BIL TITLE A COMPUTER IMPLEMENT. OF RECENT MODELS FOR EST. DOSE EQUIV. SPONSORING OFFICE(S) NRR
INREM II: A COMPUTER IMPLEMENTATION OF RECENT MODELS FOR ESTIMATING THE DOSE EQUIVALENT TO ORGANS OF MAN FROM AN INHALED OR INGESTED RADIONUCLIDE
THE INREM II CODE AS CONTAINED IN NURGE/CR-0114. ALSO TRANSMITTED IS VOLUME 1 OF A TABULATION OF INTERNAL RADIAION DOSE CONVERSION FACTORS OBTAINED USING THE INREM II CODE. THIS TABULATION IS GIVEN IN "ESTIMATES OF INTERNAL DOSE EQUIVALENT TO 22 TARGET ORGANS FOR RADIONUCLIDES OCCURRING IN ROUTINE RELEASES FROM NUCLEAR FUEL-CYCLE FACILITIES, VOL. 1, NUREG/CR-0150. THE CODE COMPUTES REFERENCE ADULT HUMAN DOSE EQUIVALENTS FROM USER-SUPPLIED DOSIMETRIC AND METABOLIC INFORMATION. IN PRINCIPLE, INREM II APPROACH IS SIMILAR TO THE ONE USED IN WASH-1400. ORGAN DOSE EQUIVALENT IS COMPUTED AS THE SUM OF CONTRIBUTIONS FROM EACH SOURCE ORGAN WHERE RADIOACTIVIY IS ASSUMED PRESENT; CROSS-IRRADIATION EFFECTS CAN BE ASSESSED. DOSE CONVERSION FACTORS IN NUREG/CR-0150 AND UPCOMING VOL. 2 ARE ILLUSTRATIVE OF INREM II CODE USE ONLY. THEY ARE NOT ENDORSED FOR ADOPTION SINCE SOME OF THE METABOLIC MODELS ARE SUBJECT TO CRITICISM WITH FURTHER DEVELOPMENT OF ACCEPTABLE METABOLIC MODELS BY ORNL, THE CODE WILL PROVIDE STATE-OF-THE-ART METHODOLOGY FOR DOSE CALCULATIONS.
PRESENT ANALYSES OF RADIATION EXPOSURE SUCH AS PREPARED FOR WASH-1400, GESMO AND IN REACTOR LICENSING ACTIONS HAVE NOT BEEN UNIFORM IN DOSE ESTIMATION METHODOLOGY. THE VARIOUS APPROACHES USED FOR THE ABOVE STUDIES AND ACTIONS REFLECT VARIOUS INTERPRETATIONS OF THE STATE-OF-THE-ART IN DOSE ESTIMATION MEHODOLOGY, THE NEEDS OF PARTICULAR STUDIES AND AVAILABILITY OF DOCUMENTED MODELS. NRC DOES NOT HAVE A BROADLY APPLICABLE, DOCUMENTED, CRITICALLY REVIEWED, STATE-OF-THE-ART DOSE ESTIMATION METHODOLOGY AVAILABLE TO VARIOUS OFFICES FOR THEIR ASSESSMENT NEEDS. THE CLOSEST IS REGULATORY GUIDE 1.109, REVISION 1, 1977, WHICH REPRESENTS A CURRENTLY APPROPRIATE APPLICATION OF A REASONABLE UP-TO-DATE DOSE ASSESSMENT METHODOLOGY AS APPLICABLE TO NUCLEAR POWER PLANT EFFLUENTS. THE OFFICE OF NUCLEAR REGULATORY RESEARCH RECOGNIZED THE NEEDS IN THIS AREA, AND HAS BEEN FUNDING RESEARCH AT THE HEALTH AND SAFETY RESEARCH DIVISION OF THE OAK RIDGE NATIONAL LABORATORY CORNL). THE RESEARCH DESCRIBED IN RIL 047 PARTIALLY FULFILLS THE NEED OF A BROADLY APPLICABLE, DOCUMENTED AND CLOSER TO THE STATE-OF-THE-ART MODEL FOR CALCULATION OF DOSES TO VARIOUS ORGANS OF A BODY FROM INTERNALLY DEPOSITED RADIONUCLIDES. HOWEVER, ITS APPLICATION TO REGULATORY PROCESSES HAS TO WAIT UNTIL SOME ADDITIONAL SUPPORTING RESEARCH IS COMPLETED (SEE COMMENTS/REMARKS) MOST OF WHICH ARE ON-GOING AT ORNL FUNDED BY RES AND SOME BENCH-MARK COMPARISONS ARE MADE.
