.unanum-14 t m' %L alic.enevre 3E 4 IE 5 4EA IE.7 4E4 4E 3 6 54 manum 841' W ait c<wnnmndt 'E 4 E** 8E 3 E7 C C 5 oall it E.J) C C C BE4 8E 3 h %mainl4:* %. all sivnemne EE.1 3E 4 IE4 4E 8 IL4 IE4 6 K4mmum.144 W.411eepene 6E 3 SE ; lE 7 7E.lu SE.5 8E4 6 Kananum.l e % all c-mpune IE +1 4E.: IE.11 C C C Dsme swf Bone surt (3E+1) (6E 21 C 9E 14 JE 7 3E4 6 54n.u n.m-147 % 4lt c erwne OE + 1 4E.: 2E-Il C C C o B.me surf Bnne surf (3E.1) (7E.:) C IE 13 4E.7 4E4 62 54 manum ISI W. all 6.wp=ne IE+4 IE 2 4E.s C C C ELI wall Bone surf clE+4) ( E*:) C lE 10 2F4 E3 6 54 manum-153 % alleepwe E+3 3E-3 IE4 4E.9 C C LLI wall (:E

• 3)

C C r 3E-5 3E4 62 54manel 5 5' % allcompiune eE +4 E5 9EA 3E.7 C C si nail <nE 43 C C r IE 3 IE.: 6 Sananeli i %. 4ti ciersne

• E 3 9E 3 4F 4 IE-8 34 7E4 61 Eeriurml 45

% all s.epiune E3 lE 3 IE 7 3E 9 lE 5 E4 al Eecum-l an % ailcierwne IE*3 IE-3 SE-7 lE-9 IE-3 IE4 el Eurip e l47 % 411mmpmne 3E*3 OE-3 7E.7 OE.9 4E4 4F 4 63 Lut.peles %,4Is,e p mnds IE-3 4E*: IE 7 SE lu IE.5 IE4 n) Eun p e l49 n. ail mmemne 1E-4 3E-3 IE4 4E 9 lE4 E.1 61 Furi cium lSo W. 46t pepwne 1E 3 EE*3 4E.6 I E.4 4E4 4E4 -(126 hi 61 Eur tmm.l * W. all ueveune NE*: 2E l 8E.9 3E ll IE 5 IE4 14 u 61 Fe ri e li:m W *ileep=r+ IE+1 6E-3 3E 6 >E /2 4E 4 4E4 hl Furipwn I t % 4ti c.ep=nds 8E*: 2E l IE-s 3E Il IE 5 IE4 63 Ew<reatu _ %. ali c,epwne SF E*) iiE.9 IE Il 7E4 7E 3 4 l'ounrune"s esppn sw est alw erulofIlss".w slorn a* t<shis t. D7799 M

NYR(*k thlusne /..luynis /997 /#n/t Appendix 11

• Annual I.nmts on intale ( Al.1) and 1)ern ed Air Concentrations (DAC) of Radionuclides l'or Occupational Expsure Elbent Concentrations Conventrations for Reicaw to Sarutary Sewcage f<mrumnt)

TaNei TaNe11 table !!! Ca;cursuerul Eth.s Releases to \\ alues Cinerarauons sewers CW l CA 2 Cd ) C41 Cd : MuttJv Oral Ingesum Estam.. Amste Aseumc Ramshde th All ALI DAC Aa w'aier Concensrauon No r,ca toco run mn ( 4'i mo (un en tuo mn 63 E e te e l55 %. all sionewJs 4E*3 9E l 4E 8 C

• E.3 5E4 D mesuri C

(IE.:) C

E 10 C

C ed Eer=m-l $e

u. all wnpurwh

(>E :

• E E7 6E.10 8E4 8E !

63 i etium It? %. all sienp eJa E*) ?E*3 'E 4 7E.9 3E.3 JE4 M Eur tmm l4* % allsiepeds OE*4 (E*4 Ed 8E 3 JE 4 3E 3 e4 G4 mnium -149' O 411 sepumJa aucp thine gn en 1 v % SE +4 7F 6E 3 E.7 C C 5t mall (SE.4) C C C 6E4 6E-3 % nudes. hsJrowles. and i6nies C IE-3 7E

• OE-7 C

C M dswum le Il we'#iid IE ) IE-;

• E.8 OE.10 2L 4 OE4

% wc "ht C 3E*' IE.7 JE.lo C C w dausmum-147 D we "ind

E*)

4E 3 E4 6E.9 JEJ 3E 4 %. we "%f C 4L+3 IE4 SE 9 C C e4 d@hme l44 D, we %1d IE*] 8E-3 3E 12 C C C ikme surf Bee surf ( E*l) (:E ;) C lE 14 3E.7 3E4 n we "'0J C 3E

• IE 16 C

C C Bee surf C (tE ) C 8E.14 C C ta Odumium-144 D we "'0J 3E 3 E3 9E.7 3E 9 4h.5 4E4 % we"'ad C E-3 IE4 3E4 C C e4 dennmm lil D we"'0J 6E.) 4E 2 E7 C 9Ed CE4 S w set C i(E ') C 9E 10 C C a we "'GJ C IE 3

• E 7 OE-9 C

C M Gemmum 15: D we "*dd

E*l IE

4E 12 C C C Dee surf Bee serf (IE+t) (E) C 3E.14 4E 7 4E4 %. we "'GJ P 4E.:

E lI C

C C Pee surf C OE ) C IE 11 C C e4 Guemurn-143 D. we "%f

• E l IE 6E 8 C

6E 9 6E4 rkte surf C 3E lu C C C ( E-3 % we "'ad C (E 2 2;. 7 RE In C C

1. 4 041,enum,144 D. we "'GJ 3E*3 EE*1 3E4 IE A 4Ed 4E4

% we"'dd t' 6E*) lE 4

1. E 9 C

C 93 3E*4 IEJ 'J 4 IT.a IE 3 6 n9 f etNe t H* % all ovnpiurgs n' ferdel4 e u. all u enpunts

• E*3 7E *:

3E.7 IE 9 7E 5 yra M Tert =um 190 % 411mnewJs 9E*) lE*4 9E4 3E 8 7E 5 7E4 69 Terh e lil W. all rep =nds 4E+) 9E*) 4E4 I E-s (Ed 'E4 M f erhum-141 %,4ti cnmpunkt SE*) 7E*) 3E4 IE 8 7E.5 7E4 l hmtmacs appear at sin' end of the.se three table.s D7898

~ __ _ _ _ i 4 Analar il SVRCR l'olume i..tugust 1997Dn*ft a Annual l inuls on intale ( Al l) and Ikroed Air Comemrations (DAC) of Radionuclides for (kcupational Esposure Emuent Concentrations Comentrauons for Releau: to Sanitary Se%erage (Comlinued) taNe1 Table !! TeNe !!! I Occupational Etnuem Releanes to I \\ alues nmcentrauons Sewers ~ Col I Col 2 Col 3 Col i Col Oral Momhbr ingestate J@glang Avernov - AMmic Raleminue shu Att ALI DAC Aar Water Cuiscredraison M t uri) t ur.) fuci mn f uci mn ipri mn f pci mn at Terbeelta %, all umpmnds E*) 4E*) E4 6E 9 2E 5 2E4 69 Terbiel

• 9

%1allu m pmtWs 6E*) 8E*3 3E4 IE 8 8E 3 IE4 69 Terbium l'6m %. all compume OE *4 3E*4 IE

• 4E 8 OE 4

E 3 (9 0 h p (9

Tertnum-l **a u.alismemna 7E

• 3 8E*3 3E4 IE 8 IE4 IF 3 (24 4 hs 64 Terbium l46

%. all simpwna IEa3 IE*3 6E 7 OE 8 IE 5 IE4 63 TerNel 57 %, ati cep mna

• E
• 4 3E*:

IE 7 C C C l_LI us11 Inme surf (5E*4) (6E* ) C BEdi) 7E4 7E 3 e4 T erNam-l ui % ail somemne IE.) 2E*l 8E 9 3E Il E3 2E 4 65 f etNe lfo % all sompmeski 8E*: E*: 9E-8 3E l.' IE-9 IE4 s 69 t erbee l61 %. all snmpwnds 2E+3 2E*) 7E 7 E9 C C LLi mall ( E+31 C C C 3E 3 3E4 em tx sremum-l u %, 441 cmemas 9E+3 3E+4 IIN9 4E.8 IE4 IE 3 fe [Merimum-It? %, ali curnpuna OE*4 6E*4 3E S 9E-8 3E4 3E 3 te (Menmum150 % all uwnpiunda IE*4 E3 lE4 3E 9 2E4 2E-3 ee IMreme lt W as' compmne IE*4 SE-4 lE 3 6E 8 E4 E3 m (Metnsie lm W 4!' compmnon bE*2 7E

• 3E 7 IE-9 C

C L Ll w all OL 2) C C C IL t IE4 n7 Iloimium-l"* %. ail oepune 4E*4 2E*3 6E 9 2E-7 (E4 6E 3 67 linimium-l 5 ? %, all compends 3E*3 IE*6 6E4 E4 4E 3 4E-f67 litumium-8 4 4* W alicegw% Eat IE*6 4E4 IE4 3E.1 3E-2 f.7 linimeum 161 %. sl uepene IE+3 4E*5 E4 6E 7 IE 3 IE 2 67 lloimium la.2m' W - ili c.nemnds $E*4 3E 3 IE4 JE 7 7E4 7E 3 67 Iloimiel6 " %, all cmp = mis SE.9 E6 IE 3 3E4 C C 5 wall IXE*5) C C C I E-2 IE 1 67 linimie le*4m' W1411 ciepmns IE** 3E 3 IE4 4E 7 IE 3 IE-67 lintrmum-BM* WL alicepmne OE % 6E S 3E4 9E 7 C C 5t weil ( L*S) C C P 3E 3 3E : 67 llalmium. leem % ellsnmpmne 60*2 7E *4 3E 9 9E l: 9E4 - 9E 5 67 ikiimsum tre % a'Isnmpuli 9E*: E*3 7E.) 2E 9 C C LLI wall 19E* ) C C C IE 3 IE4 Femmutes appear at alw ruJ nfIlww altree rahks D7999

) .WK'R l'olunse I.. Ingunt I997 thaft App:ndis 0

• Aluusal I.umte on lutake ( Al.1) and Iktned Air Coisentrations tDAC) of Radionuclides for Occupational Eyesure Elliuesit Conwentrations Colkelttratluns for Release to Sanitary Scwcrtige (Cortimped)

Table I T aNe il TaNe ill 1%cupehiral El luent Releasas to Valuse Curicentrahans $engrg Cd i Col : CW 3 C4 i Cd (wal klantNv levnhim _1r.halWit.,- Aserage Al vnes Kalma ine Clasa All ALI DAC Aw M eter Cwteaban N r #.) (pr.)

1. 1. imh (pr's mh

(#imh (#imh of il4mee lei 7 n slicepiurus OL*4 e,E *4

• E. 5 SE.a E4
• E 3

1. 4 i skum lel

% all sicipwids OE*4 6E*4 3E 3 9E 8 OE4 Of 4 44 l itwrn le t % all saenpwede 6L*4 E*! IE 9 3E 1 9E4 9E-3 (4 f rNm it*8 n alls.vnpwWs 1E * ) 3E+3 IE4 4E 9 C C LLI mall (4E*11 C C $E 3 SE 4

1. J I rNm itt u allevnewnJs AE+3 IE 4 JE4 IE 8

• E 3 SE 4 tJ 1.rNm.17 n ailovnp wWi IE*3 lt-3 eE 7 2E 9 C

C LLI mall (IE

• 3)

C C

E 5 2E4 en Thhele '

W sin onimnda 70 4 3E 3 IE4 4E 7 C C Si mall (7L*4) C C 1E.3 IE ' 69 1hhe n ev, w all snmpus h aE*) IE*4 6E4 lE d 60 5 6E 4 t'9 Thhum t67 % alic.vne w es L*3

f -3 IE 7 3E 9 C

C 1 Li m ell (;E + 3) C C 3E 3 3f 4 td thhm. b u allsivnewes llE * : E*: 9E 8 3E 10 0 C 1 L1 m all C C ltA lE4 il E

• 3) 64 Thhel 71 W. all wenpwnsk lE+4 3E+:

IE 7 C C C t.Ll mall ihme surf (ik 4, (6E 2) C 8E In E4 E3 tim T Nh e l7: W. 411 ciep uds 7L

• 2 If *1 sh-7 lE 9 C

C 1.1 l mall (llL 21 C C IE 5 IE4 69 thuhum-171 %. all siepwrds 4E*3 IE 4 sE4 lE.8 6E S 6E4 09 1Nhe l 7s' u alicompuus 7E*4 OE 1 It'4 4E.7 C C Si wall PlD 41 C C IE 3 IE

• m

) t.<*um- ; <,2* w..11cepv % wn thiw pen i.e i 71 J 3E'5 IE4 4E.7 IE 3 IE.: ).audo hsdrmien v411ev A s C 3E

• IE4 4E 7 C

C M i nteme lm n' we T h IE*) lE*3 IE 7 3E 9

E-5 lE4 4.we)h C

E*3 AE.7 JE 9 C

C h ilmNm 9 7* % we'**\\h )E.5 BE 3 3E 4 IE4 4E 3 4E.: i. w ) b C 7E 1 3E4 IE4 C C N i tic %m low W weth E*) BE* 4E 7 IE 9 E1 E4 1.we'*')h C 7E

• 2 3E 7 IE 9 C

C Fomem>us appear at the emiof thew three tables D80%

Appendis il MRC l'olume I. Augint I997 Draft Annual l+1mits on intale ( Al.1) ais! Demed Air Concentrations (DAC) of Radionuclides for Occupational ISposure L111uent Concentrations Cot 14elltrallotts for Releaw to Sanitary S$nerage fonturued) 7able l Tahne !! Tahie l' neurational Erlivens Relene.m Values C,wsentreamna Stevis J Col I Col : Col 3 Cal I C,it iltal Akmthiv truesteem _Inbalen A.wge j Asamic Rajesushde Cima ALI AL1 DAC As Waret Concenunuon iu i mh (pt's mh (pri mh (uci nih r No e re) tufii u hi ) tterNe l ?* n, sce *) b )E*) 4E*3 IE4

• E 9 C

C LLl uell OE*3) C C C 4EJ 4L4 L we *) b c 3E*] IEe ?E-9 C C fu )itectuum 177* n n '*4b '.E + 4 5E+4 !!J 48 IE 4 OE-3 Lwe*)h C SE*4 !EJ 6E 8 C C hi iltertne l ?#* W we *) b IE+4 4E+4 OEJ 6E 8 ZE4 OE-3 L we *) b c 4F+4 lE J SE 8 C C 7) I utetium 16u

n. all camp wn) even thew gnen t e )

3E * ) 4E +.1 !E4 6E 4 3E J 3E4 ). audes hhdes 4nd tluimJes C 4E+3 !E 4 6E 9 C C 71 l.u:eiie l hi n we'*lu IE+3 Of +3 GE 7 Jf 9 OE4 OE4 ) we'"Lu e OE*3 lE 7 3E 9 C C 71 luteuel ?l n. sce '*L u lE*3

E*3 IE 7 3E-9 JE4 JE4

).we'*Lu C OE*3 IE 7 3E 9 C C 71 Luteisel f: n. wv *1 u Ib3 IE+3 E7 lE 9 (Ed IE4 L we'*Lu P IE*3 SE.7 lE 9 C C 71 Luicuel?1 W, we '*i.u 4E+3 3E+2 IE 7 C 7Ed 7E4 lbme surt C OP:) C 6E 10 C C L we'*Lu e 3E*2 lE 7 4E 10 C C Luteuum 174m u.we *Lu Oba) OE*: IE 7 C C C LLI mail Done surf t3E*3) OE*:) C Ela 4E J 4E4 L we'"Lu C OL* 9E 4 3E 10 C C 71 Lutenum 6 74 % we *Lu

• E*3 IE*:

Es C E5 7E4 De surf e OE +:) C 3E 10 C C ).w *Lu r !E *: 6E 8 lE in C C 71 l.uicuum-i ften n we'*Lu RE*3 3E +4 led 3E+8 IE4 (E-3 L we '*Lu t' lE+4 vE4 3E R C C 71 L utene l ?t> n wc *1 u 7E*2 SE*u lE 0 C IE-5 IE4 Dane surf r flE +1) C lE Il C C L we'*Lu e SE+o 3E 9 IE Il C C 71 luisu e lf7m W we '*l u 7E *: lE* 'E 4 C IL 5 lE4 De surf tlE+;) f' lE la C C ) m '*Lu e RE+l 3E 2 IE lo C C 71 i victium-177 W we '*l u lE*l 2E+) 9E 7 3E 9 C C l L1 w all OE*3) C C C 4E S 4E4 ), we '*Lu O OE*3 SE-7 3E 9 C C 71 1.wecuum 174m' W.see'*Lu

• E *4 OE*?

SE 3 E7 C C 5: wall (6E*4) C C t' RE4 BE 3 L we '*l.u C OEd ES

E 7 C

C Footnotes appear at alw end of these three tables D8199

.WK'R l'olunw I *,lugu st I99? Drtijl Appendis B

• Alunwl I.imits on Intake ( Al,1) und th:rnal Air Concentrat3ons (DAC) of Radionuchdes for Occupational Especure Elliuent Concentrat3ons Concentrations for Release to Samtary Seurage fontmurd)

Table i Tat le 11 Table l!! Occupatweial f.tituent Releases to \\ alues Cormanusiums 5evers C4 i Col : Cal 3 C41 Col : Akmthh 02 1 ifvestian _,10htjets... Awf'est Awrus Radumuclaihr Cim All ALI DAC Air Water Concenstman (u i) I_uCs mh (uri mh Ipri mh i uCi mn c r Iw i) No 71 Luteuurn 17f W. sce '"t v JE*4 IE+5 5E 3 E.7 C C St w-Il 14t*4) C C C 6E4 6E.) L see '"1.u O IE*$ SE 5 OE 7 C C 71 Luwtium-lM W we E s 6E*3

E+4 SE4 3E.8 9E 3 8E4 L we '"Lu C

IE*4 6E4 30 4 C C 7: It4imum I h' D all cmpeh euert thuw gnen liv W 3L*3 6E*3 E4 IE-9 4E.! 4E4 % mias Inanmdes sabia.s end netrates C SE*3

E4 6E.9 C

C 7; ll4rruum-17; O wv *10 IE*) 9E*n 4E.9 C 20 5 OE4 thme surt C ( E*I) C 3E.1l C C % we 'hu C 4E*l E-8 C C C Bonc surt C (6E a l) C 8E Il C C 7: Il4tmum 171 O we'30 SE*3 IE*4 SE4 !E 8 7E.5 7E4 %. we *llt C IE*4 SE4 OE s C C 7: llatmum-n fo D we 'hif 3E*3 9E*: 4E.7 C 4E.5 4E4 Dee surf C (IE

• 3)

C IE.9 C C n. we *lls C IE *3 SE.7 OE.9 C C 7 llate..wn-17 7c ' O.we'3tf

E*4 6E*4

Ed

• E s 3E4 JE.3

%, we '3 tf C 9E*4 4E.5 IE 7 C C 7: il4tmum 17mm Il we "llf 3E*: IE*0 SE lo C 3E4 3E 3 Bone surf C (:E *0) C 3E.1 C C W. we '3 0 C SE*n E-9 C C C See surf C (9E *0) C IE.i t C C 7: Italmum INm () we '3tf IE*3 3E*: IE.7 C IEd IE4 Bone mef C (6E

• 2)

C RE.10 C C W we 'llf C 6E*: 3E.7 AE In C C 7: liasmal#m f) we llf 7E

• 3 lE*4 9E4 3E 4 fE4 IE.3 w. we '3 0 C

3E*4 IEJ JE.4 C C 7 il4imum-181 D we'34f IE*3 lE* 7E.8 C 20 5 !E4 Bee maf C f 42 *:) C 6E.10 C C A we'lif C 4E*

E 7 6E 10 C

C 70 lisimum-18 m* D we'3lf 4t*4 9E*4 4EJ IE 7 SF4 !E 3 W. we *lli C IE*5 6EJ OE.7 C C 7 lleimum-18 D.we'llf OL*: 8E.1 3E.10 C C C Dme surf Demeswf (4E

• 2)

(CE *u) C lE 12 SE4 SE.5 W. we 'Dif C 3E*0 IE.9 C C C Ihme maf C (7E*0) C IE Il C C lintointste.1 uppear tal the end tof thew threr tables D8298

n Arixndis il SRCR l'olume i. Aupal 1997 Drall Annual 1.imits on IntaLe ( Al.1) and lkro ed Air Concentrations (DAC) of R. ilonuclides for Occupauunal tiposure Elliuent Concentrations Concentrations for Release to Sarutan Sencrage Contmurd) TaNeI f able !! Table !!! Occupauenal Ethent Retemes to i Valws Corr.entratums Sewers Cai l Col : Col 3 Col 1 Col Oral Monthly Irigestken ._ldMG Aserage Ahwms keemlede Clan ALI A1.1 DAC Av W ater Concenestan f u 'n (ued (J'e mh f uci mh (ucumi' r uct ml) No r 7: Itainium-I s f D we'9(f OE.4 SE*4 OE4 6E 2 3E4 JE 3 u we'ht C 6E*4 2E4 BE4 C C 7 Itainmm-154 D. we "1lf lE+3 8E*3 JE4 IE.8 3E4 )E4 %. see "'ilf C 60+3 3E 4 9E-9 C C 73 Tanialwmi f.* %. ali cmipunds ewert th,=c gnen t w Y 4E.4 IE** 3E 3 OE 7 SE4 SE 3 ). elemensal T4 nules. h@udes h4Nies cartiides nitrates end niendes C IE'S 4E4 IE 7 C C 71 T antalum-171 %. we "'Ta 7E-) 2E *4 8E4 3E 8 9E4 9E-t L w "'Ta C 2E*4 7E4 OE4 C C 7.1 TanWum 174* W we"'Ta 3E 4 IE 3 4E 4 IE 7 4E4 4E.3 L we "la C 9E*4 4E 4 IE 7 C C 71 Tanulum.174 % we "'f a 6E.1

