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{{Adams
{{Adams
| number = ML15054A618
| number = ML003739450
| issue date = 06/30/2015
| issue date = 06/30/1974
| title = Applications of Bioassay for Uranium.
| title = Applications of Bioassay for Uranium
| author name = Sun C
| author name =  
| author affiliation = NRC/RES/DSA
| 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 = RG 8.11
| document report number = RG-8.11
| document report number = DG-8054
| package number = ML15054A611
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 11
| page count = 31
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION
{{#Wiki_filter:}}
Ju ly 2015 OFFICE OF NUCLEAR REGULATORY RESEARCH
Revision 1 REGULATORY GUIDE
  Technical Lead Casper Sun Written suggestions regarding this guide or development of new guides may be submitted through the NRC's 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
.  Electronic copies of this regulatory guide, previous versions of this guide, and other recently issued guides are available through the NRC's 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 NRC's Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading
-rm/adams.html,  under ADAMS Accession No. ML15054A618. The regulatory analysis may be found in ADAMS under Accession No. ML14133A612 and the staff responses to the public comments on DG
-8054 may be found under ADAMS Accession No. ML15014A269.
 
REGULATORY GUIDE
8.11 (Draft was issued as DG
-8054, dated September 2014)  APPLICATIONS
OF BIOASSAY FOR URANIUM 
 
==A. INTRODUCTION==
Purpose  This regulatory guide (RG) describes methods that the staff of the U.S.
 
Nuclear Regulatory Commission (NRC) considers acceptable for the development and implementation of a bioassay program for monitoring the intake of mixtures of uranium isotopes (U
-234, U-235, and U
-238) by occupational ly exposed workers. This RG applies to holders of special nuclear material licenses under Title 10 of the Code of Federal Regulations
(10 CFR), part 70, "Domestic Licensing of Special Nuclear Material
,"  (Ref. 1).      Applicable Rules and Regulations
  10 CFR 20.1204(a), "Determination of Internal Exposure" (Ref.
 
2), states that each licensee shall, when required under 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.
 
10 CFR 20.1201(e), "Occupational Dose Limits for Adults," requires licensees to limit the soluble uranium intake by an individual to 10
milligrams per week in consideration of the chemical toxicity.
 
Related Rules and Regulations
  10 CFR 20.1703(i), "Use of Individual Respiratory Protection Equipment," allows for an estimated dose based upon an assumption that the concentration of radioactive material that is inhaled when respirators are worn is equal to the ambient concentration in air without respiratory protection divided by the assigned protection factor. This regulation requires that if the dose is later found to be greater than the estimated dose, the corrected value must be used; if the dose is later found to be less than the estimated dose, the corrected value may be used.
 
RG 8.11, Rev. 1, Page
2  10 CFR 20.2202, "Notification of Incidents," sets forth the criteria for those events involving byproduct, source, or special nuclear material possessed by the licensee that require either immediate notification or notification within 24 hours.
 
10 CFR 20.2203, "Reports of Exposure, Radiation Levels, and Concentrations of Radioactive Material Exceeding the Constraints or Limits," sets forth the criteria for submitting a written report to the NRC on a reportable event.
 
10 CFR 20.2205, "Reports to individuals of exceeding dose limits," provides that when a licensee is required by 10 CFR 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 exposure data included in the report to the Commission.
 
10 CFR part 70, "Domestic Licensing of Special Nuclear Material," establish es procedures and criteria for the issuance of licenses to receive title to, own, acquire, deliver, receive, possess, use, and transfer special nuclear material and provide for the terms and conditions upon which the Commission will issue such licenses.
 
Related Guidance RG 8.9, "Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program" (Ref. 3), provides methods acceptable to the NRC staff for estimating intake of radionuclides using bioassay measurements.
 
RG 8.22, "Bioassay at Uranium Mills" (Ref.
 
4), describes a bioassay program acceptable to the NRC staff for uranium mills (and applicable portions of uranium conversion facilities where the possibility of exposure to yellowcake dust exists), including exposure conditions with and without the use of respiratory protection devices.
 
