ML20042F075
| ML20042F075 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/26/1990 |
| From: | Wilson B Office of Nuclear Reactor Regulation |
| To: | Kingsley O TENNESSEE VALLEY AUTHORITY |
| References | |
| IEIN-82-18, NUDOCS 9005070191 | |
| Download: ML20042F075 (3) | |
Text
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APR 2 01990 m
Docket Nos. 50-259, 50-260, 50-296 License Nos. DPR-33, DPR-52, DPR-68 l
Mr. Oliver D. Kingsley, Jr.
' Senior Vice President, Nuclear Power Tennessee Valley Authority 6N-38A Lookout Place
~1101 Market ~ Street Chattanooga, TN 37402-2801
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 intake using bioassay data should be based on the best data and models available for that purpose rather i
than the models in place at the time the NRC regulations, in 10 CFR Part 20 were implemented.
If you have any questions on the above, you may wish to call D. M. Collins at
.404-331-5586.
l Sincerely,
/5/
Bruce A. Wilson, Assistant Director.
for Inspection Programs l
TVA Projects Division Office of Nuclear Reactor Regulation
Enclosure:
Memorandum dated March 14, 1990 cc w/ enc 1:
D. Nunn, Vice President Nuclear Engineering Tennessee Valley Authority 400 West-Summit Hill Drive WT 12A 12A Knoxville, TN 37902 cc w/ enc 1:
(Cont'd on page 2) 9005070191 900426 ADOCK0500g9
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$:- n Mr;-Oliver D.:Kingsley. Jr.
2 cc w/ enc 1:
(cont'd)-
Dr. M. O. Medford Vice President and Nuclear Technical Director Tennessee Valley Authority 6N 38A Lookout Place Chattanooga. : TN 37402-2801 Chairman, Limestone County-Commission P. O. Box 188 Athens, AL 35611 Dr. Henry Myers, Science Advisor-Committee on Interior and-Insular Affairs U. S. House of Representatives Washington, D. C '20515 0.-J. Zeringue,: Site Director Browns Ferry Nuclear Plant Tennessee Valley Authority-P. O. Box 2000 1
u L
Decatur, AL 35602'
'E. G. Wallace, Manager:
l Nuclear Licensing and Regulatory Affairs Tennessee Valley.~ Authority SN 157B Lookout Place Chattanooga, TN 37402-2801 P. Carier, Site Licensing Manager
)
Browns Ferry Nuclear Plant
-[
Tennessee Valley Authority q
.P. O. Box.2000.
I Decatur, AL 35602 l
l.
1
_ G. Campbell,- Plant Manager Browns Ferry Nuclear Plant-L
' Tennessee Valley Authority l
P. 0.-Box 2000
'Decatur, AL 35602 i
l.
TVA Representative i
Rockville Office 11921 Rockville Pike Suite 402-Rockville, MD 20852 i
cc w/ enc 1:
(Cont'd on page.3)
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Mr. Oliver D. Kingsley, Jr.
3
-1 cc w/ enc 1:
(cont'd)
General Counsel Tennessee Valley Authority 400 West Sunnit Hill Drive ET llB 33H Knoxville, TN 37902 l
Claude Earl Fox, M.D.
State Health Officer State Department of Public_ Health State Office Building Montgomery, AL 36130 l
State of Alabama j
bec w/ enc 1:
S. D. Ebneter, RII D. M. Crutchfield, NRR
~
B. D. Liaw, NRR S. C. Black, NRR R. C. Pierson, NRR 4
G. E. Gears, NRR D. Moran, NRR l
W. S. Little, NRR/RII J. Rutberg, 0GC l
M. S. Callahan, GPA/CA R. H. Bernhard, NRR/RII NRC Document Control Desk 4
NRC Resident Inspector U.S.. Nuclear Regulatory Commission Route 12. Box 637 Athens, AL 35611 1
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NUCLEAR REGULATORY COMMISSION
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March 14, 1990 hEh0RANDUM FOR:' Those on the Attached List FROM:
LeMoine J. Cunningham, Chief Radiation Protection Branch.
Division of Radiation Protection and Emergency Prepareaness Office of Nuclear Reactor Regulation
SUBJECT:
DRAFT NRC INFORMATION NOTICE, "lNTERPRETATION OF B10 ASSAY MEASUREMENTS; ASSESSMENT 0F INTAKE" t
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 HRC headquarters end regional office comments 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 M
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 issued and, although~the guide is still under development, we do.not expect it-l to be issuco 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-randum enclosure in the public document room. 'Therefore, you are free to trans-
~
mit copies to licensees if you so desire.
eN e J. Cunningha, Chief Rad ation Protection Branch Division of Radiation Protection yyyjgfQyf k)P and Emergency Preparedness-F Office of Nuclear Reactor Regulation
Enclosure:
Subject Information Notice
. CONTACT: John D. Buchanan, NRR 492-1097 l
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UNITED STATES-a
- & L NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION J
WASHINGTON, D.C.
