ML20034C155
| ML20034C155 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/24/1990 |
| From: | Dan Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Beard P FLORIDA POWER CORP. |
| References | |
| IEIN-82-18, NUDOCS 9005020116 | |
| Download: ML20034C155 (3) | |
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i APR 2 41990 1
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' Docket No. 50-302 License No. DPR-72
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Florida Power Corporation Mr. Percy M. Beard, Jr.
t Senior-Vice President, Nuclear.
Operations-j" ATTN: Manager, Nuclear Operations-Licensing P. O. Box 219-NA-21 Crystal River., FL 32629 Gentlemen:
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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. l Enclosed is an NRC
-memorandum which updates a._ position taken iin LInformation Notice 82-18, e
" Interpretation of Bioassay Measurements;; Assessment of-Intakes." 'This NRC-memorandum specifies that assessment of individual. intakes using bioassay _ data-t should be based on the best data and models available' forlthat purpose rather i
than the models in place at the -time the NRC regulations '.in CFR Part 20
-were implemented.
If you have any questions on the above, please give mela' call.
-Sincerely, i
ORIGINAL.51GbMO FY"
~
DOUGLAS M. COLUNS l
Douglas M. Collins, Chief Emergency Preparedness and Radiological Protection Branch Division of Radiation Safety and Safeguards n
Enclosure:
Memorandum dated March 14, 1990 cc w/ encl:
(See page 2)
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h 9005020116 900424 PDR ADOCK 05000302 O
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FidridaPowerCorporation 2.
cc w/ enc 1:
Gary L. Boldt Vice President, Nuclear Production Florida Power Corporation P. O. Box 219-SA-2C Crystal River, FL 32629 P. F. McKee, Director Nuclear Plant Operations Florida Power Corporation P. O. Box 219-NA-2C Crystal River, FL 32629 R. C. Widell, Director Nuclear Operations Site Support Florida Power Corporation P. O. Box 219-NA-21 Crystal River, FL 32629 A. H. Stephens General Counsel Florida Power Corporation MAC - ASD P. O. Box 14042 St. Petersburg, FL 33733 Attorney General Department of Legal Affairs The Capitol Tallahassee, FL 32304 i
Jacob Daniel Nash l
Office of Radiation Control DepPtment of Health and Rehabilitative Services 1317 Winewood Boulevard Tallahassee,.FL 32399-0700 Administrator Department of Environmental l
Regulation' Power Plant' Siting Section State of Florida 2600 Blair Stone Road Tallahassee, FL 32301 (cc w/ enc 1 cont'd - see page 3)
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5 F1Erida Power Corporation 3
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State Planning and-Development Clearinghouse-Office of Planning.and Budgeting Executive Office of the Governor
-The Capitol Building Tallahassee, FL 32301 Chairman.
f Board of-County Commissioners Citrus County 110 N. Apopka Avenue i
Iverness, FL 36250 Robert.B. Borsum Babcock and Wilcox Company l
Nuclear Power Generation Division 1700 Rockville Pike, Suite 525 Rockville, MC 20852-1631 j
State of Florida bcc w/ encl:
Document Control Desk L
NRC. Resident Inspector a
U.S. Nuclear Regulatory Commission 15760 W; Power Line Street
-i Crystal River, FL 32629
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UNITED STATES "g
NUCLEAR REGULATORY COMMISSION -
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WASHINGTON. D. C. 20555
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March 14, 1990 hEh0RAliUVM FOR: Those on the Attached List FROM:
LeMuine 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 HRC headquarters onc regional office comments in 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 lthe 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 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-issueo.in the near future.
We have reconsidered. issuing the enclosed draft notkc; however,-we"again-have decided not to do.so primarily because-the regulatory guide inc *porating the-information is still planned.and because the importance of the information con -
tained in the enclosed draf t 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. -
eHL e J. Cunningha, Chief-RadTa'ionProtectionBranch Divisicn of Radiation' Protection and Ems.cgency Preparedness-Office of tbclear Reactor Regulation-
Enclosure:
Subject Information Notice CONTACT: John D. Buchanan, NRR 492-1097 f6^#11/4225 g
.?
yg UNITED STATES i:D.
