ML18149A449

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Surry Power Station Disposal of Low Level Radioactively Contaminated Soil in Dredge Spoils Pond.
ML18149A449
Person / Time
Site: Surry  Dominion icon.png
Issue date: 11/26/1986
From: CAMERON W W, TARANTINO C A, THOMASSON F L
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18149A448 List:
References
TAC-64191, TAC-64192, NUDOCS 8612090252
Download: ML18149A449 (28)
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{{#Wiki_filter:SURRY POWER STATION DISPOSAL OF LOW-LEVEL RADIOACTIVELY CONTAMINATED SOIL IN THE DREDGE SPOILS POND Prepared by: Reviewed by: Approved by: C. A. Tarantino Staff, Health Physics F. L. Thomasson Supervisor, Health Physics wvv;~~ W. W~Cameron Director, Health Physics A. B. c. D. E. F. G. H. I. e TABLE OF CONTENTS Section Introduction

                    • .

e e e e e e e e O e e e e e e

  • e
  • Cl e e e e e
  • e e Description of Contaminated Soil and Gravel *** Page No. . ..... 1 *
  • 2 Description of Dredge Spoils Pond **********************.********

4 Site Area Characteristics

                • .********************.*********

5 Meteorology

        • .5 Hydrology
            • .6 Geology ...... o ***********

ii ********** ., ********************** 7 Alternative Disposal Methods .................... ., ............... 7 Burial of Contaminated Soil ****************..************** 7 Shipment to Licensed Disposal Facility *****************.*** 8 Disposal of Contaminated Soil in the Dredge Spoils Pond ********* 8 Radiological Assessment

          • * ****** 9 Conclusion

........... o ******************* o ********************

  • 12 References

........ Cl *************************************** o **** 12 Attachment 1 -Diagrams of Dredge Spoils Pond Attachment 2 -Radiological Assessment Calculations DISPOSAL OF LOW-LEVEL RADIOACTIVELY CONTAMINATED SOIL AND GRAVEL IN THE ON-SITE DREDGE SPOILS POND AT SURRY POWER STATION A. INTRODUCTION Surry Power Station is planning to pave the yard area within the tected area, i.e., the area inside the security fence. Over the years, the grades inside the fence have been raised as a result of roadway repairs and the disposal of excess soil. Pavement construction would require the excavation of large quantities of soil from various con-struction projects. In some locations within the Radiological Control Area (RCA) the soil is low-level radioactively contaminated from previous steam releases and radioactive liquid spills. A preliminary engineering study was conducted to determine the required pavement sections for the yard areas based upon actual onsite soil conditions, to estimate quantities of materials that must be excavated in order to construct the pavement, and to investigate options for final disposal of the excavated material outside of the protected area. The study concluded that approximately 6,000 cubic yards of contaminated soil and gravel would require disposal. In addition, the study recommended that the 6,000 cubic yards figure be increased to 10,000 cubic yards to incorporate future construction activities. The contaminated soil and gravel would be disposed in the dredge spoils pond which is located on Virginia Electric and Power Company's owner controlled property. 45/1/LLR/CAT i ' e B. DESCRIPTION OF CONTAMINATED SOIL AND GRAVEL Four test pits were excavated in order ,to define sub-grade conditions for pavement design. The following is a brief description of the materials that were encountered: Stratum I All pits except one encountered approximately 5 to 6. 5 inches of dense graded crushed stone at the ground surface. Visually this material is similar to normal aggregate utilized for roadway bases and sub-bases. Stratum II A layer of old asphalt was encountered at three locations. The asphalt was only 1 to 2 inches thick and generally was observed below the crushed aggregate. Stratum III All pits encountered dense to very dense reddish brown sandy gravel either below the crushed stone or the asphalt. This material is a portion of the select granular backfill material that was used to fill the original plant excavation back to grade. A majority of the reactor containment area was excavated from an original grade of 34 feet to elevation 7 feet during construction. After completion of the major structures, the area was back-filled to plant design grade of 26.5 feet. The sandy gravel extended to variable depths of 18 to 36 inches below existing grade. Stratum IV Below the dense gravel, all excavations, except one outside the Administration Building, encountered dense tan silty sand with some fine gravel. This material was also part of the select fill for the general plant excavation. 45/1/LLR/CAT / ' \. e Stratum V One test pit and the excavation outside the Administration Building encountered stiff tan and gray silty clay immediately beneath Stratum III gravel. This material is a natural deposit occurring at the surface of the plant site. The above locations fall either outside or on the edge of the area that was excavated to elevation 7 feet, This explains why natural soil deposits were encountered at such a shallow depth. An extensive sampling program was performed to determine the identity of the contaminating radionuclides and their concentrations in the soil and gravel. Fifty-seven (57) sampling locations were identified in the yard. Locations were representative of those areas in which paving activities would generate soil and gravel requiring disposal. Surface, 6 inch and 12 inch samples were obtained and analyzed for each location for a total of 171 samples. Sample results were averaged to determine the following concentrations (µCi/gm): RADIONUCLIDE Co-60 Cs-134 Cs-137 Mn-54 AVERAGE CONCENTRATION (µCi/gm) 1.56E-06 5.26E-07 2.38E-06 2.68E-09 These isotopic concentrations were used to perform the radiological dose assessments. 45/1/LLR/CAT C. DESCRIPTION OF DREDGE SPOILS POND 2. Diagrams showing the dredge spoils area are provided in Attachment 1 for your reference.

