ML20248C945

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Paper Entitled, Radiation Protection Stds:Nrc Perspective, for Presentation at ANS Meeting on 891126-30 in San Francisco,Ca
ML20248C945
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Issue date: 11/26/1989
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  • L RADIATION PROTECTION STANDARDS:

THE NRC PERSPECTIVE Dr. Frank J. Congel U. S. Nuclear Regulatory Commission Washington, DC 20555

,; o (301) 492-1088 Introduction.

The purpose of this paper is to summarize the role and viewpoint of the US Nuclear Regulatory Commission on radiation protection standards, specifically the' major revision of 10 CFR Part 20 and-thei criteria for "below regulatory concern."

NRC Requirements NRC requirements are established by Title 10, Chapter 1, of the Code of Federal Regulations. Part 20, " Standards For Protection Against Radiation,d contains the radiation protection requirements fcr all licensee 3.

Even . though the regulations now fill over a thousand pages, generally they are not detailed enough to constitute working-level standards. The details are provided by approximately 375 regulatory guides, numerous NUREG reports and other supporting h fp$[Q h PDC _ A_ _

F.

documents.

The NRC relies heavily on consensus standards and (especially in radiation protection) the recommendations of authoritative organizations such as the International Commission on Radiological I

Protection (ICRP), the International Commission on Radiation Units and Measurements (ICRU), and the National Committee on Radiation Protection and Measurements (NCRP).

The current ICRP recommendations are strongly theoretically based and therefore difficult to include dirrectly into a practical regulatory program. Impetus to follow ICRP was added January 20, 1987 when President Reagan approved the new " Radiation Protection i Guidance to Federal Agencies for Occupational Exposure." We are proceeding to revise 10 CFR Part 20 so it is generally consistent with ICRP-26. Corresponding changes in numerous other radiation protection standards are expected to follow.

10 CFR Part 20, Standt.rds for Protection Against Radiation The proposal is for 4 complete revision of our basic radiation protection standards. The changes are being made for consistency with the Federal Guidance, ICRP-26 and NCRP-91 rather than to correct deficiencies. The Commissioners, as of July 1, 1989, have not yet approved the proposed revision of Part 20. The final regulation may differ from the staff's proposal.

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'The principal proposed' changes are as follows:

1.

1. Control'of internal doses by limiting.the weighted sum of -doses to the principal body organs, i.e. the

" committed effective dose equivalent;"

2. Limiting the weighted sum of internal' and external doses, .

rather than'having separate limits for each;

3. Limiting the annual dose to ar4y member of the public to 0.1 cSv (rem);
4. Revising the limits on concentrations of airborne radioactivity, now the " derived air concentrations" (DAC), and on concentrations in liquid effluents;
5. Lowering limits on disposal into sanitary sewer systems;
6. Lowering the occupational annual dose limit to 5 cSv

-~

(rems), i.e. eliminating the 5(N - 18) provision;

7. Limiting the dose to a declared pregnant woman to 0.5 cSv (rem) for the gestation period; .
8. Requiring special access controls for "very high radiation areas," [where a dose of 500 cGy (rads) could be received in an hour at a distance of 1 meter from the

source]; and

9. Increasing; requirements on the use of respiratory protection, including a determination of medical fitness by a physician.

There are numerous other provisions that may prove important. For example, the limit on. radon in unfiltered gaseous effluents is 0.1 pCi/L. This limit is about 33% below the average concentration in outdoor air and far below most indoor concentrations.

The proposed Part 20 does not remove the requirement for prior NRC

. approval of incineration of radioactive waste nor does it address "below regulatory concern."

The current proposcl is different in many particulars from the version published for comment in the Federal Register on January i 9, 1986. These differences largely are responses to the 813 public comment letters. Other changes resulted from the backfit analysis (Federal Register, August 29, 1986) and from staff comments.

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l Below Regulatory Concern Nature, technology and our regulatory system present a formidable l i

problem in the control of small quantities of radioactive material.