RG 8.25, "Air Sampling in the Workplace" (Ref.
 
5), provides guidance on air sampling in restricted areas of the workplace.
 
RG 8.30, "Health Physics Surveys in Uranium Recovery Facilities" (Ref.
 
6), provides guidance on health physics surveys that are acceptable to the NRC staff for protecting workers at uranium recovery facilities (e.g., uranium mills, in
-situ leach facilities, ion exchange recovery facilities, heap leach facilities) from radiation and the chemical toxicity of uranium.
 
RG 4.15, "Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination)
-Effluent Streams and the Environment" (Ref. 7), provides quality assurance (QA) guidance on monitoring measurements that support the radiation and environmental protection programs.
 
The National Council on Radiation Protection and Measurements (NCRP) Report
161, "Management of Persons Contaminated with Radionuclides" (Ref.
 
8), provides guidance for emergency treatment if a severe intake of uranium substances were to occur.
 
RG 8.11, Rev. 1, Page
3  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 NRC's regulations, to explain techniques that the staff uses in evaluating specific problems or postulated accidents, and to provide guidance to licensees and applicants. Regulatory guides are not substitutes for regulations and compliance with them is not require d. 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
, continuance or amendment of a permit or license by the Commission.
 
Paperwork Reduction Act This regulatory guide contains information collection requirements covered by 10 CFR part
20 , "Standards for Protection Against Radiation," and 10 CFR part 70 "Domestic Licensing of Special Nuclear Material," that the Office of Management and Budget (OMB) approved under OMB control number s 3150-0014 and 3150
-0009, respectively. 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==
Reason for Revision RG 8.11 was issued in June 1974 to provide guidance to NRC licensees on methods the staff found acceptable to demonstrate compliance with the then
-current version of NRC's radiation protection regulations in 10 CFR part
20. In a 1991 rulemaking (May 21, 1991; 56 FR 23360), the NRC promulgated amendments to its 10 CFR part 20 regulations, including a renumbering of those regulations. As such, this revision to the guide seeks to achieve alignment with the regulatory structure of
10 CFR part 20 by updating the guide's cro ss-references to the current 10
CFR part 20 regulations.
 
In addition, this revision identifies the bioassay interpretation methods described in NUREG/CR-4884, "Interpretation of Bioassay Measurement" (Ref.
 
9) and RG 8.9, "Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program," as being acceptable methods for the interpretation of bioassay data to estimate intakes and doses. This revision also approves for use certain sections of a voluntary consensus standard, namely, the American National Standards Institute/Health Physics Society (ANSI/HPS)
N13.22-2013 standard, "Bioassay Program for Uranium ," (Ref.1 0) as a means for licensees to demonstrate compliance with the NRC regulations
10 CFR 20.1201(e) and 10 CFR 20.1204(a). 
  Background This RG pertains to uranium bioassay programs in general; however, it does not address issues related to bioassay measurement techniques such as whole body counting and excreta bioassay sampling and measurements.
 
Specific information regarding uranium intake during mining (extracting natural uranium ore from the earth) and milling (leaching uranium from the ore and concentrating it to produce yellowcake, including UO 2 F 2, ammonium diuranate ((NH
4)2 U 2 O 7), uranyl peroxides (UO
4*n H 2O), and uranium trioxide (UO 3)) can be found in RG 8.22, "Bioassay at Uranium Mills."
 
RG 8.11, Rev. 1, Page
4  Licensee determinations regarding participation in the uranium bioassay program should be based on estimates of the type and quantity of intakes that may occur using procedures that are expected to take place at each facility during the monitoring year. The program is confirmatory in that low or zero results may indicate that the measures in the workplace to control uranium materials are effective
, and that no unexpected intakes have occurred. Based on operational experience, licensees may be able to justify adjustments in their bioassay program, such as a reduction in bioassay routine monitoring frequency, the inclusion of fewer workers in the bioassay program, or licensees may seek an alternative bioassay program.
 
