Regulatory Guide 8.20: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(StriderTol Bot change)
Line 1: Line 1:
{{Adams
{{Adams
| number = ML14064A060
| number = ML003739555
| issue date = 09/30/2014
| issue date = 09/30/1979
| title = Rev. 2, Applications of Bioassay for Radioiodine.
| title = Applications of Bioassay for I-125 and I-131
| author name = Sun C
| author name =  
| author affiliation = NRC/RES/DSA/HEB
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
| docket =  
| docket =  
| license number =  
| license number =  
| contact person = Karagiannis H
| contact person =  
| case reference number = DG-8050
| document report number = RG-8.020, Rev. 1
| document report number = RG-8-020, Rev 2
| package number = ML14064A038
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 12
| page count = 6
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION                                                       September 2014 OFFICE OF NUCLEAR REGULATORY RESEARCH                                                                  Revision 2 REGULATORY GUIDE                                                                            Technical Lead Casper Sun REGULATORY GUIDE 8.20
{{#Wiki_filter:levillm 9 U.S. NUCLEAR REGULATORY COMMISSION                                                                   81PSeptaiff 1979 o ..AuIn&..i
                                    (Draft was issued as DG-8050, dated September 2011)
    1,,
            APPLICATIONS OF BIOASSAY FOR RADIOIODINE
                            REGULATORY GUIDE
        ease,              OFFICE OF STANDARDS DEVELOPMENT
                                                        REGULATORY GUIDE 8.20
                            APPLICATIONS OF BIOASSAY FOR 1-125 AND 1-131


==A. INTRODUCTION==
==A. INTRODUCTION==
Purpose This regulatory guide describes methods that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable for the development and implementation of bioassay programs for adult workers and for licensees handling or processing unsealed materials containing iodine-123 (123I),
vitro of materials excreted or removed from the body..
iodine-124 (124I), iodine-125 (125I), iodine-129 (129I), and iodine-131 (131I), or a combination of these radionuclides. The title of this guide, therefore, was changed to Applications of Bioassay for Radioiodine, instead of the previous title, Applications of Bioassay for I-125 and I-131. However, this guide does not address measurement techniques, radiochemistry analytical procedures, or dose assessment. It applies to both reactor and materials licensees.
      Section 20. 108, "Orders Requiring Furnish ing of Bioassay Services," of 10 CFR Part 20,                                 Intake-The          total quantity          of     radioactive
"Standards for Protection Against Radiation,'                              material entering the body.


Applicable Rules and Regulations Title 10 of the Code of Federal Regulations (10 CFR), Part 20, Section 1204, Determination of internal exposure, paragraph (a) (Ref. 1) states that each licensee shall, when required under
indicates that the Nuclear Regulatory Commis sion (NRC) may incorporate into a license pro                                In vivo measurements-Measurement of gamma visions        requiring      a    specific program              of     or x-radiation emitted from radioactive material bioassay          measurements          as    necessary          or    located within the body for the purpose of desirable to aid in determining the extent of an                            detecting or estimating the quantity of radio individual's          exposure to concentrations of                       active material present.
          10 CFR 20.1502, Conditions requiring individual monitoring of external and internal occupational dose, take suitable and timely measurements of: (1) concentrations of radioactive materials in air in work areas, (2) quantities of radionuclides in the body, (3) quantities of radionuclides excreted from the body, or (4) combinations of these measurements.


Regulations in 10 CFR 20.1201, Occupational dose limits for adults, provide occupational dose limits for adult workers.
radioactive material.               In certain cases, the requirement of bioassay may also be included in                              In vitro measurements-Measurement of radio the license by reference to procedures specify                            activity in samples of material excreted from ing in vivo measurements, measurements of                                  the human body.


Regulations in 10 CFR 20.1703, Use of individual respiratory protection equipment, paragraph (c)(2), require licensees to implement and maintain a respiratory protection program that includes surveys and bioassays, as necessary to evaluate actual intakes.
radioactive material in excreta, or both.


Related Rules and Regulations Regulations in 10 CFR 20.1101 Radiation protection programs, paragraph (b), require licensees to use, to the extent practical, procedures and engineering controls based upon sound radiation protection principles to achieve occupational doses and doses to members of the public that are as low as is reasonably achievable (ALARA).
==C. REGULATORY POSITION==
Written suggestions regarding this guide or development of new guides may be submitted through the NRCs public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/reg-guides/contactus.html.
This guide provides criteria acceptable to the NRC staff for the development and implementa                              1. Conditions Under Which Bioassay Is Necessary tion of a bioassay program for any licensee handling or processing 1-125 or 1-131. It                                        a. Routine' bioassay is necessary when an further provides guidance to such licensees                               individual handles in open form unsealed 2 regarding the selection of workers who should quantities of radioactive iodine that exceed participate in a program to detect and measure those shown in Table 1 of this guide. The possible internal radiation exposure. The guide quantities shown in Table 1 apply to both the is programmatic in nature and does not deal quantity handled at any one time or integrated with measurement techniques and procedures.


Electronic copies of this regulatory guide, previous versions of this guide, and other recently issued guides are available through the NRCs public Web site under the Regulatory Guides document collection of the NRC Library at http://www.nrc.gov/reading-rm/doc-collections/. The regulatory guide is also available through the NRCs Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under ADAMS Accession No. ML14064A060. The regulatory analysis may be found in ADAMS
as the total amount of activity introduced into a process by an employee over any 3-month
under Accession No. ML14064A058 and the staff responses to the public comments on DG-8050 may be found under ADAMS Accession No.
 
ML14064A061.
 
Regulations in 10 CFR 20.2202, Notification of incidents, require each licensee to notify the NRC either immediately or within 24 hours of any event involving byproduct, source, or special nuclear material possessed by the licensee that may have caused or threatens to cause an individual to receive a dose meeting the limits specified in this section of the NRC regulations.
 
Regulations in 10 CFR 20.2203, Reports of exposures, radiation levels, and concentrations of radioactive material exceeding the constraints or limits, require a report to be sent to the NRC
        describing specified reportable events.
 
Regulations in 10 CFR 20.2205, Reports to individuals of exceeding dose limits, require that when a licensee is required by sections 20.2203 or 2204 to send a report to the Commission of any exposure of an identified occupationally exposed individual, or an identified member of the public, to radiation or radioactive material, the licensee shall also provide the individual a report of the data included in the report to the Commission.
 
Related Guidance Regulatory Guide 8.9, Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program (Ref. 2), provides methods and criteria acceptable to the NRC staff for estimating intake of radionuclides using bioassay measurements.
 
Regulatory Guide 8.25, Air Sampling in the Workplace (Ref. 3), provides methods and criteria acceptable to the NRC staff for air sampling in restricted areas in the workplace.
 
NUREG-1556, Vol. 9, Consolidated Guidance about Materials Licenses: Program-Specific Guidance about Medical Use Licenses (Ref. 4), provides methods for the development and implementation of radioiodine bioassay programs in medical facilities.
 
National Council on Radiation Protection and Measurements (NCRP) Report 159, Risk to the Thyroid from Ionizing Radiation (Ref. 5), provides protection guidance and global data on 131I
        exposures from atmospheric testing of nuclear fallouts.
 
NCRP Report 161, Management of Persons Contaminated with Radionuclides: Handbook (Ref. 6), provides guidance for emergency treatment if a severe intake of radioiodine was to occur.
 
U.S. Environmental Protection Agency (EPA), Federal Guidance Report No. 11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion (Ref. 7), provides the technical basis and values for setting upper bounds on the inhalation, ingestion, and submersion in radioactive materials.
 
Purpose of Regulatory Guides The NRC issues regulatory guides to describe to the public methods that the staff considers acceptable for use in implementing specific parts of the agencys regulations, to explain techniques that the staff uses in evaluating specific problems or postulated accidents, and to provide guidance to applicants. Regulatory guides are not substitutes for regulations, and compliance with them is not required. Methods and solutions that differ from those set forth in regulatory guides will be deemed acceptable if they provide a basis for the findings required for the issuance or continuance of a permit or license by the Commission.
 
Rev. 2 of RG 8.20, Page 2
 
Paperwork Reduction Act This regulatory guide contains information collection requirements covered by 10 CFR Part 20,
Standards for Protection against Radiation, that the Office of Management and Budget (OMB)
approved under OMB control number 3150-0014. The NRC may neither conduct nor sponsor, and a person is not required to respond to, an information collection request or requirement unless the requesting document displays a currently valid OMB control number.


==B. DISCUSSION==
==B. DISCUSSION==
Reason for Revision The NRC revised this guide to achieve better alignment with: (1) 10 CFR Part 20, and (2) the internal dose assessment methods recommended by the International Commission on Radiological Protection (ICRP) Publication 30, Limits for Intakes of Radionuclides by Workers (Ref. 8). New predetermined action levels (PALs) are specified in the Staff Regulatory Guidance section of this guide.
period.
 
This regulatory guide revision also provides new guidance for 123I, 124I, and 129I, and updates the content of the guide and its references.
 
Background The guide provides methods and criteria acceptable to the NRC staff for the development and implementation of a bioassay program for any licensee handling or processing one or a combination of the five selected radionuclides. It also provides guidance regarding the selection of workers who should participate in a program to detect and measure possible internal radiation exposure.
 
The decisions on the type of monitoring, who is to be monitored, the frequency of monitoring, and other aspects of the program must be based on estimates of what types and quantities of intakes may occur given the kinds of activities that are expected to take place at the licensees facility during the monitoring year. Based on operational experience, licensees may also justify adjustments in the bioassay program, such as reduction or increase in bioassay frequency or the use of alternative bioassay dosimetry models due to medical, prenatal, or other reasons, but the adjusted program shall meet NRC requirements and satisfy the requirements in 10 CFR 20.2301, Applications for exemptions, and 10 CFR 20.2302, Additional requirements. This guide does not include bioassay measurement techniques and procedures.