Nature's contribution was to make all material things radioactive.

I Technology then provided the means to detect and measure the I

1 radioactivity in even the least radioactive of materials. Finally, g 1' .

lL our present regulatory system fails'to' provide a firm basis for excluding any activity. from control. The limits of regulatory p control are being established on an ad hoc basis. An attempt.is o now being made to establish logical and legal bounds but it is a l

formidable problem.

The NRC staff's proposed policy statement on " exemption from l regulatory control" was published for comment on December 12, 1988 ,

in the Federal Register. Over 225 comment letters were received and analyzed. An international workshop on the subject was conducted in October 1988, with representatives of 11 other countries (NUREG/CP-0101). With this background, a revised proposed policy statement was submitted to the Commissioners on June 16,1989. The Commissioners were briefed on July 11,1989 and have not yet responded.

The NRC staff's proposal addresses "e'remption from regulatory control" because "below regulatory concern" is reserved for low level radioactive waste. Also, the NRC would retain the right to verify that the conditions of exemptions were being met. The proposal is for a policy statement that could be used as a basis for either rulemaking or licensing action. The proposal would not establish firm bounds but offers the following criteria:

1. NRC deems it of net benefit to society;
2. the maximum annual dose to any individual would not

~ -.

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- <~ . exceed.0.1 mSv (10.mrems); and

3. the annual collective dose would not exceed 5 person-Sv (500 person-rems).

Practices'would be exempted on a case-by-case basis . The'" net benefit" criterion must be met'in all cases. If the dose criteria are not met,'an specific analysis would be necessary to show the-exemption of the practice would be AIARA.

Summary The NRC'is modifying its radiation protection requirements'to be consistent with ICRP/NCRP recommendations and to avoid undue controls on' trivial risks. The problems are formidable and final resolution of many issues may not occur this calendar year.

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CALL FOR PAPERS su = ^av AMERICAN NUCLEAR SOCIETY p

1989 WINTER MEETING FrNay November 26-30,1989 June 30,1989 San Francisco, California This is the official call for papers for the ANS 1989 Winter Meeting. You an: encouraged to submit summaries of paperr, describing work that is NEW, SIGNIFICANT, and RELEVANT to the nuclear industry. To facilitate an adequate review, a summary of your paper must be in the mail to ANS headquarters by June 30,1989. The National Program Committee will then review your summary and will notify you of their decision to accept or reject it by August 16, 1989. ANS will publish all accepted summaries in the TRANSACTIONS. Yoo will present your paper orally at the meeting and are expected to register for the meeting. You may publish the completed paper elsewhere if you wish, but your summary becomes the property of ANS.

It is your responsibility to protect classified or proprietary information.

GUIDELINES FOR SUMMARIES: Authors must adhere to the guidelines below or the Program Committee may reject their summary. Questions about subject categories may be directed to the representatives listed on page 4.

CONTENT

1. Introduction-state the purpose of the work.
2. Description of the actual work-must be NEW and SIGNIFICANT.
3. Results-discuss their significance.
4. References-if any, must be closely related published works. Minimize the number of references. Do not present a bib-biographical listing.

LENGTH

1. Use at least 450 words, excluding tables and figures.
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1. Tables and figures will be reduced to fit one column (7.5 cm) or two columns (-15 cm). Use lettering that will be at least I mm high after reduction.
2. Use high quality glossy photographs or reproducible black-on white drawings. Attach to original copy of summary.
3. Put each table or figure on a separate page.

FORMAT

1. Type your summary double spaced on one side of the page only.
2. Use SI units (with English units following in parentheses, if desired). Exceptions are made for eV and barns.
3. List references numerically at the end of the summary and te superscript numbers in the text.

PAGE CHARGE 1 ANS charges $165 per final p inted page (prorated) of your summary in the TRANSACTIONS. kttach your institutional l purchase order, with purchase order number, to the original copy of the summary. Otherwise, ANS will bill you person-ally.