E.4 70 4 OE4 8E 5 8E4 L we Ta e

IE 4 6E4 OE 8 C C 73 Tamalum-lb %. we "'Ta 4E 3 lE-4 ?E4

E4 SE4

• E4 L we "'is c

IE.4 3E4 lE 8 C C 73 Tantalum I 71 n.we"'Ta IE 4 OE 4 RE4 3E-8 OE4 E.3 Y we"'Ta C E-4 7E4 lE-8 C C 73 Tantalum 175 %. we "' f a OE 4 9E-4 4EJ IE 7 OE 4 E3 ). we "' T a C 7E-4 3E4 IE.7 C C 71 T anuium-l M % we "*f a E.4 SE*3

E4 SE-9 3E4 3E4 L we "' Ta C

9E-4E 7 IE 9 C C 71 Iantalum-I As en %.we"'Ta OL-4 7E-4 3E 5 9E s 3E4 3E 3 L we"3Ta C oE-4 lE4 8E4 C C 73 14ntalum-l an u we "'T a IE 3 4E 2 lE 7 eE In E4 E4 L we "Ta C lE+1 IE4 3E Il C C 73 Tanulum it m' %.we"'To E5 SE*9 lE-4 IE 7 C C si e all (20 9) C C e JE 3 3E-L we "!a e 4E.5 lE.a 6E 7 C C 73 Taniaium. l t: W we "'Ta AE 3E*: IE 7 SE 10 IE4 IE4 L we "'in e IE eE 8 E lo C C 73 Tanuium isi

u. we "'Ta 913 IE 3

9. 7 lE 9 C

C LLI mail flE 3) C C C

E 5 lE4 L we "'Ta e

iE 3 4E.7 IE 9 C C 73 IarWum In4 %,we "Ta 21

• 3
• E*3 OE4
• E 9 3E4 3E4 Y we "Ta e

SE*3 E4 7E.9 C C 11 T anulum-is S* W. we "'Ta 3E*4 7E +4 JE 3 IE.7 AE4 4E 3 Y.we"'Ta C 6E*4 JE-3 9E-8 C C Usulnute.t uppear al Ilw end of(frew Ilaret lames. D8399

.%RCR l*olw i.iluyust 199Yurall;- lAppendit B ' Annual Limits on intake (Al.I) and iknved Air Coiwentrations (DAC) of Radionuclides for Occupational Esposure.. Emuent Concentrations Coiwentratmns for Releam: to Sanitary Seucrage (Consumah s . Table I _ Table 11 - Table !!! ompeinnal EI%ent Relemee to Values Consmaruare Seweri Col 1 Cal : Cid 3 Col i Col Mar.LNy . Oral i Ingsstian _ inhalmian Anrage Ahirms km.lue= slide t' lass ALI Al.1 DAC Aa Waer Cansentration (s vmn-e 8 v i mn (sci mn e (u 's ml) s ci) (uca _r Nn. u 71 T anialum-Ina* W. wv Ta SE*4 3* ) - IE4 JE 7 C-C' si nal! (7E*4) C C C IE 3 IE Y. werate C 2*$ 9E-$ JE 7 C .C 74 ' tweien-176 Il all eer=nds .lE*4 SE *4 2E 9 7E 8 IE4 IE 3 74 Twpaen t?? D, all enmpends E *4 9E*4 4E,5 IE 7 3E4 3E 3 74 Tureten-178 D. all ownsumis $E*3 OE*4 8E4 3E-8 7E 3 3, 74 Turpien l?# D. ali cep=rmin SE*$ 3 +6 7E4 34 7E 3 7E- . 74 Tuncien lli D. all emnp=ndi 21 4 3E*4 IE 5 ?E-8 34

E 1 14 Turpten 189 D. all cenpunde 2E*3 7E'l 3E4 9E 9 C

C LLl well 13E+3) C C i 4E 3 4E4 74 Turpien lp ? Ll all compends E*3 9E*3 4F-4 IE s 3E 5 31 4 74 Tunpicn-isa ll all comp =nda 4E+: IE*3 3E 7 OE 9 C C LLI wall (9E*:) C C C 7E4 7E 3 7i Rhemum t7f Il all comp =re sweps umin gnen for W 9E*4 JE*S IE4 4E 7 C C Si eall (IE 3) C C C 33

E:

%, ouh hsdrain and mirates C 4E+5 IE4

• E4 C

C 79 Rhenium 171*

0. see '"Re 7E *4 JE+5 IE4 4E 7 C

C 54 mail (IE*$) C C C IE 3 lE 2 W. we '"Re c 3E*3 IE4 JE 7 C C - 79 Rhemum Int D.we'"Re SE*) 9E 3 JE4 IE 8 7E 5 7E4 W.we'"Re C 9E*3 4E4 IE 4 C C L =79 Rhenmm II: D we'"Re 7E*3 IE*4 SE4

E 8 9E S 9E4 f17M

%. we '"Re C 2 *4 6E4 38 C C 79 - khemum.It: 01 we '"Re IE*3 E*3 IL4 3E 9 - E3 E4 u=e n h, %,we'"ke C

E*3 9E.'t 3E 9 C

C 1 79 khanium-lii4m D.we'"Re OE

• 3 3E*3 IE4 4E 9 3E S 3E4

- %, we '"Re C 4E*2 lE 7 - 6E in C~ C ' 79 Rhemum lW4 tl we'"Re 2E*3 4E*3 IE4 SE 9 3E S 3E4 W, we '"Re C IE*3 6E 7 OE 9 C C 73 Rhransn istwn (1 we'"Re lE*) E*3 7E 7 C C C Si =all 3: wMi s .%. we '"Re C 2E *: ~C 3E 9 2E $ 2E4 (:E* 3) ( E*3) 6E.8

E-lu C

C i 73 Rhsasum 186 D we '"Re E*3 3E*) lE4 4E 9 JE 5 3E4 W, we '"Re C E*) 7E 7 ZE 9 C C ~ Footousses appreur ut Ilw enitufsinne three table.s D8498~ a1 m - t-. ,m,,w+-- er_., ,_.-m._ .,.r.,,.,, w q,. r-r., q ,1 3,.,

htimii\\ \\l SSRCR l'olume i. 4ugrat I997 Draft I 4 Annual 1,imits on intuLe ( Al.!) alul Ikrived Air Colwentrations (DAC) of Radionuclides for Occupational Esposure 8 Elliuent Concentrations Concentrations for Release to Sanitary Sewerage (Contmenti TaNe I Table 11 ' TaNe !!! j Oxupaianal Ef! bent Releaws te I Values Cuentrauans . Sewers. Col I Col : Col 3 Col I Col : Oral Monthlv i trgestum LnlWast._, Awray. Akums Raluenstide Cl as All ALI DAC As Water Can6entrauon Nn _ v uc ) r ue.) survmn tut *e mn (promn tyci mn 74 -kbem e ls?. D. ore'~Re 6E*$ BE*$ JE4 C 8E 3 BE.: 1 Si ms11 l C (9E*$) C IE4 C C W. nee'~Re C IE*$ JE 3 lEJ C C ' 73 R.hemum Isam* D see'~Re aE*4 I E *.* 6E4

• E 7 IE 3 IE W. nce '~ke C

IE*$ 6E4 lE 7 C C 79 khem e l82 D.weke OE*3 3E*) lE4 4E 9 IE $ IE4 W.see'~Re C 3E*3 lE4 4E 9 C C-r 19 khemum Ilv D.we'~Re 3E+3 $E*3 2E4 7E 9 4E $ 4E4 1 % we'~Re C 4E*3

• E 4 6E 9 C

C + i 76 i nrmurn-I s> D. all sompanis cu;cpt tN w gntn hw W and Y IE*$ 4E*$

• E 4

$E-7 IE 3 IE 2 W halalci and muates C $E*$ E4 7E.7 C C Y, omdes and hydrwdes C $ E*.4 E4 eE 7 C C 76 (wrmum-i o' IX we '*t m lE*4 4E*4

E4 6E A 2E4

E.)

W. sce '*(

• C

$E*4 34 6E4 C C Y. ne. '*th C JE*4 'E4 6E4 C C 76 (mtmum-II: ' D. we '*t h IE*3 6E 3 E4 8E-9 3E $ 3E4 u < see '% C 4E*3 20 4 eE 9 C C 4 Y, m '*m C 4E*3 E4 6E 9 C C 76 (wmmm ist D,we'* h OE*3 $E*:

E 7 7E lo 3E-3 3E4 3

w. sce '*r m C 8E*: 3'.1 IE 9 C C L see '*( w C 8E*: 3s 7 IE 9 C C to t amielran D sce '*t m 45a4 2E*$ IE4 )EJ IE4 IE.:

w. we '* M C

OE*$ 9E $ 3EJ C C Y, see '*0s C' E-$' 7E4

E-7 C

C 7e a mmium-19tm D we'*0s IE*4 3E 4 IE $ 4E4 E4-E3 l % we '*t 4 0 2E*4 8E4 3E 8 C C Y. see '*rx C

E 4 7E4

?E4 C C 76 (annum-lH D. we '*t x E+3 E*) 9E4 3E.9 C C LLI mall } OE*3) C C C 3E $ 3E4 w we '*rx C E*) 7EJ 2E 9 C C r Y. we '*t a C IE*) 6E 7 lE 9 C C 76 (mmmm191 D. See '*t m OE*3 SE ) OE4 6E 9 C C. Ill mall (:E*3; C C C E$ E4 %. we '*i k c 3E*3 IE4 4E-9 C C 1 - . Y, we '*t h C JE*) IE4 4E 9 C C 76 f amiel04 Il we'*rx 4! *: 4E*l lE4 6E II - C C 4 LLI mtil (6E*2) C C C 8E4 4E4 w. we '*r m C eE*1

• E 4 RE Il C

C' Y we '*t a C 8E*o 3E.9 IE Il C C 1 Femnsues appear at Ilw emiofslw.se three tables D8599

~.%h'R i dume l..tugust l99? l) raft - ' Appendns B = Almual IJmits on intake (Al.1) and lknval Air Concentrations (DAC) of Radionuclides for occupional E eure t 9 Emuent Concentrations -- Concentrations for Release to Sarutary Sewerage g*artmacd) s-1

TaNei Tawe 11 Tame !!! '

Ossieshanal Esfluern iteleases to Yalues - Omr.arereures Sewers Col I Col 2 - Cal 3 Col 1 = Col Oral - Monthlv - ingssunn [nhe[etwet_ Awage Ahums - Radisewclide Cles ALI ALI DAC Aw . % eter Coruevitramn .Nn (ph) fp6) (90 mn (p6 mh (ph ml) (un'inl) 77 ledwn.la? - C allcornemmbeven - thne gncalae W and Y 4E+4 IE*5 6E 4 lE 7 C C. St wall i (4E+4) C C C 6E4 6E.3 2 W, hahdrs. netrates, and metallic enJeum C lE+$ 6E t E.7 C C Y. mwes enJ hem Jes C IE.1 SE4

E.7

-C C 77 leiJiurn-1 A4 11 we *lt 8E+3 E+4 IE.5 JE-4 IE4 (E 3 l W. we *S C 3E+4 IE4 SE 8 C C Y, see *lr C JE 4 IE 5 4E.s C C 77 leidium.ls4 fl we *h $E+3 IE+4 SE4 OE A 7E.5 7E4 W. we '"It C IE 4 SE4 E8 C C Y, we *lr C IE+4 4E4 lE 8 C -C 77 Ireelso D. see *Ir E+3 8E*3 3E4 IE 8 JE4 JE4 W. we *lt C 6E+) JE4 9E 9 C C Y, we '* Ir C 6E+3 E4 8E.9 C C 77 Indi e l87 D. W *lt IE*4 3E*4 IE4 $E.8 IE4 IE.) W see Ir C JE*4 IE.5 4E 8 C C Y,we *ir C 3E+4 lE 3 4E 8 C C 77 trw%wl AA D we'"It E*3 SE+3 2E4 6E 9 3E 5 3E4 W. nee *le C 4E+3 IE4 SE.9 C C Y.we'N!r C 3E+3 IE4 SE 9 C C 77 IreelN D. we *1r SE*3 $E*3

E4 7E 9 C

C LLl eall (5E+3) C C C 'E ? 7E4 %. see *lt C 4E+3 E4 SE 9 C C Y we *ir C 4E+3 IE4 SE 9 C C 77 treelvum' il we *lr OE*S 2E*) sE4 JE 7 OE.3 E. %. we *lr C IE+5 9E 3 3E4 C - C Y. see *lt c E*5 IE.5 3E 7 C C 77 traum-tm D. we '"tr IE*) 9E*: 4E 7 IE.9 IE.5 IE4 W. we *lr C IE*) 4E.7 IE 9 C C Y. we *lt C 9E 4E 7 IE.9 C C 77 - Iridie 190m 11 we *lt 3E*3 9E*1 4E 4 IE 10 4E4 4E4 %. we *lr C E.: 9E s 3E.In C C Y, we *lt C lE*1 6E 9 OE Il C C 77 Ireum.192 - Il we *lt 9E*2 3E*: IE4 4E lu IE 3 IE4 % we *lt C 4E*: 2E.7 6E lo C C Y.we *lt C OE*: 9E 4 JI! 10 C C 77 - ledum-l'Mm - D. we *le 6E*2 9E*l 4E-8 ' 10 10 9E4 9E $ W. wv *!r C E*2 7E-8 2E.lo C C Y. une *lt C-IE*:- 4E 4 IE 10 C C 7 7 -- treurn.t.44 11 we *tr IE*3-3E*3 lE4 4E.9 IE 1 lE4 ' W. we *lt - t' lE.1 05 7 3E 9 C C Y. we *Ir C 2E*3 8E.7 3E-9 C C ff-IrewnIv9m 11 we *le ~ sE )' 2E*4 IE4 10A IE4 IE.1 W, we *lt C 3E*4 IE.1 4E 4 C C i Y we*1r C -2E*4 9E4 1E.8 C C Favmows appear at alw end ofthese three tames L j.- D8698 L L u. ........ =

_m._,___._ f h yendi\\ll SSRCR l'olumel..lugust 1997 Drap l 4 Annual 1.imits on intale (Al.1) and Ikrised Air Concentrations (DAC)of Radionuclides for Occupational Exposure - E0luent Concentrations - Concentrations for Release to Sarutary Sewerage (Cimimuni) j-- TaNe 1 Table !! Table 111 oscentumal Emuen Releases to - \\ alues - Consentrem Sewe t Col I Col 2 Col 3 Col I Col : Oral MontMy. l Clas ALI . A;.1 DAC Aa W ater . Consentration Ingestum Inhalatum. Aserage Atomst - Rmlamuslede 3 -M rum f u mn r#.mn (#.mh (#imn-e tu ) e 4

• (

77 traum 19% ti m '*lt IE*4 4E+4

E4 6E4 24 33

%. m '*lt C ?E+4 OE4 7E 3 C C i L m Ir C 4E*4 24 6E.8 C C 78 11mmum.l A6 fl all ownpunJi IE *4 4E 4 E4-SE 8 24 33 e . 7s 1 % nunt.18A D. all ownennis OE*3 E*3 7E 7

E.9 24

=24 i 7s 114 mum-189 - D.all ownpunds IE*4 3E*4 IE4 4E4 IE4 IE 3 7s Plaimum 196 D allovnpunds - 4E 3

• E-)

JE4 IE 8 SE4 SE4 'fa - Ptsmum-luim D elle er und, 3E+3 6E-3 3E4 IE4 C C 5 LLl wall (3E 4) C C C JE4 4E4 78 Plaimum 191 D tilovnewnds JE*4 lE 4 IE $ 3E4 C C LLlwil } (5E+4) C C C 6L4 6E 3 71t I w nuntluim D a.ionewnds E*3 4E-3 E.e 6E 9 C C LLI well ( E+36 C C C 3E.$ 3E 8 f 78 Plaimum 197m'. D silovnpunda E*4 4E 4

• E4 6E 8 34 E3 l.

78 Plaimune197 0 alicepwna 3E*3 IE 4 4E 4 IE-8 4E4 4E4 4 7s Ptsmum I d Dallowsmna SE +4 IE*5 6E4 E-7 7E4 7E4 l 74 6% mum-Oisi D allowpunds IE*3 3E 3 IEe S E.9 lE.4

E4 N

GilJ 193 - D. 4:1 ownwnA euert um gnen IW W and Y 9E 3 3E*4 IE4 4E4 IE4 IE 3 %. haiedn and nitraici C lE 4 9E4 3E4 C C L mido and hsdomides C E4 8E4 3E.8 C C N G4J 444 D. m '*Au 3E*3 AE 3 3E4 IE.s 4E4 4E4 %. we '"Au C SE-3 E4 8E 9 C C + L we "Au C- $E*3 34 7E.9 C C -N~ GilJ.19% D see "Au SE*3 IE*4 SE4 E.A 7E4 7E4 l %. m '*Au C IE 3 6E 7

E.9 C

C L w '"Au C 4E.: 26 7 6E.10 C C d M' Gelusm D. m *Au IE.1 3E*3 IE> 4E 9 IE-3 IE4 % we '"Au (' IE*3 SE.7 lE.9 C C t m *Au (* IE 3 SE 7 lE 9 C C N G*l-ba D. we * \\u IE 3 4E*) lE 4 9EA

E4 E4 W. we "Au t'

lE 3 EE.7 3E.9 C .C L we '"Au - C OE 3 7E 7 E.9 C C i 79 G# tw 0 m *Au 3E+3 tee *3 - 4E4 4 E.8 C C Lt.1 well (3E + 3) C C f' 4E4 4E4 %. we *Au t' 4E*3 lE4 6E-9 C C 4 L we "Au C' 4E*3 34 SE 9 C -C 4 79 G4J-J'sen D m '"Au IE*3 4E.1 IE4 SE 9 OE-) E4 % we '"Au t' 3E*3 IE4 4E.9 C-C E m *Au C 2E*4 IE4 3E.9 C C 4 Femumen aptw as th? eminfdww dm tabla D8799

- MRCR l'o/ucw /.. luge,st 1997 Draft Appendit B

• Annual I.innta on intale ( Al.1) and Derived Air Concentrauons (DAC) of Radionuclides for occupational Exposure Et11uent Concentrations

. Colwentrations for Release to sanitary Sewerage Consurunt) TaNe1 TaNe 11 ' Table !!! Occursiamal - Efiluent Releases to i % alues Cimeenirsiuma . Sewers Cd I Cd : Cd 3 Cd t Cd Monthiv tial - trigestaan . Inhalumn Average Akwms kaJumuchJe Clau - ALI All DAC Aar Weier Cancentratum f u i mi) (pCvmh c Na (pce) (ptM - (pcimi) (pci mi) I 1 79 04:a # D we "Au 3E*4 6E*4 JE.5 9E4 4E4 4E 3 W. we '"Au C IE*4 3E4 IE.7 C C Y4we'*Au C 7E+4 3E4 IE 7 C C 19 Onid bil' D ece'"Au TE+4 2*$ 9E4 JE 7 C C Si nall (9E*4) C C C IE 3 IE.: %. we '" Au C

E*$-

IE4 - 3E 7 C C Y. see '"Au C M*5 9E4 3E 7 C C l sa Mertun-101m Vepv C IE*) 4E4 IE-I C C (=pme D 4E*3 IE*4 SE4 2E4 6E.3 6E4 D. sullaics. 3E*3 9E*) 4E4 IE 8 4E4 4E4 % ou.ks hsdrmh hainks niernet and sultues C IE*) 3E4 IE4 C C so Al<rcun.lvt Vape C 3E.4 IE4 4E4 C C Orpnic D E4 6E*4 3E4 9E 8 3E4 3E 3 D we"*"Its

• E *4 4E*4 OE4 6E4 E4 E-3 n. we lig 4E*4 IE4 6E 8 C

C 2n Niercun-lu4 \\ arme r 3E+1 IE4 JEdi C C-Orpnw D E+1 3E*l IE.a E41 E.7 lE4 D.welig 8E*: 4E*l

E4 6E.I t IE4 lE4 u. we ""Ils C

IE*: SE4 2E.10 C C Rn Niercun495m Vapy C 4E*) lE4 6E.9 C C t apnw n 3E*3 6E*3 3E4 8E.9 4E4 4E4 D. we "*lls OE*3 SE*3

E4 7E 9 3E-3 3E4 W we "*lig C

4E*) E4 SE 9 C C no Niercun.199 Vane C 3E+4 IE4 JE4 C C f nganic D E*4 SE*4

E4 6E4

• E 4 E.3 D. we **lig IE*4 4E*4 IE4 SE4

E4

E 3 W, we "*lig C

3E*4 IE4 SE-8 C C so Almun W7m Vape C SE*3 E4 7E 9 C C orgina D 4E*3 9E+3 4E4 IE4 SE4 SE4 D we"'Hg 3E*3 7E*3 3E4 IE4 4E4 4E4 %, we "*lls C $E+3 lE4 7E.9 C C Bn- ~. Niersun497 Vapv C 8E*3 ~4E4 IE4 C C orpnw D 7E*3 IE*4 6E4 lE4 9E4 9E4 i) we "*lls 6E*3 IE*4 SE4 IE4 8E4 -EE4 % we "*lls c 9E*3 4E4 IE s C C an Niertun l'M hew P 8E*4 3E4 IE 7 C C orpnw D 6E*4 lE 5 7Ed OE.7 C C 5L mall flE 8 C~ C e, ' IE4 IE

D. we "*lls 6E 4 IE*5

- 6E.5

E.7 8E4 RE-3

%'. we "*llg c ~:E*$ 7E4 lE.7 C C an. Nimun.3it 4cv C RE*2 4E 7 IE 9 C C 7E4-organse D

• E*:

IE*: 3E.7 IE 9 M4 ~ 3E4 D we""Hg E*3

IE*3

. 3E 7 lE 9 JE4 W. we Hg C IE*3 ' SE.7

E.9 C

C l' numtes aptwar at the crut of the w shree tables. a D8898

_ _ _.-._ _ _.. _..-.. _, _.. _ _ _ ~._. _..._. _. I-Agyondts II - SSRCR l'olume l' August 1997 Drap - Annual Limit.8 on intale ( Al.h and ikmed Air Concentrations (DAC) of Radionuclides for Occupational Exposure EEent Concentrations Concentrations for Release to Sanitan Scuerage (Contmwil I TaNeI 'TaNeli Table 11I i (kcuretmeal. E& ens ~ Releases in Values Cwmenuabans . Semers l rd I cal : col 3 - Col I col : Orel blanthly tr6ett** _hhl 4WML - Average l Aaew R e e si.de Class ALI ALI-DAC Aw-Water Concenushan Nn iptM fpfM ip(** mn (pri mh (p(*a mn (p("vmn si WilselNm" D.allcompwe ' 40 4 E*3 60 5 E*7 C C St # all (7E *4) C C C lE.3 IE r 81 Wlhum-l** D. sli capunds 3E*3 6E $ E4 8E 7 C C St mall (3E.$) C C C 4E 3 4E : Il Nilmm Iv$* D. 411 sepuids 6E 4 IE*3 SE-5 E7 9E4 9E 3 l 1 - 41 Nilan Iv7 D. ali senwsa 7E*4 IE*S SE 5 E4 IE 3 IE 81 Niliumtum' D 411sepwne 3E-4 SE 4 OE 3 8E-8 4E4 4E 3 4 I $1 WiliumdvM D alicepwuls lE 4 3E*4 IE 3 SE-8 3E4 3E-3 4 si Nltun-19'8 D. all sepends eE 4 SE 4 4E 3 IE ? 9E4 903-81 Wilium >s' D slisermnds nE*3 IE*4 SE4 2E.8 l t. 4 IE 3 81 Thailan >H ' alicepine 2E 4 lE*4 9E4 3E.8 E4 OE 3 81 Thrahuman: 11 a sepwnda 4E 3 $E+3 E4 7E 9 SE S 5E4 Il Nilem 34 0 alicampmne

E 3 E*3 9E4 3E 9

. 'E 5 OE4 f a: Led t94m' O. ail cenamde 6E-4 OE * $ 8E 3 3E 7 8E4 IE 3 f 8: Ledia D, ali sepwnds 3E 4 6E 4 JE $ 9E4 4E4 4E 3 8 Leadl

• D. all sep=ne OE*4 7E 4 IE 5 IEJ 3E4 3E 3 4

8 Led > si ll all eenownda 3E*) 6E 3 3E4 9E-9 JE 5 4E4 8: Ledbil D. mis e rmne 7E 3 OE 4 sE4 35.-8 IE4 IE4 -2 l ed:n m ll eil snmpune 9E-) 3E*4 IE $ 4E 8 IE4 IE 3 ,j a: 1.ed:n: D. ali cen=nds 'E 2 SE *1 E8 7E ll E4 2E.3 8: I v4:nt a 411 sepwnds SE*3 9E*3 4E4 IE4 7E 3 7E4 42 - Ledans 11 :41 sep=nds 4E 3 IE 3 6E 7 E9 SE 3 $E4 4; l s.id.!A. D slicepue OL 4 6E 4 E3 8E 8 3E4 3E 3 i 2

1. sad in

- D alicnmpends t>E l El IE 14 8 C C Bee surf Bone wrf (IE*o) (4E 1) C 6E 13 IE 4 lEJ i 52 Led:ll' - Il Wi sepwne .lE*4 6E*: 3E4 9E lo OE4 E3 42 - i.ed:l: - Il ati cep= nan sE+1 3E*l IE-8

• E-Il C

C 13nne surf (IE* ) C 'C P E4

• E 5

) 8 -- Lad:14* D, all anmpwne 9E*3 8E*: 3E4 IE 9 - lEJ IE 3 83 themutA3sP - Il muws 1E 4 sE *4 4E4 -lE 7 4E4 4E 3 %. 4ll ether cornewnJs (' IE*5 4E4 IEJ - C C l baumnes a war at the emsaufthese three tables D8999 r. ,,.evr wm..

