ML20199L578

Forwards Final Rept for Task 3,subtask 15 of Contract, Namely, Independent Analysis & Evaluation of AM-241 & Transuranics & Subsequent Dose to Two Male Workers at Connecticut Yankee Atomic Power Plant

ML20199L578
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	12/24/1997
From:	Toohey R OAK RIDGE ASSOCIATED UNIVERSITIES
To:	Donna-Beth Howe NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS)
Shared Package
ML20199L576	List: IR 05000213/1997010 ML20199L578 ML20199L589
References
NUDOCS 9802090233
Download: ML20199L578 (2)

Text

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M N ORISE Qat eCot eNWrTutt som Scit NCE AND EDUCafiCN 24 December,1997 Dr. Donna Beth Howe Office ofNuclear Materials Safety and Safeguards U. S. Nuclear Regulatory Commission White Flint North MS T8FS Washington, DC 20555-0001

Dear Dr. Howe:

This letter transmits my final report for Task 3, subtask 15 of our contract, namely, " Independent analysis and evaluation of Am-241 and transuranics and subsequut dose to two male workers at Connecticut Yankee Atomic Power Plant " This report covers the specific items listed in your letter ofMarch 7,1997 sad e-mail musage ofJune 11,1997:

1) Conduct an independent assessment to determine the best estimatedinitial intake and dose assessmentfor the two workers bc sed upon the available bioassay, radiation dosimetry, radiation measurement, chemical analysis, air sampling data, etc., provided by the licensee.

2) Determine the best estimated maximum CEDE and CDEfor the two workers based on ICRP 30 methodologies. This is to compare the estimated wiues with NRC's exposure limits outlined in 10CFR20.1201 which is based on ICRP 30 methodologies.

3) Conduct an independent assessment ofall available data anddata analysis to confirm the scientific integrity and validity of the data and data analysesperformed by the licensee.

4) ...the performing organi:ation shallprovide the NRC TechnicalMonitor with a written summary ofany infctmation discussed

5) Estimate the CEDE and CDE to workers 1 and 2 under the assumption that their intakes of radioactive material were 1) attributable to an inhalation and 2) any radioactivity transported to the GI tract resultedfrom clearancefrom the respiratory system. Perform a sensitivity analysis as to the effect ofparticle si:e on these doses. Further, inter-compare star fard respiratory clearance models with data obtained via whole-body counting andfecal analysis to estimate particle si:efor clearance purposes. Internompare the doses (from an assumedirthalation) with those calculated by the licensee 'a consultants (Combination inhalation! ingestion model) and provide an evaluation of the appropriateness ofusing an inhalation model, for dose calculation purposes, in the case of Worker 1 and 2.

9802090233 PDR 980202 0 ADOCK 05000213 PDR P O BOX 117. CM ROGE. TENNESSEE 37831 0117 Managed and coeravec by Oct Odge Assoca,ed Unrws.hes for the U 3 Departmeat of Ene gy

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. Dr. D.-B. Howe December 24,1997 Page 2 The attached report is organized into three parts:

- Part I includes my independent asessment of the intakes and resulting doses for these workers, and a comparison of my estimates with those of the licensee's consultants.

Part II contains an evaluation of the intakes as a Ametion of assumed particle size and compare the ICRP-30 and ICRP-66 lung models for the assessment of the intakes and resulting doses.-

Part III discusses the best scienti6c estimates ofintake and dose,' and also'gives doses calculated I in compliance with the requirements of 10CFR20, namely the use ofICRP-30 tissue weighting factors to compute the effective dose equivalent from the organ doses.

An Appendix contains a summary of the contacts and information exchanged among the various parties during this process, a list of reference materials used, and the spreadsheets and Sgures referenced in the text.

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- Because several versions and drafts have been previously submitted, to avoid confusion, I used the table, spreadsheet, and figure numbering schemes previously used. For example, sheet 14 in the origina report was replaced by sheet 14A in later version; thus, the final report contains only sheet 1%

Feel free to contact me at 423-576-3448 if you have any comments or questions on this report.

Sincerely, .

( Y .U Richard E. Toohey, Ph.D., CHP Director, Radiation Internal Dose Information Center

- Oak Ridge Institute for Science and Educt.thn

cc: Ron Nimitz, Region I John White, Region I Roger Pedersen, NRR Sie

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