The basic criteria in Table 1, Radioiodine Protection Properties, are specified for the development of a bioassay program. Table 1 provides the radiological half-life, annual limits on intake (ALI), derived air concentration (DAC), and the maximum bioassay duration from the beginning of an operation for the iodine isotopes. The values of radiological half-life are based on those in Federal Guidance Report No. 11. The ALI and DAC values are based on those in Column 2 and Column 3 of 10
The topics treated in this guide include de                                  b. When quantities handled in unsealed terminations of (1) whether bioassay should be form are greater than 10% of Table 1 values, performed, (2) frequencies of bioassay, (3)
CFR Part 20, Appendix B, Annual Limits on Intake (ALIs) and Derived Air Concentrations (DACs) of Radionuclides for Occupational Exposure; Effluent Concentrations; Concentrations for Release to Sewerage. The duration specified in the last column of the Table 1, Maximum Bioassay Duration from Beginning of an Operation, provides information for bioassay frequency. Specific guidance on the frequency of bioassays is found in section C of this guide.
who should participate, (4) the actions to take                              *Lines indicate substantive changes from previous issue.


The required bioassay criteria are specified in Table 2, Radioactivity Levels above which Bioassay for Radioiodine is Necessary. The criteria are presented in dual radioactivity units.
based on bioassay results, and (5) the partic ular results that should initiate such actions.                                IRoutine means here that an individual is assigned on a sche u**-edand repeatable basis to submit specimens for bioassay or to report for in vivo measurements. Either radiochemical For the user's convenience, the following                            bioassay of urine or in vivo counting is acceptable to the NRC
terms are presented with their definitions as                              staff for estimating internal radioactivity burdens or intakes.


Rev. 2 of RG 8.20, Page 3
In some cases, however, a licensee may wish to corroborate used in this guide:                                                        estimates from urinalysis data with in vivo determinations.


Table 1. Radioiodine Protection Properties Radiological        ALI by inhalation: µCi (MBq)          DAC          Maximum bioassay Isotope                                                                    µCi/mL        duration from beginning half-life        Stochastic        Non-stochastic      (Bq/mL)            of an operation
Since there are adequate references in the literature to hellp devise bioassay measurements, thia guide does not include Bioassay-The determination of the kind,                               recommended     analytical procedures.   Each  installation should quantity or concentration,                    and location of             adopt. procedures or obtain services best suited to its own radioactive material in the human body by                                  needs..
        123 I            13 hours        20,000 (740)      6,000 (220)        3E-6 (9E-2)            1 day
direct (in vivo) measurement or by analysis in                                ;See discussion in the footnote to Table 1 of this guide.
        124 I          4.2 days            300 (11)          80 (3.0)        3E-8 (1E-3)            1 week
        125 I            60 days            200 (7.4)          60 (2.2)        3E-8 (9E-4)            2 weeks
        129 I     1.6 E+7 years             30 (1.1)          9 (0.30)        4E-9 (1E-4)            2 weeks
        131 I          8.0 days            200 (7.4)         50 (1.9)        2E-8 (7E-4)            2 weeks


Half-life values have been rounded to two significant digits.
USNRC REGULATORY GUIDES                              Comments should be sent to the Secretary of the Comm.ison, U.S.


ALI and DAC values in the Table include one significant figure, which reflects the convention used in Appendix B
Nuclear Regulatory Commission, Wimington, D.C. 20555, Atten Regltory Guides are issued to describe and make available to the          tion: Docketng and Service Branch.
  of 10 CFR Part 20, Table 1, Column 2 and Column 3. When a mixture of radioiodine is present, the ALI and DAC
  values for the mixture should be established following the methods stated in 10 CFR 20.1204(e), (f), and (g).
        Table 2. Radioactivity Levels above Which Bioassay for Radioiodine is Necessary Radioactivity Levels in Unsealed Form above Which Bioassay is Necessary Types of Operations Volatile or Bound to Nonvolatile Agent Dispersible Column 1                                      Column 2                          Column 3 Processes in open room or bench, with possible escape of iodine from process vessels                            1 mCi      (37 MBq)              10 mCi (370 MBq)
  Processes with possible escape of iodine carried out within well-controlled and ventilated areas (i.e., fume hood of adequate design, face velocity, and                     10 mCi      (370 MBq)            100 mCi (3.7 GBq)
  performance reliability)
  Processes carried out within gloveboxes, ordinarily closed, but with possible release of iodine from process and occasional exposure to contaminated box            100 mCi      (3.7 GBq)                1 Ci (37 GBq)
  and box leakage


(1) Quantities should consider the cumulative amount of the radioactivity in the process handled by a worker during a
public methods acceptable to the NRC staff of implementing specific arts oh te Comrmision's regulations, to delineate techniques used      The guides are lised in the following ten broad divsons:
  3-month period. When the cumulative amount of radioactivity of iodine in unsealed forms during any 3-month period exceeds the specified quantities in Column 2 and Column 3 above, then bioassay is necessary. (2) the quantities in Column 3 may be used when it can be shown that the radioactive materials in the process are always chemically bound and processed in such a manner that all iodine compounds will remain in a nonvolatile form and will be diluted to a concentration of less than 100 mCi/g (3.7 GBq/g) of nonvolatile agent. (3) Capsules (such as gelatin capsules given to patients for diagnostic tests) may be considered to contain the iodine in sealed form, and bioassay would not be necessary unless a capsule were inadvertently opened (e.g., dropped and crushed). (4) If there is a breech in normal procedures during the administration of 131I, for example, spillage from the vial that exceeds the capacity of the absorbent pad, a bioassay would be necessary. (5) Certain compounds where radioiodine is normally bound are known to release radioiodine when the material is processed, and in this scenario Column 2 may be applicable. (6) For laboratories that only work with 125I in radioimmunoassay (RIA) kits, the quantities of 125I are very small and in less volatile forms; thus, Column 3 may be used for bioassay requirements. (7) In field operations, where reagent containers are opened outdoors for simple operations such as pouring liquid solutions, the above table does not apply; however, bioassay should be performed whenever an individual employee handles an unsealed source (e.g., an open bottle or container) of more than
    bythe staff in evaluatg .speificproblems or postulated accidents, or to wovide g            to pplicants. Regulatory Guides are not rabsti-   I.  Power Reactors                  6. Products tues for regutons, an compliance with them s not required.            2.  Research and Test Reactors      7. Transportation Methods and solut n different from those set out in the           will
  50 millicurie (mCi) (1.8 gigabecquerel (GBq)) at any one time.
                                                                  ;iakes 3.  Fuels and Materials Facilities  S. Occupational Health be acceptable if they provide a bade for the findings requiite to the     4.  Environmental and Siting        9. Antitrust and Fmandal Review isuance or continuance of a permit or license by the Comm on.             S. Materias and Plant Protection  10. General Copies of imued guides may be purchased at the current Government Comments and suggestions for improvements in these guides are            Printin# Office price. A msbscrlption service for future guides in spe encouraged at all times, and guides will be revised, as appropriate, to  cific divisions is available through the Government Priting Ofrice.


Ventilated fume hoods with face velocities that meet the design criteria in the American Conference of Governmental Industrial Hygienists (ACGIH) Industrial Ventilation Manual designed criteria, or equivalent.
accommodate comments and to reflect new information or experi-            Information on the subscription service and current GPO prices may ence. This guide was revised as a result of rubstantive comments          be obtained by writing the U.S. Nuclear Regulatory Commision, received from the public and additional staff review.                    Washington, D.C. 20535, Attention: Publications Sales Manager.


Rev. 2 of RG 8.20, Page 4
routine bioassay may still be necessary under                            3. Types of Bioasays That Should Be Performed certain circumstances. A written justification for not performing such measurements should                                      a. Baseline (preemployment or preopera be prepared and recorded for subsequent re                              tional). Prior to beginning work with radio view during NRC inspections whenever bio                                active iodine in sufficient quantity that bio assay is not performed and the quantities                                assay is specified in regulatory position 1.


Because 123I has a half-life of 13 hours, indirect (in vitro) bioassay methods may not be practical.
handled exceed 10% of the levels in Table 1.


Therefore, a direct (in vivo) thyroid count is recommended and should be performed within 24 hours of the event, and each workday thereafter. The total 40 hours (weekly) thyroid content should also be documented for dose estimates and for ALARA purposes.
b. Routine. At the frequency specified in c. Except as stated in regulatory posi                            regulatory position 4.


Because of the low specific activity of 129I, the low-energy gamma radiations, and the limited capacity of the thyroid gland for iodine (as described in Book, S.A., Iodine-129 Uptake and Effects of Lifetime Feeding in Rats (Ref. 9), which determined that the relative risk (radiological) from 129I is less than 131I in the thyroid), only indirect (in vitro) measurements are practical and acceptable to the NRC
tion 1.e, bioassay is not required when pro cess quantities handled by a worker are less                                    c. Emergency. As soon as possible after any than 10% of those in Table 1.                                           incident that might cause thyroid uptakes toi exceed burdens given in regulatory posi-i e     d. In nuclear reactor installations, employ                      tion 5.a(2), so that actions recommended inI
staff for 129I bioassay. In addition, NCRP Report 75, Iodine-129: Evaluation of Releases from Nuclear Power Generation (Ref. 10), provides a complete evaluation of 129I (i.e., physical properties, biological behavior, production sources, environmental transport, and waste management).
  ees should be bioassayed by an in vivo count                            regulatory position 5.a(2)(b) can be most within 30 days after the end of exposure in                               effective.
Harmonization with International Standards The NRC has a goal of harmonizing its guidance with international standards, to the extent practical. The International Atomic Energy Agency (IAEA) has issued a significant number of standards, guidance, and technical documents, and the ICRP has issued recommendations addressing good practices in most aspects of radiation protection. The criteria and guidance of this regulatory guide are generally consistent with the guidance in these documents. These documents include:
        ICRP Publication 30, Limits for Intakes of Radionuclides by Workers IAEA Safety Guide RS-G-1.2, Assessment of Occupational Exposure Due to Intake of Radionuclides (Ref. 11)
        The NRC encourages licensees to consult these international documents and implement good practices that are consistent with NRC regulations. It should be noted that some of the international recommendations do not correspond to the requirements specified in the NRCs regulations. In such cases, the NRCs requirements take precedence.