~ _.. -...... -.. ~. - - - -.. - .WRCR l'o/ume /.. lugs,si 1997 Dra/l - Appendix 0 Annual 1.imits on intale ( Al.1) and iknved Air Concentrations (DAC) of Radionuclides for Occupational Evosure Emui:nt Concentrations Concentrations for Release to Sanitary Sewerage (Conimunh Tele i Tele !! Table Ill = Onnaretamal Erituent Reles*es to Values Consenarmions Seuers Cal I Col 2 Lol 3 Gil I Col i Oral kkeihly . Inyseason lvibsWitut,.,,. Anrege Alan +c Remusl+Je Clana ALI A1.1 DAC Air Waser Cimeefairwm (fs\\ ifi) Ifimn sfimn tot % mn - tfiM1 84 themuth.:nt' O. we "Di IE*4 JE *4 IE.9 4E.8 2E4 33 W we**Di C JE+4 34- $E.8 C C R1 Ihwnwih.3a? D ace "Th IE*4 4E+4

Ed 6E.8 E4 -

E.3

%. nee *Di C RE*4 3E4 IE.7 C C 8 8) thamuih.00 11 we th

E*)

7E*3 3E4 9E.9 3E4 3E4 W we "th C 6E*3 3E4 9EJ C C B) hi,muth.;ut D we "Th IE*3 3E+3 IE4 309

EJ 34

%, see %s C IE*3 SEJ E.9 C C ~ R1 linmuth-te> D.we "He oE*: IE*3 6EJ OE.9 95 4 9EJ W.we"th C 9E* 4E.7 IE.9 C C

1. 3 Diunuth. u7 D we *th IE 3 3+ 3 7E.7 lE.9 IEd IE4 8

%. we % C 4E*: IE.7 $E.10 C C 8 Bl Dnmuth.:14 =n D N *Th 4E *l $E 0 E.9 C C C 8 Kainess Ldnevs (6E*l) (6E+0) C 9EJ: 8EJ 3E4 W.we *th C 7E.1 3E.10 9E.13 C C s) ihsmuth-In D. nce *lh RE*: E+; IEJ C IE4 IE4 8 C Kalnew C (4E*:) C SE.10 C C W. we "De C JE I lE.8 4E.11 C C 8 53 Dismuth. l? D we "Di $E+3 E: lEJ 3E40 7E4 7E4 %.we#*Di C JE*: IEJ 4E.10 C C 23 thunuth.28 3* D.we**Di 7E+3 3E*: IEJ 4E40 lE4 IE.3 %. we *1h C 4E*: IEJ SE.lu C C 8 si lhunu 4:14' D. we "lu E4 IE 2 3E4 IE.9 C C 34 mall (:E.4) C C C 3E4 3Ed %.we**Di C 9E.: 4EJ IE.9 C C 84 Pnhwum.)d' O. allcomemb even ihme gnen lie W 3E *4 6E 4 3EJ 9E.8 3E4 JE.3 %. mnies hvdrmides and mirees - C >E 4 4E4 IEJ C C 24 B4 mum-36' D we *% E*4 4E 4 2E.5 SE.s 3E4 3E 3 W. we "Pn C 7E 4 3E4 - IEJ C C 8

1. 4 h4wum. n1 D. we *% -

nE*3 1E+4 IE4 3E 4 IE4 lE.3 i S ~ u.we "Pa C 3E+4 IE4 4E.8 C C 8 s 4E 8 4EJ 44 Palmuum.:In - D we" % JE*n 6E t JE.10 9E. '. 3 ~C C %,w"% C-6E4 3E lo 9E.13 ' AS A a ine.. P tl halides. eE*3 3E 3 IE4 4E.9 8E4 IE4 N -W C lE 3 9EJ 3E.9 C C 59 Anine Oli D. hahdes IE* SE*l JE.8 IE.lo

E4 2E4 C

$E*l

E.4 aE ll C

C R6 Rash:31 %ith d4ughters tenuwed C 3 +4 7E4 OE.8 .C C % dh W gvesent C 31 96 9 JE.i t C C i (or 12 (or 10 ftwormres appear su alw enJaf these three table.t D9098 - ~,

9 ^\\y:ndh11 .GRCR l'olume i..lugsat i997 Drap Annual 1.inuts on intale ( Al.1) and lkrised Air Concentrations (DAC) of Radionuclides for Occupational Esposure Elliuent Concentrations Colicelltrations for Release to SanitAn SC%cragc (('oHilNWd) t T4Ne1 TaNell Table (Il Nupas.unal EfNent 8.elemes to Values Cancenumions $cutti Cd I Cd : Cd 3 Cd 1 Cd : Oral Alonthh Ingestum _10falattm Astrage Akemc Radi muctme Claas AEl ALI DAC Ar % ser Concentration (u amh c No tur:1 e uri) i udi mh Iuvi mh d uci mh %1ht) W1) s6 RaJim. :: n iih J4ughters temm ed C 10 4 4E4 IE 8 C C with daugNeri reewn C IE.: 3E-8 IE 10 C C (or 4 (ar 0 33 %L\\0 %1.) 87 Frarumm. : ' D alicapwds OE*3 SE*: 2E 7 6E 10 3EJ 3E 4 87 hancmm :21' ti all owpm f.E +: 8E*: 3E 7 IE-9 IE4 IE 5 98 Radium !;.1 W a:I cepmnde SE *n Ul 3E-10 9E 13 C C D.me sur1 (9E*o) C C C IE 7 10 4 It RaJmm-224 %. sil oopsnds RE.n 2E+o 7E lo Of 12 C t' D mc suri ( E*l) C C C IE 7 IE4 RA Radium-224 W. all s.unpwds sE+o El 3E In 9E 13 C C Done surt ( E+1) C C C OE 7 OE4 84 Radium n %,allm mp unds OE *0 6E-1 3E 10 9E 13 C C lkme surt f SE+o) C C C eE-8 6E 7 et Radiura. :P %. all comemnds E*4 IE 4 6E 4 C C C a lhme surf Bime surf (20*J) ( E 4) C 3E 8 3E4 3E 3 88 Radium :25 %. all mmemnds OE+n IE +o SE 10 lE 12 C C Dm surf HE.o) C C C 6E 8 6E 7 89 . utinsm-2 4 D. all empaand= euen mow gnen lor % 4nd i 2E 3 3E-l IE-C f-C LLI mail D(me maf (:E *3) (4E

• l)

C SE.Il 3Ed 3E4 %. handes and Mraic C SE+1 2E 8 7E Il C C Y. mides and hdroudes C SE*l IE 8 6Eil C C 59 Actinium ::t D we "%c

• Eat 3E 1 lE lo e

r C l.L1 mall Bone surf (SE+1) (SE l) C 7E 13 7E 7 7E4 %. we "'Ac C 6E l 3E 10 9E.13 C C L we "' \\c c 6E 1 JE-10 GE 13 C C R9 A41 nium 226 D we "%c IE.: 3E.o IE.9 C t' C Eti mall Bone suri' (IE *:) -(4E 4) C SE 1

E4 lEA

%. wv "'Ac t' SE o OE 9 7E 12 C C Y. we "%s C SE 9 E.9 AE l: C C 29 Atinium ;r D. we "'Ac E-l 4E4 lE 13 t' C C Done surf B.me nei (4E 1) s tE4) C IE l! $E 9 SE 4 %. we "'Ac C IE 3 7E 13 t' C C Bene awf C (JE 3) C 4E 15 C C V. nee "% C 4E 3

E.l 6E 13 C

C Footm>te.s appear at alw end r>fthese three sable.s. D9199

• WR(*R l'o/ums* /..lugtal 1997 /)ra/l Appendit lle Aiunal I inuts on intale ( Al.11 and IknYed Air Concentrations (DAC) of Radionuclides for Occuptiorr_1 Expecure I:muent Concentrations Concentrations for Release to Sarutan Sewerage fontmunh Table i Table 11 Table Ill nu;upatamal f.lDuent Rewases to Values Concentrumns Sewm Col l Col :

Cal 3 Cal I Col 2 M1nthly Oral lfgesuon jMism AMpe 8 Aamic Radmnuclide Class AEl AEl DAC Asr % ster Cceicentrahan No (901 f uf's) (ufe mn f uO mn f uO mn tuntnli 89 4tmiwn 228 (1 we8' M Ev 9E*o 4E 9 C 3E-S 3E4 l%me sd C (;E

• l)

C lE Il C C u.wed' As C 4E+1 2E 8 C C C Done surf C (6E + 1) C IE Il C C ). wed'Ac C JE*l 2E 8 6E Il C C i m %eium :;r? n' ali cepwide rucpi thimie gMn Int Y

• E O lE*

6E 8 2E.10 C C Si wall (9E

• 3)

C C C rE S 7E 4 i, oudes and harmake C IE*: 6E 8 lE 10 C C e. Weium 201 n we'*Th IE ; 3F.I T lo SE-l)

E4 lE S 1.we'*Th C

3E-l ' i. lit SE-13 C C m th.eium. :s % we *Th 6E.0 IE.: 4E l: C C C Dnne surf Dme surt ilE+1) (;E 2) C 3E 14 lE.7

E4

).we'*Th C 2E 2 7E l: 2E 14 C C m Nium-Ts % m '*Th AE 1 OE 4 4E 13 C C C lhes surt ihme surf ilF. 0) (;E 11 C JF 15 lE 3 E7 ),.cc '* Th C

E 3 IE 1

C C C Done suri C (3E 3) C 4E 15 C C un ihmum ;lu n we '*Th JE'O (E.) 3E l: C C C tumeswf Doneswi (9h 01 ( E. ) C OE 14 IE 7 IE4 E 6E l: C C C i we *% Doneswf C (;E. ) C 3E 14 C C m Theium-231 W. we '*Th .iE

• 3 6E d 3E4 9E 9

$E4 SE-4 Y.we'*Th C 6E 3 3E 4 9E 9 C C W Theium 32 % we '*1h 7E-l IE 3

• E 13 C

C C i)one surf Donc surt' ( E+u) (3E-1J C 4E 15 J E." 3E-7 ), we '* Th C 3E.3 IE-1 C C C D % set (4E 3) C 6E 15 C C m ihmum 054 W we'*Th IE E. EE-8 3E.lo C C ELI weil (4h + 2) C C C SE4 SE S i.we'*Th C OL*2 nE-4 lE 10 C C '11 t h 1:neum2 P W. 411 c.wnew e cert show pen be Y 4h*) lE.: SE-4 E lo

• E S SE4

i. mmM and b@mides C

IE* 4E.8 IE 10 C C 'Al (Wimium. :n W we "'l's IF.) tE.1 SE 9 C ES 2E4 ihme saf C ( E*l) C 3E il C C ). we "'Pa C IE*l SE 9

E il C

C l'enstonalet supresar est Iloe* voul uftles'.se* litres

• Inshles D9298

Argttdl\\ ll .%RCR l'olume I..tupel I997 Drotfl Almnal 1.muts on inlaLC ( At.1) and Ikra ed Alt Cinentrations (DAC) of Radioralides for &cupational thposure D11uent Coiwntr.itions Colu11tratimts for Release to Saillian Seucra(c 4*smtmeevil

• e4I I Me il T 4Ne !!!

ssa..rW Letberd Le6 e as so % alues Civuenustava f.<mers Pol I Cid ; Col 1 Cet 1 Cai ! t iral klemthly t Irgestum Jgawa,,,, Average hans keJumusI4e %s All ALI DAC A4r % ster Corwentretum tu i mh tieri mn ipci mn r t u .) t uri mn r s pra se Ps el.: ti tl Le 41: C C wl lvismiinium.Its u lbwe wf (vte:) C C C IL 4 10 4

1. we8'I's C

dien I L., et.l; e C 91 ft smimium ll n we l's L-1 L-) 60 1) C C C tovie swt thee swf (*bi) (403) C (ble 6L 9 6E.8 L we "'h c 4L )

L 1

C C C 14me sirf C (6L.)) C ll-14 C C 9: 1%tW. e :l! % we # 's 11*)

(

• 1

&lD9 C 21 4 2L4 f lkee wf r st e l) c

81. 11 0

C i we #Pa P 6t+1 l.s r C C lbme swt r (7t.1) e it.lu C C el 1%ien um ll 4 we "'Ps

11. )

7L : JL.7 IL 9 C C til mail (*L*)) c c c 14 E4 ) we "'Pa C 6La: L.7 IL l/i C C 91 1%tmium 2)4 %. we "'Pa !! * ) II * ) JI 4 IF 4 E9 JL 4 L we "'re r 7L.) )l..e. 49 C C 9: Utenium ;&i (1 O. I ni, I n, Ass, Abu 45:..I lL.in P c C luww surf ihme wf MI.* P) (6L.1) r RE.1) IE t 601 W. t'i k t'}. t 1 't. P 4E-1 ilu to %1) C C i 1 t ', t v g r IEel 11 10 4L 1) C C 9: l eeruum !ti

1) we '*1 '

• l.1 8L.)

3L e IL 8 C C i 1.1 m all (4L*)) C C C

61. - ?

6L 4 % we'*L C 6L*) 2E 4 10 9 C C ). we '*1! C $L*) 21 4 609 C C el t.ranium :t: P. we *t: "E-o 201 OL.Il C C C i 'bes surf IkmeswI a dE *o) (40 1) C tl.13 6L 8 60 7 u. we '*ll P 4E.1 2L.10 SE.. ) C C ), w '*l: C IE.) )L 12 IE.14 r C 92 t renmm :ll l) we "'t 11 + 1 1E.n SE.lo C C C isone swf ikew uf i:E*l) (:E+o) e El; 3E.7 30 4 W we '*1l r 7E.1 it.lo IE.1: C C ). w e '*li C 4E. 1011 (L 14 C C e 1.r nium t4' I) y, **i: It.1 IE.o sg.in e C c thew surf itane turf ( t ell f:t.nl P 08: 107 3r4 %.we'*11 r 41 )L lu 1E.12 e c ). we *t e 4E.: 2011

• E.14 c

C i femtomeet afpear at the enstu{llwte three lahleg D9399

- - = - - - -.. -.. - - Anwnda il. MR(*R IWoor i..lupas IVV1 Draft Alunut I iinits on hinde ( Al.1) and Dernal Air Colwentrations (DAC) of itadiona;hdes for Occu;ctional INecure I.Hh.ent Concentratiota Colheutralloits for Relcase 10 $aflitary Sewerage forstsesunI) 7aNei feNe il T4le 111 Nureimnet iinvers Relea es to \\ aiwee Cmemranorts Semm Col i Col : Col 3 Col I Col ; 1.lontNv hel A*We I e*** __lr/##tutL N Atomit llahmu6 teJe Clas All AEl DAC Ant % eac, Contentrauon c.i e otM (uc. mh .wei mh Iwri mn <we. mn vu av v: I reium 1t4' D we '*t! lE.1 IE o tLin C C C thee wt thew wf (;E+l) (:Ee9 C )E.1: 3E.7 JE 4 % we **t ' t' sf l JE.10 IE.12 C C 1, we **1 ' C 4E.: E.ll 6E.14 C C 9: L reiend.tv. D we U l(. + 1 lE *o ? E.10 C C C Ikme wt baneswt ( E 1) (;E-01 C JE l' 3E.7 JE4 % we *t? C IE.1 )E.10 IE.1 C C 8 Y we'*ti C af.!

E.ll f,0. l 4 C

C 9; i.ramwn '.t1 D we'*t' OE*) 3E*) IE4 4E.9 C C t l I peil f:I:*)) C C C )E.$ )E 4 N,he I b.) 7I. 7 El ( C t ue *t: e

I.3 6E 7

E.9 C

C d 9; I re uum Ds' D we'T !!

• l IE+o 6E In C

C C ftwe wt tume set ( E*h ( L*oi e 41 E7 li e % we'*U C sE.1 Lin IE.10 C C i. we '*t ' r 4E.:

E t1 6E.14 C

t' 0; t tanium4M D we **t 7t J

E.4 SE.3 3E.7 9E 8 9E.)

n we '*11 e E.t 7E.3 57 C C L we **t C

t. e eE.3

E.7 C

C u; i ranium M D we '*t IE4) 4E.) E4 49

E.3 lE 4 n' we '*t c

li. ) If 4 4E.9 C C t wv**L e E.) IE4 E9 C C 9:

1. ranium-natural' D we'*U IE*l I f +o

%IO C C C thine wt ftane wt i:E*l) (OE m) C El %7 JE4 % sce '*1! r 8E.1 )E lo 9f.l) C C ). we '*1 e Sin El4 C C 96 %mun wn-:1:* n. all onew IE.S Of. ) 47 r E.) lE Inw swf (?! 2) C 6E.9 C 91 Neumum-11 e u all ovnn.unai sE*) )E.6 IE-3 4E 4 tid.: IE.1 VI Nmwuum 234 % alleene

E )

)E 3 IE4 dE -9 JE.$ JE4 91 Neumum Un n alluep e E,4 EE.: )E.7 P C C eel mall D ww surf f E.46 (IE )) C lE.9 JE 4 3E.1 95 Neumum :te

u. ali cene w 1E.n E.:

9E.1: c C C e1 Iti. 4i} !)ane surf Ibra swf

1. 6E*0)

(?E.2) C tE.14 90 - 9E.7 91 %epunie:M n alleepw 10 3 ) Eat IE.8 c C C (::n hp ikme wf !&vw wf - f4E')) 47E*t) C it.lu 4$ 3E4 9) Nep.an.e !.l ? n' allevnpnanda 41 4E.)

E.1

f' C C Llane saf [ksw swf tlEeu) (IE. ) C IE.!4

E 8

E.7 Finottwes appear at the enkiet(Ilwy three tables D9498

O Anundn,ll SWR IWuar l e.lupst 199P I)rqll Annual 1.imits on intale i Al.1 and Iktned Air Conwntru? ms (DAC) of Radionudides for Nupational thpisure j l2.l0uctil Coruntrations i Cinentralituts for Relcaw to Sanitan Sc%crore (t'imtmml> I a fahe1 1se 4e 11 f able ill acurweimal 4.&ern keleaws w \\ alues i'.neratawms sewers Cid i Cai : Cal J Col i Col 2 (hl Weal

• Irgreatsun Jints4(itiL,,,,

As of W hmes kale mu6 tide Plaw All ALI DAC Ap % met Cimenvetum W

1. _.r si

( c.i (r.mn f ut*i mn (uc. mn (uri mn 91 Nepuheum-!.42 %, all t mipeunds ll. s ) f4 1 Jt 5 C

• L 4

'.f 4 inw est ( ke;) C 21 11 C 94 heluwavm-; W u allsienpurwin 't * )

l *)

90 7 'L 9 C C 1 t I wa'l (21 a l) C C C 'L 4

E4 91

\\eNunium; M u 4H t epiunds l*4 Bl*4 )l4 ll.1 JL4 JI-) W Plut4meum :14 % allsepiunda el +)

• 8 * :

UE 8 )!.10 ILJ ll.) eveN IV is V 19 % r

fA st s

)t.In C C W Plui, mum :1 ** %. we '"Pu 9t+4 Af 6 1L4 di e ll.' IE 3 ) weawp, p jg,6 Ild )L4 C C W $1ut'mium 21#. 4 are '*N ll +0 'L. St.l C C C ther surf lume set (4L.0) ( AL. ) C 11;.14 ,L.B til.7 ) sec '"Pu O 4E.*

• E ll f E 14 C

C 94 Pluttmoum 217 % we "Pu IL44 )E=1 IL4 !L.9

L J

• t.)