TO SUBMIT A

SUMMARY

Fill out pages 2 and 3 of this Call for Papers and attach copies of them to your original and three copies of your summary.

Mail all four sets, postmarked by JUNE 30.1989, to:

Lloyd W. McClure Technical Program Chair Attn: TRANSACTIONS OFFICE American Nuclear Society 555 North Kensington Avenue La Grange Park, IL 60525 USA YOU MUST SUBMIT TOUR COMPLETE SETS OF YOUR SUMMAkY, INCLUDING PAGES 2 AND 3 OF THIS CALL FOR PAPERS, DY JUNE 30,1989.

- - _ _ _ _ _ _ - - _ - _ - _ _ _ _ _ - 1

SUMMARY

COVER SHEET CONTRIBUTF.D/ STIMULATED PAPER INVITED PAPER O h ORIGINAL AND THREE COPlES REQUIRED h TITLE: RADIATION PROTECTION STANDARDS: THE NRC PROSPECTIVE lst Author: FRANM 1 CONAFI ANS Member: Yes Nob Company: NilCl EAR RFGill ATORY COMMISSION . Phone: 301-442 10RR Address: WASHINGTON. D.C. 20555 2nd Author: ANS Member: Yes No Company: Phone:

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Complete the top portion of page 3.

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CONTRIBUTED

SUMMARY

INVITED

SUMMARY

f Subject category number for your ANS Division d summary (from page 4) Chairman who invited you D. K. TRUBEY Alternative subject category number Subject category number (from page 4) 13.9 PUBLICATION INFORMATION Yes No E

Has the substance of this summary been presented or published previously?

If so, give details Has the paper been submitted for publication in a technicaljournal? L

'l if so, give details -

Has this summary been approved for publication by your institution or company?

If not, give details i

THIS COMPLETED

SUMMARY

COVER SHEET AND PAGE 3 OF THIS CALL FOR PAPERS MUST BE ATTACHED

- TO EACH OF THE FOUR SETS OF YOUR

SUMMARY

. DO NOT STAPLE SETS; PLEASE USE PAPER CLIP 3.

1

~

g FILING AND MAILING INFORMATION 1

h (Original cad three copies req 11 red) h ,

THIS IS YOUR MAILING LABEL.

Please print or type 'name and address of author to whom ANS should send correspondence.

1

. Dr. Frank J. Congel Mail Stop 10 E 4 Nuclear Regulatory Commission Washington D.C. 20555 Telephone: 301-492-1088 Commercial:

FIS:

492-1088 s Title or Summary RADIATION PROTECTION STANDARDS: THE NRC PERSPECTIVE b This is to acknowledge receipt of your sommary. Please use the log number above in future conespondence.

, This summary will be considered for inclusion in the program of the American Nuclear Society's 1989 Winter Meeting, San Francisen, Califcenia, November :6-30,1989.

Your paper has been reviewed and: Your paper is being returned without review because:

1. Accepted for presentation. (See Attached 1. It was received too late to be reviewed.

Instructions) 0 2. iiis segiesied that your summary be re. O 2. ii does not compiy with the 450 to,00 vised. (See Attachment) word limit.

3. It is suggested that your summary be com-bined with the summary referenced as Log
  1. (See Attachment)

O 4. ne;ecied. (see Attached Comments) l In all correspondence regarding your summary, please refer to the les Number shown above.

Thank you for submitting this summary.

