ML18153C203
| ML18153C203 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/24/1990 |
| From: | Stohr J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| References | |
| IEIN-82-18, NUDOCS 9005030071 | |
| Download: ML18153C203 (7) | |
Text
L Docket Nos. 50-280, 50-281 License Nos. DPR-32, DPR-37 APR 2 4 1990 Virginia Electric and Power Cbmpany ATTN:
Mr. W. L. Stewart Senior Vice President - Power 5000 Dominion Boulevard Glen Allen, VA 23060 Gentlemen:
off1cial
SUBJECT:
INFORMATION REGARDING INTERPRETATION OF BIOASSAY 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.
11 This NRC memorandum specifies that assessment of individual intakes using bioassay data should 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.
If you have any questions on the above, please give me a call.
Enclosure:
Memorandum dated March 14, 1990 cc w/encl:
(See page 2)
Sincerely, C?!Gf NAI SIGNED
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l,.-... LIAM t. Cl /t,,ro:
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J. Philip Stohr, Director Division of Radiation Safety and Safeguards
e Virginia Electric and Power Company cc w/encl:
E. W. Harre 11 Vice President - Nuclear Operations Virginia Electric & Power Company 5000 Dominion Boulevard Glen Allen, VA 23060 J. P. O'Hanlon Vice President - Nuclear Services Virginia Electric & Power Company 5000 Dominion Boulevard Glen Allen, VA 23060 M. R. Kansler Station Manager Surry Power Station P. 0. Box 315 Surry, VA 23883 R. F. Saunders, Manager
. Nuclear Licensing Virginia Electric & Power Co.
5000 Dominion Boulevard Glen Allen, VA 23060 Sherlock Holmes, Chairman Board of Supervisors of Surry County Surry County Courthouse Surry, VA 23683 W. T. Lough Virginia Corporation Commission Division of Energy Regulation P. 0. Box 1197 Richmond, VA 23209 Michael W. Maupin Hunton and Williams P. 0. Box 1535 Richmond, VA 23212 C. M. G. Buttery, M.D., M.P.H.
Department of Health 109 Governor Street Richmond, VA 23219 Attorney General Supreme Court Building 101 North 8th Street Richmond, VA 23219 Commonwealth of Virginia bee w/encl:
(See page 3) e 2
e Virginia Electric and Power Company*
bee w/encl:
Docume~t Control Desk NRC Resident Inspector U.S. Nuclear Regulatory Commission Route 1, Box 166 Surry, VA 23883
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3 RI~SS Jfofter 4/ // /90 DCollins 4/11/90 RII~
PFrearickson 4/p)90 e
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- UNITED STATES
'NUCLEAR REGULATORY COMM1SS1er\\i
- WASHINGTON, D. C. 20555 March 14, 1990 l*iEf.10RANUUM FOR: Those on the Attached Li st FROM:
SUliJECT:
LeMuine J. Cunningham, Chief Radiation Protection Branch Division of Radiation Protection and Emergency Preparedness Office of Nuclear Reactor Regulation DRAFT NRC INFORMATION NOTICE, u INTERPRETATION OF BIOASSAY MEASUREMENTS; ASSESSMENT OF INTAKE" In a July 13, 1968 ri1emorandum, I informed you that we had decided not to issue the enclosed.rlraft information notice which had been prepared after*resolution of NRC headquarters dnd 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 issued within a few months and we intended to have that guide incorporate the message in the enclosed draft information notice concerning the incorrect 0 position 11 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 reconsidt:red issuing the enclosed draft notice; however, w.e agafo 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 hsuar1ce 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.
Enclosure:
Subject Information Notice CONTACT:
John D. Buchanan, NRR 492-1097 Li/),'°)
f' eM
- e J~ Cunningha, Chief Radiation Protection Branch Division of Radiation Protection and Emergency Preparedness Ofhce of Nuclear Reactor Regulation
e lJPUTED STAT[S e
NUCLEAR REGULATORY COMMISSION OFFICE OF NUCLEAR REACTOR REGULATION WASHINGTON, D.C. 2osss*
June xx, 1988 NRC JNfORMATION NOTICE NO. 88-XX:
INTERPRETATION Of SJOASSAY MEASUREMENTS; ASSESS1".ENT OF INTAKES Addressees:
All nuclear power reactor fac11itfes holding an operating license or a con-struction pennit, research and test reactors, fuel facilities, and Priority J material lice~sees.
Background and
Purpose:
This information notice is intended to correct an NRC position 1n lnformition Notice 82-18 (Reference l) that was in conflict with the NR~ staff position j
published in several regulatory guides. The KRC position in Information Notice S2-l8 indicates thatD for purposes of detennin1ng compliance with the 10 CFR Part 20 intake limits, only the methodology of the International Co11111lssion on Radiological Protection (JCRP) Publication 2 (Reference 2) can be used in
- ssessing intakes of radioactive 11ater1al using bfoassay data. Another purpose of this 1988 information notice 1s to call attention to I comprehensive n~,
manual prepared for the NRC that can be.used to compute intakes from both in vivo and fn vitro bioassay measurements, *interpretation of Bioassay Jreasiiriments";' (NDR£G/tR*4884). It is expected that recipients will review the infor11atfon fn this information notice for app11cab111ty to their programs.