8

4. wr '"Pu C

JE.) IF 4 4E.9 C C W l'lemum :18 % w '"Pu u).. I 7t.) }l.1: e C C lhme surt I&me est (:L 0) (1L 0) C Ot.14

• F.8 0F,1 4 we'"Pu e

f.

si. l

• lE.14 C

C W Ptuhmium.:.19 %, we '"N 9 L.1 f4.) JL 12 C C C Hime sWt ihme surt (IL*o) (it. ) C !.14

f. -I

L 7 i ter'"Pu C

[.: 7E l! O C (' lhme set P ( 0 0) I L-14 C f W Piemium 24e % we'*N st i f,t. J 30 8: C C e ihme surf lione swf (IL*to (ik.:) C 'E.14

E I

• E.7 i.we'"Pu e

21 :

71. 1 C

C e Ikmeesf r f:L.;) C

t.14 e

c W 11# mium-44 % we **Pu 4t.1 El it.in ta C C D.me surt ihmeest i n.i; d er.1) e el.1) IE 4 IE.! i we'"Pu e st.' JE.lin c C C tioneswf C (IE mi e IL l: C C W liut.e.um.;4: W we *Pu al.I 7L) JE l C C C 4 ll.me twf Daneswf t it.o; (it.;; e

).14

L a

L.7 i w '"N e

L.

7L ll r C H e ist C (20. ) C 00 14 C C W Pl#ca m. 46 % we'"N

L.4 4E.4 lE,5 St 4 lEd 20 3.

); we '"N O 4E.4

E.5 4L.4 C

C l'nulandc.1 appcar at Ilw cust of these* IIstre tables D9599

Appenda U a .Wu 'M l'olume i..hquer Inilkall Anmul I.umin et totale ( Al.1) and 1)emeJ Air Ccatentrations (DAC) of Rmhoninhdes for Onuptonal l;gmure Illluent Cornentrations Cimwntrations for P.cleaw to Sanitary Sencrape A*orstmurd) Towei im 18 lawe til thewet wel I mwmt fleteane to \\ alues <*.esenvoimns Stoeft Col i Col 3 Cd 3 Cd i Cal ! unnhly (tal Astripe Iritesum _Weio Al<ene R adeemlide Clau 4f Mi DAC Ast % atar Canentaisari r e.$ s,c. mn .'s.i' mn tpcomn tyci mn < prii u L w e4 l'lubeiwn :M % we'"lv st.1 71.) Jt-1; C C C ikva swf ikew swf ( t *u) (tL-;) C lL 14 21 6 L.7 L on '"IN C 21 2 70 12 C C C I&re saf C (;E 2) C

• I.14 C

C 94 Plevourn l44 % are !"l% lL*) Ste)

• l. 4 60 9 30 3 jf 4

) in IN P 41 ) 14 6t.9 r C W huovudm M % sn '"19 41.! Jb; 11 7 dt.no C C t i l m ail (41_ ;) C C C eE 4 6E 4 i we '"IN r ll. e 2 1t 7 48 10 C C v4 Amnuium ;# % 411 s.wnpiunJe 4( +J lld IE4 41 7 IFJ ll ! V4 Amenium 214 % allownewids et*4 )(

• I IE4 C
• E 4 SF 4 Iww sw1 c

(f4*j) C 9l. 9 C C 04 Ameenium-:)v % all ownpiun h 4f ) if.a 4t4 Ls flA 70 4 94 Anwn num-!+i uau s..mpwiih 20 1 31.* ) 11 4 4E 4 3tA 3L4 99 Anwriuum 241 % allowupeh u t.. I el.) )l.1; e e C l%e surf livre surf (ll'0) (11.-2) C 20 14 20 4 2E.7 v4 Amus.um :a:m W.Il p,mpion.h it.) er;.) .:.1; e C C lime surf it.ww surf (it 0) (it. ) C L.14

f-8

• E.7 94 Ameruit w!47

% alls.wnc-ww di*) t[*l dl 8 r SE4

• E 4 ft.ww surf t'

(9t*l) C 11 -10 C C 94 Mnetuiwn-24i % allsanemh 51 -l 11 ) )[.1; r C lWw sw1 0,wie surl i it.u) (it ;) c

$.14

t.s

E.7 94 Ametuium l44m'

% silevnpiurde 6L*4 el' * )

• L 4 r

C C St eall Done surf tal 4) (7E 3) C 10 8 10 4 10 2 94 Ameus eum.'M W allownsmh 3E+) 26*2 8E 8 C 4Ed 4L 4 tune surt c (30 l) C 4L 10 C C v4 Ametuium-;44 W sils.wnpiunds 1(+d 4Eed !EJ IE 7 41' 4 4E.) ut 4ncicium.!* en' % sil s.wnpiunde 4f. + 4

• 04 ti 4 jf 7 C

C M ean H4

• J)

C e (' 8E4 EE.) 94 Ams'e s ium-2 4h* % alls.wnpnvids 4E*4 ll.* 4 40 4 I t'.I 40 4 dC.) 'Jh Cwium.018 % allsnmpets 20 4 IE*) 507 !L 9 20 4 2E.) un runum OM W. all s4wnpunJ4 6Ea1 601

• l.lu e

C C Ikve awf tww surf (80+1) (6Ed) C 41) IE4 IE $ l'essonsI<'s artwr nur do. e,sdo{du u dors.e* oaoMs s D9698

MR('R Idum I s,bspst I999 Drf$ Argeln il Amnal 1.umts oti Intae t Al.li and Iktnal Air unentrations (DAC) of Radionuchdes for tksupational Esposure Lilluent Concentrations uneutralnms for Release to Sarutan Seuctope (Castsnwat) Table 1 7 sh411 f able til (Ansemi LNers Leleets to VaJure C wwenustmns Sewers 04 i Col 2 Cd 3 Col i Col ! Methlt Ost ingestuvi _lQ+eWh Av* epe At.vnie 1%isimaliJe 4% alt All DAC Ar % ster C.vanniauan r i'i mit (p('6 mh f#rmh

1. pf *in f pril f gf*i min u

Nei ur. Paiwn.248 %..H e vre e IL ) JE 1 IL s C

• E.4

E 4 thwwswi C

(4E*ll C %I1 C C rwium ;4 %. a;t e.cip e JLei )f.! It.lu C C C thww swt (kee set (4Lel) ()L.1) C 4E l) 47 71 4 'wi Fwien. 41 % all somp.unds IL*n t<L.) 4E l: C C C ll.ww swf H.ww set I:L *ny ( *l. @ C 2L.14 30 8 JE.7 m ewiumd u n att sieno un,h it *n 10. 401: C C C lbww sw1 tome set Oi+N (:0h C JL.14 30 I %7 'e+ t'eua a 48 % 44 compiunds 7F. I 60.) Il 1: C C C loww swf thme suri (ll au) (ll-b c II.14 2E4 47 m rwium e u aa cunew' 7L.I 60.) JE.': C C C theeswf 14ww swf (ll: e n) (IL@ P

• 1514
• t 8

E.7 m

rwium447 % ali c4cipwnds

• L.I

61.. )

lE l: c C C Ikww surf thee swf (lL*0) (ll 7) C 'E.14

E.8

L 7 m

runumads W enemc e

f l

L.)

Lt) r C C lume sur1 tumeswt 6 4L.1) (%3, O JL.14 40 9 ef -9 wi reiam 24/ u ail ovnpiun.n SL*4

L*4 71-4 C

7L4 %) Itine swf C OL*4) C 4E B C C e reiuma % u ailsmnpe 4E.) )E4 IL 13 e C C thee surf thine swt (t E.2) I'L 41 C RE.16 9E 10 9E.9 9 lickchum44% B a.1 tiwnpiunds Is ) il*3 %7 I. 9 )E.5 3E4 97 twebumle u ad um.pwn.a JL*) )E*) If e dlA 4L 1 4E4 97 Dehehum447 W 4.l empe %I 41.. ) 'E.1; C C lbee surf Det sei s'l L *u) (9L.)) r IL.14 E.8 E.7 97 (krkehum.'N % a;luvnpe

L*:

'E*4 Lin t' C e lhme surf ikww surf Oh*2) (4E*0) C 40 12 6E4 SE.1 97 hckthum4 % W 4ti penew - OL*) 3E+2 t h.7 P 10 4 IL.) thme surt C ( 7E *:) P 109 I' O 98 Cabbwnium 444" % ailssenpWisvers IP*ne gnen liv ) 3L*4 613 2 lE.7 2010 C C Si onll ()E*41 'C C (' 4F 4 4E.) E m. des and iness.Jn C t>l. * ) lL.7 St.lu C C Faseannks apjwar at slu a.nst o{tlos.se* tlore s* tesl>Is.s D9799 ~

h5R('M l ohase I..lugu<t IH1 I) raji AWndat i1 Aluiual 1.nnits m Intale i Al.1) and ikined Atf Coiwatrations (DAC ) ol' Radior.uclides for ( Acuplienal 1:yaure l'.111uent Coruntrations Durntrations f or Releanc to Santtar) Sewerage (t'orsturiml) i P T.Nei f able 11 1able 111 rasuperial IfNees Reneues to % alues Owwevessore Geners Pal I Col : Col 1 Cui 1 Col ! klanthh nal Anrage trwestam _hs:st, As.vens RahrwaliJe fles ALI All DAC Air W ater Ccometiersimn f p 's mh f pr6 mh f Nn

1. p(M f p(* )

f p(', mh (pri mh vs raisi.vmwn-24h % ect '"i'i JL*: 9li.0 40 9 IL.Il .e g 4 gg.3 L we '"rf C 9L.0 40 9 IE.ll C C vs raldrvmum.:4s %. we '"Of 30 0 6E.: 301l C C C thew swf [kvwswf (:L+1) (10 0 C E.8)

E.7 34

) we'"rr C it.1 at.Il IE.1) C C r ht.vmum :n u we '"rl

• l..I 4L4

t.):

C C C 9: e lhme sw1 twww swf (It.u) (9L.3) C IL.14 IF 8

E.1

) ea'"rt r IE : dr 12 C C C 16<vw set C (lle ) C

1. 14 C

C va rod. mum.:to n we '"cl 10 0 9L 4 41 1: C C C (kww surt ikweset CE o) CL.:) C 3L 14 IL s JE.1 ) w '"rr r JL. !L it 4t.l4 C C J 9s rahaismum 'l % in '"l'f 41s t 4'. 3 If l: C C C li<wie swt Ikww set (11..H) (9f 4) C II.14 2E.8 lL.7 ), we '*r! C lL. 4L 12 C C C l%meswf l C (10 21 C

E.14 C

C 9: Cald. mum :42 % w '"rf Ot.ti lL.: 31 1: C C C thme wt Iww swf (*L uo (41.') C 41 14 71.8 7E.7 ). m '"rf r lh.: IL.ll SE-14 C C os ral+vmum 25,l % w, '"cl

t.

L.o 84 lo 3E.12 C C is.ww set (4t.:) C e C SL4 4E.S ). we '"et c lE o E pi L.1 C C 98 Cani,wmum 24 % n '"cl

t.o 2F.

El: 3E 14 3E 8 ll. ? t weef r

t.2 El E.14 C

C w larwnnium.2 % s u alls.ap e Jh.4 tt :

L.7 0

t>E4 6E.1 thre saf C (IE.31 C 2E-9 C C W l mnemium 241 % all c.wnp.un.h 70 1 9L.: 4E f C If4 10 4 (tme swf C (ll.3) C lE.9 C C w tm. nn,m :n a.uona

t.:

i t.o .t.io

c.i:

a4

t.s

<m wn :% w.n -n.w.a. 3c.: it.i .it.9 it.n C C n i..n (3E.2) C c C JL 4 4E.$ .t,a -ne n.o re.: 3t.n c c C t., min.wn.:9 n,w.wr nm us 1:t.o (ita C

r.o

t.)

s4 w.u..,4 it.:

it.: 36 9

c.ii es4 es.s iisi s,,m.. :.:

l o., r-:n

w..u -nra it.:

it.: 4t.9 a.n it.s ita l r l l'eustuksle.1 offmW at Iloc crosin{tlwse Ilwer tables 1 i D9898

a Aggaelula \\\\ ANM'R l'olconw i..tupost I997 Drnll Annual 1.imita on intale ( Al.ll and Derned Air Ciunenttatmns (DAC) of Radmnuclides for ( Acupitmnal thonure I.filuent Concentrations Colltentratuals for Release to Samtar) Seucrage fontsnwh iatow I Tstu Il 1shw 111 OL sugems.al l.lfluern Rekance la % alues P vuonvatscris Semers Oni I Col ! Cd 3 Ctli 1 Col I orel Mrd.lv l'ip<siom _lrhetML Ase'aye As, ems k d.wimI* t 't.ma Al 1 A1.1 DAC 4t water Caruereatum c mh s pPi mh fure mo (pri mh fu M fu M e su r e N,i lite lenmwn 44 % alls.cpiune .tk e ) 9t el ef. 4 IL.in 4L.) 4E.4 1+e1 l e#meum-;* 4 % all ticipiundt 4t+2 2 Lei 90 9 )) 11 44 44 lit # l ermewn :87 % allevrenmJe

[

• l 10 1 4 11 C

(* C lome sw1 lume sw1 14L+1) f 31) C JE-11

• E 7
• E4 loi klenkevum 247

% allseimpwe fle) $[ + l JL 8 C ll.4 lf-) Ikww swf C (9t+1) c 1L.10 C C lol uenweium :5s % allownewe 11 + 1 Of.1 IL ld C C C linne sw1 lione twt (SE*l) ()F.1) C

• L 1) 6F 7 t>L4

. Ant 44e gadomwhJe n.4 heted stunt u @ Jew m4 <thet than alrha em.m.e.in st epwam in-st $ ansl e 4th fMuu18% e heil-life leso than l hws 596mefwe' C lLal !! ? II 9 C C Ant tingie f aJemmisde fut Inted ahn e eith decas nule inhet than alpha et!tiname sp mine** fe-tvet and eith rahmine hall. P El 10 16 1f.l2 il 3 I L.7 life grealet than 2 but . Arn am6 ' f*l"malede nit inled l stone that dewt in sopha cmme.m av spmtaneman liune ne am ma. twe Irv whnh eithet the ukntity ev ihe s wiurnisatum of am rad.+ nahde m the maiwe is n.e innen C 4E4

E.13 IL 13 L.9 lL 8

- Dwnsaks aftwstr est dos

• esule(Ilus*ss llarre* hohles D9999

.WK'/t l'olume /..lugu si / W1 Drivi Appendit il f00lhof 4 4l

• *sehn.r. sum' n a lw.sai,,. gnen r s.n se.n.,,

m.n.,6,n ara,,.s um. em,, J.ed s,$m. m.uenaa s

• fkee ea.4.weeshJrs 4.ne raduikevaal 4.at inre.v leu te. n 2 A.ers 14 kwal ef ern., Jiue evenvient resened Jenne opreun.wu est4 okse o.a.hemeJJes msght in.4h et f

s.gnuksant semanhu,m th.no warson.st esp ueur the U 4C sseters he.stl raJmneskhs enher sk.nn skaar Josegnwed Cl.us *5et.nwessos

• os based epi.e the snamuturd afesn ihr J.or eget.sstent.ler ks the me.de,4 IM o.sJu.noshh mm the kn.h and.kr QQJ msteJr ponenhalk 5.gnthsant synenhehunu to kue egenwirnt in.m estern.nl espneres hsenser m,n su uhreer 16.* ca na r.* a.a ku J Inc o.,.nwent he w nosnerswn J mo pnense.ek-tot shoekt en <n.snaeat awmunng Jomse.* owr ra.hano*

n n.e.uenn. nenam, tu m..ae., noen a:sp. ear sa aneauto.or wn,phaue sus ou knea tsa o;o) o

• ha seduMr naar ors ad t '. *)M l'..')4 es.I t \\;)) on aos sbwansel kasneh an.rs kr the banhng 1.nke Ises O lfle 6 ll eM persrat hs osrght tenns knwnst W v.l)) se mat gerwer n

th,on ) the s nnennasoon aler he a as kwr e,.riesse n Q1 adhu anu ar an,em per ssbu meter af or nsrege f ur am ennshawnt the ymdest d tM.nerage st.msnto.nnon r r s an.I hant *4 espuuor Jenny e 4tLk.anor erut otra sh.stl end asserJ Ml.) tL4I:Cs hr al ekrue L4 as the spreinc strnis N the e anoem onhaled the sjes%ht.a pnh kw nator,nt r s e..u,,em a s n.,en s pro quan, e tu sprehe asnh na asser n,,ste,es se v.:)s v.1)r ans v.234,1 nar sno.s srait he St J rJ:.* suoma gosm U V Irr r rJ en 5 4

• la 4
• U JM tennJnenot
• 0 00)d tennskmenryj bA ennsha.tni 2 0 *]

s erst,e v.:)) espoqued.a penent e stre ennJn,a n na o.sent. wr s we 18 the i&nsiti al esa k v.mh mmlide m a mister n Lnime M the samentranon of eme ce mrve of Ltw enlummliJes in the mattwe es ont Lamn the DAC (sr t i sh4ll De ths etwas entrectne IMc 14 am telemabJe en the emt'se 11 ttw 4Melift ett s%h f 4h'WSWLhJs iti the trustigt is riit ben t%d si is Lhimt that rafts

• tadsamocl. des trecthed in this splendst are fius prestrit in the mtstwe the mhauwe \\1 I h F. anJ riilurni at%I srwno cuenustum bv the mittwe are the kwest valves spectlied m this artendit lot anv todamuchde that is hai Lamm to tv ewns it vvi the matst.*

Aninial 1.muti on intake ( ALD and Derned Alt Contentrations (DAC) of Radionudades for (hupational Lsposure Dlluent Concentrations Contentrations lor Release to Sanitan ScMerage Contatitre Tatae i Tahle !! Tele !!! (uupatumal if!1went R e! eases to Valace Omentrainma ?>ceen Cal l Col Col ) Cm ' Col Oral Akmthly ingestue ,_ lqhalstph Ase' age Ahems kademu6hJe clw Al! All DAC Act W ater Cinentraton r mh I9C mh Nn 4 um i gr,) Nr. mn

1. a^**
2. u e

if n is krumm thai Ac !1 O eriJ em 244 ore c 'IA )l. I1 C C C rW pewns H m additum n n ktwmn that Ao:27 % i TMN%) Th : h % Th 212 % ). I's 211 M i Np:17 %. N :WW N:M%.N 42 % Am :41.4 Am 24 m W Am-24t-% t'en :4t% t'm';4t W Um :47 %. Cm 244 %.11L 47 % t'l 24 # %. enJIT :sl W C 71 1 M.1: C C C are r*4 fawnt 10 m aiklaret a n inamn ihai sm.Iw%. Sm 147.W. OJ I4R O % OJ 142.D W. Ih 221t W ) TM bs V. t h:1:a 1.:1L Y. t '.: Ma. U:IM U,:tu th:iaa sp.:gr.% N :b% ) N W%)N*Na.NlM\\N:4\\ N.244 % ). t 'm-:4 4 % Cm 244 %. t 'l 4E % Cf 4%), r1 !bu ), Ci s t a. Cl It u ) and t'l 24% ) are n.t pewei l' 71,. 3E.11 C C C D100402

1 Appelulis il SS/CR l'oleme /. Org/) i Anntial 1.iinits in: Int.ile ( Al.1) aihl 1 Amed Air Concentrations (DAC) of Radionust:Jes for G;cupational Es;usure Elliuent Corwentrations Concentralmus l'or Releasic to sanstan ScWerage forarmmh 1sta 1 1abie il t ahie !!! t keuresemal (INeni Releases lo % alues consenustama Semers ul I Cal 2 Cal 1 Cal 1 Cnl ! Oral SLmthh Iripetthm lbb4!4l12 _, Anefalle Ahenie k aJiemmI.Je riens Al.1 Al l D AC Air % ster Carpnestam ha i#a <#a s#.mn apc mn tpr mn ipc mn it in autuve se se in m* um Pt>;l's t) lie. l* %. P.*!!iLD % Ra 21L% Re 24 4 ka 2:6%. As ;;4 O % 11h-2 1 %.).IA:144O % ), IL;.l: D % IV:Ji % em 246%.Um 24 -%- Cf 2484,i e 254W.Im ;9i % ard \\1J 246 n C 71 l JL lit C C C se he pesent (f in 6Alitem : is Lrme the Me t*4. ii44).le.#.t0 Kesas) h 300 CJ tl.tm D. rJ it ti) in It4 41 %. l a l ta.D l u l k W lif 17tm D % lH--l* -D %. bi-21'im O k a 2*4./ km :t W. Ac !!hD H ), t+2 %t%1. 112100 %.lo tal)% l.:84-D % l. W (1 %. tL;is D %, TV:414,ht:4's-A ri :* I % ). er4leS t % are tre pewm C Un R9 r C C n et n in.*n ihm.42 1 D W L t h ;;9 % L 1h It % L Pa;114% 1.P m-04m W anJ Cm :h% se n t newn. C C C f f.14 C C li in alJaum d n Lemn ihas %m 14 % (M I40-l) % (M 1 %)-1). Ih ) 3-4 ) th bL%.). (!.2.12. ) L s 11 ) L'.; t4 ). t '.214. ) t.! A4, l'.Itt4. tlAa4 \\p.%% Np 2 4 7-%.1% !WW ) 14:48 % ). 5%.019.n ) 1%- 44% L l% 24; % ) 09-4&%'3, Am 241.W. Am 24 m %. Arn 240% - Cm ;4LW rm ;4& %. Cm 241 % Cm. A%. Om:47 %. fiL;47-W ri :4 8 % 1 Ot.24,t%.L Of l41.% Ler ';,% ), anJPl NW ) C C C 1f.Il C C are n.s pocnt li in eaJdes it n Arma 6 hat sm 147.%, (N II % l% $1bl). lIs.) lim %. 0%)likU.U. ke ;) u ka 204.W ks ;2n-% Ac,;24-1)% ) Ih !!th L U. tLil%.L i'.242 D %.ILNet-% IV'41.% rm.246% Um.!4; % Pl. 44 % ) 1 s ;t4% Sm '*7 % 4nd \\lJ :ss % are as C C C IE.1: O C Fornt lt. in aa.laam is n Lumn 04 l e w l Sent rd.ll)m.CJ-II) trolit l.120 i C.,114 Km.144. 5m.147 (M-144 (W-141 llg 14*4 f ev$4ntt L 16. 2lim ks. ;l Ra 204 Ra ;;' A5 2:4 W::t TK:vi (.:14. U' u 1: ;tt ta;w (. ta 1:^4: em 24;.Pl 2411 i n '54 I m.:41 enJ su ;*aw r 4 pewn C C C e Ir.4 it, 5 I l D101401

.WN'R l'ohcee /.. istysat / 991/)ns/t Anwndit B ' i n.,n.u,...a i.a.. .ns a.we,. .. a, oo m,v. tao r.mw.i.w,w o sinie se o i.erna..s u n o. u. v. i.4 m.,,.

m...

u.