C. STAFF REGULATORY GUIDANCE
work locations where concentrations exceeded, or might have exceeded,                  9 x 10-1Q pCi/ml                      d. Postoperational and with Separation Phys averaged over any 40-hour period. Table 1 and                            ical. A bioassay should be performed within 2 regulatory position 4 regarding frequency of                             weeks of the last possible exposure to 1-125 or bioassays        are    not    applicable      to reactor              1-131 when operations are being discontinued I licensees.                                                               or when the worker is terminating activities with potential exposure to these radionuclides.
1.       Conditions under which Bioassay is Necessary a.        Conditions under which Routine Bioassay is Necessary1Routine bioassay is necessary when an individual handles or works near unsealed quantities of a radioiodine substance that exceed those values specified in Table 2, Radioactivity Levels above Which Bioassay for Radioiodine is Necessary, of this guide. The quantities shown in Table 2 apply to both the quantity handled at any one time or integrated as the total amount of activity introduced into a process by an employee over a period of 90 days.


b.       Conditions under which Routine Bioassay May Be NecessaryWhen an individual routinely handles and works near unsealed radioiodine quantities greater than 10 percent but less than 100 percent of the Table 2 values, a routine bioassay should still be
e. Special bioassay measurements should e. Diagnostic. Followup bioassay should be be performed to verify the effectiveness of                              performed within 2 weeks of any measurements respiratory protection devices and protective exceeding levels given as action points in clothing. If an individual wearing a respiratory                        regulatory position 5 in order to confirm the protective device or protective clothing is sub initial results and, in the case of a single jected to a concentration of 1-125 or 1-131 (in                         intake, to allow an estimate of the effective any form) in air such that his or her intake                            half-life of radioiodine in the thyroid.
  1 Routine, as used in this guide, means that an individual is assigned on a scheduled and repeatable basis to submit specimens for indirect bioassay or to report for in vivo measurements, i.e., direct bioassay, at the frequency specified in section C of this guide. Either radiochemical urinalysis or in vivo thyroid counting is acceptable to the NRC staff. In some cases, a licensee may wish to corroborate estimates from urinalysis data with in vivo determinations. Since there are adequate references in the literature to help devise bioassay measurements, this guide does not include analytical procedures. Each installation should adopt procedures or obtain services best suited to its own needs.


Rev. 2 of RG 8.20, Page 5
with no protection would have exceeded the limits specified in paragraph 20.103(a)(1) of                          


performed unless justification is provided for not performing routine bioassay (e.g.,
===4. Frequency===
                licensees could demonstrate by ALARA records or use of protection devices at the facility that the frequency of bioassay could be reduced/eliminated). Written justification for not performing normally required bioassay should be prepared and documented in auditable form on site for NRC inspections. When an individual routinely handles and works near unsealed quantities of less than 10 percent of those in Table 2, routine bioassay is not necessary.
  10 CFR Part 20,3 bioassays should be per formed to determine the resulting actual 1-125                                  a. Initial Routine. Except in situations or 1-131 intake. These special bioassay proce                            where thyroid burdens may exceed quantities dures should also be conducted for personnel                            specified in regulatory position 5.a(2), a bio wearing respirators if for any reason the 1-125                        assay      sample or measurement should be or 1-131 concentration in air and the duration                          obtained within 72 hours following entry of an                -1
'of exposure are unknowvn or cannot be conser                              individual into an area where bioassay is I vatively estimated by calculation.                                      performed in accordance with regulatory posi tions 1 and 2 (but waiting at least 6 hours for distribution of a major part of the iodine to the thyroid')        and    every      2 weeks        or more
  2. Participation                                                        frequently thereafter as long as the conditions;
                                                                            described in regulatory positions 1 and 21 AUl workers handling radioactive iodine or                        exist. When work with radioactive iodine is on sufficiently close to the process so that intake                        an infrequent basis (less frequently than every is possible (e.g., within a few meters and in                            2 weeks), bioassay should be performed within the same room as. the worker handling the                                10 days of the end of the work period during material) should participate in bioassay pro                              which radioactive iodine was handled (but not grams described in regulatory position 1.                                sooner than 6 hours unless emergency actions to obtain an early prognosis and thyroid
    3 blocking treatment are appropriate4).
      Muitfplying the concentrations riven in Appendix B to
  10 CFR Part 20, Table r, column i, 5 x 10-9 wCi/ml for 1-125                    b. After 3 Months. When a periodic meas (soluble) and 9 x 10-9 *Ci/ml for 1-131 (Soluble), by 6 3 x 108 m= gives the corresponding quarterly intake of the respective            urement frequency             has been selected in iodines by inhalation. These quarterly intakes would be about            accordance with regulatory position 4.a, it may
  3.2 pCi for 1-125 and 5.7 pCi for 1-131, which would give a              be changed to quarterly if, after 3 months, all thyroid dose commitment of about 7. rems to a 20-gram thyroid integrated over all future time using effective half-lives of 41.8        the following conditions sre met:
  days for I-I25 and 7.6 days for 1-131 and using a quality factor (QF) of 1.7 to calculate effective disintegration energy in the                      (1) The average thyroid burden for case of 1-125. (This QF of 1.7 ie used for conservatism, even            each individual working in a given area was though the International Commission on Radiological Protection
  (1969) and the National Council on Radiation Protection (1971)              4 have published a QF of 1, because some calculations in more                    NC*RP Report No. 55, "Protection of the Thyroid Gland in recent scientific Literature have suggested the use of QF values          the Event of Releases of Radlioodine," National Council on higher than I for electron or beta energies of 0.03 MeV or                Radiation Protection and Measurements, Washington, D C.,
  less.)                                                                    August 1, 1977, p. 21.


c.       Routine Bioassay at Reactor FacilitiesIn nuclear power installations, employees should receive a bioassay within 30 days after the end of exposure in work locations where concentrations exceeded, or might have exceeded, 1.0 DAC of radioiodine, averaged over any 40-hour period. Table 1, regarding frequency of bioassays, and Table 2 are not applicable to power reactor licensees.
8.20-2


d.       Special BioassayA bioassay measurement should be performed within 24 hours of notification. Special bioassay measurements should be performed to verify the effectiveness of respiratory protection devices and protective clothing. If an individual wearing a respiratory protective device or protective clothing is subjected to a concentration of radioiodine (in any form) in air such that his or her intake with no protection would have resulted in a dose that would have exceeded the limits specified in
less than 0.12 pCi of 1-125, less than 0.04 pCi                    § 20.103 of 10 CFR Part 20 to be exceeded, the of 1-131, and less than the corresponding pro                      licensee  should     restrict the worker    from portionate amounts of a mixture of these                            further exposure until the source of exposure nuclides during the initial 3-month period;                        is discovered and corrected.
                10 CFR 20.1201, perform bioassays as necessary to verify that the actual intake will not result in a dose in excess of the limits. These special bioassay procedures should also be conducted for personnel wearing respirators or other protective clothing if for any reason the radioiodine concentration(s) in air or the duration of the exposure are unknown or cannot be conservatively estimated by calculation.


2.      Participation All workers handling radioactive iodine or sufficiently close to the process so that intake is possible (e.g., within a few meters or in the same room as the worker handling the material, as appropriate) should participate in bioassay programs described in staff regulatory guidance C.1.
(c) Corrective actions that will elim
            (2) The quarterly average radioiodine concentration (pCi/ml) in air breathed by any                      inate or lower the potential for further expo worker (as obtained when measurements of                            sures should be implemented.


