ML20043C169
| ML20043C169 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 05/22/1990 |
| From: | Ronald Bellamy NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Steiger W LONG ISLAND LIGHTING CO. |
| References | |
| RTR-NUREG-CR-4884 NUDOCS 9006040169 | |
| Download: ML20043C169 (2) | |
Text
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MAY 2 21990 Docket No. 50-322 Long Island Lighting Company ATTN: Mr. William E. ' Stieger, Jr.
Assistant Vice President - Nuclear
~P. O. Box 618 Shoreham-Nuclear Power. Station Wading River, New York 11792 Gentlemen:
Subject:
INTERPRETATION OF BIOASSAY MEASUREMENTS; ASSESSMENT OF INTAKE 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:
LJCunningham Letter, " Draft NRC Information Notice,
' Interpretation of Bioassay Measurements; Assessment of Intake'". dated March 14, 1990 fm n)O' a
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'I 0FFICIAL RECORD COPY MULTI LTRS - 0046.0.0 t'(h 05/08/90 9006040169 900522
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!lg PDR ADOCK 05000322 P
PDC j-.
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_Long Island Electric Company 2
MAY 2 2193) cc w/ attachment:
-J. Scalice, Plant Manager R. Gutmann, iianager, Nuclear Operations Support R. Kascasak, Manager, Nuclear Engineering J. Futter, General Counsel W. Maloney, Manager,.QA Department Director, Power Division State of New York, Department of Law Shoreham Hearing Service List
'Public Document Room (PDR)
Local Public Document Room (LPDR)
Nuclear Safety Information Center (NSIC)
NRC Resident Inspector.
-State'of New York bec w/ attachment:
Region I Docket Room (with concurrences)
Management-Assistant, DRMA (w/o enc 1)
R. Bellamy, DRSS M. Knapp, DRSS W. Hodges, DRS L. Doerflein, DRP P. Kauffman, DRP J. Nakoski, DRP.
M. Conner, SALP Reports Only M.-Young, 0GC.
K. Abraham, PA0 (20) SALP Report and (2) All Inspection Reports J. Caldwell, NRR S. Brown, NRR L. J. Cunningham, NRR-J. D Buchanan, NRR OFFICIAL RECORD COPY MULTI LTRS - 0047.0.0 05/08/90
14-e 141
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'e UNITED STATES l',pW/[g NUCLEAR REGULATORY COMMISSION I. e w ash NGTON, D, C. 20555
- QQ March 14, 1990 liEh0RANDUM 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:
ORAFT NRC INFORMATION NOTICE, "lNTERPRETATION OF B10 ASSAY MEASUREMENTS; ASSESSMENT OF INTAKE" in a July 13, 1988 memorandum, I.informeo you that we-had decided not to issue the enclosed craft information notice which had been prepared after resolution of NRC headquarters 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 reguistory 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 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 act expect it to be issued in the near future.
We have reconsidered issuing the enclosed draft notice; however, we a5ain 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.
eM 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 492-1097 l
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i UNITED STATES r
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NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION j
WASHINGTON, D.C.
20555 June xx, 1988 NRC INTORMATION NOTICE NO. 88 XX:
INTERPRETATION OF B10 ASSAY MEASUREMENTS; ASSESSMENT OF INTAKES Addressees:
All nuclear power reactor facilities holding an operating license or a con-struction pemit, research and test reactors, fuel facilities -and Priority I eaterial licensees.
Background and
Purpose:
This information notice is intended to correct an NRC position in Infomation-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 Part 20 intake limits, only the methodology of the International Commission on Radiological Frotection (ICRP) Publication 2 (Reference 2) can be used in assessing-intakes of radioactive material using bioassay data. Another purpose of this 1988 information notice is to call attention to e comprahensive new manual prepared for the NRC that can be used to compute intakes'from both in vivo and in vitro bionssay measuremehts, "Interpretetion of Sioassay-Reasurements? ThWIG/CR-4884).
It is expected that reetpients 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 assessment of individual intake using bioassay 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 wi11 continue to use the ICRP ~ Publication 2 methodology in detemining cospliance
.with'10 CFR 20 until the revision of 20 CFR 20 has been published as a final ruie.'
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IN 88-XX
[g June xx,1988 Page 2 of 3 l
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 assessin-bicassay data to determine compliance with 10 CFR Part 20 and (2) conflicts with the NRC steff position expressed in relevant regulatory l
guides. Although-ICRP Publication 2 provides the basis for current 10 CFR Part 20 limits on intake (based on long-tem, chronic exposures) -it does not 4
always provide an adequate basis for assessing individual intake because it does not provide information on body content or excreta foHowing single j
(acute) intake or information applicable to an individual differing from the 1
n l
- standard man
- defined in ICRP Publication 2.
This inadequacy is recognized in l
2CRF Fub11 cations 10 and 10A (References 3 and 4), which are endorsed in i
L Regulatory Guide 8.9 and which are mentioned in Information Notice 82-18 as j
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) s of a draft report, " Interpretation of Bionssay Measurements (Reference 5),
prepared by Broothaven National Laboratory (BNL) under'an NRC contract. This report (which was published in July 1987) is a comprehensive manual that, for i
I the first time, provides information on how to com>ute intakes from both in vivo and in vitro bioassay measurements and contains tables for the interpretation c4 bionssay results, in terms of intake, for several hundred nuclides. This manuel 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 J
andDOSEDAY/DOSEYR). The use of this report, with its straightforward method.
ology, could help licensees avoid the difficulties associated with the use of l
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 bionssay measurements.
In the interim, use of this report l
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
~
20 CFR 20.103 and based on ICRP Publication 2 continue to a> ply 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.
L 2
IN 88 XX 1988 June xx,f 3 L
Page 3 o
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No specific action or written res sonse is required by this information notice.
If you have any questions about tiis satter please contact the regional adtrinistrator of the appropriate regional office or this office.
Charles E. Rossi, Director Division of Operational Events Assessment Office of Nuclear Reactor Regulation Joka D. Buchanat?
Technical Contacts: W, NRR 8cu-dard 6 8 coo /CS, RAS (301) 492-W /d g
g pg 5
(301)'492-3422 J
References (1) IE Information Notice 82-18, " Assessment of Intakes of Radioactive Material by-Workers," June II,1982.
(2)
- Report of Comittee II on Permissible Dose 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,' Recosmendations of the International Comission on Radiological Protection ICRP Publication 10, 1968.
(4) "The Assessment of Internal Contamination Resulting from Recurrent or Prolonged Uptakes; A Report of ICRP Comittee 4 " Recomendations of the International Comission 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 (BNL-NUREG-52063, July 1987.
Attachment:
List of Recently Issued NRC Information Notices O
.