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| {{Adams | | {{Adams |
| | number = ML081140498 | | | number = ML003739243 |
| | issue date = 07/01/2008 | | | issue date = 06/30/1974 |
| | title = (Revision 1), General Safety Standards for Installations Using Nonmedical Sealed Gamma-Ray Sources | | | title = General Safety Standard for Installations Using Nonmedical Sealed Gamma-Ray Sources |
| | author name = | | | author name = |
| | author affiliation = NRC/RES | | | author affiliation = NRC/RES |
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| | docket = | | | docket = |
| | license number = | | | license number = |
| | contact person = Orr M/RES/415-6373 | | | contact person = |
| | case reference number = DG-6006
| | | document report number = RG-6.5 |
| | document report number = RG-6.500, Rev 1 | |
| | package number = ML081140458
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| | document type = Regulatory Guide | | | document type = Regulatory Guide |
| | page count = 4 | | | page count = 2 |
| }} | | }} |
| {{#Wiki_filter:U.S. NUCLEAR REGULATORY COMMISSION | | {{#Wiki_filter: |
| July 2008 Revision 1REGULATORY GUIDE
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| OFFICE OF NUCLEAR REGULATORY RESEARCH
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| REGULATORY GUIDE 6.5 (Draft was issued as DG-6006, dated January 2008)
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| GENERAL SAFETY STANDARDS FOR INSTALLATIONS USING NONMEDICAL SEALED GAMMA-RAY SOURCES
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| ==A. INTRODUCTION== | | ==A. INTRODUCTION== |
| This guide directs the reader to the type of information acceptable to the U.S. Nuclear Regulatory Commission (NRC) to approve the initial transfer of devices containing byproduct material to persons generally licensed under Title 10, Section 31.5, "Certain Detecting, Measuring, Gauging, or Controlling Devices, and Certain Devices for Producing Light or an Ionized Atmosphere," of the Code of Federal Regulations (10 CFR 31.5) (Ref. 1) or equivalent regulations of an Agreement State.
| | Section 20.101, "Exposure of Indcividuals to Radia tion in Restricted Areas," of 10 CFR Part 20, "Stand ards for Protection Against Radiation," provides that, subject to certain enumerated exceputios, no licensee shall xces, use, or transfer licensed material in such a manner as to cause any indiidual in a restncted area to receive a dose in excess of the limits specified therein. |
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| The requirements for transferring gamma-ray sources to general licensees appear in 10 CFR 32.51, "Byproduct Material Contained in Devices for Use Under § 31.5; Requirements for License to Manufacturer, or Initially Transfer" (Ref. 2). One method of complying with the requirements of 10 CFR 32.51 appears in NUREG-1556, Volume 3, "Consolidated Guidance about Materials Licenses: Applications for Sealed Source and Device Evaluation and Registration" (Ref. 3).
| | Paragraph (c) of §20.1 provides that licensees, in addition to complying with the requirements set forth m Part 20, should make every reasonable effort to maintain radiation exposures as far below the limits specified in Part 20 as practicable. |
| This regulatory guide endorses the description of the information to be submitted in the application for the initial transfer and installation of sealed gamma-ray sources contained in the current revision of Volume 3 of NUREG-1556 as a method acceptable to the NRC staff.
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| Volume 3 of NUREG-1556 provides the applicants and reviewers with information concerning how to file a request, a listing of the applicable regulations and industry standards, policies affecting evaluation and registration, administrative procedures to be followed, information on how to perform the evaluation and write a registration certificate, and the responsibilities of the registration certificate holder. The NRC issues regulatory guides to describe and make available to the public methods that the NRC staff considers acceptable for use in implementing specific parts of the agency's regulations, techniques that the staff uses in evaluating specific problems or postulated accidents, and data that the staff needs in reviewing applications for permits and licenses. 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.
| | This guide describes general safety practices which are acceptable to the Regulatory staff a methods for nonmedical users of sealed garnrna-ray sources to corn ply, in part, with the above Commrnission regulations. |
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| This guide was issued after consideration of comments received from the public.
| | Basic to this general safety standard are the use of appropriate equipment, ample shielding, and safe oper ating procedures. |
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| Regulatory guides are issued in 10 broad divisions C1, Power Reactors; 2, Research and Test Reactors; 3, Fuels and Materials Facilities; 4, Environmental and Siting; 5, Materials and Plant Protection; 6, Products; 7, Transportation; 8, Occupational Hea lth; 9, Antitrust and Financial Review; and 10, General.