3.      Types of Bioassay that are Performed a.      Baseline (pre-employment or preoperational). Before beginning work with radioactive iodine in sufficient quantity that bioassay is necessary, as specified in C.1.a through C.1.c.
radioiodine concentrations in air are required)
does not exceed 25% of the concentration values                                (d) A repeat bioassay        should be for "soluble"(s) iodine given in Appendix B to                      taken within 2 weeks of the previous measure
10 CFR Part 20, Table I, Column 1, (5 x 10-9                      ment and should be evaluated within 24 hours pCi/ml for 1-125 and 9 x 10-9 pCi/ml for 1-131),                   after measurement in order to confirm the i.e., 25% of these concentrations multiplied by                    presence of internal radioiodine and to obtain the total air breathed by an employee at work                      an estimate of its effective half-life for use in during one calendar quarter, 6.3 x 108 ml,                          estimating dose commitment.


b.       Routine. As described in C.1.a through C.1.c, at the frequency specified in C.4.
does not exceed 0.8 pCi of 1-125 or 1.4 pCi of
1-131. The appropriate proportionate amounts                                  (e) Reports or notification must be of a mixture of these nuclides should be used                      provided as required by §§ 20.405,        20-408, as a guide when both 1-125 and 1-131 are                            and 20.409 of 10 CFR Part 20 or as required present; and                                                        by conditions      of the license pursuant      to
                                                                    § 20.108 of 10 CFR Part 20.


c.      Emergency. As soon as possible after any incident that might cause thyroid uptakes to exceed the PAL specified in C.5.b., bioassays (including the initial post-event bioassays and all subsequent diagnostic bioassays) should be performed as discussed in C.5.b.
(3) The working corditions during the
3-month period with respect to the potential for                          (2) If the thyroid burden at any time exposure are representative of working condi                        exceeds 0.5 pCi of 1-125 or 0.14 pCi of 1-131, tions during the period in which the quarterly                      the following actions should be taken:
bioassay frequency will be employed, and there is no reasonable'expectation that the criteria in                              (a) Carry out all steps described in regulatory positions 4.b(1) and 4.b(2) above                        regulatory position 5.a(1).
will be exceeded.


d.       Post-operational and physical separation. A bioassay should be performed within the maximum bioassay duration specified in Table 1 when operations are being discontinued or when the worker is terminating. A contingency plan should be developed to ensure the collection of the post-operational or termination bioassay measurements, to the extent practicable.
(b) As soon as possible, refer the c. After Use of Respiratory Protection De                        case to appropriate medical consultation for vices. Between 6 and 72 hours after respiratory                    recommendations regarding therapeutic proce protective devices, suits, hoods, or gloves are                     dures that may be carried out to accelerate used to limit exposure as stated in regulatory                      removal of radioactive iodine from the body.


Rev. 2 of RG 8.20, Page 6
position 1. e.                                                      This should be done within 2-3 hours after exposure when the time of exposure is known For individuals placed on a quarterly                      so that any prescribed thyroid blocking agent schedule, sampling should be randomly distri                        would be effe,-rive. 4 buted over the quarter but should be done within one week after a procedure involving                                    (c) Carry out repeated measurements the handling of 1-125 or 1-131. This will pro                      at approximately 1-week intervals at least until vide a more representative assessment of expo                      the thyroid burden is less than 0.12 pCi of 1-125 sure conditions                                                    or 0.04 pCi of 1-131. If there is a possibility of longer-term compartments containing 1-125 or
5. Action Points and Corresponding Actions                          1-131 that require evaluation, continue meas a. Biweekly or More Frequent Measurements                      urements as long as necessary to ensure that appreciable exposures to these other compart
        (1) Whenever the thyroid burden at the                    ments do not go undetected.


e.         Diagnostic. Follow-up bioassay should be performed within the maximum bioassay duration specified in Table 1 of any measurements exceeding PAL levels given as action points in C.5 in order to confirm the initial results and, in the case of a single intake, to allow an estimate of the effective half-life of radioiodine in the thyroid.
time of measurement exceeds 0.12 pCi of 1-125 or 0.04 pCi of 1-131, the following actions                                b.  Quarterly Measurements. Carry out should be taken:                                                  actions at levels as indicated under regulatory position 5.a(1) and (2). If measurements and (a) An investigation of the opera                    surveys indicate an appreciable likelihood that tions involved, including air and other in-plant                  a   worker    will  receive  further exposures surveys, should be carried out to determine                        exceeding the criteria of regulatory          posi the causes of exposure and to evaluate the                         tions 4.b(1) and 4.b(2), reinstitute biweekly potential for further exposures.                                    or more frequent bioassays.


f.        Special. As described in C.1.d.
(b) If the investigation           indicates that further work in the area might result in exposure of a worker to concentrations that                                      
 
4.      Frequency of Routine Bioassay The basis for adjusting an individuals bioassay frequency should be documented and retained on site in an auditable form.
 
a.        Initial Routine (within First 3 Months). Except in situations where thyroid contents may exceed the PAL level specified in C.5.a, a bioassay should be performed within the maximum bioassay duration specified in Table 1 following initial entry of an individual into an area where bioassay is performed in accordance with C.1 and C.2 or more frequently thereafter as long as the conditions described in C.1 and C.2 exist. When work with radioactive iodine is on an infrequent basis (less frequently than every 2 weeks),
                    bioassay should be performed within the maximum bioassay duration specified in Table 1 (but not sooner than 6 hours unless emergency actions to obtain an early prognosis and thyroid blocking treatment are appropriate (Ref. 5)).
        b.        Routine after 3 Months. When a periodic measurement frequency has been selected in accordance with C.4.a, it may be changed to quarterly if, after 3 months, all the following conditions are met:
                    (1)      The average thyroid content for each individual working in a given area was less than the PAL specified in C.5.a.
 
(2)      The 3-month average radioiodine concentration in air breathed by the worker (as obtained when measurements of radioiodine concentrations in air are required)
                              did not exceed 25 percent of the DAC values specified in Table 1.
 
(3)      There is no reasonable expectation that the criteria in C.4.b(1) and C.4.b(2) above will be exceeded during the period in which the quarterly bioassay frequency will be employed.
 
5.      Predetermined Action Level If the thyroid contents exceed PAL values, specific actions should be performed. These values and the associated recommended actions are described as follows:
        a.        Whenever the thyroid content at the time of measurement exceeds 1.0 Ci (37 kBq)2, the following actions should be taken:
  2 PAL is based on 131I and the product of the 10 percent of ALI (stochastic) and the intake retention fraction of 0.07 as iodine in the thyroid 8-hours post-intake presented in NUREG/CR-4884, Interpretation of Bioassay Measurement (Ref. 12).
                                                    Rev. 2 of RG 8.20, Page 7
 
(1)      An investigation of the operations involved, including air and other in-plant surveys, should be carried out to determine the causes of exposure and to evaluate the potential for further exposures.
 
(2)      Corrective actions that will eliminate or lower the potential for further exposures should be implemented.
 
(3)      A repeat direct (in vivo) bioassay for thyroid measurement should be performed within 24 hours of the last measurement, in order to confirm the presence of intake. Where direct bioassay is not feasible, indirect (in vitro) bioassay should be performed within 2 weeks of the last measurement or within the maximum bioassay duration specified in Table 1, whichever is less.
 
b.        Whenever the thyroid content at the time of measurement exceeds 5.0 Ci (185 kBq), the following actions should be taken:
            (1)      Carry out all steps described under C.5.a.
 
(2)      As soon as possible, refer the case to appropriate medical consultation for recommendations regarding therapeutic procedures that may be carried out to accelerate removal of radioactive iodine from the body. This should be done within 2-3 hours after exposure when the time of exposure is known so that any prescribed thyroid-blocking agent may be effective. NCRP Report 161 could provide guidance for emergency treatment if a severe intake of radioiodine were to occur.
 
(3)      Carry out repeated measurements at approximately 1-week intervals or within the maximum bioassay duration specified in Table 1, whichever is less, until the thyroid content is less than 1 Ci (37 kBq). If there is a possibility of radioiodine retention in certain parts of the body that requires evaluation, continue bioassay as long as necessary to ensure that appreciable exposures do not go undetected.
 
(4)      If the investigation indicates that further work in the area might result in exposure of a worker to concentrations that would cause the dose limits in
                      10 CFR 20.1201 to be exceeded, the licensee should restrict the worker from further work until the source of exposure is discovered and corrected.
 
c.        Quarterly Measurements3. Carry out actions at levels as indicated under C.5.a. If measurements and surveys indicate an appreciable likelihood that a worker will receive further exposures that do not meet the criteria of C.4.b(1) and C.4.b(2), reinstitute biweekly or more frequent bioassays.
 
3 For individuals placed on a quarterly schedule, bioassay should be randomly distributed over the quarter but should be done within one week after a procedure involving the handling of radioiodine (except that if 123I is the isotope of concern, bioassay should be performed within 1 day after a procedure, due to its short physical half-life.). This will provide a more representative assessment of exposure conditions.
 
Rev. 2 of RG 8.20, Page 8
 
6.      Reports and Notifications to the NRC and Exposed Individual If an overexposure occurs, immediate or 24-hour notifications shall be made to the NRC as required by 10 CFR 20.2202. In addition, a report of the exposure shall be submitted to the NRC as required by 10 CFR 20.2203, and a report shall be sent to the individual as required by 10 CFR 20.2205.


==D. IMPLEMENTATION==
==D. IMPLEMENTATION==
The purpose of this section is to provide information to applicants and licensees regarding the NRCs plans for using this regulatory guide.
would cause the limiting intakes established in The purpose of this section is to provide in ssee Appendix B to this guide for a description and example of using this condition for mixtures                              formation to applicants and licensees regarding
 
                                                            8.20-3
Methods or solutions that differ from those described in this regulatory guide may be deemed acceptable if they provide sufficient basis and information for the NRC staff to verify that the proposed alternative demonstrates compliance with the appropriate NRC regulations. Current licensees may continue to use guidance the NRC found acceptable for complying with the identified regulations as long as their current licensing basis remains unchanged. Backfit and issue finality considerations do not apply to licensees and applicants under 10 CFR Part 20.


Rev. 2 of RG 8.20, Page 9
the NRC staff's plans for using this regulatory                        incorporated in their licenses in                    accordance guide.                                                                 with § 20.108 of 10 CFR Part 20.