• or,< u u,,,

i..n c..r, -.%. us..m.:n v t..m w,a

. i. am,=.<.

ii..nc,. a. .ni.......e u J If I,w hkni A val.a c.,e. d.'.,h,.J l+Je,a e ennt e,e L, wies the 14mdag n las fewlJ is ilenivJ m 1ilkies deie,mww fis em.h,. Jean.l 6, in the smu e. Uw,suo .m ..n.-. =,,,,u,,w u.... w w,ni,u . w i,a.. .a.n.u.n n.. .....n.. u. a ,ia

• m. u,,

..... i n..,., u n,a. ia, e n.ns c.,,.

c. c, c,. w ir u wu,i, tac... os. ox w ou..., msn.i. u. a te.e.,1f D.et.h.ll ly limdeil.* th e lh ' j.O m t,y,ti.ter htl, g gists X<

Xn Xs S, JAX< JAXa JAXs D102402

I i Apgc SMR l'ulume I..tugust 1997 Dntil PART D A PPl:NDIN C OliANTITil:S E OF l.lCI:NSI:D OR REGISTERED %1 ATI: RIAL, REOl11 RING lAlli:1. LNG (in Atomic Number Order) Quantit Radionuclide Quantity Radionuclide (FCi)! y (FCi? Ilydrogen 3 1,000 Scandium 48 100 Beryllium 7 1,000 Scandium-49 1,000 Heryllium.10 1 Titanium 44 1 Carbon 11 1,000 Titanium 45 1,000 Carbon 14 1,000 100 Vanadium 47 1,000 Fluorine.18 1,000 Vanadium 43 100 Sodium 22 10 Vanadium 49 1,000 Sodium 24 100 Chromium 48 1,000 hiagnesium 28 100 Chromium 49 1,000 Aluminurn 26 10 Chromium 51 1,000 Silicon 31 1,000 hianganese 51 1,000 Silicon 32 1 hianganese 52m 1,000 Phosphorus 32 10 hianganese 52 100 Phosphorus 33 100 hianyanese 53 1,000 Sulfur 35 100 hianganese 54 100 Chlorine 36 10 51anganese 56 1,000 Chlorine 38 1,000 Iron 52 100 Chlorine 39 1,000 Iron 55 100 Argon 39 1,000 Iron 59 10 Argon 41 1,000 Iron 60 l Potassium 40 100 Cobalt 55 100 Potassium 42 1,000 Cobalt 56 10 Potassium 43 !000 Cobalt 57 100 Potassium 44 1,000 Cobalt 58m 1,000 Potassium 45 1,000 Cobalt 58 100 Calcium 4l 100 Cobalt 60m 1,000 Calcium 45 100 Cobalt 60 l Calcium-47 100 Cobsit 61 1,000 Scandium 43 1,000 Cobalt-62m 1,000 Scandium-44m 100 Nickel 56 100 Scandium 44 100 Nickel 57 100 Scandium 46 10 Nickel 59 100 Scandium 47 100 Nickel 63 100

• I See esplanusuus at end qfrin s lo sturg
• ' lo cornert jt 's to LIIq. multiply the it 's wlue by J 7.

Dl03443

MRCH Ihlume I..Ingust 1997 Ikull AWndm C OUANTITIES' OF LICEN$ED OR REGl5TERED MATERIAL REOUIRING LABELING (in Atomic Number Order) tr*<mtm m h Radionuclide Quanuty Radionuclide Quantuy (fCif tFCi? l Nickel 65 l.000 Selenium 70 1,000

• r Nickel.66 10 Selenium 73m 1,000 Copper 60 1,000 Selenium 73 100 100 Copper-61 1,000 Selenium 75 Copper.64 1,000 Selenium.79 100 Copper 67 1,000 Selenium.81m 1,000 Zine 62 100 Selenium 81 1,000

- Zinc 63 1,000 Selenium 83 1,000 Zinc.65 10 Bromine 74m 1,000 Zinc 69m 100 Bromine.74 1,000 Zinc 69 1,000 Bromine.75 1,000 Zinc.71m 1,000 Bromine.76 100 Zinc 72 100 Bromine.77 1,000 Gallium 65 1,000 Bromine.80m 1,000 Gallium 66 100 Bromine 80 1,000 Gallium 67 1,000 Bromine-82 100 Gallium.68 1,000 Bromine 83 1,000 Gallium.70 1,000 Bromine 84 1,000 Gallium 72 100 Krypton 74 1,000 Gallium 73 1,000 Krypton.76 1,000 Germanium 66 1,000 Krypton.77 1,000 Germanium 67 1,000 Krypton 79 1,000 Germanium 68 10 Krypton 81 1,000 Germanium 69 1,000 Krypton 83m 1,000 Getmanium 71 1,000 Krypton.85m 1,000 Germanium.75 1,000 Krypton 85 1,000 Germanium 77 1,000 Kr>pton 87 1,000 Germanium.78 1,000 Krypton 88 1,000 f Atsenic 69 1,000 Rubidium 79 1,000 Arsenic 70 - 1,000 Rubidium 81m 1,000 Atsenic 71 100 Rubidium 81 1,000 Arsenic 72 100 Rubidium 82m-1,000 Arsenic 73 100-Rubidium.83 100 Atsenic.74 100 Rubidium 84 100 Arsenic 76 100 Rubidium.86 100 - Arsenic 77 100 Rubidium 87 100 Atsenic.78 1,000 Rubidium 88 1,000

• ) See rsplwratran at emlofshes hstmg U Tocanvrtit 's to Lily. muhirle theit 's sulue by 37.

l D104H2 _. _. ~..,.

r Argwndm C SSRCR l'olume I. 4upnt IH1 Drall OUANTITIES' 0F LICENSED OR REGISTERED MATERIAL REOUIRING LABELING (in Atomic Number Order) = d'antanurell Ibdionuclide Quantit) Radionuclide Quantity tfCif tFCif Rubidium 89 1,000 Niobium 98 1,000. i Strontium 80 100 hiolybdenum 90 100 Strontium 81 1,000 hiolybdenum 93m 100 Strontium 83 100 hiolybdenum 93 10 a Strontium 85m 1,000 hiolybdenum 99 100 Strontium 85 100 hiolybdenum 101 1,000 Strontium 87m 1,000 Technetium 93m 1,000 Strontium 89 10 Technetium 93 1,000 1 Strontium 90 0.1 Technetium 94m 1,000 Strontium 91 100 Technetium 94 1,000 Strontium 92 100 Technetium 96m 1,000 ~ Yttrium 86m 1,000 Technetium 96 100 Yttrium 86 100 Technetium 97m 100 Yttrium 87 100 Technetium 97 1,000 Yttrium 88 10 Technetium 98 10 Yttrium 90m 1,000 Technetium 99m 1,000 Yttrium 90 10 Technetium 99 100 Yttrium 91m 1,000 Technetium 101 1,000 Yttrium 91 10 Technetium 104 1,000 Yttrium 92 100 Ruthenium 94 1,000 Yttrium 93 100 Ruthenium 97 1,000 Yttrium 94 1,000 Ruthenium 103 100 Yttrium 95 1,000 Ruthenium-103 1,000 Zirconium 86 100 Ruthenium 106 1 Zirconium 88 10 Rhodium 99m 1,000 Zirconium 89 100 Rhodium 99 100 Zirconium 93 I Rhodium 100 100 Zirconium 95 10 Rhodium 10lm 1,000 Zirconium 97 100 Rhodium 101 10 Niobium 88 1,000 Rhodium 102m 10 Niobium 89m (66 min) 1,000 Rhodium 102 10 Niobium 89(122 min) 1,000 Rhodium 103m 1,000 Niobium 90 100 Rhodium 105 100 Niobium 93m 10 Rhodium 106m 1,000 Niobium 94 l Rhodium 107 1,000 Niobium 95m. 100 Palladium 100 100 Niobium 95 100 Palladium 101 1,000 Niobium 96 100 Palladium 103 100 Niobium 97 - 1,000 Palladium 107 10

• ) Ses replanatism as ensin(Ilus losting

'? To csunvrt s 't to Lily, multiply t;ae it's wlue by 37. n D10543

.WRCH l'oln w I,,luptst IV91Ibenft Argwndn C

• OUANTITIES* OF LICENSED OR REGISTERED MATEklAL REQUIRING LABELING (in Atomic Nundwr Order) d'ontinued)

Radionuclide Quantity Radionuclide Quamity ( J ( FCh'" (FCO* Palladium 109 100 Tin.113 100 .l l Silver.102 1,000 Tin 117m 100 Silver.103 1,000 Tin 119m 100 Silver.104m 1,000 Tin 121m 100 Silver.104 1,000 Tin 121 1,000 Silver 105 100 Tin 123m 1,000 Silver 106m 100 Tin 123 10 Silver.106 1,000 Tin 125 10 i l Silver 108m i Tin 126 10 Silver.llom 10 Tin 127 1,000 l Silver.ll i 100 Tin 128 1,000 Silver.ll2 100 Antimony ll5 1,000 t i Silver 115 1,000 Antimony.116m 1,000 Cadmium 104 1,000 Antimony 116 1,000 Cadmium 107 1,000 Antimony l17 1,000 Cadmium 109 l Antimony.118m 1,000 Cadmium 1l3m 0.1 Antimony.119 1,000 Cadmium 113 100 Antimony 120 (16 m!n) 1,000 Cadmium 115m 10 Antimony 120 (5.76 d) 100 Cadmium.l l$ 100 Antimony.122 100 Cadmium 117m 1,000 Antimony 124m 1,000 Cadmium.ll7 1,000 Antimony 124 10 Indium 109 1,000 Ant! mony 125 100 indium l10 (69.I min) 1,000 Antimony 126m 1,000 Indium-110 (4.9 h) 1,000 Antimony 126 100 Indium 111 100 Antimony 127 100 indium l12 1,000 Antimony.128 (10.4 min) 1,000 ^ Indium 113m 1,000 Antimony.128 (9.01 h) 100 indium ll4m 10 Antimony.129 100 Indium 115m 1,000 Antimony 130 1,000 Indium 115 100 Antimony.131 1,000 Indium 116m 1,000 Tellurium.116 1,000 Indium.I17m 1,000 Tellurium 121m 10 Indium l* / 1,000 Tellurium 121 100 Indium 119m 1,000 Tellurium 123m 10 Tin 110 100 Tellurium 123 100 Tin 1I1 1,000 - Tellurium.125m 10 'I See explamotuus or coulof thus hsimg. U To consart it'i to Allq. multat,1v the it'i wlue by,11, D106142

l Argwtm,Ik C .WRl*R l'eluxor ]. 4ugtsst I997 !)rqll l 00 ANTITIES* QE LICENSED Ok REGl5TERED MATEKlAL REOUIRING LABELING (In Atomic Number Order) d'ontinued) l Radionuclide Quanuty Radionuclide Quantity s (FCif (FCi? Tellurium.127m 10 Cesium 125 1,000 Tellurium 127 1,000 Cesium 127 1,000 Tellurium 129m 10 Cesium 129 1,000 Tellurium 129 1,000 Cesium 130 1,000 Tellurium 13lm 10 Cesium.131 1,000 Tellurium 131 100 Cesium.132 100 i Tellurium 132 10 Cesium 134m 1,000 l Tellurium 133m 100 Cesium 2134 10 Tellutium.133 1,000 Cesium 135m 1,000 Tellurium.134 1,000 Cesium 135 100 -lodine 120m 1,000 Cesium.136 10 lodinc.120 100 Cesium 137 10 lodine.121 1,000 Cesium.138 1,000 j lodine.123 100 Barium.126 1,000 l lodine 124 10 Barium.128 100 i t lodinc.125 i Barium 13im 1,000 lodine 126 i Barium.131 100 lodine 128 1,000 Barium.133m 100 lodine.129 I Barium.133 100 lodin1130 10 Barium 135m 100 lodine 131 i Barium.139 1,000 lodine 132m 100 Barium 140 100 lodine.132 100 Barium.141 1,000 lodin< 133 10 Barium.142 1,000 lodme.134 1,000 Lanthanum 131 1,000 lodine 135 100 Lanthanum.132 100 Xenon.120 1,000 Lanthanum 135 1,000 Xenon.121 1,000 Lanthanum 137 10 Xenon.122 1,000 Lanthanum.138 100 Xenon.123 1,000 Lanthanum.140 100 Xenon.125 1,000 Lanthanum.141 100 Xenon.127 1,000 Lanthanum.142 1,000 Xenon.129m I,000 Lanthanum.143 1,000 Xenon.13 im 1,000 Cerium 134 100 Xenon.133m 1,000 Cerium 135 100 - Xenon.133 1,000 Cerium 137m 100 Xenon.135m 1,000 Cerium 137 1,000 Xenon.135 1,000 Cerium.139 100 Xenon.138 - 1,000 Ceriur>l41 100 ') See explauwtuus os esultfolus instong M To omers i s to LHg. multiply the it i wlue by 31, t' Dl07444

,WU'M l'olume I.,ingun 1991 Ikujt hl3xnda C e OUANTITIES* OF LICENSED OR REGl$TERED M ATERIAL REQUIRING LADELING (in Atomic NunterOrder) tt'emtonued) Radionuclide Quantit) Radionuclide Quantit) (FCif (FCif Cerium 143 100 Samarium I$1 10 Cerium 144 1 Samarium 153 100 Praseodymium 136 1,000 Samarium 155 1,000 Praseodymium 137 1,000 Samarium 156 1,000 Praseodymium 138m 1,000 Europium 145 100 Praseodymium.139 1,000 Europium 146 100 Praseodymium 142m 1,000 Europium 147 100 Praseodymium 142 100 Europium 148 10 Praseodymium 143 100 Europium 149 100 Praseodymium 144 1,000 Europium 150 (12.62 h) 100 Praseodymium 145 100 Europium 150 (34 2 y) 1 Praseodymium 147 1,000 Europium 152m 100 Neodymium 136 1,000 Europium 152 1 Neodymium 138 100 Europium 154 1 Neodymium 139m 1,000 Europium 155 10 Neodymium 139 1,000 Europium 156 100 Neodymium 141 1,000 Europium 157 100 Neodymium.147 100 Europium 158 1,000 Neodymium 149 1,000 Gadolinium 145 1,000 Neodymium 151 1,000 Gadolinium 146 10 Promethium 141 1,000 Gadolinium 147 100 Promethium 143 100 Gadolinium 148 0.001 Promethium 144 10 Gadolinium 149 100 Promethium 145 10 Gadolinium-151 10 Promethium 146 i Gadolinium 152 100 Promethium 147 10 Gadolinium 153 10 Promethium 148m 10 Gadolinium-159 100 Promethium 148 10 Terbium 147 1,000 Promethium 149 100 Terbium 149 100 Promethium-l50 1,000 Terblum 150 - 1,000 Promethium ISI 100 Terbium 151 100 Samarium 14Im 1,000 Terbium 153 1,000 Samarium 141 1,000 Terbium 154 100 Samarium 142 1,000-Terbium 155 1,000 Samarium 145 100 Terbium 156m(5.0 h) 1,000 Siamarium 146 Terbium 156m (24.4 h) 1,000 Samarium 147 100 Terbium 156 100 4

• ) Ser uplanasoon as rout ofolns snong a

V To cemen i s to wq mulaply IIw pt's value by 31. t' D108H2

= I AptvskIn C .%RCR l'ulume l e.tural 1997 Draft OUANTITIES* OF LICENSED OR REGISTERED MATERIAL REOUIRING LABELING (in Atomi Number 0 dct) tr 'ontonueth Radionuclide Quantit) Radionuclide Quantity tFCif tFCif Terbium 157 10 Ytterblum 178 1,000 Terbiur.158 1 1,utetium 169 100 t Terbium 160 10 Lutetium 170 100 Terbium 161 100 Lutetium 171 100 i Dysprosium 155 1,000 Lutetium 172 100 i Dysprosium 157 1,000 Lutetium 173 10 Dysprosium 159 100 Lutetium 174m 10 Dyspro:ium.165 1,000 Lutetium 174 10 Dysprosium 166 100 Lutetium 176m 1,000 llolmium 155 1,000 Lutetium 176 100 lloimium 157 1,000 Lutetium 177m 10 Iloimiem 159 1,000 Lutetium 177 100 i llolmium 161 1,000 Lutetium 178m 1,000 lloimium 162m 1,000 Lutetium 178 1,000 Iloimium 162 1,000 Lutetium 179 1,000 llolmium 164m 1,000 llafnium 170 100 Ilolmium-164 1,000 llafnium 172 1 11olmium 166m 1 11afnit.m 173 1,000 lloimium 166 100 11afnium 175 100 llolmium 167 1,000 11afnium 177m 1,000 Erbium 161 1,000 11afnium 178m 0.1 Erbium 165 1,000 liafnium 179m 10 Erbium 169 100 11afnium 180m 1,000 Erbium.171 106 Ilafnium 181 10 Erbium-l72 100 llafnium 182m 1,000 Thulium 162 1,000 llafnium 182 0.1 Thulium 166 100 11afnium 183 1,000 Thulium 167 100 11afnium 184 100 Thulium 170 10 Tantalum 172 1,000 Thulium 171 10 Tantalum 173 1,000 Thulium 172 100 Tantalum 174 1,000 i Thulium 173 100 Tantalum 175 1,000 Thulium 175 1,000 Tantalum 176 100 Ytterbium 162 1,000 Tantalum 177 1,000 Ytterbium 166 100 Tantalum 178 - 1,000 Ytterbium 167 -1,000 Tantalum 179 100 Ytterbium 169 - 100 Tantalum 180m 1,000 Ytterbium 175 - 100 Tantalum 180 100 Ytterbium 177 1,000 Tantalum 182m 1,000 1-

• ) See est'lanothno at coulof thus hstuog U To cannrrt pt's to 199q. muhoply the 4 's wlue by 31.

t 4 D109H3

M*R l'olume I,loigust IVVilkaft Appenanc

• OU ANTITIES* OF LICENSED OfGLCatSTERED MATERIAL REOUlklNG LABELING i

(In Atomic Number Order) fi'onttnuedl i Radionuclide Quantity Radionuclide Quantity arcit - (rci? Tantalum 182 10 Iridium 185 1,000 l Tantalum 183 100 Iridium 186 100 Tantalum 184 100 Iridium 187 1,000 Tantalum 185 1,000 . iridium 188 100 Tantalum 186 1,000 Iridium IS9 100 Tungsten 176 1,000 Iridium 190m 1,000 Tungsten.I77 1,000 Iridium 190 100 Tungsten 178 1,000 Iridium 192m (1.4 min) 10 Tungsten 179 1,000 Iridium 192 (73.8 d) 1 l Tungsten 181 1,000 indium 194m 10 - Tungsten 185 100 Iridium 194 100 Tungsten 187 100 Iridium 195m 1,000 1 Tungsten 188 10 Iridium 195 1,000 Rhenium 177 1,000 Platinum 186 1,000 Rhenium 178 1,000 Platinum 188 100 Rhenium 181 1,000 Platinum 189 1,000 Rhenium 182 (12.7 h) 1,000 Platinum 191 100 Rhenium 182 (64.0 h) 100 Platinum 193m 100 Rhenium 184m 10 Platinum 193 1,000 Rhenium 184 100 Platinam 195m 100 Rhenium 180m 10 Platinum 197m 1,000 - Rhenium 186 100 Platinum 197 100 Rhenium.I87 1,000 Platinum 199 1,000 Rhenium I88m 1,000 Platinum 200 100 Rhenium-188 100 Gold 193 1,000 Rhenium 189 100 Gold 194 100 Osmium 180 1,000 Gold 195 10 Osmium 181 1,000 Gold 198m 100 Osmium 182 100 Gold 198 100 Osmium 185 100 Gold.199 100 Osmium 189m 1,000 Gold 200m 100 Osmium 191m 1,000 Gold 200-1,000 Osmium 191 100 Gold 201 1,000 Osmium 193 100 -hiercury 193m 100 Osmium 194 1 hiercury 193 1,000 Iridium l82 1,000 hiercury 194 1 Iridium 184 1,000 hiercury 195m 100- 'i See e.nplanatum at eralo(Ilus losturg. t 'i to 193. multiply tire g 'i value by 31. U Toetmverti 4 D110443 ..:,-~-,-,,-,---.--n-,- -r,--~.rm

---

n--

-nm-- - -.----------,,-,,---.,-,,e,+-n-----,.,,--mvarv,w-e .---rvv.,--,- ,,,,,+-w,r-------------- r ~,v-sv ++

h)pnin C .%RCR l'olume I 4urnt 1997 Draft OUANTITIES' 0F l.lCENSED OR REGl$TERED M ATERIAL REOtllRING LABELifiQ (In Atomic Number Order) Cumnisurd) Radionuclide Quantit) Radionuclide Quantity i iFCif (FCi)* Mercury 195 1,000 Bismuth 212 10 4 Mercury 197m 100 Bismuth 213 10 i Mercury 197 1,000 Bismuth 214 100 l Mercury 199m 1,000 Polonium 203 1,000 Mercury 203 100 Polonium 205 1,000 Thallium 194m 1,000 Polonium 207 1,000 Thallium 194 1,000 Polonium 210 0.1 Thallium 195 1,000 Astatine 207 100 Thallium 197 1,000 Astatine 211 10 ThcIlium 198m 1,000 Radon 220 1 Thallium 198 1,000 Radon 222 1 Thallium 199 1,000 Franclum 222 100 Thallium 201 1,000 Francium 223 100 Thallium 200 1,000 Radium 223 0.1 j l Thallium 202 100 Radium 224 0.1 Thallium 204 100 Radium 225 0.1 Lead 195tn I,000 Radium 226 0.1 Lead 198 1,000 Radium 227 1,000 { Lead 199 1,000 Radium 228 0.1 1 Lead 200 100 Actinium 224 1 Lead 201 1,000 Actinium 225 0.01 Lead 202m 1,000 Actinium 226 0.1 Lead 202 10 Actinium 227 0.001 Lead 203 1,000 Actinium 228 i Lead 205 100 Thorium 226 10 Lead 209 1,000 Thorium 227 0.01 Lead 210 0.01 Thorium 228 0.001 Lead 211 100 Thorium 229 0.001 Lead 212 1 Thorium 230 0.001 Lead 214 100 Thorium 231 100 Bismuth 200 1,000 Thorium 232 100 Bismuth 201 1,000 Thorium 234 10 Bismuth 202 1,000 Thorium natural 100 Bismuth 203 100 Protactinium 227 10 Bismuth 205 100 Protactinium 228 1 Bismuth 206 100 Protactinium 230 0.1 Bismuth 207 10 Protactinium 231 0,001 Bismuth 210m 0.1 Protactinium 232 1 Bismuth 210 i Protactinium 233 100

• ) See esplarmonuo al cad eftlus Intmg U To vsnowrt jn 't to Uiq. multiply the pi'i wlue by 37.