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| Electronic copies 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's Electronic Reading Room at http://www.nrc.gov/reading-rm/doc-collections/ and through the NRC's Agencywide Documents Access and Management System (ADAMS) at http://www.nrc.gov/reading-rm/adams.html, under Accession No. ML081140498.
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| Rev. 1 of RG 6.5, Page 2 Radiation safety programs for sealed gamma-ray sources or devices are structured on two key points. First, the byproduct material will not breach its containment and contaminate the environment or unnecessarily expose individuals to radiation. Second, the sealed source or device will be installed and operated correctly and in accordance with the manufacturer's instructions. Regulatory Guide 6.4, "Verification of Containment Properties of Sealed Radioactive Sources," discusses verification of the byproduct containment system. This guide directs the reader to the type of information necessary for the NRC to review the safety standards for the installation of the source or device.
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| This regulatory guide contains information collection requirements covered by 10 CFR Parts 31, and 32 that the Office of Management and Budget (OMB) approved under OMB control numbers 3150-0016, 3150-0001, 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.
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| ==B. DISCUSSION== | | ==B. DISCUSSION== |
| As part of its redesign of the materials license program, the NRC consolidated and updated numerous guidance documents for material licenses into the multivolume NUREG-1556. Various volumes in the NUREG-1556 series provide current, program-specific guidance on testing, licensing, decommissioning, and terminating materials licenses.
| | American National Standards Institute Subcommittee N43-5 has revised National Bureau of Standards Hand book 93, "Safety Standard for Non-Medical X-Ray and Sealed Gamma-Ray Sources," and the revised standard, designated ANSI N543-1974 1 and now entitled "Gen eral Safety Standard for Installations Using Non-Medical X-Ray and Sealed Gamma-Ray Sources," was approved by the American National Standards Institute in 1974. The standard provides recommendations for appropriate |
| | 'Copwe., ma, bc o bý3 aied fromtn the A-,mencan NationaJ Standards Inst:lutc, In,.. '430 ay, Nevttr York, Ne'S r York 10018.Jun8e 1974 GUIDE equipment, shielding, and operating procedures. |
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| Volume 3 of NUREG-1556 provides guidance to applicants for requests for sealed source or device safety evaluations and registrations. It also provides reviewers of such requests with the information and materials necessary to determine that the products are acceptable for licensing purposes. It provides the applicants and reviewers with information concerning how to file a request, a list of the applicable regulations, industry and consensus standards, policies affecting evaluation and registration, administrative procedures to be followed, information on how to perform the evaluation and write a registration certificate, and the responsibilities of the registration certificate holder.
| | Con tamied in appendixes to the standard are guiddTce and extensive data for use in deter-rruruuon of se d barrier thicknees for inrstallatcon.s usiig XVra,, e-uip mernt or sealed sources of cobaJt-6,0. |
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| Many of the volumes of NUREG-1556 also contain appendices that include (1) copies of necessary forms, (2) sample applications and completed examples for different types of applications, and (3) examples of the types of supporting information, such as implementing procedures that the applicant may need to prepare. The NRC is placing added emphasis on conducting its regulatory activities in a risk-informed and performance-based manner. This approach is intended to be less prescriptive and to allow licensees the flexibility to implement the agency's regulations in a manner that is more specific to their needs yet still meets the regulatory requirements. By supplying examples, the NRC seeks to provide information to meet the needs of applicants for licensure without being prescriptive. Guidance in NUREG-1556 represents one means of complying with NRC regulations and is not intended to be the only means of satisfying the regulatory requirements.