IJoyd W. McClure ANS Technical Program Chair 1989 Winter Meeting t

f L

g.

s ANS 1989 WINTER MEETING San Francisco, California-November 26-30,1989

. SUBJECT CATEGORIES FOR CONTRIBUTED AND INVITED SESSIONS

1. BIOLOGY AND MEDICINL-M. Guven Yalcmtas (615/574-4495) * *10 4 Safety Margim in Transpunat on and Storage 3.1 Biology and Me&cuw.-General **
  • 10.S Safety Murpm sa hssde Maienal Momiors

" 1.2 Recent Advances m Act valon Analysis * *10 6 Safety Margms in Prubabihsuc Rnk Analyus

    • l .3 Actnanon Analyus of Biological Maienals 11. NUCLEAR REACTOR 5AFETY-Debu Mayimdar (208"l241805)

"1.4 Neutron Acuvaien Analysis for Mercury 11.1 Reactor Safetroeneral 11.2 Thermal and rast Reactor Safety "I Ji Orgamc Syntheus w sth isotopic Carten and Hydrogen

" 1.6 invesugation of Kidney Diseases Uun II .3 Rehabihty and Risk Assessnrnt

2. EDUCATION AND TRAINING--Gregg vier Smith (g Radmnuclules 6816313; IESD] 11.4 Severe Accident Analyus and Mmgation IESD) 2I innovauons m Nulcar Engmrenng IAucation and Trammg 11.5 Off Ceequences of Severe Reactor Accidents ILSDI
  • 2.2 Divnmn Chair's Roundtable: Imegrating 1rammg and IAucauon **ll 6 Safety and Rehabihty of Space Nuclear Power Syuems ILSD)

"2.3 Other Trammg Needs Beyuw! the Requurments 12 70WER-Roger Nelson f504 $95 2869) 12 4 Tutonal- Modu:ar HTGRs *12.1 SP.100 Ground Test Engmeenns

3. ENVIRONMENTAL SCIENCES-Carl Manola (803725 3746) " 12.2 Safety and Rehabihry Imphcatens of Nuclear Power Reactor 31 Environmental Sciences-General Support Systems (NRSDI "3.2 Pubhc Concems About Radioacuve Matenals m the Environment " 12.3 Quahry Achwvetnent. Innuencing the Extemal Vendor

[RPSD] Envronruent "3.3 Rak from Man-Made Versus Naturally Ra&oactwe Matenals " 12 4 Configurauon Management. Are You Operatmg the Plam You

    • 3 4 Radecuve and Tosic Maienal Epidenuological Studies Licensed' (ROD]

a15 Regional Environmental Measurements of Releases from Cmhan " 12 5 Prudence Assessnrnts-Preparauon, Conduct. and Comp.arisons Naicar Facihties " 12 6 Impact of Outude Evaluauan Programs on Engmeenng Excchence C36 Imemanonal Environmemal Concems *12.7 Plam Secunty Systems-Innovauon . Upgrades and issues "3.7 DOE FRMAP Implementa's Program " 12 8 The Role of Nuclear Power m Miugaung the Greenhouse Effect "38 Dose Assessment Under Corr.plca Meleorulogical Conditas (ESD)

"39 Geographic Informanon Systems " 12.9 Recent Flow Stabihty lasues

" 3 10 Chemobyl Accident Environmema! Stu&es IRPSD) " 12.10 Effects of Defense Pmgrarm on Public Percepuon of Commercial

4. FUEL CYCLE AND % ASTE MANAGIMENT-Hassan A. Hassan Nuclear Power Plants (804/385 3208) " 12.11 How Are Individual Plant Enanunatens Waring'[NRSD) 4i Fuel Cycle and Waste Managemen;--Generaf " 12 12 Licensmg issues of Centralind Generstmg Compames "42 Imeracuan Between Reload Design and Fuel Cycle Econonves 13. RADIATION PROTECTION AND SHIELDING-Wsiham Urban "43 Imemanonal Progress m Fuel Repmcessms and Separata (50$r667-4024)

Technology 13. ! Operanonal Ra&auon Pmtection [ ROD)

"44 Current Uuhry Fuel Cycle Cost Evaluation Pracuces 13.2 Radiauon Transpan Methods and Data lMCD)

"4.5 Techmcal & Design Updaic of the LLW Compact Program (ESD) 13 3 Neutronics and Shielding Apphcanom "46 Status of the Yucca Moumam Project 13 4 Source Terms and Accident Analyus 'ESD NRSD1 "47 Wasic '4anagement si DOE Defense Nuclear Facihues [ESD) 13.5 Radisuon Measwement Techniques (LSD)

"48 LLW Disposal Costs for New Facibues " 13.6 Phyucal. Radmboological, and legal Aspects of Hot Parucie.

