ML20043C317
| ML20043C317 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 05/22/1990 |
| From: | Ronald Bellamy NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Sieber J DUQUESNE LIGHT CO. |
| References | |
| RTR-NUREG-CR-4884 NUDOCS 9006050050 | |
| Download: ML20043C317 (2) | |
Text
_ _. _. _... _..
s MAY 2 21990 Docket Nos. 50-334 50-412 h
- Duquesne Light Company ATTN:
Mr. J. D. Sieber Vice President Nuclear Group Post Office Box 4 Shippingport, Pennsylvania 15077 Gentlemen:
Subject:
INTERPRETATION OF B10 ASSAY MEASUREMENTS; ASSESSMENT OF INTAKE I
In accordance with the attached information, Region I Reactor licensees are advised that assessing intakes of radioactive material using bioassay data should be based on the best data and models available for that purpose.
Licensees are no longer restricted to the assessment methodology in ICRP Publication 2~in determining compliance with 10 CFR 20 intake limits.
Licensees may use improved and generally accepted methodology such as provided in recent ICRP Publications and NUREG/CR-4884.
Sincerely, R aid R. Bellamy, Chief Facilities Radiological Safety and Safeguards Branch Division of Radiation Safety and Safeguards
Attachment:
LJLs
..f r Letter, " Draft NRC Information Notice,
' Interpretation of Bioassay Measurements; Assessment of Intake'". dated March 14, 1990 i
g
.f .,
p,.,vg 1
g
/.
1 N/
0FFICIAL RECORD COPY MULTI LTRS - 0028.0.0 05/08/90 900605o050 900522 PDR ADOCK 05000334 p
~-
Duquesne Light Company 2
l!.AY 2 21990 cc w/ attachment:
J. J. Carey, Executive Vice President, Operations -
J. O. Crockett, General Manager, Corporate Nuclear Services W. S.' Lacey, General Manager, Nuclear Ooerations N. R. Tonet, Manager, Nuclear Engineering T. P. Noonan, Gentr:1 'sanager, Nuclear Operations S. C. Fenner, i)4 7byvr K. D. Grada, Maizgert kuc} ear Safety H. R. Caldwell, G.anetal Superintenent, Nuclear Operations Public Document-Ruom (PDR)
Local Public Document Room (LPDR)
NuclearSafetyInformationCenter(NSIC)
NRC Resident Inspector Commonwealth of Pennsylvania bec w/ attachment:
Region I Docket Room (with concurrences)
Management Assistant, DRMA (w/o encl)
R. Bellamy, DRSS C. Cowgill, DRP M. Conner, SALP Reports Only K. Abraham, PA0 (20) SALP Report and (2) All Inspection Reports J. Caldwell, NRR P. Tam, NRR
-L. J. Cunningham, NRR J. D. Buchanan, NRR OFFICIAL RECORD COPY MULTI LTRS - 0029.0.0 05/08/90
......-u..
[po mog'o UNITED STATES y
4
'g NUCLE AR REGULATORY COMMISSION g
.-l W ASHINGTON, D. C. 20$$5 March 14, 1990 hEh0RANUUM FOR: Those on the Attached List FROM:
LeMoine J. Cunningham, Chief Radiation Protection Branch Division of Radiation Protection and Emergency Preparedness Office of Nuciear Reactor Regulation SU3 JECT:
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 craft information notice which had been prepared after resolution of NRC'he6dquarters and 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,-"Interpretaticn of Bioassey 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 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 to be issued 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 f ree to trans-mit copies to licensees if you so desire.
eH e J. Cunningha, Chief Rad ation Protection Branch Division of Radiation Protection and Emergency Preparedness Office of Nuclear Reactor Regulation
Enclosure:
Subject Information Notice CONTACT: John D. Buchanan, NRR i
492-10 h dpo3NO225 W
r M:ekt.we n
p UNITED STATES M.
NUCLEAR REGULATORY COMMISSION
}
OTTICE OF NUCLEAR REACTOR REGULATION 1.*
WASHINGTON, D.C.