1. The dredge spoils pond is located adjacent to the low-level intake structure, east of the plant. The pond is approximately 2,700 feet long and 600 to 1,300 feet wide. The facility was designed to accommodate dredged materials from the channel north of the intake structure in the James River. The pond has a top of crike elevation of 44 feet and the maximum permissible water elevation in the pond is 42 feet. If the water elevation approaches the maximum, a discharge pipe through the northwest corner of the dike can route excess water into the intake canal. Results of slope stability analyses demonstrate that all slopes in the dredge disposal area are stable. Further, there would be no adverse impact on the function of the low-level intake canal even in the event of slope failure or erosion. The liquefaction potential under the dredge disposal area was also evaluated by comparing earthquake induced stresses with shear stresses necessary to cause liquefaction.

Results of these examinations showed that the construction of the dredge disposal area effectively reduces the liquefaction potential under the dredge disposal basin and dike. The liquefaction potential at the high-level intake canal is not affected by the construction of the dredge spoils area. The dredge disposal dike has been designed to retain the spoil pile for both static and dynamic loading conditions. 45/1/LLR/CAT The area within the toe of the dike at the base of the dredge disposal area is lined with a minimum of one (1) foot of compacted clay. This clay liner was designed and installed to minimize seepage from the dredge spoils pond into underlying groundwater and to prevent a resultant rise in the groundwater level in the vicinity of the pond. The dikes that comprise the perimeter of the pond were also constructed of compacted clay soils. Both the dike and liner materials were referenced as "Impervious Fill" in the project specifications. The complete design and installation specifications were perfomed by Stone and Webster Engineering Corporktion and are contained in Reference

6. D. SITE AREA CHARACTERISTICS
1. Meteorology The Surry site is located in a humid sub-tropical climate area which receives an average monthly rainfall of 3.77 inches. The total accumulated snow for the Surry region is approximately 10 inches each year. An average of two hurricanes each year comes close enough to the coast to affect Virginia.

However, less than one hurricane (0.6 per year) actually crosses the state. Additional meteorological and climatological information may be obtained from Surry Power Station UFSAR, Volume I. 45/1/LLR/CAT e It is our assessment, given these meteorological conditions, that the disposal of contaminated soil in the spoils pond will not be impacted in a detrimental way by the climatological characteristics of the Surry region. 2. Hydrology The hydrologic boundaries of the Surry site are the James River on the east and west, Hog Island Creek to the north, and Chippokes and Hunnicut Creeks about one mile to the south. A water analysis indicates that, of the total precipitation, 37% runs off and the remaining 63% is lost through evaporation and transpiration by the surrounding foliage. Low soil permeabilities preclude significant ground-water recharge from local precipitation. An analysis of the probable rise in the James River mean water level at the site associated with the flood discharges indicates that even for a flood discharge recurrence interval of once in 50 years, the water level at the site would rise no more than one foot above the normal mean river level. Due to the wide floodplain at the site the rise above normal water levels of the James River is minor even under severe flooding conditions. Additional ground water hydrology studies are provided in Surry Power Station UFSAR, Volume I. 45/1/LLR/CAT

3. e Geology The Surry site is located on Gravel Neck, in Surry County, Virginia.