| | cesiurr.,3 indirm-192. |
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| Rev. 1 of RG 6.5, Page 3
| | C. REGULATORY |
| | POSITION The requirements and recommended practices con tamed in ANSI N543 1 are acceptable for the construc tion and use of installations unng sealed pmma-ra> sources for nonmedical purposs subject to the follo,.w ing: 1. Table I of ANSI N543 lists maximum permissible dose lirmts. In lieu of those listed limits, the user of this guide should refer to the dose limits prescribed by 10 CFR Part 20, -Standards for Protection Against Radiation." Every reasonable effort shoulc be made to maintain radiation exposures as far below these lirris as practicable. |
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| ==C. REGULATORY POSITION==
| | 2. The words "Cauton" and "Danger" may be used intrchan ably on warning |
| This regulatory guide endorses the description of the information to be submitted in the application for the initial transfer and installation of sealed gamma-ray sources contained in the current revision of NUREG-1556, Volume 3, as a process that the NRC has found to be acceptable.
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| ==D. IMPLEMENTATION== | | ===3. Paragraph === |
| The purpose of this section is to provide information to applicants and licensees regarding the NRC's plans for using this regulatory guide. The NRC does not intend or approve any imposition or backfit in connection with its issuance.
| | 3.1.7 of ANSI N5-43 implies that osees oi" rrdlLhrerns in any one hour and 100 rrnllirerns in an;. seven consecutive days are absoluute hrruts imposed the Comrmssion for expcoures in unrestnrcted areas. The user of this guide is directed to §20.105(a) |
| | of 10 CFR Part 20 which provides that, Lnder certair conditions, the Commission will approve dos hmits greater than 2 millirems mn any one hoJr and 10C millirems in an', seven consecuove days |
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| In some cases, applicants or licensees may propose or use a previously established acceptable alternative method for complying with specified portions of the NRC's regulations. Otherwise, the methods described in this guide will be used in evaluating compliance with the applicable regulations for license applications, license amendment applications, and amendment requests.
| | ===4. Paragraphs === |
| | 3.2.5 and 3.4.3 of ANSI .N543 ,rpl. a dose rate of 5 mdllirems per hour is tre on., USAEC REGULATORYf GUIDES COP~-" Of ;.0Vp.dS qW 'd" L, OCý@ W t" 14,0a, N~ -e' -,, Rmqa~o, G ,4j 11ý 100ý tw 1d o tV >bC 0"'sdto "N4 ,S, Atc'-c Ewe-, Co,- 16,,0a owh-rc 2a1to' .A IV,'. h ~ .4,. C C-#~c tb. aý ,~ .~ o '.~, Am*!, ,"o D0 CO 00 Rp, t.-ao,- S'-'' Co,.-ý',.. |