NUCLEAR REGULATORY COMMISSION 0FFICE OF NUCLEAR REACTOR REGULATION
=i WASHINGTON, D.C.
20555 June xx, 1988-NRC INTORMATION NOTICE NO. 88 XX:
INTERPRETATION OF B10ASSLY HEASUREMENTS; 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.
Background and
Purpose:
This information notice is intended to correct an MRC position in Information Notice 82-18 (Reference..I) that was in conflict with the NR9 staff position
.s 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 Part 20 intake limits, only the methodology of the International Comission on-Radiological Protection (ICRP) Publication 2 (Reference 2) can be used in assessing intakes of radioactive material using bioassay data. Another purpose
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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 measurements, " Interpretation of Bioassay Neasurements? 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 staf f position with respect to bioassay is presented in'NRC Regulatory Guides 8.9, 8.11, 8.20, 8.22, and 8.26. In general, the position is that 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 I
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 coupliance l
with 10 CFR 20 until the revision of 10 CFR 20 has been published as a final rule."
DRAFT
_ _ _ _ _. _ _ _. ~ _ _ _ _ _. _ _ - _ _ _ _ _ - _ _. - - _ _ _ _ _ _
l' $
D D R '"T IN 88-XX gj d g June xx, 1988 Page 2 of 3 The NRC staff now recognizes that this position in Information Notice 82-28 (2) is incorrect in implying that only. ICRP Publication 2 can be used for assessing bicassay data to determine compliances 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 30 CFR Part 20 limits on intake (based on long-term, chronic exposures), it does not always provide an adequate basis for assessino individual intake because it does not provide information on body content or excreta following single (acute) intake or information applicable to an individuai differing from the This inadequacy is recognized in
' standard man" defined in.CRP Publication 2.
2CRF Publications 10 and 10A (References 3 and 4), which are endorsed in Regulatory Guide B.g 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 position in Information Notice 82-18asaresultofreviewsanddiscussionsduring[ftsdraftstage) of a draf t 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 tables for the interpretation of This manual bionssay results, in terms of intake, for several hundred nuclides.
conforms 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/DOSEYR). The use of this report, with its straightfomard 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 comunent, a draft regulatory guide that would endorse the BNL report for use in assessing intakes of radioactive material from the results of bicassay 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 sqr 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 20 CFR Part 20.
t I
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IN gg.xx June ax 1933 I
Page 3 of 3 r
,No specific action or written response is required by this information notice.
If you have any questions about this matter please contact the regional administrator'oftheappropriateregionalofficeer.this. office..
a Charles E.-Rossi, Director Division of Coerational Events Assesssent.
Office of Nuclear Reactor Regulation =
,/e/m D. Buchanan
~
Technical Contacts:-4usteessuggush, NRR 3arddtro 6. 8rpoASf RAS f
(30/) Y92-373$
,e (301) 492 3422-e References (1) IE Information Notice 82-18, " Assessment of Intakes of Radioactive Material by Workers ' June. 22,1982.
(2)
- Report of Comittee !! on permissible Ouse for' Internal Radiation,*
Recomendations of the~ International ~ Cosmission on Radiological Prstectioni ICRP Pub 1fcation 2, 1959.
(3) " Report of Comittee IV on Evaluation of Radiation Doses in Sody Tissues from Internal Contamination due to Occupational' Exposure " Reconnendations:
of the International Commission on Radiologica1' Protection, ICRP j
Publication 10. 1968.
L (4) 'The Assessment of' Internal Contamination Resulting from Reasrrent or A Report of ICRP Cosmittee 4,* Recomendations of the Prolonged Uptakes;ission on Radiological Protaction, ICRP Publication 20A, International Cosn 1969.
(5) Edward T. Lessard, Xia Yihua,'Kenneth W. Skrable, et'a1..ilnterpretation.
ni of Bioassay Neasurements,' NUREG/CR-4884 (8NL-NUREG-52063),' July 1987.
j
Attachment:
List of Recently Issued NRC Infomation Notices O
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