The site is situated in the Coastal Plain province approximately halfway between the Atlantic Ocean and the Fall Zone which is the boundary between the Piedmont and Coastal Plain Provinces. Surface inspections and subsurface investigations in the immediate vicinity of the Surry site show no evidence of structural tion. Borings indicate no offsets or strata holding. There is no surface or subsurface evidence of prior landslides, cratering, or fissures that may be indicative of prior intense earthquake effects. E. ALTERNATIVE DISPOSAL METHODS Two alternative disposal methods were evaluated. These included: (1) burying the contaminated soil outside the Radiological Control Area (RCA) but not in an area of proposed construction and (2) shipping the inated soil to a licensed disposal facility.

1. Burial of Contaminated Soil The excavated materials from the yard area within the RCA could be buried onsite in an area which is not under proposed construction.

However, since there exists a "permitted" dredge spoils pond which affords a confinement for the 10,000 cubic yards of low-level radioactively contaminated soil, the option of burying elsewhere 45/1/LLR/CAT

  • , e on-site is not a preferred choice. The various engineering and environmental studies that have been performed on the spoils pond demonstrate its viability.
2. Shipment to a Licensed Disposal Facility The volume allocation necessary for the disposal of the contaminated soil at a shallow land burial site far exceeds the current annual volume allocation at the Barnwell Waste Management Facility of approximately 25,000 cubic feet for Surry Power Station. more, a cost estimate for the disposal of 10,000 cubic yards of soil at a licensed disposal facility shows the cost to be prohibitive.

F. DISPOSAL OF CONTAMINATED SOIL IN DREDGE SPOILS POND A station Health Physics procedure will be developed to address the disposal of contaminated soil in the Surry dredge spoils pond. The key elements of the procedure would include: (1) a tracking system for accountability of the amount of contaminated soil disposed in the pond; (2) requirements for transfer of the contaminated soil from the yard area within the RCA to the dredge spoils pond; and (3) Health Physics erations to include adequate surveys, contamination control, and nel monitoring. The transfer and disposal operations will be performed under the technical guidance and review of Health Physics personnel. 45/1/LLR/CAT \ _, -e G. RADIOLOGICAL ASSESSMENT I. The following exposure pathways were examined in assessing the radiological impact of disposing the low-level radioactively inated soil in the dredge spoils pond: a. The unrestricted area liquid effluent percent maximum sible concentration (MPC) was determined for the instantaneous release of all contaminated soil activity disposed in the spoils pond. b. The unrestricted area liquid effluent percent maximum sible concentration (MPC) was determined for the release of contaminated soil activity disposed in the spoils pond during dredging operations.

c. The total body and critical organ doses to a member of the general public from radioactive material in liquid effluents released during dredging operations were determined.
d. The total body and critical organ (lung) doses from inhalation of radionuclides resuspended in air were calculated for the Company worker(s) and member(s) of the general public. e. The annual dose from external irradiation due to radionuclides deposited onto the ground surface of the dredge spoils pond was determined for the Company worker(s) and member(s) of the general public. 45/1/LLR/CAT e e Unless otherwise specified, the radiological assessment was formed using assumptions and methodologies contained in Regulatory Guide 1.109, Rev. 1, 1977, Surry Power Station Offsite Dose lation Manual, and Reactor Shielding Design Manual by T. Rockwell III. 2. The dredge spoils pond is located on Virginia Electric and Power Company owned property.