D1i1443

S%'R l'ulum 1.inpost iVV7 Drup App nda C r OUANTITIES* OF l.lCENSED OR REGISTERED MATERIAL REOUIRING LABELING (in Atomic Number Order) 3 d'entunurd) Radionuclide Quantity Radionuclide Quantity (FCif (FCif Protactinium 234 100 Americium 239 1,000 ) Uranium 230 0.01 Americium 240 100 Uranium 231 100 Americium 241 0.001 Uranium 232 0.001 Americium 242m 0.001 Uranium 233 0.001 Americium 242 10 Uranium 234 0.001 Americium 243 0.001 i Uranium 235 0.001 Americium 244m 100 Uranium 236 0.001 Americium 244 10 Uranium 237 100 Americium 245 1,000 Uranium 238 100 Americium 246m 1,000 Uranium 239 1,000 Americium 246 1,000 Uranium 240 100 Curium 238 100 Uranium natural 100 Curium 240 0.1 Neptunium 232 100 Curium 241 1 Neptunium 233 1,000 Curium 242 0.01 i Neptunium 234 100 Curium 243 0.001 Neptuniurn 235 100 Curium 244 0.001 Neptunium 236 (l.15E+5 y) 0.001 Curium 245 0.001 Neptunium 236 (22 5 h) 1 Curium 246 0.001 i Neptuniurn 237 0.001 Curium 247 0.001 Neptunium 238 10 Curium 248 0.001 Neptunium 239 100 Curium 249 1,000 Neptunium 240 1,000 Berkelium 245 100 Plutonium 234 10 Berkelium 246 100 Plutonium 235 1,000 Berkclium 247 0.001 Plutonium 230 0.001 Berkelium 249 0.1 Plutonium 237 100 Berkelium 250 10 Plutonium 238 0.001 Californium 244 100 Plutonium 239 0.001 Californium 246 1 Plutonium 240 0 001 Californium 248 0.01 Plutonium 241 0.01 Californium 249 0.001 Plutonium 242 0.001 Californium 250 0.001 Plutonium 243 1,000 Californium 251 0.001 Plutunium 244 0 001 Californium 252 0.001 Plutonium 245 100 Californium 253 0.1 Americium 237 1,000 Californium 254 0.001 Americium 238 100 Einsteinium 250 100

• ) See etrianatuur at rout of tlns hstuty U To nutters i s to Lisq. mulrople the i t value I,y 31.

t' t' D112142 -r. =w .w, ..,y..w.~ey#p.-.,w-.,e, -m., -,w--., ,-wrr, ,m._, =.-.......v...

l Anukla C .WR('R l'olume I..lugust 1991 Drqil OUANTITIES* OF LICENSED OR REGISTERED MATERIAL REQUIRING LABELING i l (In Atomic Number Order) tt'emtmurtil i Radionuclide. Quantity Radionuclide Quantity: i (FCif (FCif Einsteinium 25l 100 Einsteinium 253 0.1 i Einsteinium 254m i Einsteinium 254 0.01 l Fermium 252 1 Fermium 253 1 Fermium 254 10 Fermium 255 1 Fermium 257 0.01 j hiendelevium 257 10 hiendelevium 258 0.01 1 a i b

• ) See e.tplanatuur at coulof tins isstung.

U To coresvr1 pi's to LIIq. neultiply else it 't salue by 31 Dil343

SVRCit l'olume I..Ingust 1997 Drg/t Artendis C OUANTITIEg OF LICEN$ED OR REGl51 ERED MATERIAL REOUIRING LABELING (in Atomic Number Order) it'emtmurJ) Radionuclide Quanti 13 Radionuclide Quantity (FCif (FCif Any alpha emitting Any radionuclide radionuclide not other than alpha-listed above or emitting radionuclides mixtures of alpha not listed above, or emitters of unknown mixtures of beta - composition 0.001 emitters of unknown composition 0.01 .Vull;; For purp<nes af I) vo e.13 905a. mul ()1;Ola uhere there is involved a combination of rcahonucldes in knou anwonts. the huntfor the <umhmanon shall be JerneJ asfollows: Jeternune,for each raJwnuehJe m the combmanon, Ihr r between the quannte present m the combmatwa arkt the hmtt otherutse establishedfor the specific ralwnuchJe uhen no comhmalmn 1he sum ol sm h ranos for all rahonnchdes m the combmatwn snar not escred "I"- that is, ump..

• 1he quantmes hsted above uere derned by talmg i 10th of the most restracane All hsted m Table I. Columns I wJ 2 Apperulir il to l' art I), rounding to the necorestfatIor of10. inut constraming the svlues Itsted betu een 37 Bq cosJ 31 mkl I,000 M'll. l'alues of) l.tllly t100 R'il hint been afslyneJ}or rahonuchdes h0Vmg Q rallvaCltre h0![hfe in etcess of E + 9 years, escept Ihennnn. 37.t thy t1.000 M 'n. to take onto account their lou spectfic activin.
• To comvrt M *t to Anq. mukople the H't sulue by 31.

D114144 . a

Arlmta t) .%RCR l'olume i. 4ugun I997 Dmfl PART D i APPENDIN D j REOlllREM ENTS FOR TRANSFER OF l.OW l.EVEL RADIOACTIVE WASTE FOR DISPOSAL, AT l AND DISPOSAL, FACil ITIES AND M ANIFESTS 1 J Section 1. Manifest.. The shipment manifest shall contain the name, address, and telephone number of the person generating the waste. The manifest shall also include the name, eddress, and telephone number or the name and the 1 1 Environmental Protection Agency hazardous waste idemiGeation number of the person transporting the waste to the land disposal facility. The manifest shah ;w indicate: a physical description of the waste, the volume, radionuclide identity and quantity, the total radioactivity, and the principal chemical form. The solidi 0 cation agent shall be specified Waste containing more than 0.1 percent chelating agents by weight shall be identified and the weight percentage of the chelating agent estimated, Wastes classi0cd as Class A, Class 11, or Class C in Section I of Appendix E shall be clearly identitled as such in the manifest. The total quantity of the radionuclides hydrogen 4, carbon 14, technetium 99, and iodine 129 shall be shown The manifest required by this paragraph may be shipping papers used to meet the Department of Transportation or the Environmental Protection Agency regulations or requirements of the receiver, provided all the required information is included. Copics of manifests required by this section may bc legible carbon copies or legible photocopics. Eegtion ll CeningaMan. The waste generator shallinclude in the shipment manifest a certi0 cation that the transported materials are properly classined, described, packaged, marked, and labeled and are in propt condition for transportation according to the applicable regulations of the Department of Transportation and the Agency. An authorized representative of the waste generator shall sign and date the manifest. Ststion 111 - Control and Traghing. I (a) Any radioactive waste generator who transfers radioactive waste to a land disposal facility or a licensed waste collector shall comply with the requirements in (a)(1) through (8). Any radioactive waste generatoi who transfers waste to a licensed waste processor who treats or repackages waste shall comply with the requirements of(a)(4) through (8). A licensee shall: (1) Prepare all wastes so that the waste is classified according to Section I of Appendix E and meets the waste characteristics requirements in Section 11 of Appendix E; (2) Label each package of waste to identify whether it is Class A waste, Class B waste, or Class C waste, in accordance with Section I of Appendix E; (3) Conduct a quality control program to ensure compliance with Section I and 11 of Appendix E; the program shall include management evaluation of audits; Dll54+7 .~

~ _ _ _.. .%k('M iislaw I..tugua lHP Unp At,rnda D (4) Prepare shipping manifests to meet the requirements of Section I and 11; (5) Forward a copy of the manifest to the intended recipient, at the time of shipment, or deliver to a collector at the time the waste is collected, obtaining acknowledgment of receipt in the form of a signed copy of the manifest or equivalent documentation from the collector; (6) Include one copy of the manifest with the shipment; Retain a copy of the manifest and documentation of acknowledgment of receipt a (7) record of transfer oflicensed material as required by C.40 of these regulations; and (8) For any shipments or any portion of a shipment for which acknowledgment of receipt has not been received within the times set forth in this section, conduct an investigation in accordance with Section Ill.(e). (b) Any waste collector licensee who handles only prepackaged waste shall: (1) Acknowledge receipt of the waste from the generator within I week of rece.pt by retuming a signed copy of the manifest or equivalent documentation; (2) Prepare a new manifest to re0cct consolidated shipments; the new manifest shall serve as a listing or index for the deta; led generator manifests. Copies of the generator manifests shall be a part of the new manifest. The waste collector may prepare a new manifest without attaching the generator manifests, provided the new manifest contains for each - package the information specified in Section 1. The collector licensee shall certify that nothing has been done to the waste that would invalidate the generator's certification; (3) Forward a copy of the new manifest to the land disposal facility operator at the time of thipment; (4) include the new manifest with the shipment to the disposal site; (5) Retain a copy of the manifest and documentation of acknowledgement of receipt as the record of transfer oflicensed material as required by C.40 of these regulations, and retain information from generator manifest until the license is terminated and disposition is authorized by the Agency; and (6) For any shipments or any portion of a shipment for which acknowledgement of receipt is not received within the times set forth in this section, conduct an investigation in -accordance with Section Ill.(e). (c) Any licensed waste processor who treats or repackagus wastes shall: Dil6He

Anuda D SSRCR l'olume I.Jupat I99? thqtt (1) Acknowledge receipt of the waste from the generator within I week of receipt by returning a signed copy of the manifest or equivalent documentation; (2) Prepare a new manifest that meets the requirements of Section I and 11. Preparation of the new manifest reflects that the processor is responsible for the waste; (3) prepare all wastes so that the waste is classified according to Section I of Appendix E and meets the waste characteristics requirements in Section 11 of Appendix E; (4) Label each package of waste to identify whether it is Class A waste, Class B waste, or Class C waste, in accordance with Section I and ill of Appendix E; (5) Conduct a quality. control program to ensure compliance with Section I and 11 of Appendix E. The program shallinclude management evaluat on of cudits; i (6) Forward a copy of the new manifest to the disposal site operator or waste collector at the time of shipment, or deliver to a collector at the time the waste is collected, obtaining acknowledgement of receipt in the form of a signed copy of the manifest or equivalent documentation by the collector, (7) include the new manifest with the shipment; (8) Retain copics of original mdnifests and new manifests and documentation of acknowledgement of receipt as the record of transfer oflicensed material required by C.40 of these regulations, and (9) For any shipment or portion of a shipment for which acknowledgement is not received within the times set forth in this section, conduct an invert ation in accordance @h g Section 111(c) (d) The land disposal facility operator shall: (1) Acknowledge receipt of the waste within I week of receirt by returning a signed copy of the manifest or equivalent documentation to the shipper. T he shipper to be notified is the licensee who last possessed the waste and transferred the waste to the operator. The returned copy of the manifest or equivalent documentation shallindicate any discrepancies between materials listed on the manifest and materials received; (2) Maintain copics of all completed manifests or equivalent documentation until the Agency authorires their disposition; and (3) Notify the shipper, that is, the generator, the collector, or processor, and the Agency when any shipment or portion of a shipment has not arrived within 60 days afler the advance manifest was received. D 11744-7

SWR lWuw I..Ingust IVV11) raft Ansnda t) (e) Any shipment or ponion of a shipment for which acknowledgement is not received within the times set fonh in this section shall: (1) lle investigated by the shipper if the shipper has not received noti 0 cation or receipt wil 20 days aner transfer; and (2) De traced and reported to whom. The investigation shall include tracing the shipment and Gling a repon with the Agency. Each licensee who conducts a trace investigation shall file a written repon with the Agency within 2 weeks of completion of the investigation. i Dil8448

Anahn it .%RCR l'olum I..lugust IV91I) tall PART D l APPENDIXE l Cl,ASSlFICATION AND CH ARACTERISTICS OF 1,0W.I.EVEl, l RADIOACTIVE WASTE Section I. CimiRSAtlon of Radioactive Waste forland Disposal (a) Comidnalipnt Determination of the classification of radioactive waste involves two considerations. First, consideration must be given to the concentration oflong lived radionuclides (and their shorter lived precursors) whose potential hazard will persist long after such precautions t as institutional controls, improved waste form, and deeper disposal have ceased to be effective. These precav' ions delay the time when long lived radionuclides could cause exposures. In addition, the magnitude of the potential dose is limited by the concentration and availability of1: e radionuclide at the tirne of esposure. Second, consideration must be given to the concentiation of shorter. lived radionuclides for which requirements on instituttor.al controls, waste form, and disposal methods are elTective (b) Claunshutitt (1) Class A waste is waste that is usuall) segregated from othei waste classes at the disposal site. The physical form and characteris'ics of Class A v.aste must meet the minimum requirements set fonh in Section ll.(a). If Class A waste also meets the stability require. ments set forth in Section 11 (b), it is not necessary to segregate the waste for disposal. (2) Class B waste is waste that must meet more rigorous requirements on waste form to ensure stability after disposal. The physical form and characteristics of Class B waste must meet both the minimum and stability requirements set forth in Section II. l (3) Class C waste is waste that not only must meet more rigorous requirements on waste form to ensure stability but also requires additional measures at the disposal facility to protect against inadvertent intrusion The physical form and characteristics of Class C waste must meet both the minimum and stability requirements set forth in Section 11. (c) CJianiftration dstermined by lonu. lived _ adionuclides, if the radioactive waste contains only r radionuclides listed in Table IV, classification shall be determined as follows: (1) If the concentration does rot exceed 01 times the value in Table IV, the waste is Class A. (2) If the concentration exceeds 0.1 times the value in Table IV, but does not exceed the value in Table IV, the waste is Class C. 1 (3) If the concentration exceeds the value in Table IV, the waste is not generally acceptable for land disposal. l D11918

.%Rt 'R l'ohme i..tugust IVV1I)rqft Apgeth E* (4) For wastes containing mixtures of radionuclides listed in Table IV, the total concentration

• shall be determined by the sum of fractions rule described la Section 1.(g).

TABLEIV Concentration Radionuclide Curie / Cubic Meter 8 Nanocurie/Gramb C 14 8 C.14 in activated metal 80 Ni 59 in activated metal 220 Nb 94 in activated metal 0.2 Tc 99 3 1129 0.08 Alpha emitting transuranic radionuclides with half. life greater than five 100 years Pu 241 3,500 Cm 242 20,000 100 Ra 226

• 10 corn ert the t's m' values to gigabecquerel(GBq)per cubic nwter, multiply the Ct m' value by 37.

I 1c converI the nt 's y values to becquerel (Bq)per gram muitopiv the n('t g value by 37, d) flaniQgation determined by short lived radionuclides if the waste does r 1 contain any of the radionuclides listed in Table IV, classification shall be determined based o se concentrations shown in Table V. Ilowever, as specified in Section 1.(f), if radioactive waste does not con:ain any nuchdes listed in either Table IV or V,it is Class A. 1) If the concentration does not exceed the value in Column 1, the waste is Class A. 2) If the concentration exceeds the value in Column 1 but does not exceed the value in Column 2, the waste is Class D. 3) If the concentration exceeds the value in Column 2 but does not exceed the value in Column 3, the waste is Class C. 4) If the concentration exceeds the value in Column 3, the waste is not generally acceptable for near surface disposal. D129M2

Agy:tulk li SSRCR l'olune I.lugust I997 Dra)1 5) For wastes containing mixtures of the radionuclides listed in Table V, the total concentration shall be determined by the sum of fractions rule described in Section 1.(g). TABLE V Radionuclide Concentration Curie / Cubic Meter

• Column 1 Column 2 Column 3 Total of all radio-nuc! ides with less than 5-year half-life 700 H-3 40 Co-60 700 Ni 63 3.5 70 700 Ni-63 in activated metal 35 700 7000 Sr-90 0.04 150 7000 Cs-137 1

44 4600

• lGlaiT Nullo To convert the Ci m' value to gigabecquerel(GBq) per cubic meter, muktply the C m' value by 37. There are no hun.s estabhshedfor these rahamoclides m Class B or C wastes. Practical ccmstJeratums such as the effects of external rahanon and unternal heat generation on traitsportation, handhng, andshsposal will knut the comentranonsfor these wastes. These wastes shallbe Class B unless the concentranons of other rauhonnchJes on Table l'Jeternune the naste to be Class C indepenJent of these rinhonischsles.

(e) Classi6 cation determined by both lone-and short-lived radionuclides. If the radioactive waste contains a mixture of radionuclides, some of which are listed in Table IV and some of which are listed in Table V, classification shall be determined as follows: (1) If the concentration of a radionuclide listed in Table IV is less than 0.1 times the value listed in Table IV, the class shall be that determined by the concentration of radionuclides listed in Table V. (2) If the concentration of a radionuclide listed in Table IV exceeds 0.1 times the value listed in Table IV, but does not exceed the value in Table IV, the waste shall be Class C, provided the concentration of radionu:lides listed in Table V does no exceed the value shown in Column 3 of Table V. (f) Eassi6 cation of wastes with radionuclides other than those list;d in Tables IV and V. If the waste does not contain any radionuclides listed in either Table IV or V, it is Class A. D121G3

.M 'R l'olume I.. lugust 1997 I)enf Ap;enda1: (g) The sum of the factions rule for mixtures of radionuclides. For determining classification for, waste that contains a mixture of radionuclides, it is necessary to determine the sum of fractions by dividing each radionuclide's concentration by the appropriate limit and adding the resulting valucs. The appropriate limits must all be taken from the same column of the same table. The sum of the fractions for the column must be less than 1.0 if the waste class is to be determined by that column. Example. A waste contains Sr 90 in a concentration of 1.85 TBq/m' (50 Ci/m') and Cs-137 in a concentration of 814 GBq/m' (22 Ci/m'). Since the concentrations both exceed the values in Column 1, Table V, they must be compared to Column 2 values. For Sr 90 fraction, 50/150 = 0.33, for Cs-137 fraction, 22/44 = 0.5; the sum of the fractions = 0.83. Since the sum is less than 1.0, the waste is Class B. (h) Determination of concentrations in wastes The concentration of a radionuclide may be determined by Md' ect methods such as use of scaling factors which relate the inferred concentration af i ne radicauclide to another that is measured, or radionuclide material accountability, f we is reasonat.e assurance that the indirect methods can be correlated with actual measurements The concentration of a radionuclide may be averaged over the volume of the waste, or weight of the waste if the units are expressed as becquerel (nanocurie) per gram. Section 11 Radioactive Waste Characteristics (a) The following are minimum requirements for all classes of waste and are intended to facilitate handling and provide protection of health and safety of personnel at the disposal site. (1) Wastes saall be packaged in conformance with the conditions of the license issued to the site operator to which the waste will be shipped. Where the conditions of the site license are more restrictive than the provisions of Part D, the site license conditions shall govern. (2) Wastes shall not be packaged for disposalin cardboard or fiberboard boxes. (3) Liquid waste shall be packaged in sutTicient absorbent material to absorb twice the volume of the liquid. (4) Solid waste containing liquid shall coatain as little free-standing and non-corrosive liquid as is remnably achievable, but in no case shall the liquid exceed I percent of the volume. (5) Waste shall not be readily capable of detonation or of explosive decomposition or reaction at normal pressures and temperatures, or of explosive reaction with water. (6) Waste shall not contain, or be capable of generating, quantities of toxic gases, vapors, or fumes harmful to persons transporting, handling, or disposing of the waste. This does not apply to radioactive gaseous waste packaged in accordance with Section II.(a)(8). (7) Waste must not be pyrophoric. Pyrophoric materials contained in wastes shall be tieated, prepared and packaged to be nonflammable."2 &c., \\ A of the.se regulatwnsfo: depmtwn ofpyrophonc matenal. D122G2

. _ _ _... _ _. _. _. _ _ ~ _. r hrrakh Ii SSRCR l'olume i..iugunt i997 Drap 8) Wastes in a gaseous form shall be packaged at an absolute pressure that does not exceed 1.5 atmospheres at 20EC. Total activity shall not exceed 3.7 TBq (100 Ci) per container. 9) - Wastes containing hazardous, biological, pathogenic, or infectious material shall be treated to reduce to the maximum extent practicable the potential hazard from the non-radiological materials. b) The following requirements are intended to provide stability of the waste. Stability is intended to ensure that the waste does not degrade and affect overal1 stability of the site through slumping, collapse, or other failure of the disposal unit and thereby lead to water infiltration. Stability is also a factor in limiting exposure to an inadvertent intruder, since it provides a recognizable and nondispersible waste. 1) Waste shall have structural stability. A structurally stable waste form will generally maintain its physical dimensions and its form, under the expected disposal conditions such as weight of overburden and compaction equipment, the presence of moisture, and microbial activity, and internal factors such as radiation effects and chemical changes. Structural stability can be provided by the waste form itself, processing the waste to a stable form, or placing the waste in a disposal container or structure that provides stability i afler disposal. 2) Notwithstanding the provisions in Section ll.(a)(3) and (4), liquid wastes, or wastes containing liquid, shall be converted into a form that contains as little free standing and non-corrosive liquid as is reasonably achievable, but in no case shall the liquid exceed 1 percent of the volume of the waste when the waste is in a disposal container designed to ensure stability, or 0.5 percent of the volume of the waste for waste processed to a stable form. 3) Void spaces within the waste and between the waste and its package shall be reduced to j the extent practicable. Section 111. - Labeline. Each package of waste shall be clearly labeled to identify whether it is Class A, Class B, or Class C waste, in accordance with Section 1. t 4 - D123 6

SSRCR \\blumeI.tugust 1901 Draft Appendis F* lPART D - APPENDIX F OllANTITIES FOR LISE WITH DECOMMISSIONING' . Material Microcurie' Americium 241 - 0.01 - Antimony-122 100 Antimony 124 10 10 Antimony-125 Arsenic-73 100 Arsenic 74 10 Arsenic 76 10 Arsenic 77 100 Barium 131 10 Barium-133 10 Barium 140 10 ' Bismuth 210 1 Bromine 82 10-Cadmium 109 10 Cadmium 115m 10-Cadmium 115 100 Calcium-45 10 Calcium-47 10 Carbon-14 100 Cerium-141 100 Cerium-143 100 Cerium-144 i Cesium 131 1,000 Cesium-134m 100 - Cesium-134 1 Cesium 135 10 Lesium-136 10 Cesium-137 10 Chlorine 36 10 Chlorine 38 10 Chromium-51 1,000 Cobalt 58m 10 Cobalt-58 10

• 11n.s.Ipremhr n retamedfor nse by d:sse.lgrerment States that needto adopt decommissiomng regulations compatible with the Nuclear RegulatoryComnussion.

