ML20034C159
| ML20034C159 | |
| Person / Time | |
|---|---|
| Site: | 07001113 |
| Issue date: | 04/24/1990 |
| From: | Dan Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Lewis W GENERAL ELECTRIC CO. |
| References | |
| IEIN-82-18, NUDOCS 9005020122 | |
| Download: ML20034C159 (1) | |
Text
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oRicrai APR 2 4 890 Docket No. 70-1113 License No. SNM-1097 General Electric Company ATTN: Mr. Wayne P. Lewis, General Manager Nuclear Fuel and Component Manufacturing Department P. O. Box 780 Wilmington, NC 26402 Gentlemen:
SUBJECT:
INFORMATION REGARDING INTERPRETATION OF B10 ASSAY MEASUREMENTS This is to provide you information reaarding the interpretation of bioassay measurements to assess intakes of radfoactive material.
Enclosed is an NRC memorandum which updates a position taken in Information Notice 82-18.
" Interpretation cf Bioassay Measurements; Assessment of Intakes."
1his NRC memorandum specifies that assessment of individual intakes using bioassay data should be based on the best data and models available for that purpose rather than the models in place at the time the NRC regulations in 10 CFR Part 20 were impicmented.
If you have any questions on the above, please give me h call.
Sincerely.
ORIGINAL SIGNf0 BY bgkN.dobN,NEhief Emergency Preparedness and Radiological Protection Branch Division of Radiation Safety and Safeguards
Enclosure:
Memorandum dated March 14, 1990 cc w/ enc 1:
T. Preston Winslow, Manager Licensing and Nuclear Materials Management General Electric Company P. O. Box 780, Mail Code J26 Wilmington, NC 28402 State of North Carolina bcc w/ enc 1:
Document Control Desk bec'w/o enc 1:
I License Fee Management Branch RI
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1 March 14, 1990 liEh0RANDUM FOR:
Thuse on the Attached List FROM:
LeMoine J. Cunningham, Chief h
Radiation Protection Branch Division of Radiation Protection and Emergency Preparedness Office of Nuclear Reactor Regulation
SUBJECT:
DRAFT NRC INFORMATION NOTICE, "lNTERPRETATION OF B10 ASSAY HEASUREMENTS; ASSESSMENT OF IHTAKE" In a July 13, 1968 memorandum,1 informed you that we had decided not to issue the enclosed draft information notice which had been prepared after resolution of NRC headquarters end regional office comments on earlier drafts.
(Note:
l The technical contacts have been updated on the enclosed copy of the draf t.)
A primary reason for this decision was that a regulatory guide endorsing the use of NUREG/CR-4884, " Interpretation of Bioassay Heasurements," was to have been issued within a few months and we intended to have that guide incorporate the message in the enclosed draft information notice concerning the incorrect
" position" in Information Notice No. 82-18. That regulatory guide has not been-l issued and, although the guide is still under development, we do not expect it t
to be issueo in the near future, We have reconsidered issuing the enclosed draft notice; however, we again have decided not to do so primarily because the regulatory guide incorporating the.
information is still planned and because the importance of the information con-tained in the enclosed draft is below the current threshold of importance suf-ficient to warrant issuance of an NRC information notice.
However, to make this information available to the public, we are placing a copy of this memo-l randum enclosure in the public cocunent room.
Therefore, you are free to trans-mit copies to licensees if you so desire.
L eh ' e J. Cunningha, Chief Rad ation Protection Branch Division of Radiation Protection i
and Emergency Preparedness Office of Nuclear Reactor-Regulation
Enclosure:
Subaect Information Notice CONTACT: John D. Buchanan, NRR 492-1097
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UNITED STATES th.
NUCLEAR REGULATORY COMM!$$10N' ak 4
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i 0FFICE OF NUCLEAR REACTOR REGULATION
,i WASHINGTON, D.C.
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June xx,1988 NRC INTORMTION NOT1CE NO. 88 XX:
INTERPRETATION OF B10 ASSAY MEASUREMENTS;
)
ASSESSMENT OF INTAKES i
Addressees:
All nuclear power reactor facilities holding an operating license or a con-J struction permit, research and test reactors, fuel facilities, and Priority I i
material licer. sees.
l Background and
Purpose:
This information notice is intendM to correct an NRC position in Information l
Notice 82-28 (Reference 1) that was in confitct with the NR9 staff position s
published in several regulatory guides. The NRC position in Information Notice 82-28 indicates that, for p'urposes of detersining compliance with the 10 CFR i
Part 20 intake limits, only the methodology of the International Commission on l
Radiological Protection (ICRP) Publication 2 (Reference 2) can be used in assessing intakes of radioactive material using bloassay data. Another purpose of this 1988 information notice is to call attention to a comprehensive new manuel prepared for the NRC that can be used to compute intakes from both in vivo and in vitro bionssay measurements, 'Interpretetton of Bioassay r
Easurements? TMIG/CR-4884).