Harmonization with International Standards The NRC has a goal of harmonizing its guidance with international standards, to the extent practical. The International Commission on Radiological Protection (ICRP) and the International Atomic Energy Agency (IAEA) have issued a significant number of standards, guidance and technical documents, and recommendations addressing good practices in most aspects of radiation protection. The guidance of this RG is generally consistent with the guidance in the following documents:
  ICRP Publication 30, "Limits for Intakes of Radionuclides by Workers" (Ref. 1 1),  ICRP Publication 60, "Recommendations of the International Commission on Radiological Protection" (Ref. 1 2),    ICRP Publication 66, "Human Respiratory Tract Model for Radiological Protection
" (Ref. 1 3),  ICRP Publication 68, "Dose Coefficients for Intakes of Radionuclides by Workers" (Ref.
 
1 4),  ICRP Publication 71, "Age-Dependent Doses to Members of the Public from Intake of Radionuclides-Part 4 Inhalation Dose Coefficients" (Ref. 1 5),    IAEA Safety Guide RS
-G-1.2, "Assessment of Occupational Exposure due to Intake of Radionuclides" (Ref. 1
6), and  International Organization for Standardization (ISO/IEC) 17025, "General requirements for the competence of testing and calibration laboratories" (Ref.
 
17). The ISO/IEC 17025 specifies the general requirements for the competence to carry out tests and/or calibrations, including sampling. It covers consensus testing and calibration methods for QA.
 
The NRC encourages licensees to consult these and other international documents and implement good practices, where applicable, that are consistent with NRC regulations. It should be noted that some of the recommendations issued by these international organizations do not correspond to the requirements specified in the NRC's regulations. In all cases, the NRC's requirements take precedence.
 
Documents Discussed in Staff Regulatory Guidance This regulatory guide endorses, in part, the use of one or more codes or standards developed by external organizations, and other third party guidance documents.
 
These codes, standards and third party guidance documents may contain references to other codes, standards or third party guidance documents ("secondary references").
If a secondary reference has itself been incorporated by reference into NRC regulations as a requirement, then licensees and applicants must comply with that standard as set forth in the regulation.
 
If the secondary reference has been endorsed in a regulatory guide as an acceptable RG 8.11, Rev. 1, Page
5  approach for meeting an NRC requirement, then the standard constitutes a method acceptable to the NRC staff for meeting that regulatory requirement as described in the specific regulatory guide.
 
If the secondary reference has neither been incorporated by reference into NRC regulations nor endorsed in a regulatory guide, then the secondary reference is neither a legally
-binding requirement nor a "generic" NRC approved acceptable approach for meeting an NRC requirement. However, licensees and applicants may consider and use the information in the secondary reference, if appropriately justified , consistent with current regulatory practice, and consistent with applicable NRC requirements.
 
C.  STAFF REGULATORY GUIDANC
E  The NRC staff considers certain sections of ANSI/HPS N13.22
-2013, "Bioassay Programs for Uranium," acceptable for use as stated in the staff regulatory positions listed below.
 
1. Participation Criteria Licensees should ensure that the appropriate individuals are assigned on a scheduled basis (e.g., quarterly) to submit specimens for bioassay or to report for in
-vivo measurements in the bioassay program. Decisions about which individuals should participate in bioassay programs should be based on the criteria described below:
  a. individuals who could receive certain dose s as stated in 10 CFR 20.1502(a)
or (b);    b. individuals who work with uranium or who are close enough to the chemical process using uranium that exposure and intake is possible (e.g., within a few meters and in the same room as the worker handling the radioactive material); or c. individuals described in Section 5 ("Selection of Individuals for Bioassay") of ANSI/HPS N13.22-2013 and individuals who work under the specified conditions listed in Table 1 ("Implementation Levels: Mass or Activity Levels Above Which at Least Minimum Uranium Bioassay Program Shall be Implemented") of ANSI/HPS N13.22
-2013.    2. Conditions under which Bioassay Should Be Performed Licensees should ensure that bioassays are performed for appropriate conditions. Section 3 ("Establishing the Need for an Internal Dosimetry Program") of ANSI/HPS N13.22
-2013 describes acceptable conditions under which a uranium bioassay should be performed.    3. Types of Bioassay Monitoring that Should Be Performed Licensees should ensure that the types of monitoring implemented by the bioassay program are appropriate for the types of material present at the licensee's facility. For example, inhaled materials of different lung classes will likely call for different monitoring techniques. The procedures and methods described in ANSI/HPS N13.22
-2013 are considered acceptable for selecting and implementing the appropriate monitoring techniques
.    4. Bioassay Frequency In any particular facility, the frequency of bioassays should be based on estimates of the type and quantity of intakes that are likely to occur during the monitoring year.
 