| | ff'3d ~ AE 91,t~ -10 1a A6 11 aI ,f 0, *~' '9-~ D.K I " 0"t, Of oa~* t ' * .t ý t& .-a' ~diC~30 .''t 4S I h Co.,. o '..-or O o. -,.. _- 0, ,, "of at~ , Of T"a CO'-samo" U.S A',-'c Er'* Co-msrn YC-' Wa," VC -.C ~2o, "I"e- 1b &CJ -Pr , C I~O ýf 0, 004tWbcb c-%0-C o-ocot Oj-'Cý8a64 to Art*,!o, O C "'fr P~ý P-o'c**6 p. SLt Ir *rc ao-n R -..g..r,oy G-6d. '-, 0 S,o! !.,~ fo, .9,t "I, 4"I*". crm --tf [he Is -WOf , -ý J44 , ok a"< *0 .,f- ,ffa, -~.f '0.- tQ44 10 ,, Ttw qu 09*im .4' ''I c 17 o.. q t #- c. u it -.o -s" t he 9,,-d -.1I Do `oCa*Ofsb. |
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| Rev. 1 of RG 6.5, Page 4 REFERENCES
| | ' f ', WC-0.O a t-S fo, Tra f,,d- roo pr ~tt o the u*,Ks-0 0' 1 of a pa'-! ~o- hce-'A by tht Co.,vm-so, I Pl R4 0 6POt, 2 Afta'dh w.4 Tts' R*,cioi 3 ~.'ta W a, wdah F...,t-ý- |
| 1. 10 CFR Part 31, "General Domestic Licenses for Byproduct Material," U.S. Nuclear Regulatory Commission, Washington, DC. | | 8 0ý.p Oc P b M3 ~. 9 d., -3 ta '- -o to ,.oOg 4 E- Itao-a -.ý I-co''-ca- |
| | 4ý a~~or 14a Si -1 9 A't r-1 RAl ta-a. C C-' 11 W v to ' 1aý-r-,. rIr'r o.- &, wV*&i'., 6 Ut. i a PaProlu-ct-., tO0 a U.S. ATOMIC ENERGY COMMISION |
| | REGULATORY |
| | DIRECTORATE |
| | OF REGULATORY |
| | STANDARDS |
| | REGULATORY |
| | GUIDE 6.5 GENERAL SAFETY STANDARD FOR INSTALLATIONS |
| | USING NONMEDICAL |
| | SEALED GAMMA-RAY |
| | SOURCES |
| | craterion for determining a radiation area. The user of Or-' guide is directed to §20.202(bX2) |
| | of 10 CFR P.j, r 20 which provides that does levels of either 5 mhlirenis in any one hour or 100 miliirems in any 5 c,,iseculive days may be used to determine a radiaarea 5. Ii addition to the rate of exposure provisions in paragraph |
| | 3.3.3 of ANSI N543, the user of this guide is directed to the requirements of 10 CFR 20.105, "Per-missible Levels of Radiation Exposure in Unre stricted Areas." The requirements of §20.105 should also be considered when applying Appendix B of ANSI N543, "Determination of Gamma Ray Shield ing Barrier Thicknesses." |
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| 1 2. 10 CFR Part 32, "Specific Domestic Licenses to Manufacture or Transfer Certain Items Containing Byproduct Material," U.S. Nuclear Regulatory Commission, Washington, DC.
| | ===6. Piragraph === |
| | 6.5.2 of ANSI N543 permits the use of a suitable lock in place of an interlock for a temporary exposure room. The user of this guide should comply with the specific provisions of §§20.203(cX2Xiii) |
| | and 2O.203(cX4) |
| | of 10 CFR Part 20 if he elects to use a lock in place of an interlock. |
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| 3. NUREG-1556, Volume 3, "Consolidated Guidance about Materials Licenses: Applications for Sealed Source and Device Evaluation and Registration," U.S. Nuclear Regulatory Commission, Washington DC, most current date and revision.