It is expected that recipients will review the information in this information notice for applicability to their programs.
However, suggestions contained in this information notice do not constitute NRC requirements; therefore, no specific action or written response is required.
l Discussion:
The NRC staff position with respect to bioassay is presented in NRC Regulatory 8.22, and 8.26.
In general, the position is that 8.9, 8.11, 8.20,l intake using bioassay data should be based on the best Guides assessment of individua data and models available for that purpose.
IE Information Notice 82-18, ' Assessment of Intakes of Radioactive Material by Workers," issued in 1982, pointed out that the present NRC limits on intake are based on ICRP Publication 2 and concluded with the NRC position:
'The NRC will continue to use the ICRP Publication 2 methodology in detemining coupliance with 10 CFR 20 until the revision of 10 CFR 20 has been published as a final rule."
l DRAff I
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n IN 88.XX ISES i
June ar,f 3 s
Page 2 o The E C staff now recognizes that this position in Information Notice $2 18 i
(3) h incorrect in te& ying that only ICRP Publication 2 can be used for l
assessing bicassay data to determine comp 11anca with 10 CFR Part 20 and i
(2) conflicts with the NRC staff position sapressed in relevant regulatory guides. Although ICRP Publication 2 provides the basis for current 30 CFR Part 20 limits on intake (based on long tem, chronic exposures),because it it does not always proitce an adequate basis for assessing individual intake does not provide information on body content or escreta ro110 wing single (acute) intake or information applicable to an individual differing from the This inadequacy is recognized in
' standard man' defined in JCRP Publication 2.
2CRF Fub11 cations 20 and 10A (References 3 and 4), which are endorsed in Regulatory Guide 8.g and which are mentioned in Information Notice 8218 as being used by the NRC to evaluate bioassay data to determine compliance with l
regulatory requirements.
The NRC staff became aware of the problem with the NRC posigion in Information Notice 82 28 as a result of reviews and discussions during g'its draft stage) of a draft report, ' Interpretation of Bionssay Neasurements (Reference $),This prepared by Brookhaven National Laboratory (8NL) under an NRC contract.
report (which was published in July 1987) is a comprehensive manual that, for j
the first time, provides information on how to compute intakes from both in vivo and in vitro bioassey measurements and contains tables for the interpretation cf This manual bionssay results, in terms of intake, for several hundred nuclides.
confoms to the positions in existing regulatory guides,, and the computed intake retention fractions in the report have been verified by conparison with results generated by other computer models using the same set of assumptions (REMEDY andDOSEDAY/DDSEYR). The use of this report, with its straightforward method.
clogy, could help licensees avoid the difficulties associated with the use of the methodology in ICRP Publication 2.
for cowenent, a draf t regulatory guide that would The NRC plans to issue,for use in assessing intakes of radioactive material endorse the SNL report from the results of bionssay measurements.
In the interim, use of this report for the interpretation of bioassay measurements is consistent with the reguia-tory positions in existing regulatory guides or, bioassays therefore, the report Of course, the Ifmits on intake given in may be used for this purpose.
30 CFR 20.103 and based on ICRP Publication 2 continue to apply until they are changed in a revision of 10 CFR Part 20.
Furthermore, to the extent it is applicable ICRP Publication 2 may continue to be used for assessing intakes of radioactive material for comparison with the intake limits of 20 CFR Part 20.
1 I
t IN C3.XX 1988-i June ax,f 3 j
Page 3 o No specific action or written res >onse is required by this information notice.
If you have any questions ebout ttis matter please contact the regional edrinistrator of the appropriate regional office or this office.
I Charles E. Rossi, Director.
l Division of Operational Events Assessment Office of Nuclear Reactor Regulation -
l I
J'& D. Buchanart Technica) Contactst
, NRR A ctr f a r a G g,,po y, g a.g kiri-(2 */) +'92
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(303) 492 3422 I
References l
(2) IE Information Notice 32-18, #.ssessment of Intakes of Radioactive Material
[
by Workers " June 13,1982.
i (2) ' Report of Comittee !! on /ersissible Dose for Internal Radiation,'
Recomendations of the International Comission on Radiological Protection, ICRP Pub 1(cation 2, 1959.
- Report of Comittee JY en Evaluation of Radiation Doses in Body Tissues (3) from Internal Contamination due to Occupational Exposure,' Recommendations of the International Consission on Radiological Protection, ICAP Publication 10, 1968.
(4) 'The Assessment of Internal Contamination Resulting from Recurrent or A Report of ICRP Cosalttee 4,' Recomendations of the Prolonged Uptakes;ission on Radiological Protection, ICAP Publication 10A, Internationsi Com
)
2969.
(5) Edward T. Lessard, Ria Y1hua, Kenneth W. Skrable et al.3), Interpretation of Bioassay Measurements,' NUREG/CR 4884 (SNL.NUkEG 5206 July 1987.
. 1
Attachment:
List of Recently Issued NRC Information Notices 8
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