*** NRR: IMPACT OF RESULTS ***
THE RESULTS HAVE CONFIRMED OUR UNDERSTANDING OF INTERNAL DOSIMETRY MODELING, BUT HAVE NO DIRECT IMPACT ON LICENSING UNTIL AFTER SOME ADDITIONAL STUDY IS PERFORMED.
NNN NRR COMMENTS AND REMARKS *NN
ICRP HAS AN ONGOING CONTRACT W/HEALTH & SAFETY RESEARCH DIV. OF ORNL TO DEVELOP REVISED NUCLEAR DATA, S-FACTORS, METABOLIC PARA- METERS, DOSIMETRIC MODELS, ETC. FOR USE IN ICRP'S FORTHCOMING PUBLICATION #30. IT IS NOT KNOWN THAT ORNL INTERNAL DOSIMETRY MODEL FOR ICRP IS SOMEWHAT DIFFERENT FROM THAT FOR NRC (INREM-II) ALTHOUGH BOTH MODELS ARE BASED ON ICRP'S TASK GROUP LUNG MODEL (1966, 1972)& EVE'S GI-TRACT MODEL (1966). ORNL MODEL FOR ICRP IS MORE COMPLETE IN THAT IT HAS THE BODY FLUIDS (BLOOD) REPRESENTED IN MODEL AS ADDITIONAL COMPARTMENT WHICH IS LACKING IN INREM-II. INCLUSION OF A BLOOD COMPARTMENT IS APPROPRIATE CONCEPTUALLY AS WELL AS FROM VIEW POINT OF REALISTIC MODELING, IT IS LIKELY TO REDUCE THE ORGAN DOSE CONVERSION FACTORS PARTICULARLY FOR THE SHORTER LIVED RADIONUCLIDES DUE TO DECAY DURING PARTIAL HOLD-UP IN BLOOD. BENCHMARKING INREM-II RESULTS W/ICRP'S WILL BE PRUDENT BEFORE OUR USING THEM. BEST VALUES OF METABOLIC PARAMETERS REQUIRED AS INPUTS TO RUN INREM-II ARE NOT YET AVAILABLE. NOMINAL VALUES OF PARAMETERS USED BY AUTHORS OF 2 VOLUMES (VOL. 2 IN PREPARATION OF DOSE CONVERSION FACTOR TABULATIONS ARE FOR PURPOSES OF ILLUSTRA- TING USE OF INREM-II, & AUTHORS DO CAUTION AGAINST UNCRITICAL USE OF THESE TABLES IN RADIOLOGICAL APPLICATIONS BECAUSE THEY CON-13 SIDER THESE RESULTS AS PRELIMINARY. RES SHOULD BE REQUESTED TO INCLUDE TASK OF GENERATING & PERIODICALLY UPDATING DATA LIBRARY OF BEST VALUES OF METABOLIC PARAMETERS FOR USE IN INREM-II IN THEIR CONTINUING RESEARCH PROGRAMS WITH ORNL. A SET OF VALUES OF META- BOLIC PARAMETERS IS BEING USED IN ICRP WORK AT ORNL. ICRP VALUES ARE NOT YET AVAILABLE TO USE, BUT WHEN AVAIL, IT WILL BE PRUDENT TO COMPARE VALUES H/PRELIMINARY VALUES USED BY ORNL FOR NRC, & MAKE APPROPRIATE REVISION IF NECESSARY. NUCLEAR DATA DEVELOPED & UTILIZED BY ORNL FOR NRC NOT NECESSARILY SAME AS BEING DEVELOPED FOR ICRP. THOUGH SUBSTANTIAL DIFFERENCES NOT ANTICIPATED IN AREA, IT WILL BE PRUDENT TO COMPARE DATA ALSO.
BIL TITLE: A TECTONIC OVERVIEW OF THE CENTRAL MIDCONTINENT SPONSORING OFFICE(S): SD, NRR
"A TECTONIC OVERVIEW OF THE CENTRAL MIDCONTINENT", NUREG-0382, IS THE MOST UP-TO-DATE SYNTHESIS OF GEOLOGIC KNOWLEDGE OF THE EARTHS CRUST IN THE STUDY AREA. IT CONTAINS THE MOST COMPLETE BIBLIOGRAPHY OF THE GEODYNAMICS OF THE AREA AND WILL AID IN NUCLEAR POWER PLANT LICENSING. IT IS RECOMMENDED THAT THE INFORMATION AND HYPOTHESES BE USED AS INPUT TO THE DEVELOPMENT OF A TECTONIC PROVINCE OR SEISMIC ZONING MAP OF THE EASTERN U.S. AND TO PROVIDE A BASIS AND GUIDE FOR ONGOING STUDIES IN THE AREA.