20555 June xx, 1988 NRC INFORMTION NOTICE NO. 88-XX:
INTERPRETATION OF B10 ASSAY MEASUREMENTS; ASSESSMENT OF INTAKES Addressecs:
All nuclear power reactor facilities holding an operating license or a con-struction permit, research and test reactors, fuel facilities, and Priority I material licer. sees.
Background and
Purpose:
This information notice is intended to correct an 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 Infomation Notice 82-18 indicates that, for p'urposes of-determining compliance with the 10 CFR i
Part 20 intake limits, only the methodology of the International Commission on. -
i Radiological Protection (ICRP) Publication 2 (Reference 2) can be used in assessing intakes of radioactive material using bionssay data. Another purpose of this 1988 information notice is to call attention to a comprehensive new manual prepared for the NRC that can be.used to compute intakes from both in vivo and in vitro bioassay measuremehts, " Interpretation of Bionssay Weasurements' TNURIG/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.
Discussion:
The NRC staff position with respect to bioassay is presented in NRC Regulatory Guides B 9, 8.11, 8.20, 8.22, and 8.26. In general, the position is that 3
assessment of individual intake using bionssay data should be based on the best 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 conpliance i
with 10 CFR 20 until the revision of 10 CFR 20 has been published as a final' rule."
1 O
DRM
g:
IN 88-XX y !') f h
hs, June xx, 1988 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 bicassay 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-term, chronic exposures), it does not always pronide an adequate basis for assessing individual intake because it does not provide information on body Tcontent or excreta following single (acute) intake or information applicable to an indivi@n1 differing from the
- standard man" defined in ICRP Publication 2.
This inadequecy is recognized in ICRF Publications 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 bioassay data to determine compliance with i
l regulatory requirements.
The NRC staff became aware of the problem with the NRC position in Information Notice 82-18 as a result of reviews and discussions during [its draft stage) i of a draf t report, " Interpretation of Bioassay Measurements (Reference 5),
prepared by Brookhaven National Laboratory (BNL) under an NRC contract. This report -(which was published in July 1987) is a comprehensive manual that, for the first time, provides information on how to compute intakes from both in vivo and in vitro bioassay measurements and contains taales for the interpretaIIon of i
bioassay results, in terms of intake, for several hundred nuclides. This manual conforms to the positions in existing regulatory guides,, and the computed intake retention fractions in the report have been verified by comparison with results generated by other computer models using the same set of assumptions (REMEDY l
andDOSEDAY/DOSEYR). The use of this report, with its straightforward method-ology, could help licensees avoid the difficulties associated with the use of the methodology in ICRP Publication 2.
The NRC plans to issue, for coment, a draf t regulatory guide that would endorse the BNL report for use in assessing intakes of radioactive material from the results of bionssay measurements.
In the interim, use of this report for the interpretation of bioassay measurements is consistent with the regula-tory positions in existing regulatory guides on bioassay; therefore, the report may 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 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 10 CFR Part 20.
t
_ _ _ _ _ _ _ _. _ _. _ _ _ _ _ _ _ _ _.. _ ______________j
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IN 88 XX l'. * * ' '
June xx,f 3 1988 Page 3 o i
No specific action or written res >onse is required by this information notice.
If you have any questions about t11s matter please contact the regional adininistrator of the appropriate regional office or this office.
I i
I Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation John.o. Buchanart -
Technical Contacts:-4iliisiliSinlyssh, NRR Ocu-/ded 6. Jroo AS j RAf i
(301) 492-3BSP- /4 97, g,
ppy y7p Nor I
(301) 492-3422 e
3.
References (1) IE Information Notice 82-18, ' Assessment of Intakes of Radioactive Material l
by Workers," June 12, 1982.
t I
(2) " Report of Comittee II on Iermissible Dose for Internal Radiation,"
4 l
Recomendations of the International Comission on Radiological Protection, i
ICRP Publication 2, 1959.
(3) " Report of Comittee IV on Evaluation of Radiation Doses in Body Tissues from Internal Contamination due to Occupational Exposure," Recommendations l
cf the International Cemission on Radiological Protection, ICRP Publication 10, 1968.
(4) "The Assessment of Internal Contamination Resulting from Recurrent er.
Prolor.ged Uptakes; A Report of ICRP Comittee 4 " Reconnendations of the International Cosnission on Radiological Protection. ICRP Publication 10A, 1969.
(5) Edward T. Lessard, Xia Yihua, Kenneth W. Skrable, et al.,)" Interpretation of Bioassay Measurements," NUREG/CR-4884 (BNI.-NUREG-52063, July 1987, f
Attachment:
List of Recently Issued NRC Information Notices l
l l '
i
.