RG 8.11, Rev. 1, Page
6  The bioassay frequencies for routine sampling, as well as for bioassays in other situations, that are described in Section 4.2 ("Frequencies") of ANS/HPS N13.22
-2013, are acceptable. If special circumstances exist at the licensee's facility, a submittal should be provided to NRC for review and assessment of the proposed frequencies. Table 8 of ANSI/HPS N13.22
-2013 prescribes the minimum frequencies of bioassays that are acceptable. Section 4.2.2 ("Other Frequency Situations") of ANSI/HPS N13.22-2013 describes those situations where it may be necessary to sample more frequently than is indicated in Table
8.
 
5. Action Levels and the Associated Actions
 
Licensees should ensure that the appropriate actions are taken based on bioassay results. The action levels for bioassay that are listed in Table 2 ("Urinalysis Action Levels") and Table
7 ("Action Levels for Special Class Y Uranium") and described in Section
6 ("Action Levels and Follow
-up Actions") of ANSI/HPS
N13.22-2013 are acceptable. However, where exposure conditions and the characteristics of the materials differ significantly from those recommended in the ANSI standard, the licensee may modify the derivation of the action levels to conform to local conditions at the facility.
 
6. Limiting Chemical Toxicity and Work Restrictions Soluble uranium is a Class D or Type F aerosol as defined in ICRP Publications 30 and 66 , respectively, based on the retention time in the pulmonary region. The NRC regulation, 10 CFR 20.120 1(e) requires that licensees limit the soluble uranium intake by an individual to
10 milligrams in a week in consideration of chemical toxicity, which may cause damage to the kidneys.  Paragraph 20.120
1(e) also directs licensees to footnote 3 of appendix B of 10 CFR part 20; footnote 3 concerns soluble mixtures of U
-234, U-235 and U-238 in air. Licensees should develop the required procedures to prevent soluble uranium exposures from exceeding this non
-radiological limit.
 
7. Bioassay Interpretation Licensees should ensure that bioassay data is interpreted to estimate intakes and doses using the retention and excretion data. RG
8.9, Section 4 ("Interpretation of Bioassay Measurements"), or in NUREG/CR-4884, "Interpretation of Bioassay Measurements," provide guidance on bioassay interpretation.
 
In addition, commercial software is available for bioassay interpretations and internal dose calculations. For NRC staff to accept the calculations developed by such software, the assumptions relied upon by the licensee, including the conditions of the uranium and sampling information associated with the bioassay result
, should be presented to NRC. The licensee should demonstrate the accuracy of its assumptions (i.e., by verification and validation).
    8. Uranium Air Concentrations Licensees should ensure that uranium concentration in air is appropriately determined. Methods for airborne uranium surveillance and for determining uranium air concentrations are described in
 
RG 8.25, "Air Sampling in the Workplace" and in RG 8.30, "Health Physics Surveys in Uranium Recovery Facilities."  The guidance in RG 8.22, "Bioassay at Uranium Mills," may also be applicable depending on involvement of uranium materials at the licensee's facility.
 
RG 8.11, Rev. 1, Page
7  9.    Quality Assurance (QA)  The "Quality Assurance" procedures of licensee bioassay programs that satisfy the requirements of the ASME standard NQA
-1-19 94, "Quality Assurance Program Requirements for Nuclear Facilities (with Addenda)"
will be deemed acceptable to the NRC staff. The reference to this ASME standard is also included in RG
4.15, "Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination
)-Effluent Streams and the Environment" and in ANSI/HPS N13.22-2013, Section 7, "Quality Assurance and Control."
10. Reports and Notifications to the NRC and Exposed Individual If an overexposure occurs, licensees are subject to the NRC incident reporting requirements in  10 CFR 20.2203 and 20.2205. Licensees should be familiar with these reporting requirements.
 