However, suggestions contained 1n this information notice do not constitute NRC require~ntsi therefore, no specific 1ctfon or written response fs required.
Discuss ion:
The NRC staff position with respect to bioassay is presented fn NRC Regulatory Guides 8.9, 8.11, S.ZO, 8.22. ind 8.26. Jn general, the position ts that assessment of individual intake ustng b1oassay data should be based on the best data and models available for that purpose.
JE Information Notice 82-18, *Assessment of Intakes of Radioactive Material by Workers,* issued in 1982, pointed out that the present IRC li11fts on intake are based on ICRP Publication 2 and concluded wftll the NRC posttton: *Jhe NRC will continue to use the ICRP Publication 2 methodology fn determining coq,111nce with 10 CFR 20 until the revision of 10 CFR 20 has been publtshed as I final rule.*
DRAFT
DRnFT lN 88-XX June xx, l 988
.P1ge 2 of 3 Tfle NRC staff now recognizes* that this position in *1nfonnation Notice 82-18 (l) is incorrect in implying that only JCRP Pub1ic1tfon 2 car. 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 Pub11cation 2 provides the basts for current JO CFR Part 20 limits on intake (based on long-ten:i, chronic exposures), it does not always pro~ide an adequate basis for assessing 1nd1vfdual intake because ft does not provide information on body content or excreta following single (acute) intake or information applicable to 1n individual differing from the
- standard man* defined in ICRP Pub1icat1on 2. Thfs inadequacy is recognized in JCRF Publications 10 and lOA (References 3 and 4), which are endorsed in Regulatory Guide 8.9 ind which are mentioned 1n Information Notice 82-18 1s being used b1 the NRC to evaluate bioassay data to determine compliance with regulator,1 requirements.
The NRC staff became aware of the problem with the NRC pos1l1cn 1n Information
~otice 82-18 1s a result of reviews and discussions during lits draft sta9e) of a dreft report, *interpretation of Bioassay Measurements (Reference SJ, prepared by Brookhaven National Laboratory (BNL) under an NRC contract. This report (~hich ~as published in July 1987) fs I comprehensive 111nu11 thate for the first time,* provides fnfonnatfon on how to compute intakes from both fn vfvo and in vitro bioassay measurements and contains tables for the 1nterpretat'ro~
bioassay results, in terms of intake, for several hundred nuclides. This manual confonns to the positions in exfsting regulatory vutde~. 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 and DOSEDAY/DOSEYR).
The use of thfs report, with its straightfon,ard method-ology, could help J1 censees 1void the difficulties assoctated wtth the use of the methodology in ICRP Publication 2.
The NRC plans to issue, for c011nent, 1 draft regulatory guide that would endorse the BNL report for use in assessing intakes of radioactive material from the results of b1oassay 1111surements. 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 bto1ssay; therefore, the report ma.>' be used for this purpose. Of course, the 1fm1ts on tnt1te 9tven in 10 CFR 20.103 and based on JCRP Publicatton 2 continue to apply until they are changed in a revision of 10 CFR Part 20. Furthermore, to the extent 1t is applicable. JCRP Publication 2 may continue to be used for assessing intakes of radioactive 11ateri11 for co~arfson with the intake 1fmits of 10 CFR Part 20e DRAFT J
e IN 88-IX June xx, 1988 P1ge 3 of 3 No specific action or written *response is required by thfs 1nfonnatfon notice.
If you have any questions about this 111tter, please contact the regional
-*d~inistrator of the appropriate regfonal office or this office.
Charles E. Rossi, Director Dfvfsfon of Operational EYents Assessment Office of Nuclear Reactor Regulation Jal,r1 L),. Euc luv1ar, Techni ca 1 Contacts: --e* E T ij nell, NRR (301} 492-l!*r /(J ~7 c.~~ry/ A, ?rt, l-f-1er 81 ali Cs ec.1, IMSS (301) 492-3422.
/3a.ri>a.ra G. '3roc IC s, ~ e.s (3()/) '1,/92-f733 References (1) IE Jnformatfon Notice 82-18, *Assessment of Intakes or-Rad1oaeth*1 Materitl by Workers,* June ll, 1982 *
(2) *Report of Cor;in1ttee II on Per111ss1ble Dose for Internal Radiation,*
Reconrnendations of the Internatfonal CoDlllfssfon on Radfological Protection, ICRP Publication 2, 1959.
(3) *Report of Comiittee IV on Enluatfon of Radfatfon Doses 1n Bocb' Tissues from Internal Contamination due to Occupatfonal Exposure,* Reconnendations of the International ColllZlfssfon on Radfologtcal Protection, ICRP Publication 10, 196S.
(4) *rhe Assessment of Internal Contamfnatfon Resultfnl from Reairrent or Prolonged Uptakes; A Report of ICRP Connittee 4,* econmendattons of the International Co111111ssion on Rad1ologtca1 Protection, ICRP Publication lOA, 1969.
(5) Edward T. Lessard, Xfa Yihua, Kenneth V. Skrable, et 11., *interpretation of Bioassay Measurements,* IIUREG/CR-4884 (BNL-NUREG-52063), July 1987.
Attactanent: L.tst of Recently Issued IIRC Jnfoniatton Notices
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