GLOSSARY
Except in those cases in which the applicant or licensee proposes an acceptable alternative                            If an applicant or licensee wishes to use the method described in this regulatory guide on method,      the staff will use the methods
annual limit on    The derived limit for the amount of radioactive material taken into the body of an intake (ALI)        adult worker by inhalation or ingestion in a year. ALI is the smaller value of intake of a given radionuclide in a year by the Reference Man that would result in a committed effective dose equivalent of 5 roentgen equivalent man (rem)
[described herein after December 15, 1979, in evaluating the radiation protection programs of licenseer      who have bioassay requirements or before December 15, 1979, the pertinent portions of the application or the licensee's performance will be evaluated on the basis of this guide.
                    (0.05 sievert (Sv)) or a committed dose equivalent of 50 rem (0.5 Sv) to any individual organ or tissue.


assessment          A planned and documented task performed to determine whether various elements within a quality management system are effective in achieving the stated quality objectives.
L
                                                                Table I
                    ACTIVITY LEVELS ABOVE WHICH BIOASSAY FOR 1-125 OR 1-131 IS NECESSARY
                                                                                                        ActivityHandled in Unsealed Form Making Bioassay Necessary$
                                                                                                    Volatile          Bound to or            Nonvolatile Types of Operation                                                      Dispersible*          Agent*
      Processes in open room or bench, with possible escape
                                                                                                      1 mCi                10 mCi of iodine from process vessels Processes with possible escape of iodine carried out                                          10 mCi              100 mCi within a fume hood of adequate design, face velocity, and performance reliability Processes carried out within gloveboxes, ordinarily                                          100 mCi            1000 mCi closed, but with possible release of iodine from process and occasional exposure to contaminated box and box leakage
      'Quantities may be considered the cumulative amount in process handled by a worker during a 3-month period;
      total quantity introduced into a chemical or physical process over a 3-month                                        e.g. , the period, or on one or more occasions in that period, by opening stock reagent containers from which radioactive iodine may escape. Quantities in the right-hand column may be used when it can be shown that activity in process is always chemically bound and processed in such a manner that 1-125 or 1-131 will remain in nonvolatile form and diluted to concentrations less than 0.I mCi/mg of nonvolatile agent. Capsules (such as gelatin capsules given to patients for diagnostic tests) may be considered to contain the radloiodine in nonfre6 form, and bioassay would not be necessary unless a capsule were inadvertently opened (e.g.,
      dr*pped and crushed). However, certain compounds where radiolodine is normaly bound are known to release radioiodine when the material Is in process, and the left-hand column may then be applicable.


bioassay            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 (in-vitro analysis).
In those laboratories working only with I~-1  in radioimmunasaay (RIA) kits, the quantities of [-125 are very small and in less volatile forms; thus, bioassay requirements may be Judged from the right-hand column. In field operations, where reagent containers are opened outdoors for simple operations such as pouring liquid solutions, the above table does not apply; bioassay should be performed whenever an individual employee handles in open form (e.g. ,
derived air        The concentration of a given radionuclide in air which, if breathed by the concentration      reference man for a working year of 2,000 hours under conditions of light work (DAC)              (inhalation rate of 1.2 cubic meters of air per hour), results in an intake of 1 ALI.
                                                                                an open bottle or container) more than 50 mCt at any one time.


derived air        The product of the average concentration of radioactive material in air during a concentration-hour  specified period (expressed as a fraction or multiple of the derived air (DAC-hour)          concentration) and the duration of exposure to that radionuclide in hours. The DAC-hour expresses an exposure, and 2,000 DAC-hours represent an intake of
Operations involving the routine use of 1-125 or 1-131 in an open room or bench should be discouraged. Whenever practýicsble, sealed bottles or containers holding more than 0.1 mCi of
                    1 ALI, equivalent to a committed effective dose equivalent of 5 rem (0.05 Sv).
                                                                                1-125 or 1-131 should be opened at least initially within hoods having adequate face velocities of 0.5 m/sec or more.
direct bioassay    Measurement of gamma or x-radiation emitted from radioactive material located (in vivo)          within the body for the purpose of detecting or estimating the quantity (and sometimes the location) of radioactive material present.


indirect bioassay  Measurement of radioactivity in samples of material (usually urine and feces)
8.20-4                                                                  L
(in vitro)          excreted or removed from the human body.


intake              Radioactivity that enters the body through the respiratory tract, the gastrointestinal tract, or the skin. Intake may be acute, meaning a single intake occurring over a very short time, usually taken to be instantaneous, or chronic, occurring over a specified time. Common units used in this guide for intake are microcuries (µCi) and kilo-becquerel (kBq).
APPENDIX A
overexposure        Individual doses received in excess of the annual limits listed in Title 10 of the Code of Federal Regulations (10 CFR) 20.1201(a).
                    SUGGESTED REFERENCES TO ASSIST IN ESTABLISHING A BIOASSAY PROGRAM
uptake              The quantity of material that enters the body fluids from the respiratory tract, the gastrointestinal tract, or through the skin. The term also is sometimes used to indicate material taken into a tissue or organ from circulation. Common units used in this guide for uptake are µCi and kBq.
    In response to public comments, this list of publications is provided to assist the licensee in estab lishing measurements and administrative procedures for a bioassay program appropriate to his opera tions. This list is not intended to be exhaustive and does not replace the need for professional assis
!tance in establishing analytical procedures or services.


Volatile/volatility A measure of the tendency of a substance to vaporize.
1. American National Standard, ANSI N44.3-1973,              Radiological Protection,      Pergamon    Press,
      "Thyroid Radioiodine Uptake Measurements                Oxford, p. 17, 1968.


Rev. 2 of RG 8.20, Page 10
Using a Neck Phantom," American National Standards Institute, Inc., 1430 Broadway,            9. ICRP Publication 10A, "The Assessment of New      York,  N.Y.    10018,    approved            Internal    Contamination    Resulting    from August 24, 1973.                                         Recurrent or Prolonged Uptakes," Recom mendations of the International Commission
  2.   R. C. Brown, "1211 Ingestions in Research                on    Radiological    Protection,    Pergamon Personnel," Operational Health Physics,                  Press, Oxford, 1969.


REFERENCES
pp. 276-278,    1976, proceedings of the Ninth Midyear Topical Symposium of the              10. A. L. Orvis, "What Is a 'Reportable' Thy Health Physics Society, Denver, Colorado,                roid Burden?" op. cit., Ref. 2., pp. 268 February 1976 (P.       L. Carson, W. R.                271.
1Title 10 of the Code of Federal Regulations, 10 CFR Part 20, Standards for Protection against Radiation. U.S. Nuclear Regulatory Commission, Washington, DC.4
2. Regulatory Guide 8.9, Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program. U.S. Nuclear Regulatory Commission, Washington, DC.


3Regulatory Guide 8.25, Air Sampling in the Workplace. U.S. Nuclear Regulatory Commission, Washington, DC.
Hendee, and D C. Hunt, Eds., Central Rocky Mountain Chapter, Health Physics              11P. Plato, A. P. Jacobson, and S. Homan, Society, P.O. Box 3229, Boulder, Colorado                "In Vivo Thyroid Monitoring for Iodine-131
      80303, $15).                                            in the Environment,"        Int. J. A lied Radiat. and Isotopes, vol. 27, pp          539
  3. E. J. Browning, K. Banerjee, and W. E.                    545, 1976.


4. NUREG/CR-1556, Consolidated Guidance about Materials Licenses: Program-Specific Guidance about Medical Use Licenses. U.S. Nuclear Regulatory Commission, Washington, DC,
Reisinger, Jr., "Airborne Concentration of
    2008.
      1-131 in a Nuclear Medicine Laboratory," J.        12. Radiological Protection Bulletin 25, "Safe Nucl. Med., vol. 19, pp. 1078-1081, 1978.                Working with Iodine-125," National Radio logical Protection Board, Harwell, Didcot,
  4. J. G. Dare and A. H. Deutchman, "The                      Oxon, England, pp. 19-20, 1978.


5.  National Council on Radiation Protection and Measurements (NCRP) Report 159, Risk to the Thyroid from Ionizing Radiation. Bethesda, MD, 2008. 5
Decay Scheme of Iodine-125 and Its Rela tionship to Iodine Bioassay," op. cit.,             13. R. P. Rossi, J. Ovadia, K. Renk, A. S.
6. NCRP Report 161, Management of Persons Contaminated with Radionuclides.


Bethesda, MD, 2008.
Ref. 2, pp. 250-254.                                    Johnston,     and S.      Pinsky,    "Radiation Safety Considerations in the Management of
  5.  B. C. Fasiska, "Radiation Safety Proce                  Patients Receiving Therapeutic Doses of dur,. and Contamination Control Practices                i13I," op. cit., Ref. 2, pp. 279-286.


7. Environmental Protection Agency, Federal Guidance Report No. 11, Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion. Office of Radiation Program, Washington, DC 20460, September
Involved in High Level 1-131 Thyroid Thera py Cases," op. cit., Ref. 2, pp. 287-291.          14. C. T. Schmidt, "Thyroid Dosimetry of 1251 and an Instrumental Bioassay Procedure,"
    1988.6
  6.  A. Gavron and Y. Feige, "Dose Distribu                  Program and Abstracts: Twenty-Third An tion and Maximum Permissible Burden of                              1      bioassay, Environmental
8. International Commission on Radiological Protection (ICRP) Publication 30, Limits for Intakes of Radionuclides by Workers: Part 1. Pergamon Press, Oxford, England, 1979. 7
      1251  in the Thyroid        Gland,"  Health            and   Analytical
9. Book, S.A., Iodine-129 Uptake and Effects of Lifetime Feeding in Rats. Health Physics 1983 July; 45(1):61-66. 8
                                                                                1977. CL-      y    I
10. National Council on Radiation Protection and Measurements Report 75, Iodine-129: Evaluation of Releases from Nuclear Power Generation. Bethesda, MD, 2008.
      Physics, vol. 23, pp. 491-499, 1972.                    Sept. 15, 16,
  7. B. Y. Howard, "Safe Handling of Radio                15. A. Taylor, J. W. Verba, N. P. Alazraki, iodinated Solutions," op. cit., Ref. 2, pp.              and W. C. McCutchen, "Monitoring of 1-125
      247-249.                                                 Contamination Using a Portable Scintillation Camera," J. Nucl. Med., vol. 19, pp. 431
  8. ICRP Publication 10, "Report of Commit                    432, 1978.