20555 June xx, 1988 NRC INTORMATION NOTICE ND. 88 XX:
INTERPRETATION OF B10 ASSAY MEASUREMENTS; ASSESSMENT OF INTAKES Addressees:
All nuclear power reactor facilities holding an operating license or a con-struction permit, research and test reactors, fuel facilities, and Priority I material licensees.
Saekaround 'and
Purpose:
This information notice is intended to correct an NRC position in Information Notice 82-18(Reference 1)thatwasinconflictwiththeNR9staffposition published in several regulatory guides. The NRC position in Information Notice 82-18 indicates that, for p'urposes of deteretning compliance with the 10 CFR Part 20 intake limits, only the methodology of the International Comdssion on Radiological Protection (ICRP) Publication 2 (Reference 2) can be used in assessing intakes of radioactive saterial using bioassay data. Another purpose of this 1988 information notice is to call attention to a comprehensive new senval prepared for the NRC that can be used to compute intakes from both in vivo and in vitro bioassay measuremehts. *1nterpretation of Bioassay Easurements? TMIG/CR-4884).
It is expected that recipients will review the information in this information notice for appifcability 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 staf f position with respect to bioassay is presented in NRC Regulatory and 8.26. In general, the position is that 8.9. 8.11, 8.20, 8.22,ke using bioassay data should be based on the best Guides assessment of individual inta 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 determining cospliance with 10 CFR 20 until the revision of 10 CFR 20 has been published as a final rule."
DRAFT
1N 8BoXX M[f June xx,1988 y
gg Page 2 of 3 The NRC staff now recognizes that this position in Information Notice 82-18 (2) is incorrect in 1:1 plying that only ICRP Publication 2 can be used for assessin-bioassey date 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 20 CFR Part 20 limits on intake (based on long tem, chronic exposures),because it it does not always provide an adequate basis for assessing individual intake does not provide information on body content or excreta following single (acute) intake or information applicable to an individual differing from the This inadequacy is recognized in
' standard man' defined in ICRP Publication 2.
ICRT 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 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) of a draft report, " Interpretation of Bioassay Measurements (Reference 5),
This prepared by Brookhaven National Laboratory (BNL) under an NRC contract.
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 tesles for the interpretation c,f bioassay results, in terms of intake, for several hundred nuclides.. This manual confores 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 assus:ptions (REMEDY andDDSEDAY/DDSEYR).
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.
for comment, a draft regulatory guide that would The NRC plans to issue,for use in assessing intakes of radioactive material endorse the BNL report from the results of bioassay measumments.
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 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 Furthermore, to the extent it is changed in a revision of 10 CFR Part 20.
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.
f:,_
IN 88 XX
- 1988 June xx,f 3
~'
Page 3 o No specific action or written ressonse is required by this information notice.
If you have any questions about tifs matter please contact the regional administratoroftheappropriateregionalofficeorthisoffice.
l l
l -
Charles E. Rossi Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation
,Jebn A BuCAanar?
Technical Contaets:-4iiiSiiiSiliityssh, NRR 8cu-42ra 6. Broo A5, R86 (30/) V92
.7738 (301) 492-3422 l
References (1) IE Information Notice 82-18, ' Assessment of Intakes of Radioactive Material by Workers,' June 13, 1982.
i (2) ' Report of Comittee II on Permissible Cose for Internal Radiation,'
Recomendations of the International Comission on Radiological Protection, ICRP Publication 2, 1959.
(3) " Report of Comittee IV on Evaluation of Radiation Doses in Body Tissues from Internal Contamination due to Occupational Exposure," Reconsnendations of the International Comission on Radiological Protection, ICRP l
Publication 10, 1968.
(4) "The Assessment of Internal Contamination Resulting from Recurrent or A Report of ICRP Committee 4," Recomendations of the Prolonged Uptakes;ission on Radiological Protection, ICRP Publication 20A, International Com 1969.
(5) Edward T. Lessard, Kia Yihua, Kenneth W. Skrable, et al.,)' Interpretation of Bioassay Measurements,' NUREG/CR-4884 (8NL-NUREG-52063, July 1987.
Attachment:
List of Recently Issued NRC Infomation Notices O
~
i
.