| | ===7. Paragraph === |
| | 7.2 of ANSI N543 lists cqanges which require a radiation protection resurvey or reevalua tion by a qualified expert. A resurvey or reevaluation should also be performed when a change in radiation source may have adversely affected radiation protec tion. |
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| 2 (http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr1556/)
| | ===8. Paragraph === |
| | 8.4.6 of ANSI N543 recommends consider ation of the guidance provided in ANSI N13.6-1966(R1972), "American National Standard Practice for Occupational Radiation Exposure Records Systems." The user of this guide should also consider Regulatory Guide 8.7, "Occupational Radia tion Exposure Records Systems," which provides an acceptable definition of "bioassay" and notes that records must be maintained in accordance with §20.401 of 10 CFR Part 20. 9. Appendix A of ANSI N543 proides guidance for planning shielding where adequate occupancy data are not available or when complete installation use data are not available. |
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| 1 All NRC regulations listed herein are available electronically through the Electronic Reading Room on the NRC's public Web site, at http://www.nrc.gov/reading-rm/doc-collections/cfr/. Copies are also available for inspection or copying for a fee from 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 email PDR@nrc.gov. 2 The multivolume NUREG-series report listed herein was published by the U.S. Nuclear Regulatory Commission. These volumes are available electronically through the Electronic Reading Room on the NRC's public Web site, at http://www.nrc.gov/reading-rm/doc-collections/nuregs/. Copies are also available for inspection or copying for a fee from 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 email PDR@nrc.gov. In addition, copies are available at current rates from the U.S. Government Printing Office, P.O. Box 37082, Washington, DC 20402-9328, telephone (202) 512-1800; or from the National Technical Information Service (NTIS), at 5285 Port Royal Road, Springfield, VA 22161, online at http://www.ntis.gov, by telephone at (800) 553-NTIS (6847) or (703) 605-6000, or by fax to (703) 605-6900.}}
| | Persons using the occupancy factors and use factors in Appendix A for planning purposes should make appropriate observations and records to substantiate use of factors less than 1.2 L}} |
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Category:Regulatory Guide
MONTHYEARML24038A3102024-04-30030 April 2024 Rev 1 Dedication of Commercial-Grade Items for Use in Nuclear Power Plants ML23286A2512024-02-0202 February 2024 Watermarked DG-5073 - Fitness for Duty Program for Part 53 - 10-13-23 ML23263A9972024-02-0202 February 2024 Watermarked - DG-5072 - Rev 0 of RG 5.90 - Guidance for Alternative Physical Security Requirements for Small Modular Reactors and Non-Light-Water Reactors ML23286A2682024-02-0202 February 2024 Watermarked - DG-5074 - Access Authorization - Econcurrence Version Clean (02-03-23) ML23286A2782024-02-0202 February 2024 Watermarked - DG-5075 - Cyber Security 10-13-23 ML23286A2822024-02-0202 February 2024 Watermarked - DG-5076 - Physical Protection for Part 53 - 10-13-23 ML23286A2862024-02-0202 February 2024 Watermarked - DG-5078, Fatigue Management for Nuclear Power Plant Personnel -10-13-23 ML23194A1942023-08-31031 August 2023 Draft Regulatory Guide DG-1404, Revision 1 (RG 1.253 Rev 0) Guidance on Ticap for Non-LWRs ML22165A0722023-02-28028 February 2023 DG-4027, Draft Regulatory Guide 4.2 Supplement 1, Preparation of Environmental Reports for Nuclear Power Plant License Renewal Applications, Revision 2 ML23012A2422023-02-28028 February 2023 DG-1374 RG 1.152 Rev 4 Criteria for Programmable Digital Devices in Safety-Related Systems of Nuclear Power Plants ML23018A2932023-02-16016 February 2023 Draft Regulatory Guide DG-1418 (RG 1.212 Rev 2), Sizing Large Lead-Acid Storage Batteries. (ACRS Copy) Regulatory Guide 5.892022-11-0101 November 2022 Rev.0, Fitness-for-Duty Programs for Commercial Power Reactor and Category I Special Nuclear Material Licensees ML22067A0142022-03-31031 March 2022 Rev 3 ACRS Spent Fuel Heat