11. International Atomic Energy Agency, Safety Guide No. RS-G-1.2, Assessment of Occupational
tee IV on Evaluation of Radiation Doses to Body Tissues from Internal Contamination            16. Technical Reports Series No. 148, "Control Due to Occupational Exposure," Recommen                  of Iodine in the Nuclear Industry," Inter dations of the International Commission on              national Atomic Energy Agency, Vienna, 1973.
4 Publicly available NRC published documents are available on line through the NRC Library on the NRCs public Web site at http://www.nrc.gov/reading-rm/doc-collections/. The documents can also be viewed online or printed for a fee in the NRCs Public Document Room (PDR) at 11555 Rockville Pike, Rockville, MD; the mailing address is USNRC
    PDR, Washington, DC 20555; telephone 301-415-4737 or (800) 397-4209; fax (301) 415-3548; and e-mail pdr.resource@nrc.gov.


5 NCRP reports may be purchased from the publishing organization at http://www.ncrponline.org/Publications/Publications.html.
8,20-5


6 Publication is available at http://www.epa.gov/radiation/docs/federal/520-1-88-020.pdf or may be obtained through the EPA Web site at: http:www.EPA.org.
APPENDIX B
                          CALCULATION OF ACTION LEVELS FOR MIXTURES OF 1-125 AND 1-131
                                                                                                                            -1 B.I Controlling Instantaneous Thyroid Burdens                            period when air concentration data are avail Regulatory position 4.b(1) is based on con                          able to assess the potential exposure of the worker either to random single intakes or to trolling the instantaneous amount in the thy                            variable or constant continuous exposures. The roid and is taken as 25% of the maximum per                              quantities of 0.8 pCi of 1-125 and 1.4 pCi of I
missible organ burden (MPOB) of 1-125 or 1-131                            131 were obtained by calculating 25% of the that would give a dose rate of 0.6 rem/week if                            total quarterly intakes of 3.2 pCi of 1-125 or continuously present in the thyroid. If a mix                            5.7 pCi of 1-131 (see footnote 3) that would be ture of both nuclides is present in the thyroid                          inhaled when breathing a total of 6.3 x 108 ml and X is the fractional activity that is 1-125, a                        per quarter working at the standard man
3-month interval may be resumed when the                                 breathing rate for 40 hours per week for 13 total activity of 1-125 and 1-131 is below                                weeks.


7 ICRP documents may be purchased from the publishing organization at http://www.icrp.org.
0.12X + 0.04(1 - X)                                  Example Example                                                                    If the average quarterly concentrations esti mated from air sampled in a worker's breathing If the measurements of 1-125 and 1-131 in a                          zone are 3 x 10-9 pCi/ml for 1-125 and 5 x 10-f worker's thyroid are 0.10 pCi of 1-125 and 0.05                          pCi/ml for 1-131, the total quarterly intakes pCi of 1-131, the fractional 1-125 activity is                            are:
                  X = 0.10/(0.10 + 0.05)                                    3 x 10-9 x 6.3 x 108 = 1.89 pCi 1-125
                      = 0.667
                                                                            5 x 10-9 x 6.3 x 108 = 3.15 pCi 1-131 Then Total = 5.04 pCi
0.12X + 0.04(1 - X) = 0.12(0.667) + 0.04(0.33)
                              = 0.0932                                    Also, X, the proportion of 1-125, is 1.89/5.04 =
                                                                          0.375 Total= 0.10 + 0.05= 0.15 I.Ci Thus    the control level for maintaining Thus, in this case, the worker involved                              biweekly or more frequent bioassay checks is:    1, should remain on the biweekly (or more fre quent) schedule and should not be put on the                            0.8X + 1.4(1 - X) = 0.8(0.375) + 1.4(1 - 0.375)
quarterly frequency.                                                                   Total = 1. 18 pCi for this mixture.


8 Copies of Health Physics publication may be purchased through their Web site at http://www.hps.org Rev. 2 of RG 8.20, Page 11
B.2 Controlling Total Intakes                                              Since the intake of 5.04 pCi is greater than Regulatory position 4.b(2) is based on con                          1.18, this employee should stay on the more frequent bioassay schedule.


Exposure Due to Intake of Radionuclides. Safety Standards Series, Vienna, Austria, 1999.9
trolling total intakes 6 during a quarterly
12. NUREG/CR-4884, Interpretation of Bioassay Measurements. U.S. Nuclear Regulatory Commission, Washington, DC, July 1987.
    $The limiting total quarterly intakes are in different propor        Note: The numbers of significant digits carried tions for 1-125 and 1-131 than are the MPOBs. This difference                    in the above calculations do not imply is a result of the fact that permissible concentrations are                      any given degree of accuracy of mea inversely proportional to effective half-liver where" an MPOB
is calculated aasuning a constant burden in the organ of con                    surement. Enough digits are carried to cern that is miuntained by continuous intAke of            activity              allow following the arithmetic for pur balanced by an equal rate of elimiation from the organ                          poses of the examples.


9 Copies of International Atomic Energy Agency (IAEA) documents may be obtained through the agencys Web site at:
8.20-6                                                    I}}
    http:www.iaea.org or by writing the International Atomic Energy Agency, P.O. Box 100 Wagramer Strasse 5, A-1400Vienna, Austria. Telephone (+431) 2600-0, Fax (+431) 2600-7, or e-mail at Official.Mail@IAEA.Org Rev. 2 of RG 8.20, Page 12}}


{{RG-Nav}}
{{RG-Nav}}

Revision as of 10:32, 28 March 2020

Applications of Bioassay for I-125 and I-131
ML003739555
Person / Time
Issue date: 09/30/1979
From:
Office of Nuclear Regulatory Research
To:
References
RG-8.020, Rev. 1
Download: ML003739555 (6)


levillm 9 U.S. NUCLEAR REGULATORY COMMISSION 81PSeptaiff 1979 o ..AuIn&..i

1,,

REGULATORY GUIDE

ease, OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 8.20

APPLICATIONS OF BIOASSAY FOR 1-125 AND 1-131

A. INTRODUCTION

vitro of materials excreted or removed from the body..

Section 20. 108, "Orders Requiring Furnish ing of Bioassay Services," of 10 CFR Part 20, Intake-The total quantity of radioactive

"Standards for Protection Against Radiation,' material entering the body.

indicates that the Nuclear Regulatory Commis sion (NRC) may incorporate into a license pro In vivo measurements-Measurement of gamma visions requiring a specific program of or x-radiation emitted from radioactive material bioassay measurements as necessary or located within the body for the purpose of desirable to aid in determining the extent of an detecting or estimating the quantity of radio individual's exposure to concentrations of active material present.

radioactive material. In certain cases, the requirement of bioassay may also be included in In vitro measurements-Measurement of radio the license by reference to procedures specify activity in samples of material excreted from ing in vivo measurements, measurements of the human body.

radioactive material in excreta, or both.

C. REGULATORY POSITION

This guide provides criteria acceptable to the NRC staff for the development and implementa 1. Conditions Under Which Bioassay Is Necessary tion of a bioassay program for any licensee handling or processing 1-125 or 1-131. It a. Routine' bioassay is necessary when an further provides guidance to such licensees individual handles in open form unsealed 2 regarding the selection of workers who should quantities of radioactive iodine that exceed participate in a program to detect and measure those shown in Table 1 of this guide. The possible internal radiation exposure. The guide quantities shown in Table 1 apply to both the is programmatic in nature and does not deal quantity handled at any one time or integrated with measurement techniques and procedures.

as the total amount of activity introduced into a process by an employee over any 3-month

B. DISCUSSION

period.

The topics treated in this guide include de b. When quantities handled in unsealed terminations of (1) whether bioassay should be form are greater than 10% of Table 1 values, performed, (2) frequencies of bioassay, (3)

who should participate, (4) the actions to take *Lines indicate substantive changes from previous issue.

based on bioassay results, and (5) the partic ular results that should initiate such actions. IRoutine means here that an individual is assigned on a sche u**-edand repeatable basis to submit specimens for bioassay or to report for in vivo measurements. Either radiochemical For the user's convenience, the following bioassay of urine or in vivo counting is acceptable to the NRC

terms are presented with their definitions as staff for estimating internal radioactivity burdens or intakes.

In some cases, however, a licensee may wish to corroborate used in this guide: estimates from urinalysis data with in vivo determinations.

Since there are adequate references in the literature to hellp devise bioassay measurements, thia guide does not include Bioassay-The determination of the kind, recommended analytical procedures. Each installation should quantity or concentration, and location of adopt. procedures or obtain services best suited to its own radioactive material in the human body by needs..

direct (in vivo) measurement or by analysis in ;See discussion in the footnote to Table 1 of this guide.

USNRC REGULATORY GUIDES Comments should be sent to the Secretary of the Comm.ison, U.S.