"49 Advances m Spem-Fuel Handimg and intenm Storage Cask " 13.7 Radiation Protecten Aspects of Radon [IRD)

Dengns " 13 8 shicidmg Design for Spent-Fuel Storage and Transportate Casks "410 % asic Managemem Systems Evalusten and Project Deciuon " 13 9 Radianon Protecton Standards Analyus Simulanons "1310 De Maunu and Below Regulatory Concern IESD, FCWMD)

"4!! %asie isolanon Pdo Plant (WIPP Operanons " 13 11 Performance Assessnem of ILW Disposal Facihtws (ESD.

" 4 12 Regulatory Status of Naturally Occurnne Radioacuve Maiertals FCWMD) and Wastes Below Regulatory Concern IESD. RPSDJ " l3.12 L1W Clasuficaten-Measurement and Analysis (FCWMD; C4.13 Durcuans for Momiored Retnewable Storage Plannmg (LSDj 14 REAC70R OPERATIONS-C. Thomas Snow (701M4-5151)

C4 14 trisutuuanal Public Interaction Dynamics and Techmques Cl4.1 Soluuorn to Presens-Day Plani Operaung Problems C415 Ouhry Operanonal Lapenence with %aste Management IESD. " 14.2 impact of Turbu e Performance and Mamienance on Plant RODI Rehabihiy (PDj

5. FUSION ENERGY-Rchard F. Mattas (312/972 8673) " 14.3 Impact of Stanon Blactout Rulms on Plant Operauons 5i Fuuon Energv-General " 14 4 Avosdmg Plant shutdown Through Design Baus Reconsuruten
6. HUMAN FACTORS-hhihp Berghausen. 3i. (415/6924652) " 14.5 Irr. pact of the Commerenal Nuclear Power Plam Mamtenance Rule "6I Current issues an Human Rehabihry " 14 6 Plam Perfonnance indscators-6 lave or Master?

"'6 2 Acmdatauan and Requahficanon issues (LTD. RODI " 14.7 Stnving for Lacellence Through Profesuonahsm "6.3 Alictnauwe Appruaches to Fulfalhng the Espected NRC Degree " 14 8 Economs Trends in Plam Operauons (PD)

Requirements " 14 9 Non-U.S. Rector Operatmg tapenence-4roblems and Solunans "64 Mental Modehng IPD)

"6.5 Apphcanons of Aruficial imelkgence (AI) m Nuclear f.mgirrenng 15. REACTOR PHYSICS-Charles Rcstdmugh (8171478-1826)

(MCD) 15.1 Reactor Analyus Methods (MCD]

"66 Espen Syuems in Maimenance [fCWMDI 15,2 ncrmrJ Reactor Dengn. Validauon. and Operaung Empenence

7. ISOTOPLS AND RADIATION-Ned Wogman (509'375-2451) 15.3 Fast Reaciar Des gn, vahdsmn, and Operaung Empenence 7.1 Isotopes ard! Radiaten-General 15 4 Nuclear Data and lastrument.umn [ESD)
    • 7.2 Charged Parucle Date-Measurement. Theory, and Evaluauon " 15.5 Renew of the Convnts and Performance of ENDFS.VI (RPSD) "f 5 6 Applsauons of Improved Phyucs Methods in Reactor Momtoring "7.3 Forensic Activanon Analyus (ESD)

