ML20042F082
| ML20042F082 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/26/1990 |
| From: | Wilson B Office of Nuclear Reactor Regulation |
| To: | Kingsley O TENNESSEE VALLEY AUTHORITY |
| References | |
| IEIN-82-18, NUDOCS 9005070204 | |
| Download: ML20042F082 (3) | |
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APR 2 61990 Docket Nos. 50-327,'50-328 License Nos. DPR-77, DPR-79 Mr. Oliver D. Kingsley, Jr.
Senior Vice President, Nuclear Power Tennessee Valley Authority 6N 38A Lookout Place 1101 Market Street Chattanooga, TN 37402-2801 I
Dear Mr.!Kingsley:
SUBJECT:
INFORMATION REGARDING INTERPRETATION OF B10 ASSAY MEASUREMENTS This 'is to provide you information regarding the interpretation of bioassay -
measurements' to assess intakes of radioactive material.
Enclosed is an NRC memorandum which updates a position taken in Information Notice 82-18,
" Interpretation of Bioassay Measurements;. Assessment of Intakes."
This NRC memorandum specifies that assessment of. individual intakes using. bioassay data q
shculd 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 implemented.
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.If you have any questions on the above, you may wish to call ~ D.: M. Collins at 404-331-5586.
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Sincerely, ls\\
Bruce A. Wilson, Assistant Director for Inspection Programs TVA Projects Division Office-of-Nuclear Reactor Regulation
Enclosure:
Memorandum dated March 14, 1990 cc w/ encl:
(See page 2) t t
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9005070204 900426 ADOCK0500((7 p
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e Mr. Oliver D. Kingsley, Jr.
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cc w/ enc 1:
D. Nunn, Vice President Nuclear Engineering Tennessee Valley Authority 400 West Summit Hill Drive j
WT'12A 12A I
Knoxville, TN 37902 1
L Dr. M. O. Medford i
Vice President and Nuclear Technical Director Tennessee Valley Authority 6N'38A Lookout Place Chattanooga, TN 37402-2801 County Judge Hamilton. County Courthouse Chattanooga,.TN 37402 Dr. Henry Myers, Science Advisor Committee on Interior and Insular Affairs o
U. S.' House of Representatives l
Washington, D. C.
20515 C. A. Vondra,-Plant Manager Sequoyah Nuclear Plant Tennessee Valley Authority P. O. Box 2000
. Soddy-Daisy, TN 37379 E. G. Wallace, Manager Nuclear Licensing and l'
Regulatory Affairs Tennessee Valley Authority SN 157B Lookout Place Chattanooga, TN 37402-2801 M. Burzynski Site Licensing Manager Sequoyah Nuclear Plant P. O. Box 2000 Soddy-Daisy, TN 37379 TVA Representative Rockville Office 11921 Rockville Pike Suite 402 Rockville, MD 20852 (cc w/ enc 1 cont'd on page 3)
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Mr. 01.iver D. Kingsley, Jr. -
3-(cc w/ enc 1:
cont'd)
General Counsel Tennessee Valley Authority 400 West Sunnit Hill Drive ET 11B 33H Knoxville, TN-37902 Michael H. Mobley, Director Division of > Radiological Health
'T.E.R.R.A. Building 150 -9th Avenue North Nashville, TN 37203 I
State of Tennessee bec w/ enc 1:
S. D. Ebneter, Rll D. M. Crutchfield, NRR B. D. Liaw, NRR S. C. Black, NRR R. C. Pierson, NRR B. A. Wilson, NRR/Rll L. J. Watson, NRR/Rll J. B. Brady, NRR/RII J. Rutberg, 0GC NRC Document Control Desk NRC Resident Inspector ~
U.S. Nuclear Regulatory Connission:
2600 Igou Ferry Soddy-Daisy, TN 37379 RI -
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March 14,'1990 hEh0RAliDUM FOR:. Those on the Attached List FROM:
LeMoine J. Cunningham, Chief Radiation Protection Branch Division of Radiation Protection and Emergency Preparedness-Office of Nuclear Reactor Regulation
SUBJECT:
DRAFT NRC INFORMATION NOTICE, "lNTERPRETATION OF B10 ASSAY MEASUREMENTS; ASSESSMENT OF INTAKE" in a July 13, 1968 memorandum, I informed you that we had decided not to issue the enclosed draft information notice which had been prepared after resolution of NRC headquarters and regional office coments on earlier drafts.
(Note:
The technical contacts have been updated on the enclosed copy of the draft.)
A primary reason for this decision was.that a regulatory guide endorsing the use of NUREG/CR-4884, " Interpretation of-Bioassay Measurements," 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 tha incorrect i
" position" in Information Notice No. 82-18. That regulatory guide has not been issued and, although the guide is still under development, we do not' expect it to be issueo in the near future.
I We have reconsidered issuing the enclosed draft notice; howevar, 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-randum enclosure in the public document room. Therefore, you are free to trans-L mit copies to licensees if you so desire.
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eM e J. Cunningha Chief l
Rad ation Protection Branch.
Division of Radiation Protection l
ggfMM and Emergency Preparedness j~
Office of Nuclear. Reactor Regulation
Enclosure:
Subject Information Notice l
CONTACT: John D. Buchanan, NRR 492-1097
nrsh w e UNITED STATES NUCLEAR REGULATORY C0W.15510N OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C.