Generation in an ISFSI ML22048B8222022-02-18018 February 2022 DG-1389 (ACRS Version for 3-16-22 Meeting) - Alternative Radiological Source Terms for Evaluating Design Basis Accidents at Nuclear Power Reactors ML22040A0822021-10-30030 October 2021 Document to Support ACRS Subcommittee Meeting - Redline RG 1.57, Rev 3, Design Limits and Loading Combinations for Metal Primary Reactor Containment System Components ML21167A3512021-06-0101 June 2021 Rev 5 Final Watermarked for ACRS ML21092A1512021-05-0505 May 2021 Rev. 4 ACRS Version ML21092A1342021-05-0505 May 2021 Rev. 2 ACRS Version ML21181A2492021-04-30030 April 2021 Watermark for ACRS Fc Meeting RG 1.9 Rev 5 ML21006A3352021-04-0101 April 2021 DG 1381 for Rev 0 of RG 1.244 - Control of Heavy Loads for Nuclear Facilities ML20168A8832021-04-0101 April 2021 DG-1371, Proposed Rev 6 of RG 1.26, Quality Group Classifications and Standards for Water-, Steam-, and Radioactive-Waste-Containing Components of Nuclear Power Plants ML21006A3372021-04-0101 April 2021 Regulatory Analysis - DG 1381 - Control of Heavy Loads for Nuclear Facilities ML21083A2892021-02-28028 February 2021 Draft for Acrs Review ML21048A4482021-02-17017 February 2021 Rev. 2 ML20120A6312021-01-31031 January 2021 Inservice Inspection Code Case Acceptability, ASME Section XI, Division 1, Revision 20, (DG-1367) ML21011A2312021-01-31031 January 2021 Rev 4 (Draft for ACRS Fc Review on 2-3-21) ML20120A6272021-01-31031 January 2021 ASME Code Cases Not Approved for Use, Revision 7 (DG-1369) ML20120A6292021-01-31031 January 2021 Operation and Maintenance Code Case Acceptability, ASME OM Code, Revision 4, (DG-1368) ML20120A6332021-01-31031 January 2021 Design, Fabrication, and Materials Code Case Acceptability, ASME Section III, Revision 39, (DG-1366) ML21012A1972021-01-12012 January 2021 A Performance-Based Approach to Define the Site-Specific Earthquake Ground Motion, RG 1.208, Revision 0 Regulatory Guide 1.200, Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities2020-12-31031 December 2020 Acceptability of Probabilistic Risk Assessment Results for Risk-Informed Activities ML20183A4232020-12-31031 December 2020 Draft Regulatory Guide DG-1361 (Proposed Rev. 2 to Reg. 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[Table view]Some use of "" in your query was not closed by a matching "". |
A. INTRODUCTION
Section 20.101, "Exposure of Indcividuals to Radia tion in Restricted Areas," of 10 CFR Part 20, "Stand ards for Protection Against Radiation," provides that, subject to certain enumerated exceputios, no licensee shall xces, use, or transfer licensed material in such a manner as to cause any indiidual in a restncted area to receive a dose in excess of the limits specified therein.
Paragraph (c) of §20.1 provides that licensees, in addition to complying with the requirements set forth m Part 20, should make every reasonable effort to maintain radiation exposures as far below the limits specified in Part 20 as practicable.
This guide describes general safety practices which are acceptable to the Regulatory staff a methods for nonmedical users of sealed garnrna-ray sources to corn ply, in part, with the above Commrnission regulations.
Basic to this general safety standard are the use of appropriate equipment, ample shielding, and safe oper ating procedures.
B. DISCUSSION
American National Standards Institute Subcommittee N43-5 has revised National Bureau of Standards Hand book 93, "Safety Standard for Non-Medical X-Ray and Sealed Gamma-Ray Sources," and the revised standard, designated ANSI N543-1974 1 and now entitled "Gen eral Safety Standard for Installations Using Non-Medical X-Ray and Sealed Gamma-Ray Sources," was approved by the American National Standards Institute in 1974. The standard provides recommendations for appropriate
'Copwe., ma, bc o bý3 aied fromtn the A-,mencan NationaJ Standards Inst:lutc, In,.. '430 ay, Nevttr York, Ne'S r York 10018.Jun8e 1974 GUIDE equipment, shielding, and operating procedures.
Con tamied in appendixes to the standard are guiddTce and extensive data for use in deter-rruruuon of se d barrier thicknees for inrstallatcon.s usiig XVra,, e-uip mernt or sealed sources of cobaJt-6,0.
cesiurr.,3 indirm-192.