W To conwrt pri to Llig, multiply the pc's value by 37. D124M8

.? A p:ndis I: %RCR l'olume i vlugust 1997 Drap T l 0 OllANTITIES FOR USE WITH DECOMMISSIONING * (Confimted) Material Microcurie' Cobalt 60 1 Copper-64 100 Dysprosium-165 10 Dysprosium-166 100 Erbium 169 100 Erbium 171 100 Europium 152 (9.2 h) 100 Europium 152 (13 yr) 1 Europium 154 .I Europium 155 10: Florine 18 1,000 Gadolinium 153 10 I Gadolinium 159 100 Gallium-72 10 Germanium 71 0 Ilafnium 181 10 4 lioimium-166 100 Hydrogen-3 1,000 Indium-Il3m 100 indium-114m 10 Indium 115m 100 Indium-115 10 lodine-125 1 lodine 126 1 lodine-129 0.1 lodine-13 I 1 L lodine-132 10 _ lodine-133 1 lodine 134 10 lodine-135 10 Iridium-192 10 Iridium 194 100 . Iron-55 100 ' 1ron 10 . Krypton 85 100 - Krypton 87-10-Lanthanum-140-10

• This. typehbr at retamedfor use by those,lgreement states that needto alopt decomunssionmg regulanons compatible with the Nuclear RegidatoryComunsswn.

W Tu conwrt pri to Lily, mnhipir the pro value by 37, D125129

MRl'R l'ohone i.. lugust IVV71) raft AgynbsV ' Oll ANTITIES FOR llSE WITil DECOMMISSIONING' (Conliinted) Microcurie" Material 100 Lutetium-177 10 Manganese 52 10 Manganese-54 10 Manganese-56 100 Mercury 197m 100 Mercury 197 10 Mercury-203 100 Molybdenum-99 100 Neodymium-147 100 Neodymium-149 100 Nickel 59 10 Nickel-63 100 Nickelv5 10 Niobium 93m 10 Niobium-95 10 Niobium-97 10 Osmium 185 100 Osmiur 191m 100 Osmium-191 100 Osmium-193 100 Palladium-103 100 Palladium 109 10 Phosphorus 32 100 Platinum-191 100 ~ Platinum 193m 100 Platinum 193 100 Platinum-195m 100 Platinum-197 0,01 Plutonium-239 0.1 Polonium-210 10 Potassium-42 100 Praseodymium-142 100 Praseodymium-143 10 Promethium-147 10 Promethium-149 0.01 Radium-226 100 Rhenium 186 1hus,Iprenshs as relauredfor use by those.lgreement States that need to alopt decommessoomng regulatrons compatible wuth W the Nuclear Regulatory Commiwon. W To conwrt pri to Lily, multiply the p('i value by 37. Dl26M8

S AFTendm V SSRCR l'olume i August 1997 Drap OllANTITIES FOR llSE WITH DECOMMISSIONING' (C< unimed) - Material Microcuric" Rhenium 188 100 Rhodium-103m 100-Rhodium 105. 100 Rubidium 86 : 10 Rubidium 87 10 Ruthenium 97 100 Ruthenium 103 10 Ruthenium 105 10 Ruthenium 106 1 Samarium-151 10 Samarium 153 100 Scandium-46 10

Scandium-47 100.

Scandium 48 10 Selenium 75 10 -Silicon-31 100 Silver 105 10 F" rer-1 IOm 1 ... er-1 1 1 100 Sodium-22 i Sodium-24 10 Sirontium-85 10 Strontium-89 1 Strontium 90 0.1 Strontium-91 10 Strontium-92 10 Sulfur -35 100 Tantalum 182 10 __ Technetium-96 10 Technetium-97m 100 Technetium-97 100 Technetium 99m 100- - Technetium 99 10 Tellurium-125m 10 Tellurium-127m 10 Tellurium 127 10 Tellurium-129m m

• ' This spresults Is ret:~sestfor use by those Agreensent States that need to alopt decomnusswning regulations comp with the Nuclear Regulatory l'ommis sion.

W To conwrt it 'l to ally. muluply the pri value by 37. -.. Dl37W

.WRt'R l'olune I.. iugu et I997 I)ruft Appendsx V ' OllANTITIES FOR USE WITH DECOMMISSIONING * (Continued) Material Microcurie' Tellurium-129 100 Tellurium-131m 10 Tellurium !32 10-Terbium 160 10 Thallium 200 100 Thallium'201 100 Thallium 202 100 Thallium 204 10 Thorium (natural)S 100 Thulium 170 10 Thulium 171 10 Tin-l l3 - 10 -l Tin-125 10 10 Tungsten-181 10 Tungsten 185 - 100 Tungsten 187 Uranium (natural)4 100 Uranium 233 0.01 0.01 Uranium 234 Uranium-235 0.01 Vanadium-48 10 i l Xenon 131m 1,000 Xenon-133 100 100 Xenon 135 Ytterbium 175 100 Yttrium-90 10 Yttrium-91 10 Yttrium-92 100 Yttrium-93 100 Zinc-65 10 Zinc-69m 100 Zinc 69 1,000 Zirconium 93 10 Zirconium-95 10 Zirconium-97 10

• 1his. \\ppenshr is retantedfor use by those ilgreement States that need to adopt decommsssionmg regulations compatible with 6te Nuclear Regadatmy t 'onunis soon, W To conwrtit'i to Aliq. multiph the I 'i value by 37.

A Basedon alpha desmtegranon rate of Th-232. Th-230 amitheir daughterproducts. i ga,,g,,,j g,y,,,,,,,,,,,,,,,,,y g,yyg, y,yy,,,g y_yy3, p D128428 i

s [ App:ndnx t' SSRCR l'olume I. August 1997 Drap OUANTITIES FOR USE WITH DECOMMISSIONING * (Cr>nlimted) Material Microcurie' Anfalpha emitting . radionuclide not listed above or mixtures of alpha emitters of unknoivn composition 0.01 Any radionuclide other. than alpha emitting radionuclides, not listed above or mixtures of beta emitters of unknown composition 0.1 NOTE;Where there is involved a combination.of isotopes in known amounts, the limit for the combination should be derived as follows: Determine, for each isotope in the combination, the ratio between the quantity present in the combination and the limit otherwise established for tne specific isotope when not in combination. The sum of such ratios for all the isotopes in the - combination may not exceed "1" -- tht.i is, unity.]- 0

• Ila,. lpperuhr os retamedfor use by those lgreement States that need to adopt decommissiomng regulanons compatsble with the Nuclear Regadatory Commis.ston.

W To wnwrt pCi to Lily, omdtsply the pri value by 37. ___M29M9 _ _ _ _ _ _ _ _ _ _ _ _

SWR l*vlume I.tugust 1997 Ikall Appenda G i PART D IAPPENDLX G REOUIREMENTS FOlCfjlANSFERS OF LOW-1 EVFl> RADIOACTIVE WASTE INTENDED FOR DISPOSAL AT I IfENSED LAND DISPOSAL FACII ITIES AND MANIFESTS SsctionJ - Maoifen A waste generator, collector, or processor.who transports._ otoffers.for_ transportation.Jow-Jeyel radioactive waste intended for ultimate disposal at a. licensed. low-level. radioactive _ waste land. disposal facility.must prepare a ManifesLreflectinginfatmanolutquultd olapplisabic [NRC Entms 540] Asto.cy o Ectms.[ insert appropriate number] (Uniform LcmLcycl.Radioactirc Waste hianifest1 Shipping.fapst)) and[ 541] (Uniform Low Level Radioactive Wastelianifest.(Container.and Waste Description)).andjf necessary, on an applicable [NRC Form 542). Agency. Form { insert appropriate number] (Uniform Low: Level. Radioactive Waste Manifest _(ManifestjndetandlegionaLCompacLTabulatian)1 iNRC_Earms M0.and..S0A] Agency _Eorms_[inserLappinpriate numbetsl_.must_bs completed and muSLphysically accompany the pertinent low level radioactive waste shipment, Upon agreementbetween shipper _and consignee, [NRC Forms 541 and 541 A and 542 and 542A] Agency Forms { insert appropriate numbers] may be completed, transmitted,.and storedjrtelectronic_mediamithJhe.sapability_fatptoducintlegibJL accurate..and complete. records _onahe_respsctiys fonns_Licensecs aIc noltcQuited hy the Agency _to comply with the manifesting regiiirements of this Part when they_ ship; (a) LLW for processing.and.expecLits.I.eturn (iAlQts10Lage undcLtheirjicenscl.priRLtQ..dispp. sal at a licensed land disposal. facility; (b) LLW that is being returned to the licensee who is the " waste generator" ' generator.".as defmed in this Part or (c) Radioactivity contaminated material to a " waste processor".that.becomes the processor's. residual waste. Ectguidance_in_ completing.these forms..refetto the_insttustionLthaLaccompany 1he_ forms. Copietof manifests required by this appendix may be legible carbon.copics..photocopics..otcomputer printouls that reproduce the data in the format of the uniform manifest. Agency..Eorms [ insert appropriate _ number 5] and the_.attempanyinginstructions. in hard copy, may be obtained from [ insert name and address). This. appendix. includes information.r.equirsoteniLolth.c]spatimenLnf_Ir30.spo.nalian._atsndifitd_la 4.2 CER Part 172 information..on_ hazardous._medicaLor other waste requiIsd to me t Environmental Protection Agency regulations, as codified.in.40.CER_ Paris.219. 26Lotelsewhetc.js_noLaddressedj0 this section, and must be provided on the required EPA _ forms..However. the required.EPAforms must ascomparty. he Uniform Lo.w Level.lhdionclixs Wasts 3Janifc:1.by_thit.ssstion. t Dl3090

l AnxndMi SSkCR Iblume i. lugust I997 Drall As.used.in this appendix the.following.definitiontapply; " Chelating agent" has the same meaning as that gisen in Part A.2. " Chemical.Jescription".means.a_desstiption of the principal chemisaLcharacteristics of.a. lone'ere] radioactivi: waste. " cob 1puterreadab]C medium" mpans. that the regulalgfy_agensy's _ computer can trans{er the iDfoImaliQtLIDm_the.mcjigm into its memgIy, " Consignee" means tLe designated receiver of the shipment oilow-level radioactive _ waste. "Decentaminai!on.facdity"_mcatu.a. facility ogerating under an Agency. U S. Nucitadegulaloly Commission, Agreement State or Licensing State. license _whose principal._ purpose _is decontamination of ec,uipment or materials _to_ accomplish _ recycle,_ reuse,_or.cther_weste management.objectiyo,.and...f01.p.urpoleLof_thil.PaELjs_n9LC901idcr.td to be a_cnnsignes_for LLW_ shipments. " Disposal container" means a container principally _used.to.. confine low-level radioactive _ waste d.uting Aisposal. operations.aLa land..disposalfacility f.also_see "higitintegrJ!y conigi_0er") Note that forsome. shipments, theJisposalcontaintclnay_bs theAmspon. package. " EPA identifcation number" means the number received by.a transporter.following application _to theAdministrator of EPA as.tequired_byRGRhtL261 " Generator" means a licensee operating undetan Agency..U S NucleatRegulatory_ Commission or Agreement State license who (1) it a waste generator as.defmed.in this part,_or.(2) is.the licensee to.whom waste can.be attributsd withituheggntest of th.giqw-Lsycl Radi.onctixc.lyasig P.olicyAmendmen' AcLofRSi(e4JAsle.SeneIaled as A.Lesult of drECDiamination or recycle activities). _.."High integrity _ container (HIC)".rnianta. contajnet.19mm9nly dsligned to meet the3ntc.tuta] stability _requitemerds_.ollpgendiy E. Section 11 of Part D. and to meet Degaumcal 0f Transportation requirements for a Type A package, " Land disposal facility" has the same_rnea0!Dg.AS_tbalgiXfn.in.Part AJ " Package" means the assembly of components necessary to. ensure compliance with_the packaging requirements of DOT regulations, together..with_its radioactive. contents. as_ presented _for transpo.rt. " Physical description" means the items cal!cd fotonlNRC. Form 54l} Agency.F.0tm [inscrl fotm number] to describe a low-level radioactive waste. D13149

S%RCR l'olume I..lugust 1997 I) raft Appendm G * "Besidualwaste"_means_lelcrel. radioactive waste resulting from orocessing or decontamination, activities that cannot be easily separated _into. distinct._ batches _ attributable._to._ specific _ waste generators. This waste is attributable.to the processor..or decontamination facility as applicable, " Shipper".means_the licensed entity _(i.e, the waste senstator. waste _ collector. or waste processor) who ofTers low level radioactlyc_ waste for.ttansportation. typically.Sonsigning this type of waste to a licensed waste collector, waste processor..or. land disposalfacility. operator. " Shipping paper" means [NRC.Eorm140 and. if reouited. NRC Form 540A] AgencyJorm [ insert form rumber) and, if required Agency Form [insenform number]which. includes.the_information rtquirca by DOT in 49 CFR Part 172, " Source. material"_has_the_same.meanmgas_that gnenin_Sec.A2 of Part A. " Uniform Low-Level Radioactive. Waste _ Manifest"..or_A " Uniform _ Manifest".means_the combination _of [NRC Forrnsl4A_ML and.lf_nss.cisary. 542L68ency Forms [ insert form numbets}. and_if_necessaty._{inseILform number]. and their resp.ectire continuation shecti_as needed, or equivalent. " Waste _collecto.r".means an atitymopsraling _undri._an Agency, U.S. b'ugicatlegulatory Commission.. Agreement 3 tate._ot. Licensing State license. whose principalpurpose.ls_to collect and consolidate waste generated by_others..and to_ transfer _this_ waste._without.. processing.or repackaging the collected waste, to another licensed waste collector, licensed waste processor..or licensed. land dispo. sal facility. " Waste description" means the physical,_chemicaLand_radiologicaldescription_of_a_lomlevel radioactive waste as called for on [NRC Form 541} Agency Form (insert form numberl ____" Waste _ generator" means_an_ entity.__ operating undet._an Agency: U S. _NucleaLRegulatory Commission, Agreement State, or Licensing State. license,aho..(l). possesses _any_materiaLor component that contains radioactivity or.is..radioactlycly_contaminatedfor_which_the licensee forsees.no further use, and_(2)_transferLthitmatgrial or componsnt_Lo itlissnigsLland_ disp.91al facility.or.to a licensed wasteSolleclot.orptosessor for handling or tIralmtal. prior to disposal. A licensee performing processing or decontamination. seryices_may..be_a waste _generatot."if the transfer oflow level radioactive waste from its facility is defmed as.Aresidual waste " " Waste ptoressor" means__an_Intity._opstatiDg under an Agency. U S. Nuclear RegulatoIy Commission, Agreement State, or Licensing. State license, whose. principal. purpose _is_to ptocess, repackage, or otherwise treat low-level radioactive _ material.or_ waste generated..by.others prionto eyentual transfer _ of waste to a licsnsredlow-level radinagtive waste land disposal facility. " Waste t3: .neans a waste within a disposalcontainethaying a_ unique physicaldescriplian-(is. a specific waste descriptor code or description; or.a waste.. sorbed onStsolidified in.a specifically defined _ media), l l D132G0

-... ~ ..-~. - o-hpreth G MRCR l*olume i.Aupat I997 Draft ? INFORMATION REO'llRFMENTS i A._ General information Ihe_shippetof_the_ low:levelradioactivemaste, shall oroYide_the_follawing information on the uniform e i manifest; l 1.m _..Jhe_narne, facility add 1ess and_tglephonc_aumhe. r of tbe licentes_thipping the waste: 2. An explicit declaration indicting _whether_the,.shippet_is. acting _as_A_ waste _senerator, collector, processor, or a combination of.these idendfiers.fotpurposeLof_the_ manifested 4 shipment; an.d i 3. The name, address, arvi telephone number, or themame_and EPAidentificationJnumberfor the carrier transporting the vaste. IL_ Shipment.information The shipper of the radioactive waste shall provide the following information regarding the3vaste shipment oILihe unyonttmanifest 1. The date of the waste shipment; 2a Thelotalnumber.of. packages /disposalcontainen; 3, The total disposal volume and disposal. weight in the shipment. 4 T.he. total radionuclide activity in.the_ shipment, i 5. The activity of each of the radionuclides 113, C-14,Jc-99, and.1-129_ contained _in_the. shipment; and 6. The_ total masses _oflU-23LU-215.and_ plutonium.iILtheform of scecialnuclear material _and_the total mass of uranium and thorium in the form of. source material, j 'C,_ Disposal Container and Was.te info 1mation The shipper of the radioactive waste shall provide the following information on the uniform..tnanifest regarding the waste and each disposal container of waste in the shipment: L An_ alphabetic.or Jiumeric identification that uniquely _identiftes_each disoosal container in the -shipment; 1 A physical descriptiortof_thejispgsal container. including the manufac.tEer and model of.any high integrity _ container; DD33G9

.%Rt'R \\ *olume I.tupat 1997 Ikaft Arpendh G

• I 3.

Thesolume. displaced.by the disposaLco.ntainer; 4. The gross weight of the disposal container, including the waste, 1. Eotwaste_ consigned.to_a.disposaLfacility the maximutn.tadiationlersLatthe surface _oLeash disposal container; 6. A physical and. chemical.descripJion.9f.1hemas12. 7. The total weight percentage of chelating agenLfor.anylwaste.containing more thar1Al?&. helating c agent by weight, plus the identify of the principalchelating agent; 8 IhtapproximateSolumtof3vaste.withinA.containct. 9. The sorbing or solidification media, if any, and the identity of the solidification media vendor and brand name. 10 The identities and activities ofindividual radionuclides contained.in each. container..the.massetof U-233, U-235, and plutonium in the form of special nuclear material, and the masses of uranium and. thorium in the form of source _matsrial_.EcLdisstsic nEtc typsLRs actintedJ114terialt contaminated _ equipment._ _ mechanical _ filters._ sealed _sontcelderices._and wastes _ _a solidification / stabilization media), the_ identities _and activities of individual;adionuclides associated with a disposal container shall be reported, 1 L_The.tetal radioactivity within eachsontainet; and 12. For wastes consigned to a disposal facility, the classification of the waste pursuant to Appendix E. Ssqtiertl. sffart Om Wastc.not mes. ting thLsitusntralitability J.cquitsmentLof_Ap.nendiLE. Section ll(bLof Part D must be identified. D._Uncontainerized Waste information Ihe_shippetof the radioactive waste _shalLptmide the_following mfonnatiotto.n the_uniformJnani[ cit regarding a waste shipment delivered without a disposal container; L The_ approximate volume. an.dle.ighLef thelaitt; 2. A physical and chemical description of the waste; 3, The total weight percentage of chelating 3 gent.iflhelhelating. agent.sscsedLOJ %.byseight._plus the. identity _of.the principal. chelating. agent. 4. For waste consigned to a disposal facility, the classification oEthe. waste.pursuanLlo.AppenditE. Section_i_offart Q, Waste.noLmeeting_the_structur.alstability_Isauir.ements of Anoendix E. Section_ll(bloffarLD must be.identifted; D134MO

.--n. 4 . Appendidi SSRCR t'olumei 4upalI997Drap 5. The. identities.and. activities ofindividual radionuclides contained in the waste. the maues of U. 233, U-235, and plutonium in the form.of.specialnuclear. material and.thcanassesAfstanium.and thorium in the form of source material; and 6 Eatwastes_ consigned.to.a_disposaLfacility. the maximum radiation levels at the surface of the Waste. E._A1piti GencIntor msposal containetinfoImatioit. Thitsection_ applies to disposal containers _ enclosing _mistutetsfiaste_otiginating_ftom_different F generators. (Note: The origin of the LLW resulting.from a. processor's activities may.be, attributable.to nat_ntJnote." generators" (including "wastc_generalpis")_at_ defined in this Part) 11 also__ applicLig mixtutetof_wastet shipped _inJm_uncontaincriz.ed. form for which oortions of the mixtutc_Mithin_the j shipment originate from different generators. L Eothomogeneous_misturcLpf_xaste _s.uch_atincinstalar ash. crovide the wastg._dgSstipJioa applicable.to thejilixture and the_volutnemf_the_ waste.atitibuted_tosacitgenerator. 2. For heterogeneous mixtures of waste, such as the combined products from.a..large.. compactor, identify.cach generator contributing wasteJq1ht.disposalcontainct._and._foI.dissrs.te wastelynes (i.e. activated materials._ contaminated.sauipinent mcchanicaLfthers icated source / devices. and wastes in solidification / stabilization media), the identities and activities of.individualfadionuclides contained on these waste types within the_ disposal container._For each. generator, provide _the following (a) The volume of waste within the disposaLcontainet; (b) A physical and chemical.d.escriptin.rtofthcEasic..includingJheJ91idificalian. agent. if any: (c) The total weight percentage.of chelating. agents.for.any.. disposal.containetcontaininglnare i than 0.1% chelating agent by weight..plus the identity of the principalchelating agent; (d) The_sorbinger. solidiftcation_ media if any. anilhe identity of the solidification media vendor and brand name if the media is claimed to meet stability requirements.inAppendix E, Section ll(b) of Part D-; and (e) Radionuclide_ identities.and.activitics_ contained in the waste the masses of U-233. U-235. and plutonium in the form of.specialnucleatmaterial._and_the_ masses _of_.utaniuritand thorium in the form of source material if contained in the waste. Section.ll - Certification An authorizw representative of the waste generator, processor, or_ collector shallecctify by signing.And dating the shipment. man.ifest.that _the.transp.qttrimatfIiAltaic p-QPfIly_slassified. described. oackaged., marked and. labeled.and. ate _inproper_ condition for transoodation according to the applicable regulations of the Department of Transponation and the Agency._ A.collectotin. signing.theSertification.is cettifying .D035H9

.._ _ _. _ -~_.._..____._ _ _ _ _- MRCit ibhome I..lugust i997 I)ruft Appendh G i that_nothing_has.heertdone_to the collested waste which would invalidate the waste ceneratofs, i certification.. Sectjon_Ill:. Control and Tracking. As Any licensee who transfers radioactive. waste _to_ajand disposalfacility_otajicensed_ waste collector shall comply with the requirementsjalaragraphsA.Lthroughlof_this_Section Any licensee who transfers wastejo a ljEtnstd_WastC_pIQstslar for waste treatmcat.or repackaging _Qf ParagraphsAAthroughloDhis Section A licensee shall: 1. Prepare all wastes so that the waste.is classified.according to. Appendix E..Section.l and meets waste characteristic.s.IrguitsRicais_inAppendix Election !! of Part D: _2 Label each disposal container (or transport package if potentialradiationjiazardspreclude-labeling of the individual disposal container) of_ waste to.. identify _whether.itas. Class.A waste,_ Class B waste, Class C wastr._qt.gtcatsr than_ Class _C wa1Lc in_acs.qtdancs with 7 Appendix Ejection.LofTart.D; I Conduct a quality assurance program to. assure compliance with Appendix E, Section l. l 3. l And Section.lkof Pan _Dlthe_prestanunusijaciudemanagementcraluationsf_ audits 1 l Prepare the Agency Uniform Low-LevelRadioactive_ Waste Manifest as required by this l 4.