"7.4 Acuvemn Analyus of Envimnmental Matenals [ESD) " 15.7 Advances in the Appimatmn of Sensitivity Theory and Data "7.5 Processms and Mordtonng Transuranium Isotopes A@ustmem Techmques for Reactor Analyus "7.6 1AEA Nuclear Malenal Measurement Taget Values 16 REMOTE S YSTEMS TEUNOLLIGY-Fred Ditorenzo (208'52f>7149)

"7.7 Aspects of Matenal Control to Enhance Safeguards *16 i Remcte Waste Packagmr and Handimg [FCWMD)

"7.8 Lapermace with implementation of DOE Order 5633.3 -16.2 Roboucs and Advanced kemote $ystems for Hot Cells "79 Lapenesce an large-Scale landman r w-..mn [ESD. *16.3 Rerrete Handimg and Automauon an Glove Bones KWMD] al6 4 large-Area Remote Handimg'Roboucs "7.10 The Value and Cost of Umversity Researcl Reactors to Sonery al6.5 Remote Handimg'Roboucs m Waste Vatnficanon (ETD) al6 6 Roboucs m Analyucal Operauons

" 7 11 Safeguards Aspects of Spem-Fuel Management (FCWMD) =16 7 Internauonal and Domestic Remote Technolo

8. MATERIALS SCIENCE AND T10iNONY-G. E.1mcas 17. THERMAL HYDRAULICS-Yassm Hassan (409/845 iODU) gy Development (80596140b9) 17.3 General Thermal-Hydraubcs Modchng and Expenmeets
  • 8. I Appicauons of Fernuc Steels for Nuclear Fbwer Systems 17.2 Thermal-Hydraulws Reactor Sysicms
  • 8.2 Malenals Aspects of Fahncauan and Reprocessmg of Lagmd Metal ~17.3 Scalmg and Uncertamues m Computer Code Pre &ctnis Reactor (LMRI fuels {FCWMD) *17.4 Thermal-Hydrauhc Aspeco of Pass we Safety and New Generaten
  • 83 Behavior and Properties of LMR Fuels Reactors [NRSD)
9. MATHEMATICS AND COMPUTATION--R. Arthur Forster =l7.5 Therne! Hyd sulss of Severe Acendena and Degraded Cores (505 4 67 5777.* INRSD)
9. I Mathernanent Modehng--Genera! ~17.6 Thermal Hydrawles of Reactor Opersuons 9.2 Reaciar Physics Metteds 9.3 Methods an Thermal Hydrauhes anc Reactor Safety (NRSD) * --lanted supers 9.4 Methods an Neutral and Charged 81utcle Transpn " -Inviend and comribued pper "9.5 Vasushranon of large-Scah Calcadens ' -Panel &acuumn
  • 96 Chaos and Other Nochnear Phenomena sa Nuclear Eastry 8 -Tutonal Product on (RPD. NRSD) () --Cosponsonns &vssmn "S7 Bifurrmuon. Nonlmear Dynames. Chaos, and Fncials a the * -Full requeed for NCSD paper revww in July FULL Analysis of Nuclear System [RPD) P 'S ON MAT 3 DUE 3UNE 30.1989. Camact ANS
  • 9.8 A Revrw of Nucleare anal Mr*%ods and Their Headquarters for outs and sostructions for paper preparauun Call Apphcauom (RPSD) Mary beth Gardner. ANS Pubisauuns Departnrat,312/352-
10. NUCLEAR CRI'ICA1Jry $AFETY-Adolf S. Garcas (20052f*7252) 6611.
  • "10.1 Safety Margms a Neutrun Muluphcanon Cniena * -Summa *y required for accepumce and pubicauon in
    • 10.2 Safety Margw sn h 5sta Measurements TRANSACTIONS Full paper requaed before presentauon to be
    • 10.3 Safety Margas an the Camrol of Moderanon sad Possons putdishnd a &vismo proceedmgs

! Oral presentations are normally allotted 20 minutes for presentation and questions.

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