NO COMMENT AT THIS TIME DUE TO PRELIMINARY NATURE OF THE WORK. WE PLAN AN EXTENSIVE REVIEW WHEN THE PROJECT IS FURTHER ALONG.
RIL TITLE: IN VITRO DISSOLUTION ON URANIUM PRODUCT SAMPLES SPONSORING OFFICE(S): SD
IN VITRO DISSOLUTION OF URANIUM PRODUCT SAMPLES FROM FOUR URANIUM MILLS
FILTRATE OF BLOOD SERUM AND 0. IM HCL. THE MEASUREMENT OF THE SOLUBILITY OF VARIOUS FORMS OF YELLOWCAKE IN VITRO UTILIZED THO SOLVENT SYSTEMS A SIMULANT OF AN ULTRATHE RESULTS OF THIS STUDY WILL BE USED TO DETERMINE WHETHER YELLOWCAKE SHOULD BE CONSIDERED A SOLUBLE COMPOUND WITH RESPECT TO 10 CFR 20. THE DATA OBTAINED USING THE SERUM SIMULANT SHOW THAT 25 TO 64 PERCENT OF ALL SAMPLES THE PURPOSE OF EXPOSURE CONTROL. TESTED DISSOLVED WITH HALF-TIMES LESS THAN 16 HOURS. IDEALLY, SOLUBILITY CLASSIFICATIONS SHOULD BE BASED ON THE DISSOLUTION HALFTIMES OF THE PARTICULAR PRODUCT UNDER CONSIDERATION. THE DATA INDICATE THAT YELLOWCAKE SHOULD BE TREATED AS A CLASS D COMPOUND FOR
OFFICE: SD IMPACT STATEMENT
THIS TOPIC IS PRESENTLY CONTEMPLATED. THE RESULTS OF THIS RESEARCH WILL BE USED IN FINALIZING REGULATORY GUIDE 8.22, "BIOASSAY AT URANIUM MILLS." NO FURTHER RESEARCH ON
SINCE 1957, THE NUCLEAR SAFETY GUIDE HAS PROVIDED USERS OF FISSIONABLE MATERIAL WITH SIMPLE METHODS TO ASSURE SYSTEM SUBCRITICAL- ITY. RESEARCH INFORMATION LETTER 950 TRANSMITS NUREG/CR-0095, "NUCLEAR SAFETY GUIDE, TID-7016, REVISION 2." THIS REVISION UTILIZES IMPROVED CRITICALITY DATA AND COMPUTATIONAL TECHNIQUES NOT AVAILABLE IN THE PREVIOUS GUIDE ISSUED IN 1961. REVISION 2 SHOULD BE REGARDED AS A SUPPLEMENT TO PREVIOUS GUIDES SINCE IT DOES NOT HAVE INTENTIONAL CONSERVATISMS INCLUDED AS IN PREVIOUS GUIDES. IN USING REVISION 2 OF THE GUIDE, THE USER MUST IMPOSE APPROPRIATE SAFETY FACTORS FOR HIS APPLICATION AND THE NRC STAFF MUST DETERMINE THAT THE SAFETY MARGINS PROPOSED BY THE USER OF REVISION 2 ARE ADEQUATE.
THE REVISED NUCLEAR SAFETY GUIDE IS QUOTED TO THE LICENSEES WHENEVER THEIR AMENDMENT OR RENEWAL OF APPLICATIONS REFER TO THE 1961 VERSION OF THE GUIDE AND FAIL TO RECOGNIZE NEW DEVELOPMENTS IN NEUTRON INTERACTION-ACTION, CERTAIN OF WHICH ARE SUMMARIZED IN THE UPDATED GUIDE. THESE NEW DEVELOPMENTS, SOME OF WHICH HAVE RESULTED FROM NRC-SPONSORED RESEARCH, HAVE RENDERED QUESTIONABLE CERTAIN PAST PROCEDURES IN THE ANALYSES OF NEUTRON INTERACTION.
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