Appendix, di i

W .___L_Eorward_a_ copy..or elcctronically transfet.the_1.!nifamLLow-LereLRa oactre._ aste Manifest to the intended consignee sojhat.either_(i) receipt of_the_ manifest.precedesJhe LLW shipment or (ii) the manifest is delivered to the consignee.with.the. waste at the time the waste is transferrrd.t0Jhe_C.onsignee. Usine both (i) andfji)js_al.ss_arseplahlt 6. Include [NRC Form 540 (and.NRC From M0A, if required)] Agencylorm.(insert form number)(and Agency Form (insert form number),if required).with the shipment regardless of the option.in. Paragraph 21of this St.9. tion.. 7. Receive acknowledgement of.the.receiplofjhe.shipmentin_the forntof.a_signedSopy_.of (NRC Form 540] Agency Form (insert form. number); 8. Retain _a_ copy _of_otelectr.onically_stme the Uniform Low-Level Radioactive Waste Manifest and documentation of acknowledgement,of_ receipt as the. record ofaransfetof licensed material as required by Part C; and 9. EOLany_5hipments_or_any_part of a shioment for which acknowledgemenLof receipihas not been received within the. times..setforthjn.thisAppendix, conduct an.investigationin accordance with Paragraph E of.thisAppendix, O. Any_ Waste,collectQrjiccasce.Who_handjgs only Drepackaged waste shall: Dl36H0

.-- - - ~._- - -....~.. - - -. - - -.~- e.

h p:nda ti SSRCR Iblumei hgust I997I)taJl i

i e 1. .Schno.W} edge _.feceipLnfJhe waste from the thinner within one week of receipt by returning a signed copy _of[NRCformJi40] Agency.Eorm.(inscri.fonn number). _._ 2. Prepare.a new manifest.to.r.e0cGLsonsplidattd.shipmentL1halmett_thtJ.tquifsmentL9f-thitappendis._Ibe._ waste.sollector shall ensure that. for each container of waste in the shipment, the manifest identifies the.generatolof.thatsontainet.ofwaste; ~ .._ _ 3. Forward a. copy _or_ ele.ctroni.cally ttaasfer the Uniforrn Low-Level Radioksliye_Wasis Manifestto_the intended consignee so that either: (i) Receipt of the manifest oreced.es the LLW shipment or (ii) the manifest.is delivered.to.thesonsignee_with the, waste.althe_ time the waste is transferred to the consignee _Usingboth (i) and (ii).is also_ acceptable; 3 include.{NRC. EormJAIL(and NRC From 540A if required)] Agency Form (insert form _ number) (and. Agency _EornL(inserLform._numbst).._if.JequiredLwithJhe_ shipment regardless of the option chosen infaragraph Mof.this.Section; i _ _ J., Receive acknowledgemenlofthe_teteiplof the shioment in the form of a signed copy nf [NRC Form 540] Agency Form (insert form number); I L . Retain a copy of or.._electrpni.qAlly_ store the Uniform Low-LeveLRadioac.tive wasle Manifelland. documentation..ofacknowledgement of rescipt; - 7. For any shipments or any part of.a shipment for which acknowledgement of receipthas noth.een received withirtthelimsuet fonh irLthis Appendix. co.DdRCLAn iHYsiligali9R.iD accordance_withfaragraph.E_of thisAppendix;.and ( 8. Notify tre shipper and the Agency when any.. shipment,_or. part of.a. shipment. has not I BInyed.aithin30. days.aflerIrssinLO.f.srLadyaDre manifts.luMDiels HD.tillsd_hy the._S.hipSsf thalthe_ shipment hasheenrantelled. h C. Any licensed waste processor who treats or. repackages waste shall; } -- _L Acknowledge.receiptof.theavaste from the_ shipper witin one week of receiot by returnmg a signed copy of[NRC Form 540] Agency. Form (insertform. number); 'l Prepare a new manifest.thalmetts theleguirements of thisAppSndiL. Prepatalion of the GeW manife5LrCQects that the pr.oressor is responsible for meeting these requirements. For each container of waste _in_the shipment,ithe_ manifest shalLidsntifyJhe_ waste -generators, the preprocessed_ waste _..yolume,_and..other._information_.as_requitsd in Paragraph.LEJ.of.thitAppsadis;. 3. ~ Prepare all' wastes so that the waste,is. classified according.to. Appendix EJiestion_lJf Part D and meets the waste characteristics requirements..in. Appendix..E,.Section lloffart D, 4 Dl37G9

.,%RCR IWwnb l..Ingent 1997 bra)I Agyendis G 4. LabcLeach. package.oLwaste to identifv whether it is Class A waste. Clata B waste or ', Class C. waste, in accordancesith AppendixI..Section. Land _SectionJitoffan_D; _. ; 5 Conduct a quality assurance program to assure complianCr with Aopendir E. Section__I and ll offan.Q.(the. program shallinclude management evaluation of audits): 6. Forward a copy or electronicallyJransfer_theiUnifornt.Lo. :LeycLRadioactlyc_ Waste w MaoifesLlo_thelntended consignee so that either: (i) receiot of the manifest orecedes the LIXshipmenLoL{ii)Jhe manifest is delivered to the consignee with the waste at the time the waste is transferred to thc. consignee Using.both.(ilAnd.(iilis.nlactacceptable; 7c Joclude {b'RC FomL510_(andMC Form 54QA)]. Agency Form (insert form number) and Agency _EornL(insertfomLnumber, if required) with the shipment regardless of the option chosen in Paragraph C.6_of this.Section; 8. Receive ackno_wledgemenLoflhele.csiptof.thc.sf ament in the form of a sinacicopy_of [NRC Eorm.5_40] Agency _EamL(insen form numbtrj; 9. Retain a copy of or electronically _ store the Uniform. Low-LeveLRadioactive_ Waste Man.ifest and.do44meD1Alio_n_of_geknowledgement of receipLatthe record of transfer of licensed.materialanequied by Part C; ~.- _10. For any shipment or any part of a shipment for which acknowledgementof_ receipt.has not - been_Jeceived withinahc_t.imeticLfonh_in this Aopsndix. condyscLa.n jnytstination in i accordanCe.withfaragraplLE of this Anpendir and ~.11. Notify the shipper and the Agency when any~ shipment, or any part.of a shipment. has.not ai rited yit hin.60_d ays_aflet.Lec.eip19f_an.adYanccJnanife11._unic.51.ltolifisd.hylheJihippst 'JiatJhe.shipmentlias_b.cen_canc.cIled. D. The land disposal facility operator shall: 1 ACknOWICdge.rCCeiplDf3heJyaste within one week of recelot by returning, as_a_ minimum.- f a signed copy of[NRC Form 540] Agency. Form (insert form number) to.the.shippermThe shipper to be notified is the licensee who last possessed the, waste and transferred.Jhe waste to the oper;t.ot_lf any discrepancy existthetweenloa.tgrials listed _on the Uniform Lo_W-leyeLRadioactlycJNaste Manifest and materials receiysd cooies or electronic transfer of the afrected forms must_be. returned. indicating that discrepancy. .. Maintain. cop.es...ofJllcampleted manifests and_clectronic. Ally store the information until i ..~. 2.. . theAgency_terminatesJhe.jicsnse._and 3,~ Notify the shipper and the Agencyavhen any_ shipment. or_part of_a shipment. haa_not arriyed3jthin10_dayLa.fttrltcript of an advance manifest. unless notified by_the shioper thauhe_shipmenLi;as been cancelled. D138M0 ~ .a

hrpman G SSR(*R l'oluar i.Aupal 1997 Draf ' - E___Any_ shipments.otpart.ofi. shipment for which acknowledgement is not received within the times set for1h in this section must: ~ ._..... L Be investigated by the shippetif.the shipoer has not received no.t:fication or receigt within XLdays>tlettransfenand - 2, Be traced and reported. The investigation shall include tracing the shipment and filing a - r.epprtJith_the.AgencyJIhjitenste who conducts.a trasc.jnvestigation shall file-a writtenicport.with.thc3gency within 2 weeks of c_ompletiOILQ the investination.] f e 1 i k 3 l 1 [ + Dl3999 . ~

.c o. S n J.t J. i l SSRCR l'olume ! 3 27 97 Drg/l PART J NOTICES, INSTRUCTIONS, AND REPORTS TO WORKERS; INSPECTIONS Ecc J.1 - Purpose and Scope This Part establishes requirements for notices, instructions and reports by licensees or registrants to individuals engaged in activities under a license or registration and options 1 available to such individuals in connection with Agency inspections oflicensees or registrants to ascertain compliance with the provisions of the Act and regulations, orders, and licenses issued thereunder regarding radiological working conditions. The regulations in this Part apply to all persons who receive, possess, use, own, or transfer sources of radiation registered with or licensed by the Agency pursuant to Parts B and C of these regulations. General Regulatory Provisions and Specific Requirements Sic J.11 - Postina of Notices to Workers Each licensee or registrant shall post current copies of the following documents: a. i. The regulations in this Part and in Part D of these regulations; ii. The license, certificate of registration, conditions or documents incorporated into the license by reference and amendments thereto; i

iii, The operating procedures applicable to activities under the license or registration; and 1-iv.

Any notice of violation involving radiological working conditions, proposed imposition of civil penalty, or order issued pursuant to Part A of these regulations, and any response from the licensee or registrant. b. If posting of a document specified in J. lla.i., ii., or lii. is not practicable, the licensee or registrant may post a notice which describes the document and states where it may be examined. Agency Form X " Notice to Employees" shall be posted by each licensee or registrant as required c. by these regulations. d. Agency documents posted pursuant to J.lla.iv, shall be posted within 5 working days after receipt ~of the documents from the Agency; the licensee's or registrant's response, if any, shall be posted within five working days aller dispatch from the licensee or registrant. Such documents shall remain posted for a minimum of five working days or until action correcting the violation has been completed, whichever is later, Documents, notices, or forms posted pursuant to J.l l shall appear in a sufficient number of places e. to permit individuals engaged in work under the license or registration to observe them on the way to or from any particular work location to which the document applies, shall be conspicuous, and shall be replaced if defaced or altered. Jl

r SNRCR Iblume I. 101696I)nfl Sec.J.t2 J.I3 Sec, J.12 - Instructions to Workers a. All individuals whn in_the_ course._of_cmploymentate likely to receive itaJeat an occupational dose in excess ofimSdl00.mtem): i. Shall be kept informed of the storage, transfer, or use of sources of radiation in the licensee's or registrant's workplace; ii. Shall be instructed in the health protection problems associated with exposure to radiation or radioactive material to the individual and potential offspring, in precautions or procedures to minimize exposure, and in the purposes and functions of protective devices employed; iii. Shall be instructed in, and instructed to observe, to the extent within the worker's control, the applicable provisions of these regulations and licenses for the protection of personnel from exposures to radiation or radioactive material; iv. Shall be instructed of their responsibility to report promptly to the licensee or registrant any condition which may constitute, lead to, or cause a siolation of the Act, these regulations, or license condition, or any unnecessary exposure to radiation or radioactive material, Shall be instructed in the appropriate response to warnings made in the event of any v. unusual occurrence or malfunction that may involve exposure to radiation or radioactive material, and vi. Shall be advised as to the radiation exposure reports which workers shall be furnished pursuant to J.13. b. The extent of these instructions shall be commensurate with potential radiological health protection problems present in the workplace. Sec j 13 - Notific.ations and Reports to individuals. Radiation exposure data for an individual and the results of any measurements, analyses, a. and calculations of radioactive material deposited or retained in the body of an individual shall be reported to the individual as speciGed in J.13. The information reported shall include dat and results obtained pursuant to these regulations, orders, or license conditions, as shown in records maintained by the licensee or registrant pursuant to D.1107 of these regulations. Each noti 6 cation and report shall: i. De in writing; ii. Include appropriate identifying data such as the name of the licensee or registrant, the name of the individual, and the individual's identification number, preferably social security number; J2

e Sec 113 314 SSRCR Iblume1 1916 96 l) rap iii. Include the individual's exposure information; and iv. Contain the following statement: "This report is furnished to you under the provisions of [ cite appropriate Agency regulations] Part J. You should preserve this report for further reference." b. Each licensee or registrant shall furnish to each worker annually a written report of the worker's dose as shown in records maintained by the licensee or registrant pursuant to D.1107 of these regulations. Each licensee or registrant shall furnish a wntten report of the worker's exposure to sources of c. radiation at the request of a worker formerly engaged in activities controlled by the licensee or registrant. The report shall include the dose record for each year the worker was required to be monitored pursuant to D.502 of these regulations. Such report shall be furnished within 30 days from the date of the request, or within 30 days afler the dose of the individual has been determined by the licensee or registrant, whichever is later. The report shall cover the period of time tiiat the worker's activities involved exposure to sources of radiation and shall include the dates and locations of work under the license or registration in which the worker participated during this period. d. When a licensee or registrant is required pursuant to D.1202, D.1203, or D.1204 [or D.1206] of l these regulations to report to the Agency any exposure of an individual to sources of radiation, the licensee or the registrant shall also provide the individual a written report on the exposure data included therein. Such reports shall be transmitted at a time not later than the transmittal to the Agency. At the request of a worker who is terminating employment with the licensee or registrant in work c. involving exposure to radiation or radioactive material, during the current year, each licensee or registrant shall provide at termination to each such worker, or to the worker's designee, a written report regarding the radiation dose received by that worker from operations of the licensee or registrant during the current year or fraction thereof. If the most recent individual monitoring results are not available at that time, a written estimate of the dose shall be provided together with a clear indication that this is an estimate. Sec J 14 - Presence of Repmentatives of Licensees or Recistrants and Workers During Inspection. Each licensee or registrant shall atTord to the Agency at all reasonable times opportunity to a. inspect materials, machines, activities, facilities, premises, and records pursuant to these regulations. b. During an inspection, Agency inspectors may consult privately with workers as specified in J.15. The licensee or registrant may accompany Agency inspectors during other phases of an inspection. If, at the time ofinspection, an individual has been authorized by the workers to represent them c. during Agency inspections, the licensee or registrant shall notify the inspectors of such J3

o Sec,J.l4-).l6 MRCR Iblume I.1016 96 I)ra}l authorization and shall give the workers' representative an opportunity to accompany the inspectors during the inspection of physical working conditions. d. Each workers' representative shall be routinely engaged in work under control of the licensee or registrant and shall have received instructions as specified in J.12. DifTerent representatives oflicensees or registrants and workers may accompany the inspectors e. during ditTerent phases of an inspection if there is no resulting interference with the conduct of the inspection. Ilowever, only one workers' representative at a time may accompany the inspectors. f. With the approval of the licensee or registrant and the workers' representative, an individual who is not routinely engaged in work under control of the licensee or registrant, for example, a consultant to the licensee or registrant or to the workers' representative, shall be afTorded the opportunity to accompany Agency inspectors during the inspection of physical working conditwns. Notwithstanding the other provisions of J.14, Agency inspectors are authorized to refuse to g. permit accompaniment by any individual who deliberately interferes with a fair and orderly inspection. With regard to atem containing information classified by an Agency of the US Government in the interest of national security, an individual who accornpanies an inspector may have access to such information only if authorized to do so. With regard to any area containing proprietary information, the workers' representative for that area shall be an individual previously authorized by the licensee or registrant to enter that area. Sec J.15 - Cops iltation with Workers Durina inspections, Agency inspectors may consult privately with workers concerning matters of occupational a. radiation protection and other matters related to applicable provisions of these regulations and licenses to the extent the inspectors deem necessary for the conduct of an effective and thorough inspection b. During the course of an inspection, any worker may bring privately to the attention of the inspectors, either orally or in writing, any past or present condition which the worker has reason to believe may have contributed to or caused any violation of the Act, these regulations, or license condition, or any unnecessary exposure of an individual to sources of radiation under the licensee's or registrant's control Any such notice in writing shall comply with the requirements of J.16a. The provisions of J.15b shall not be interpreted authorization to disregard instructions c. pursuant to J.12. Sec. J.16 - Requests by Workers for inspections. Any worker or representative of workers believing that a violation of the Act, these regulations, a. or license conditions exists or has occurred in work under a license or regist:ation with regard to radiological working conditions in which the worker is engaged may requcst an inspection by giving notice of the alleged violation to the (Radiation Control Program). Any such notice shall be in writing, shall set forth the specific grounds for the notice, and shall be signed by the worker or representative of the workers. A copy shall be provided to the licensee or registrant by the [ Radiation Control Program) no later than at the time ofinspection except that, upon the request J4

e Sec 3 l6 -).IT SSRCR l'olurne i.10 iM6 Drap of the worker giving such notice, such worker's name and the name of individuals referred to therein shall not appear in such copy or on any record published, released, or made available by the Agency, except for good cause shown. b. If, upon receipt of such notice, the (Radiation Control Program] determines that the complaint meets the requirements set forth in J.16a., and that there are reasonable grounds to believe that the alleged violation exists or has occurred, an inspection shall be made as soon as practicable to determine if such alleged violation exists or has occurred. Inspections pursuant to J.16 need not be limited to matters referred to in the complaint. No licensee, registrant, or contractor or subcontractor of a licensee or registrant shall discharge or c. in any manner discriminate against any worker because such worker has filed any complaint or instituted or caused to be instituted any proceeding under these regulations or has testified or is about to testify in any such proceeding or because of the exercise by such worker on behalf of such worker or others of any option afforded by this Part. Sec J.17 - Inspections Not Warranted: Informal Review, a. i. If the [ Radiation Control Program] determines, with respect to a complaint under i 16, that an inspection is not warranted because there are no reasonable grounds to believe that a violation exists or has occurred, the [ Radiation Control Program] shall.otify the complainant in writing of such determination. The complainant may obtain review of such determination by submitting a written statement of position with the [ cite appropriate State agency ]. Such Agency will provide the licensee or registrant with a copy of such T statement by certified mail, excluding, at the request of the complainant, the name of the complainant. The licent.c or registrant may submit an opposing written statement of position with the [ cite appropriate State agency ]. Such agency will provide the complainant with a copy of such statement by certified mail. ii. Upon the request of the complainant, the [ cite appropriate State agency ] may hold an informal conference in which the complainant and the licensee or registrant may orally present their views An informal conference may also be held at the request of the licensee or registrant, but disclosure of the identity of the complainant will be made only following receipt of written authorization from the complainant. After considering all writt.n and oral views presented, the [ cite appropriate State agency ] shall aflirm, modify, or reverse the determination of the [ Radiation Control Program] and furnish the compleinant and the licensee or registrant a written notification of the decision and the reason therefor. b. If the [ Radiation Control Program] determines that an inspection is not warranted because tb requirements of J.16a. have not been met, the complainant shall be notified in writing of such determination. _ Such determination shall be without prejudice to the filing of a new complaint meeting the requirements ofJ.16a. ?The agency cuted here should be the agency wluch, under State achninistrattw procedures, has the power to review decisiorn Hlikit by the Ndhalion ContrOf frograin. J5

07/29/97 Draft Itatmnatefor l'an J __ 1997 RATIONALE FOR REVISIONS PART J NOTICES, INSTRUCTIONS, AND REPORTS TO WORKERS; INSPECTIONS Inngsfuqtion Part 3 of the Suggested State Regidationsfor Control ofRadiation is based on 10 CFR Part 19, which is intended to provide options to workers concerning inspections of working conditions comparable to those provisions provided for inspections pursuant to the Occupational Safety and Health Act. The Nuclear Regulatory Commission continues to revise its standards for protection against ionizing radiation in 10 CFR Part 20. This revision incorporated updated scientific information and reflected changes in the basic philosophy of radiation protection councils for internal doses. Part 19 was revised to incorporate the necessary changes to accommodate the revisions to Part 20, thus necessitating associated changes to Part J. f_onipatibililyltquirements The revision of Part 20, including corresponding changes to Part 19 was published in the Federal Regi.sLet on July 13,1995 (60 FR 36038) and became etTective on August 15, 1995. The Nuclear Regulatory Commission considers the adoption of these regulations a matter of compatibility for all Agreement States. See the July 13,1995, Ecdcral Reuister notice for further background information on specific changes to the revision to Part 19 which corresponds to the Part J revision. Other editorial changes consistent with the Conference of Radiation Control Program Directors, Inc., Policies and Procedures for the Pretmration and Publication of the Suggested State Regulations for Control of Radiation will not speci6cally be noted in the rationale discussion for each section. Specine Provisions J.12a The Working Group revised J.12a. to conform to the revision of Part 20. J 13d "[or D.1206]" was added in brackets since "D.1206" is optional. 1 Matters for Future Consideration At this time there are no Matters for Future Consideration. w}}