Nuclear Regulatory Commission, Wimington, D.C. 20555, Atten Regltory Guides are issued to describe and make available to the tion: Docketng and Service Branch.

public methods acceptable to the NRC staff of implementing specific arts oh te Comrmision's regulations, to delineate techniques used The guides are lised in the following ten broad divsons:

bythe staff in evaluatg .speificproblems or postulated accidents, or to wovide g to pplicants. Regulatory Guides are not rabsti- I. Power Reactors 6. Products tues for regutons, an compliance with them s not required. 2. Research and Test Reactors 7. Transportation Methods and solut n different from those set out in the will

iakes 3. Fuels and Materials Facilities S. Occupational Health be acceptable if they provide a bade for the findings requiite to the 4. Environmental and Siting 9. Antitrust and Fmandal Review isuance or continuance of a permit or license by the Comm on. S. Materias and Plant Protection 10. General Copies of imued guides may be purchased at the current Government Comments and suggestions for improvements in these guides are Printin# Office price. A msbscrlption service for future guides in spe encouraged at all times, and guides will be revised, as appropriate, to cific divisions is available through the Government Priting Ofrice.

accommodate comments and to reflect new information or experi- Information on the subscription service and current GPO prices may ence. This guide was revised as a result of rubstantive comments be obtained by writing the U.S. Nuclear Regulatory Commision, received from the public and additional staff review. Washington, D.C. 20535, Attention: Publications Sales Manager.

routine bioassay may still be necessary under 3. Types of Bioasays That Should Be Performed certain circumstances. A written justification for not performing such measurements should a. Baseline (preemployment or preopera be prepared and recorded for subsequent re tional). Prior to beginning work with radio view during NRC inspections whenever bio active iodine in sufficient quantity that bio assay is not performed and the quantities assay is specified in regulatory position 1.

handled exceed 10% of the levels in Table 1.

b. Routine. At the frequency specified in c. Except as stated in regulatory posi regulatory position 4.

tion 1.e, bioassay is not required when pro cess quantities handled by a worker are less c. Emergency. As soon as possible after any than 10% of those in Table 1. incident that might cause thyroid uptakes toi exceed burdens given in regulatory posi-i e d. In nuclear reactor installations, employ tion 5.a(2), so that actions recommended inI

ees should be bioassayed by an in vivo count regulatory position 5.a(2)(b) can be most within 30 days after the end of exposure in effective.

work locations where concentrations exceeded, or might have exceeded, 9 x 10-1Q pCi/ml d. Postoperational and with Separation Phys averaged over any 40-hour period. Table 1 and ical. A bioassay should be performed within 2 regulatory position 4 regarding frequency of weeks of the last possible exposure to 1-125 or bioassays are not applicable to reactor 1-131 when operations are being discontinued I licensees. or when the worker is terminating activities with potential exposure to these radionuclides.

e. Special bioassay measurements should e. Diagnostic. Followup bioassay should be be performed to verify the effectiveness of performed within 2 weeks of any measurements respiratory protection devices and protective exceeding levels given as action points in clothing. If an individual wearing a respiratory regulatory position 5 in order to confirm the protective device or protective clothing is sub initial results and, in the case of a single jected to a concentration of 1-125 or 1-131 (in intake, to allow an estimate of the effective any form) in air such that his or her intake half-life of radioiodine in the thyroid.

with no protection would have exceeded the limits specified in paragraph 20.103(a)(1) of

4. Frequency

10 CFR Part 20,3 bioassays should be per formed to determine the resulting actual 1-125 a. Initial Routine. Except in situations or 1-131 intake. These special bioassay proce where thyroid burdens may exceed quantities dures should also be conducted for personnel specified in regulatory position 5.a(2), a bio wearing respirators if for any reason the 1-125 assay sample or measurement should be or 1-131 concentration in air and the duration obtained within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> following entry of an -1

'of exposure are unknowvn or cannot be conser individual into an area where bioassay is I vatively estimated by calculation. performed in accordance with regulatory posi tions 1 and 2 (but waiting at least 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for distribution of a major part of the iodine to the thyroid') and every 2 weeks or more

2. Participation frequently thereafter as long as the conditions;

described in regulatory positions 1 and 21 AUl workers handling radioactive iodine or exist. When work with radioactive iodine is on sufficiently close to the process so that intake an infrequent basis (less frequently than every is possible (e.g., within a few meters and in 2 weeks), bioassay should be performed within the same room as. the worker handling the 10 days of the end of the work period during material) should participate in bioassay pro which radioactive iodine was handled (but not grams described in regulatory position 1. sooner than 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> unless emergency actions to obtain an early prognosis and thyroid

3 blocking treatment are appropriate4).

Muitfplying the concentrations riven in Appendix B to

10 CFR Part 20, Table r, column i, 5 x 10-9 wCi/ml for 1-125 b. After 3 Months. When a periodic meas (soluble) and 9 x 10-9 *Ci/ml for 1-131 (Soluble), by 6 3 x 108 m= gives the corresponding quarterly intake of the respective urement frequency has been selected in iodines by inhalation. These quarterly intakes would be about accordance with regulatory position 4.a, it may

3.2 pCi for 1-125 and 5.7 pCi for 1-131, which would give a be changed to quarterly if, after 3 months, all thyroid dose commitment of about 7. rems to a 20-gram thyroid integrated over all future time using effective half-lives of 41.8 the following conditions sre met:

days for I-I25 and 7.6 days for 1-131 and using a quality factor (QF) of 1.7 to calculate effective disintegration energy in the (1) The average thyroid burden for case of 1-125. (This QF of 1.7 ie used for conservatism, even each individual working in a given area was though the International Commission on Radiological Protection

(1969) and the National Council on Radiation Protection (1971) 4 have published a QF of 1, because some calculations in more NC*RP Report No. 55, "Protection of the Thyroid Gland in recent scientific Literature have suggested the use of QF values the Event of Releases of Radlioodine," National Council on higher than I for electron or beta energies of 0.03 MeV or Radiation Protection and Measurements, Washington, D C.,

less.) August 1, 1977, p. 21.

8.20-2

less than 0.12 pCi of 1-125, less than 0.04 pCi § 20.103 of 10 CFR Part 20 to be exceeded, the of 1-131, and less than the corresponding pro licensee should restrict the worker from portionate amounts of a mixture of these further exposure until the source of exposure nuclides during the initial 3-month period; is discovered and corrected.

(c) Corrective actions that will elim

(2) The quarterly average radioiodine concentration (pCi/ml) in air breathed by any inate or lower the potential for further expo worker (as obtained when measurements of sures should be implemented.

radioiodine concentrations in air are required)

does not exceed 25% of the concentration values (d) A repeat bioassay should be for "soluble"(s) iodine given in Appendix B to taken within 2 weeks of the previous measure

10 CFR Part 20, Table I, Column 1, (5 x 10-9 ment and should be evaluated within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> pCi/ml for 1-125 and 9 x 10-9 pCi/ml for 1-131), after measurement in order to confirm the i.e., 25% of these concentrations multiplied by presence of internal radioiodine and to obtain the total air breathed by an employee at work an estimate of its effective half-life for use in during one calendar quarter, 6.3 x 108 ml, estimating dose commitment.

does not exceed 0.8 pCi of 1-125 or 1.4 pCi of

1-131. The appropriate proportionate amounts (e) Reports or notification must be of a mixture of these nuclides should be used provided as required by §§ 20.405,20-408, as a guide when both 1-125 and 1-131 are and 20.409 of 10 CFR Part 20 or as required present; and by conditions of the license pursuant to

§ 20.108 of 10 CFR Part 20.

(3) The working corditions during the

3-month period with respect to the potential for (2) If the thyroid burden at any time exposure are representative of working condi exceeds 0.5 pCi of 1-125 or 0.14 pCi of 1-131, tions during the period in which the quarterly the following actions should be taken:

bioassay frequency will be employed, and there is no reasonable'expectation that the criteria in (a) Carry out all steps described in regulatory positions 4.b(1) and 4.b(2) above regulatory position 5.a(1).

will be exceeded.

(b) As soon as possible, refer the c. After Use of Respiratory Protection De case to appropriate medical consultation for vices. Between 6 and 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after respiratory recommendations regarding therapeutic proce protective devices, suits, hoods, or gloves are dures that may be carried out to accelerate used to limit exposure as stated in regulatory removal of radioactive iodine from the body.

position 1. e. This should be done within 2-3 hours after exposure when the time of exposure is known For individuals placed on a quarterly so that any prescribed thyroid blocking agent schedule, sampling should be randomly distri would be effe,-rive. 4 buted over the quarter but should be done within one week after a procedure involving (c) Carry out repeated measurements the handling of 1-125 or 1-131. This will pro at approximately 1-week intervals at least until vide a more representative assessment of expo the thyroid burden is less than 0.12 pCi of 1-125 sure conditions or 0.04 pCi of 1-131. If there is a possibility of longer-term compartments containing 1-125 or

5. Action Points and Corresponding Actions 1-131 that require evaluation, continue meas a. Biweekly or More Frequent Measurements urements as long as necessary to ensure that appreciable exposures to these other compart

(1) Whenever the thyroid burden at the ments do not go undetected.

time of measurement exceeds 0.12 pCi of 1-125 or 0.04 pCi of 1-131, the following actions b. Quarterly Measurements. Carry out should be taken: actions at levels as indicated under regulatory position 5.a(1) and (2). If measurements and (a) An investigation of the opera surveys indicate an appreciable likelihood that tions involved, including air and other in-plant a worker will receive further exposures surveys, should be carried out to determine exceeding the criteria of regulatory posi the causes of exposure and to evaluate the tions 4.b(1) and 4.b(2), reinstitute biweekly potential for further exposures. or more frequent bioassays.

(b) If the investigation indicates that further work in the area might result in exposure of a worker to concentrations that

D. IMPLEMENTATION

would cause the limiting intakes established in The purpose of this section is to provide in ssee Appendix B to this guide for a description and example of using this condition for mixtures formation to applicants and licensees regarding

8.20-3

the NRC staff's plans for using this regulatory incorporated in their licenses in accordance guide. with § 20.108 of 10 CFR Part 20.