20555 L
June xx, 1988 NRC INFORMATION NOTICE NO. 88-XX:
INTERPRETATION 0F 810 ASSAY MEASUREMENTS; i.
ASSESSMENT OF INTAKES L
Addres sees:
All nuclear power reactor facilities holding an operating license or a con-struction permit, research and test reactors, fuel facilities, and Priority I material licersees.
Background and
Purpose:
This information notice is intended to correct en NRC position in Information Notice 82-18 (Reference 1) that was in conflict with the NR9 staff position published in several regulatory guides. The NRC position in Information Notice 82-18 indicates that, for purposes of determininl1 compliance with the 20 CFR Part 20 inthe limits, only the methodology of t WInternational Connission on Radiological Protection (ICRP) Publication 2 (Reference 2) can be used in assessing intakes of radioactive material using bioassay data.
nnether purpose of this 1988 information notice is to call attention to a e p shensive new manual prepared for the NRC that can be used to compute f atakes from both in vivo and in vitro bioassay measuremefits, 'Interpretetion of 810 assay Neasurements? TNURG/CR-4884).
It is expected that recipients will review the information in this information notice for applicability to their programs, i
However, suggestions contained in this information notice do not constitute NRC requirements; therefore, no specific action or written response is required.
Discuss _ig:
l 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 bionssay data should be based on the best 1
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 t
based on ICRP Publication 2 and concluded with the NRC position: 'The NRC will continue to use the ICRP Publication 2 methodology in determining cospliance with 10 CFR 20 until the revision of 10 CFR 20 has been published as a final rule."
RAFT l
'1
- IN 88 XX Ni June xx,1968 5A sus Page 2 of 3 The NRC staff now recognizes that this position in Information Notice 82-18 (1) is incorrect in implying that only ICRP Publication 2 can be used for assessing bioassay data to determine compliance with 10 CFR Part 20 and (2) conflicts with the NRC staff position expressed in relevant regulatory guides. Although ICRP Publication 2 provides the basis for current 10 CFR Part 20 limits on intake (based on long-tere, chronic exposures),because it it does not always provide an adequate basis for assessing individual intake does not provide information on bo@ content or excreta roHowing single (acute) intake or information appitcable to an individual differing from the This inadequacy is recognized in
' standard man' defined in ICRP Publication 2.
ICRF Pubitcations 10 and 10A (References 3 and 4), which are endorsed in Regulatory Guide 8.9 and which are mentioned in Information Notice 82-18 as being used by the NRC to evaluate bicassay data to determine compliance with regulatory requirements.
The NRC staff became aware of the problem with the NRC posiijion in Information Notice 82-18 as a result of reviews and discussions during sits draft stage) of a draf t report, ' Interpretation of Bioassay Neasurements' (Reference 5),
This prepared by Brookhaven National Laboratory (8NL) under an NRC contract.
report (which was published in July 1987) is a comprehensive manual that, for the first time, provides infonnation on how to compute intakes from both in vive and in vitro bioassay measurements and contains tables for the interpretation of This manual bioassay results, in terms of intake, for several hundred nuclides.
conforms to the positions in exfsting regulatory guides,, and the computed intake retention fractions in the report have been verified by comparison with results generated by other computer sodels using the same set of assumptions (REMEDY andDOSEDAY/DOSEYR). 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.
The NRC plans to issue, for comment, a draft regulatory guide that would endorse the BNL report for use in assessing intakes of radioactive material from the results of bioassay measurements.
In the interim, use of this report for the interpretation of bicassay measurements is consistent with the regula-tory positions in existing regulatory guides on bioassay; therefore, the report say be used for this purpose. Of course, the limits on intake given in 10 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 tie 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 10 CFR Part 20.
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IN 88oRX-1988
. June xx,f 3 Page 3 o J
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f No specific action or written res >onse is required by this information notice.
If you have any questions about tifs matter please contact the regional j
administrator of the appropriate regional office or this office.
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Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation I
J'e/m D. Buchuart L
Technical Contacts: N, NRR 8ardded 6 8rv0NSj 8 85
[30/) V92-2738 g,
.(301) 492-3422 J
References (1) IE Information Notice 82-18, ' Assessment of Intakes of Radioactive Material by Workers,' June 12, 1982.
I (2) " Report of Comittee !! on Iersissible Dose for Internal Radiation,'
Reconnendations of the International Commission on Radiological Protection, ICRP Publication 2,1959.
(3)
- Report of Cosaittee IV on Evaluation o. Radiation Doses in Body Tissues
~
from Internal Contamination due to Occupational Exposure," Recossendations of the International Cosmission on Radiological Protection, ICRP Pubitcation 10,1968.
(4) 'The Assessment of Internal Contamination Resulting from Recurrent or A Report of ICRP Cosmittee 4,* Recoseendations of the Prolonged Uptakes;ission on Radiological Protection. ICRP Publication 10A, International Cosn 1969.
. (5) Edward T. Lessard, Xia Tihua, Kenneth W. Skrable, et al.$), Interpretation of Bioassay Measurements,' NUREG/CR-4884 (8NL-NUREG-5206 July 1987.
Attachment:
List of Recently Issued NRC Information Notices 1
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