C. REGULATORY
POSITION The requirements and recommended practices con tamed in ANSI N543 1 are acceptable for the construc tion and use of installations unng sealed pmma-ra> sources for nonmedical purposs subject to the follo,.w ing: 1. Table I of ANSI N543 lists maximum permissible dose lirmts. In lieu of those listed limits, the user of this guide should refer to the dose limits prescribed by 10 CFR Part 20, -Standards for Protection Against Radiation." Every reasonable effort shoulc be made to maintain radiation exposures as far below these lirris as practicable.
2. The words "Cauton" and "Danger" may be used intrchan ably on warning
3. Paragraph
3.1.7 of ANSI N5-43 implies that osees oi" rrdlLhrerns in any one hour and 100 rrnllirerns in an;. seven consecutive days are absoluute hrruts imposed the Comrmssion for expcoures in unrestnrcted areas. The user of this guide is directed to §20.105(a)
of 10 CFR Part 20 which provides that, Lnder certair conditions, the Commission will approve dos hmits greater than 2 millirems mn any one hoJr and 10C millirems in an', seven consecuove days
4. Paragraphs
3.2.5 and 3.4.3 of ANSI .N543 ,rpl. a dose rate of 5 mdllirems per hour is tre on., USAEC REGULATORYf GUIDES COP~-" Of ;.0Vp.dS qW 'd" L, OCý@ W t" 14,0a, N~ -e' -,, Rmqa~o, G ,4j 11ý 100ý tw 1d o tV >bC 0"'sdto "N4 ,S, Atc'-c Ewe-, Co,- 16,,0a owh-rc 2a1to' .A IV,'. h ~ .4,. C C-#~c tb. aý ,~ .~ o '.~, Am*!, ,"o D0 CO 00 Rp, t.-ao,- S'- Co,.-ý',..
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REGULATORY
DIRECTORATE
OF REGULATORY
STANDARDS
REGULATORY
GUIDE 6.5 GENERAL SAFETY STANDARD FOR INSTALLATIONS
USING NONMEDICAL
SEALED GAMMA-RAY
SOURCES
craterion for determining a radiation area. The user of Or-' guide is directed to §20.202(bX2)
of 10 CFR P.j, r 20 which provides that does levels of either 5 mhlirenis in any one hour or 100 miliirems in any 5 c,,iseculive days may be used to determine a radiaarea 5. Ii addition to the rate of exposure provisions in paragraph
3.3.3 of ANSI N543, the user of this guide is directed to the requirements of 10 CFR 20.105, "Per-missible Levels of Radiation Exposure in Unre stricted Areas." The requirements of §20.105 should also be considered when applying Appendix B of ANSI N543, "Determination of Gamma Ray Shield ing Barrier Thicknesses."
6. Piragraph
6.5.2 of ANSI N543 permits the use of a suitable lock in place of an interlock for a temporary exposure room. The user of this guide should comply with the specific provisions of §§20.203(cX2Xiii)
and 2O.203(cX4)
of 10 CFR Part 20 if he elects to use a lock in place of an interlock.
7. Paragraph
7.2 of ANSI N543 lists cqanges which require a radiation protection resurvey or reevalua tion by a qualified expert. A resurvey or reevaluation should also be performed when a change in radiation source may have adversely affected radiation protec tion.
8. Paragraph
8.4.6 of ANSI N543 recommends consider ation of the guidance provided in ANSI N13.6-1966(R1972), "American National Standard Practice for Occupational Radiation Exposure Records Systems." The user of this guide should also consider Regulatory Guide 8.7, "Occupational Radia tion Exposure Records Systems," which provides an acceptable definition of "bioassay" and notes that records must be maintained in accordance with §20.401 of 10 CFR Part 20. 9. Appendix A of ANSI N543 proides guidance for planning shielding where adequate occupancy data are not available or when complete installation use data are not available.
Persons using the occupancy factors and use factors in Appendix A for planning purposes should make appropriate observations and records to substantiate use of factors less than 1.2 L