==D. IMPLEMENTATION==
The purpose of this section is to provide information on how licensees may use this RG. In addition, it describes how the NRC staff complies with the backfitting provisions in 10
CFR 70.76(a)(1).    Use by Licensees Licensees may voluntarily use the guidance in this RG to demonstrate compliance with the underlying NRC regulations.
 
Methods or solutions that differ from those described in this RG 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 (i.e., persons holding a NRC issued license as of the date of issuance of this RG) may continue to use guidance the NRC found acceptable for complying with the identified regulations as long as their current licensing basis remains unchanged. The acceptable guidance may be from the previous version of this RG. Licensees may use the information in this RG for actions which do not require NRC review and approval. Licensees may also use the information in this RG to resolve regulatory or inspection issues.
 
Use by NRC Staff The NRC staff does not intend or approve any imposition or backfitting of the guidance in this RG. The NRC staff does not expect any current licensee to use or commit to using the guidance in this RG, unless such licensee makes a change to its licensing basis. The NRC staff does not expect or plan to initiate NRC regulatory action that would require the use of this RG. Examples of such regulatory actions include the issuance of an order or generic communication, or the promulgation of a rule
, requiring the use of this RG without further backfit consideration.
 
During regulatory discussions on licensee
-specific operational issues, the NRC staff may discuss with licensees various actions consistent with staff positions in this RG, as one acceptable means of meeting the underlying NRC
regulatory requirement s. Such discussions would not ordinarily be considered backfitting
, even if prior versions of this RG are part of the licensee's licensing basis. However, unless this RG is part of the licensee's licensing basis, the staff may not represent to the licensee that the licensee's failure to comply with the positions in this RG constitutes a violation.
 
If a current licensee voluntarily seeks a license amendment or change and (1) the NRC staff's consideration of the request involves a regulatory issue directly relevant to this RG and (2) the specific subject matter of this RG is an essential consideration in the staff's determination of the acceptability of the licensee's request, then the staff may request that the licensee either follow the guidance in this RG 8.11, Rev. 1, Page
8  regulatory guide or provide an equivalent alternative process that demonstrates compliance with the underlying NRC regulatory requirements.
 
Such a request by the NRC staff is not considered backfitting as defined in 10 CFR 70.76(a)(1).
  If a licensee believes that the NRC is either using this RG or requesting or requiring the licensee to implement the methods or processes in this RG in a manner inconsistent with the discussion in this Implementation section, then the licensee may file a backfit appeal with the NRC in accordance with the guidance in NRC Management Directive 8.4, "Management of Facility
-Specific Backfitting and Information Collection"
(Ref. 18) and NUREG-1409, "Backfitting Guidelines" (Ref. 19).       
RG 8.11, Rev. 1, Page
9  REFERENCES
1  1. Title 10 of the Code of Federal Regulations, (10 CFR), part 70, "Domestic Licensing of Special Nuclear Material." U.S.
 
Nuclear Regulatory Commission (NRC), Washington, DC.
 
2. 10 CFR part
20, "Standards for Protection against Radiation." NRC, Washington, DC.
 
3. NRC, Regulatory Guide (RG) 8.9, "Acceptable Concepts, Models, Equations, and Assumptions for a Bioassay Program." NRC, Washington, DC.
 
4. NRC, RG 8.22, "Bioassay at Uranium Mills." NRC, Washington, DC.
 
5. NRC, RG 8.25, "Air Sampling in the Workplace." NRC, Washington, DC.
 
6. NRC, RG 8.30, "Health Physics Surveys in Uranium Recovery Facilities." NRC, Washington, DC.    7. NRC, RG 4.15, "Quality Assurance for Radiological Monitoring Programs (Inception through Normal Operations to License Termination)
- Effluent Streams and the Environment." NRC, Washington, DC.
 
