ML20198C509
| ML20198C509 | |
| Person / Time | |
|---|---|
| Site: | 07000036 |
| Issue date: | 12/19/1997 |
| From: | Sharkey R ABB COMBUSTION ENGINEERING NUCLEAR FUEL (FORMERLY, ASEA BROWN BOVERI, INC. |
| To: | Soong S NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| TAC-L30981, NUDOCS 9801070309 | |
| Download: ML20198C509 (3) | |
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' Docket No. 70. )6 1.icense No. JNht 33 Dr. Sean Soong 1 icensing Ilranch Division of Fuel Cycle Safety and Safeguards, NhiSS U.S. Nuclear itegulatory Commission Washington, DC 20555 0001 l
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Subject:
Additionalluformation: Amendment ih quest to Update the Decommluloning Plan for the Evaporation Ponds (TAC NO,1,30981) linclosures: 1) Itesponses to 1.etter from NitC, Sean Soong, to Cli, Itobert Sharkey, dated November 21,1997.
Dear Dr. Soong:
Enclosed are responses to questions posed in your letter dated November 21,1997. If there are questions regarding this matter, please feel free to contact Dr. liarl Saito of my staff at (314) 937 4691 !!xt. 461 or myself at (314) 937-4691 lixt. 399 i
Sincerely, COMilUSTION ENGINiililtlNG, INC.
/
s 12-11-97 Itobert W. Sharkey Date:
Director,llegulatory AiTairs ec: Patrick lliland Itegion 111 RA97/666
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' Resp'onse to letter from Sean Soong, NRC, to Robert Sharkey,- CE, dated
. November 21,1997.
Question 1: Please estimate solid and liquid waste volumes and contaminant l
concentrations which are expected to result from the remediation project.
Compare to tne current total waste volumes at your facility, in addition, compare t
_- to the waste estimates that were expected prior to the latest characterization study when the original 1994 Decommissioning Plan was Submitted to the NRC.
Response: The solid radioactive waste generated by this action is estimated to be apprmimately 100 m at an average concentration of approximately 300 pCl/g.
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The liquid waste volume, primarily from rala water collection, over a 6 month 3
period is estimated to be approximately 900 m. The maximum average concentration of the effluent is estimated to be less than 3E 7 pCl/ml leading 'o a maximum transfer of 270 pClin six months.
8 During 1996 and 1997 CE disposed of 500 m of solid radioactive waste at Envirocare, of Utah. Presently the waste water treatment plant releases 20 m* of water a day with an average concentration less than 3E-7 pCi/ml. At this daily rate,'less than 1,000 pCi of uranium is released in 6 months.
The estimated waste expected prior to the latest characterization study was only i
3 several cubic meters of solid waste. The current estimate is 100 m. The estimated amount of liquid effluent has remained unchanged.
Question 2: Provide an occupational dose assessment (individual and cumulative for the decommissioning work. Compare to current average fccility-wide exposure rates. In addition, indicate significant changes in this dose estimate following the recent characterization of the evaporation ponds.
Response: The dose assessment assumes the following; 50% class D uranium, 50% class Y uranium,500 pCl(uranium)/g dust at the PEL of 15 mg/m',8 weeks of work,40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> of work a week, no ingestion, and external dose rate < 0.01 mrem /hr (measured).
Internal Dose (Inhalation)
U cone. = Dust PEL x conversation from mg to g a
x conversation m to ml
.x concentration of U in soll lSmgdust) g(dwt) n 5E -4pCi(U) y,,
m' 1E3mgJust) 1E6ml 6 dust)
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f Eccimure I to RA97/666
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I/ctmc = 7.5E-12prilint A worker Inhales 2,400 m'/y (2.4 E9 ml/y, year is a 2,000 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> work year,1.2 m /hr). It is conservatively assumed that uranium i
8 becomes airborne at 50 % class Y (All of 0.04 pCl) and 50% class D (ALI of 2 pCl).
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'E x0.5x $ +
Dmc(CEDE) = [
"" x x
hr project.
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2pCl 5
1.2E6ml 320hr 7.9E - 12pCl Au x0.5x h,000 mrem hr project ml 0.04pCI AU Dose (CEDE) = 200mremiproject External Dose 320hr ggg), 0.0lmrem g
hr project Dose (DDE) = 3 mrem This result in a Total Effective Dose Equivalent (TEDE) of 200 mrem. A TEDE of 200 mrem is less than the 500 mrem / year limit requiring monitoring for an occupational worker, as listed in 10 CFR 20. A TEDE of 200 mrem is r!so below the 1997 projected plant average of 500 mrem. The dose estimate is very conservative because it assumet 1) dust at the PEL, although in a wet environment no significant dust loading is expected and 2) an average soil coritamination level which is greater than the measured soil contamination level.
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