It is an isolated area, routinely patrolled. Consequently, use of the property would be restricted, thereby precluding the growing of food crops and grazing by milk or meat producing animals. pathways were not considered. Therefore, these ingestion exposure 3. Estimates for public use of adjacent land and water surrounding the dredge spoils pond site for recreational and contractual work activities has been conservatively estimated to occur approximately one month (744 hours) during the year. Therefore, the annual inhalation and direct radiation doses to the member(s) of the general public were calculated based on an occupancy period of one month in a given year. The annual inhalation and direct radiation doses to Company personnel working at the dredge spoils pond are based on an annual occupancy period of 2000 hours per year. 4. The inhalation and direct radiation doses to the member(s) of the general public have been calculated for the site boundary location. Doses at the nearest resident location, which is approximately 1.65 miles from the dredge spoils pond, are negligible. 45/1/LLR/CAT -5. Attachment 2 provides the dose assessment assumptions and lations. 6. Results: a. The percent of unrestricted area liquid effluent MPC for the instantaneous release of all contaminated soil activity is 8.16. b. The percent of unrestricted area liquid effluent MPC for the total release of contaminated soil activity during dredging operations is 1.33E-02.

c. The total body and critical organ (GI-LLI) doses to the ber (s) of the general public from radioactive materials in liquid effluents released during dredging operations are 5.22E-03 mrem and 8.48E-03 mrem respectively.
d. The annual total body and critical organ (lung) doses to the member(s) of the general public from the inhalation of nuclides resuspended in air are 1.35E-01 mrem and 1. 33 mrem respectively for 744 hours per year (one month) occupancy.

The annual total body and critical organ doses to the Company worker from the inhalation of radionuclides resuspended in air are 3.63E-Ol mrem and 3.56E+OO mrem respectively for 2000 hours occupancy period. 45/1/LLR/CAT " e. The annual dose from external radiation due to radionuclides deposited onto the ground surface within the dredge spoils pond to the member(s) of the general public is 8.33E-04 mrem for 744 hours per year (one month) occupancy. The annual dose from external radiation to the Company worker is 2.24E-03 mrem for 2000 hours occupancy period. H. CONCLUSIONS The results reported in section G.6 are well below the regulatory limits contained in 10 CFR Part 20. Furthermore, the transfer and disposal of low-level radioactively contaminated soil and gravel from the yard area within the protected area to the dredge spoils pond has negligible radiological impact and poses no health hazards to members of the public and/or on-site personnel. This disposal method is a cost effective means of handling large tities of material in a contained and efficient manner. I. REFERENCES

1. Regulatory Guide 1.109, Rev. 1, Oct. 1977, Calculation of Annual Doses to Man from Routine Releases from Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I. 2. Surry Power Station, Off site Dose Calculation Manual, November 5, 1985. 45/1/LLR/CAT
3. J. W. Healy, Los Alamos Scientific Laboratory, LA-4558-MS, September 1971 "Surface Contamination:

Decision Levels". 4. Report of Extended Type I Study: Contaminated Soil and Gravel in the RCA; Surry Nuclear Power Station, NP-0536, Virginia Electric and Power Company, December, 1984. 5. Surry Power Station UFSAR, Volume I, Chapter 2. 6. Stone and Webster Engineering Project, J.O. #12313. 7. Reactor Shielding Design Manual, T. Rockwell III, D. VanNostrand Company, Inc., 1956. 8. NBS Handbook No. 29, Cross Sections, Attenuation Coefficients and Energy Absorption Coefficients From 10 keV to 100 GeV, 1969. 9. ANSI/ ANS 6 .1.1 Neutron and Gamma-ray Flux-to-dose Rate Factors, 1977. 10. Radiological Health Handbook, . January 1970, U. S. Department of Health Education and Welfare, PHS. 11. Code of Federal Regulations, Part 10CFR20.302.

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.. , . . LL2!l0 -..%-,* * * " 1 r-:'lL I'-' /-oGj\--. c 11 1,. __ -=4 CRAVfl\ 1 1 II I flll[R BERY ! I I ! : l'-o' 119(L-8) r-*--i ~(_ 2-\?mEL l PIP(...j.t.:._~* urr. [YE IN:EATS : *.,: , .J~-*-2.-*F."P. ru;. ;s* 1 ,,;p l CONC.."'TAIN£A -' 1/f.\, -..!, 7*k-l1 *er --CONC. TO 8£ CAST AROUND PIPC Al LAYOCW .. AAF' A. '\. l~S. R-0~' f t~:;Q~*: __ :*. PICA .,. .._ ' ODLE z .. \"tGALV. * . SOLIS 14"1.li. 4 -* .. . -*'u>. -~ ;_. .. .:.:. . 19-19 (G-1) sc*u,1*-r-0* ' I. Problem e e ATTACHMENT 2 A. PERCENT UNRESTRICTED AREA MPC CALCULATIONS -INSTANTANEOUS RELEASE .* ' Determine the unrestricted area (10CFR20.106) liquid effluent percent MPC for the release of all contaminated' soil activity disposed in the dredge spoils pond. II. Assumptions