Except in those cases in which the applicant or licensee proposes an acceptable alternative If an applicant or licensee wishes to use the method described in this regulatory guide on method, the staff will use the methods

[described herein after December 15, 1979, in evaluating the radiation protection programs of licenseer who have bioassay requirements or before December 15, 1979, the pertinent portions of the application or the licensee's performance will be evaluated on the basis of this guide.

L

Table I

ACTIVITY LEVELS ABOVE WHICH BIOASSAY FOR 1-125 OR 1-131 IS NECESSARY

ActivityHandled in Unsealed Form Making Bioassay Necessary$

Volatile Bound to or Nonvolatile Types of Operation Dispersible* Agent*

Processes in open room or bench, with possible escape

1 mCi 10 mCi of iodine from process vessels Processes with possible escape of iodine carried out 10 mCi 100 mCi within a fume hood of adequate design, face velocity, and performance reliability Processes carried out within gloveboxes, ordinarily 100 mCi 1000 mCi closed, but with possible release of iodine from process and occasional exposure to contaminated box and box leakage

'Quantities may be considered the cumulative amount in process handled by a worker during a 3-month period;

total quantity introduced into a chemical or physical process over a 3-month e.g. , the period, or on one or more occasions in that period, by opening stock reagent containers from which radioactive iodine may escape. Quantities in the right-hand column may be used when it can be shown that activity in process is always chemically bound and processed in such a manner that 1-125 or 1-131 will remain in nonvolatile form and diluted to concentrations less than 0.I mCi/mg of nonvolatile agent. Capsules (such as gelatin capsules given to patients for diagnostic tests) may be considered to contain the radloiodine in nonfre6 form, and bioassay would not be necessary unless a capsule were inadvertently opened (e.g.,

dr*pped and crushed). However, certain compounds where radiolodine is normaly bound are known to release radioiodine when the material Is in process, and the left-hand column may then be applicable.

In those laboratories working only with I~-1 in radioimmunasaay (RIA) kits, the quantities of [-125 are very small and in less volatile forms; thus, bioassay requirements may be Judged from the right-hand column. In field operations, where reagent containers are opened outdoors for simple operations such as pouring liquid solutions, the above table does not apply; bioassay should be performed whenever an individual employee handles in open form (e.g. ,

an open bottle or container) more than 50 mCt at any one time.

Operations involving the routine use of 1-125 or 1-131 in an open room or bench should be discouraged. Whenever practýicsble, sealed bottles or containers holding more than 0.1 mCi of

1-125 or 1-131 should be opened at least initially within hoods having adequate face velocities of 0.5 m/sec or more.

8.20-4 L

APPENDIX A

SUGGESTED REFERENCES TO ASSIST IN ESTABLISHING A BIOASSAY PROGRAM

In response to public comments, this list of publications is provided to assist the licensee in estab lishing measurements and administrative procedures for a bioassay program appropriate to his opera tions. This list is not intended to be exhaustive and does not replace the need for professional assis

!tance in establishing analytical procedures or services.

1. American National Standard, ANSI N44.3-1973, Radiological Protection, Pergamon Press,

"Thyroid Radioiodine Uptake Measurements Oxford, p. 17, 1968.

Using a Neck Phantom," American National Standards Institute, Inc., 1430 Broadway, 9. ICRP Publication 10A, "The Assessment of New York, N.Y. 10018, approved Internal Contamination Resulting from August 24, 1973. Recurrent or Prolonged Uptakes," Recom mendations of the International Commission

2. R. C. Brown, "1211 Ingestions in Research on Radiological Protection, Pergamon Personnel," Operational Health Physics, Press, Oxford, 1969.

pp. 276-278, 1976, proceedings of the Ninth Midyear Topical Symposium of the 10. A. L. Orvis, "What Is a 'Reportable' Thy Health Physics Society, Denver, Colorado, roid Burden?" op. cit., Ref. 2., pp. 268 February 1976 (P. L. Carson, W. R. 271.

Hendee, and D C. Hunt, Eds., Central Rocky Mountain Chapter, Health Physics 11. P. Plato, A. P. Jacobson, and S. Homan, Society, P.O. Box 3229, Boulder, Colorado "In Vivo Thyroid Monitoring for Iodine-131

80303, $15). in the Environment," Int. J. A lied Radiat. and Isotopes, vol. 27, pp 539

3. E. J. Browning, K. Banerjee, and W. E. 545, 1976.

Reisinger, Jr., "Airborne Concentration of

1-131 in a Nuclear Medicine Laboratory," J. 12. Radiological Protection Bulletin 25, "Safe Nucl. Med., vol. 19, pp. 1078-1081, 1978. Working with Iodine-125," National Radio logical Protection Board, Harwell, Didcot,

4. J. G. Dare and A. H. Deutchman, "The Oxon, England, pp. 19-20, 1978.

Decay Scheme of Iodine-125 and Its Rela tionship to Iodine Bioassay," op. cit., 13. R. P. Rossi, J. Ovadia, K. Renk, A. S.

Ref. 2, pp. 250-254. Johnston, and S. Pinsky, "Radiation Safety Considerations in the Management of

5. B. C. Fasiska, "Radiation Safety Proce Patients Receiving Therapeutic Doses of dur,. and Contamination Control Practices i13I," op. cit., Ref. 2, pp. 279-286.

Involved in High Level 1-131 Thyroid Thera py Cases," op. cit., Ref. 2, pp. 287-291. 14. C. T. Schmidt, "Thyroid Dosimetry of 1251 and an Instrumental Bioassay Procedure,"

6. A. Gavron and Y. Feige, "Dose Distribu Program and Abstracts: Twenty-Third An tion and Maximum Permissible Burden of 1 bioassay, Environmental

1251 in the Thyroid Gland," Health and Analytical

1977. CL- y I

Physics, vol. 23, pp. 491-499, 1972. Sept. 15, 16,

7. B. Y. Howard, "Safe Handling of Radio 15. A. Taylor, J. W. Verba, N. P. Alazraki, iodinated Solutions," op. cit., Ref. 2, pp. and W. C. McCutchen, "Monitoring of 1-125

247-249. Contamination Using a Portable Scintillation Camera," J. Nucl. Med., vol. 19, pp. 431

8. ICRP Publication 10, "Report of Commit 432, 1978.

tee IV on Evaluation of Radiation Doses to Body Tissues from Internal Contamination 16. Technical Reports Series No. 148, "Control Due to Occupational Exposure," Recommen of Iodine in the Nuclear Industry," Inter dations of the International Commission on national Atomic Energy Agency, Vienna, 1973.

8,20-5

APPENDIX B

CALCULATION OF ACTION LEVELS FOR MIXTURES OF 1-125 AND 1-131

-1 B.I Controlling Instantaneous Thyroid Burdens period when air concentration data are avail Regulatory position 4.b(1) is based on con able to assess the potential exposure of the worker either to random single intakes or to trolling the instantaneous amount in the thy variable or constant continuous exposures. The roid and is taken as 25% of the maximum per quantities of 0.8 pCi of 1-125 and 1.4 pCi of I

missible organ burden (MPOB) of 1-125 or 1-131 131 were obtained by calculating 25% of the that would give a dose rate of 0.6 rem/week if total quarterly intakes of 3.2 pCi of 1-125 or continuously present in the thyroid. If a mix 5.7 pCi of 1-131 (see footnote 3) that would be ture of both nuclides is present in the thyroid inhaled when breathing a total of 6.3 x 108 ml and X is the fractional activity that is 1-125, a per quarter working at the standard man

3-month interval may be resumed when the breathing rate for 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> per week for 13 total activity of 1-125 and 1-131 is below weeks.

0.12X + 0.04(1 - X) Example Example If the average quarterly concentrations esti mated from air sampled in a worker's breathing If the measurements of 1-125 and 1-131 in a zone are 3 x 10-9 pCi/ml for 1-125 and 5 x 10-f worker's thyroid are 0.10 pCi of 1-125 and 0.05 pCi/ml for 1-131, the total quarterly intakes pCi of 1-131, the fractional 1-125 activity is are:

X = 0.10/(0.10 + 0.05) 3 x 10-9 x 6.3 x 108 = 1.89 pCi 1-125

= 0.667

5 x 10-9 x 6.3 x 108 = 3.15 pCi 1-131 Then Total = 5.04 pCi

0.12X + 0.04(1 - X) = 0.12(0.667) + 0.04(0.33)

0.0932 Also, X, the proportion of 1-125, is 1.89/5.04

0.375 Total= 0.10 + 0.05= 0.15 I.Ci Thus the control level for maintaining Thus, in this case, the worker involved biweekly or more frequent bioassay checks is: 1, should remain on the biweekly (or more fre quent) schedule and should not be put on the 0.8X + 1.4(1 - X) = 0.8(0.375) + 1.4(1 - 0.375)

quarterly frequency. Total = 1. 18 pCi for this mixture.

B.2 Controlling Total Intakes Since the intake of 5.04 pCi is greater than Regulatory position 4.b(2) is based on con 1.18, this employee should stay on the more frequent bioassay schedule.

trolling total intakes 6 during a quarterly

$The limiting total quarterly intakes are in different propor Note: The numbers of significant digits carried tions for 1-125 and 1-131 than are the MPOBs. This difference in the above calculations do not imply is a result of the fact that permissible concentrations are any given degree of accuracy of mea inversely proportional to effective half-liver where" an MPOB

is calculated aasuning a constant burden in the organ of con surement. Enough digits are carried to cern that is miuntained by continuous intAke of activity allow following the arithmetic for pur balanced by an equal rate of elimiation from the organ poses of the examples.

8.20-6 I