8. National Council on Radiation Protection and Measurements (NCRP) Report 161, "Management of Persons Contaminated with Radionuclides." National Council on Radiation Protection and Measurements, Bethesda, MD, 2008.2  9. NUREG/CR-4884, "Interpretation of Bioassay Measurement." NRC, Washington, DC.
 
10. American National Standards Institute
/Health Physics Society Standard, N13.22
-2013, "Bioassay Programs for Uranium." American National Standards Institute: Health Physics Society, McLean, VA.3  11. International Commission on Radiological Protection (ICRP) Publication 30, "Limits for Intakes of Radionuclides by Workers:  Part 1." International Commission on Radiological Protection, Pergamon Press, Oxford, England, 1979.
 
4                                         
    1  Publicly available NRC
-published documents are available online through the NRC Library on the NRC's 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 NRC's 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
.  2  Copies of the National Council on Radiation Protection and Measurements documents may be obtained through the organization's Web site:  http://www.ncrponline.org/Publications/Publications.html] or by writing to NCRP at 7910 Woodmont Avenue, Suite 400, Bethesda, MD  20814
-3095, telephone 301
-657-2652, fax: 301
-907-8768.  3  Copies of American National Standards Institute documents may be purchased through their Web site at: http://webstore.ansi.org/
.  4  Copies of the International Commission on Radiological Protection (ICRP) documents may be obtained through the organization's Web site: http://www.icrp.org/
or by writing to ICRP at 280 Slater Street, Ottawa, Ontario  K1P 5S9, CANADA, telephone +1(613) 947
-9750, fax: +1(613) 944
-1920.
 
RG 8.11, Rev. 1, Page
10  12. ICRP Publication 60, "Recommendations of the International Commission on Radiological Protection." ICRP, Pergamon Press, Oxford, England , 1991.  13. ICRP Publication 66, Human Respiratory Tract Model for Radiological Protection , 1 st Edition, Pergamon Press, Oxford, England, 1994.
 
14. ICRP Publication 68, "Dose Coefficients for Intakes of Radionuclides by Workers." ICRP, Pergamon Press, Oxford, England, 1994.
 
15. ICRP Publication 71, "Age-Dependent Doses to Members of the Public from Intake of Radionuclides
-Part 4 Inhalation Dose Coefficients." ICRP, Pergamon Press, Oxford, England, 1995.  16. IAEA, Safety Guide No. RS
-G-1.2, "Assessment of Occupational Exposure due to Intake of Radionuclides." International Atomic Energy Agency, Safety Standards Series, Vienna.1999.
 
5  17. International Organization for Standardization (ISO/IEC) 17025:2005, "General requirements for the competence of testing and calibration laboratories." International Organization for Standardization, Geneva, Switzerland. 2005.
 
6 http://www.iso.org/iso/Catalogue_detail?csnumber=39883
.  18. NRC Management Directive 8.4, "Management of Facility
-Specific Backfitting and Information Collection." NRC, Washington, DC.
 
19. NUREG-1409, "Backfitting Guidelines." NRC, Washington, DC
 
5  Copies of International Atomic Energy Agency (IAEA) documents may be obtained through their Web site at: http://www.iaea.org or by writing the International Atomic Energy Agency P.O. Box 100 Wagramer Strasse 5, A
-1400 Vienna, Austria. Telephone (+431) 2600
-0, Fax (+431) 2600
-7, or E-Mail at Official.Mail@IAEA.org.
 
6  Copies of International Organization for Standardization (ISO) documents may be obtained through their Web site at:
http://www.iso.org or by writing the International Central Secretariat, 1, c
 
====h. de la Voie====
-Creuse, CP 56, CH
-1211 Geneva 20, Switzerland. Telephone (+41) 22 749 01 11, Fax (+41) 22 733 34 30, or E-Mail at Central@ISO.org.}}


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Revision as of 17:28, 31 August 2018

Applications of Bioassay for Uranium
ML003739450
Person / Time
Issue date: 06/30/1974
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Office of Nuclear Regulatory Research
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RG-8.11
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