1) Dredge .spoils. pond releases into the high-level intake canal, through the station, to the discharge canal, to the James River. 2) . Sampling program results provide average isotopic concentrations of contaminated soil. 3) Two of the eight circulating water pumps are running. The capacity of each water pump is 2.00E+OS gallons per minute. 4) There is an instantaneous release of activity (i.e., 1 minute). 5) 10,000 yd 3 of soil to be disposed in the dredge pond. III. Calculations A. Average specific activity from all soil samples. Isotope Co-60 Cs-134 Cs-137 Mn-54 Specific Activity (µCi/g) 1. 56E-06 5.26E-07 2.38E-06 2.68E-09 B. Density of soil and sand p = 2.2g/cc C. Number of cm 3 of = 10,000 yd 3 x 27 ft 3 x 28.32 1 x 1000 cc contaminated soil yd 3 ft 3 1 Number of cm 3 of = 7.65E+09 cc contaminated soil D. Total activity in 10,000 yd 3: Isotope Activitl (µCi/g) X 2.2 (g/ cc) x 7.65E+09 (cc) = µCi Co-60 l.56E-06 X 2.2 X 7.65E+09 = 2.63E+04 Cs-134 5.26E-07 X 2.2 X 7.65E+09 = 8.85E+03 Cs-137 2.38E-06 X 2.2 X 7.65E+09 = 4.01E+04 Mn-54 2.68E-09 X 2.2 X 7.65E+09 4.51E+Ol 45/5/MPC/CAT l-. ,. e E. Concentration in dredge spoils pond Total volume of pond = 2700 ft x 600 ft.x 1 ft= 1.62E+06 ft 3 Total gallons= 1.62E+06 ft 3 x 7.481 gal= 1.21E+07 gal Total cc= 1.21E+07 gal x 3.79 1 x gal Isotope µCi + 4.58E+l0 (cc) Co-60 2.63E+04 + 4.58E+l0 Cs-134 8.85E+03 + 4.58E+10 1000 cc = 1 = = = *-. ----* Cs-137 4.01E+04 + 4.58E+l0 = Mn-54 4.51E+Ol + 4.58E+l0 F. Dilution Factor Dilution factor 1.21E+07 Dilution factor l.21E+07 + (2 x 2.00E+05) 0.968 G. Concentration in discharge canal Dredge Spoils Pond Concentration Dilution Isotope (µCi/cc) X Factor = Co-60 5.73E-07 X 0.968 = Cs-134 1.93E-07 X 0.968 = Cs-137 8.74E-07 X 0.968 = Mn-54 9.83E-10 X 0.968 = H. Percent unrestricted area MPC Concentration Isotope µCi/cc + MPG (µCi/cc) Co-60 5.55E-07 + 3E-05 Cs-134 1. 87E-07 + 9E-06 Cs-137 8.46E-07 + 2E-05 Mn-54 9. 52E-10 + lE-04 Percent of unrestricted area MPC = 8.16 45/5/MPC/CAT 4.58E+10 cc µCi/cc 5.73E-07 1.93E-07 8.74E-07 9.83E-10 = = = = = Discharge Canal Concentration

(µCi/ cc) 5.55E-07 1.87E-07 8.46E-07 9.52E-10 Cone. /MPC 1.85E-02 2.08E-02 4.23E-02 9.52E-06 8.16E-02 '--I

  • e B. PERCENT UNRESTRICTED AREA MPC CALCULATION

-DREDGING OPERATION I. Problem Determine the unrestricted area (10CfR20.106) liquid effluent percent MPC for the release of contaminated .,soil activity disposed in the dredge spoils pond during dredging operations. II. Assumptions ,, NOTE: 1) Dredging operat~ori. takes 5 weeks, 7 days per week, 20 hours per day. 2) Dredging flow rate from pond is l.20E+04 gallons per minute. 3) Total activity (µCi) of radionuclides in dredge spoils pond de-termined in A.III.Dis valid. 4) Two of the eight circulating water pumps are running. The capacity of each pump is 2.00E+05 gallons per minute. 5) 6) Dredge spoils pond releases into the high-level intake canal, through the station, to the discharge canal, to the James River. Release through the effluent discharge structure is at maximum water elevation in pond (Drawing #12313-EY-llB-l, #1213-EY-llA-l). Assumptions

  1. 1 and #2 are based on the first 2 dredgings of the spoils pond. Information was provided by Surry, E&C. III. Calculations A. Total volume of water in pond. Volume of pond, ft 3 2700 ft X 600 where 2700 ft 600 ft 18.5 ft ft X 18.5 ft, = length of pond, = width of pond = maximum dredge pond elevation

-min. elevation of slope toe = 42.0 ft. -23.5 ft. Total gallons 3.00E+07 ft 3 X 7.481 gal = 2.24E+08 gal t?" Total cc = 2.24E+08 gal X 3.79 1 X 1000 cc = 8.49E+ll gal 1 B. Concentration based on 10,000 yd 3 of disposed soil. Isotope Total Activity (µCi) + 8.49E+ll(cc) µCi/cc Co-60 2.63E+04 + 8.49E+ll = 3. lOE-08 Cs-134 8.85E+03 + 8.49E+ll = l.04E-08 Cs-137 4.01E+04 + 8.49E+ll 4. 72E-08 Mn-54 4.51E+Ol + 8. 49E+ll 5.31E-ll 45/6/MPC/CAT . . . C. Dilution factor Dilution factor = l.20E+04 1.20E+04 + (2 x 2.00E+05) Dilution factor = 2.91E-02 , ,/ D. Percent unrestricted area MPC-' Concentration Dilution Isotope µCi/cc X Factor Co-60 3.lOE-08 X 2.91E-02 Cs-134 1.04E-08 X 2.91E-02 Cs-137 4.73E-08 X 2. 91E-02 Mn-54 5. 32E-ll X 2. 91E-02 + + + + + Percent of unrestricted area MPC 1.33E-02 45/6/MPC/CAT MPC 3.0E-05 9.0E-06 2.0E-05 1.0E-04 Concentration = MPC = 3. OlE-05 = 3.36E-05 = 6.88E-05 = 1.55E-08 z: = 1. 33E-04 .... ' . .. I. Problem e C. LIQUID EFFLUENT DOSE CALCULATIONS -DREDGING OPERATION Determine the dose commitment to the m~mber(s) of the general public from radioactive material in liquid effluents released from the dredge spoils pond during dredging operation. II. Assumptions

1) Radioactive mater~~l is only released during dredging operations.

/ 2) Dredging operation takes 5 weeks, 7 days per week, 20 hours per day. -The pond is designed to contain material for one future dredging.

3) Dredging flow rate from pond is l.20E+04 gallons per minute (4.54E+07 cc/min). 4) Total activity (µCi) of radionuclides in dredge spoils pond termined in A.III.Dis valid. 5) Two of the eight circulating water pumps are running. The capacity of each pump is 2.00E+OS gallons per minute. 6) Dredge spoils pond releases into the high-level intake canal, through the station, to the discharge canal, to the James River. 7) Release through effluent discharge structure is at maximum water elevation in pond (Drawing #12313-EY-llB-l, #1213-EY-llA-l).

III. Calculations A. Total volume of water in pond. Volume cc = 8.49E+ll cc from B.III.A. B. Total activity released from pond during dredging operation. -4.54E+07t/8.49E+ll A. = A . (1 -e ) 1 01 where 45/2/DC/CAT A. = 1 Total activity, in µCi of isotope i, released from pond at time t. ,----.....___, __ e A = Total activity, in µCi of isotope i, originally in pond. oi t = Total time, in minutes, of dr.(idging operation. --/ / t = 5 weeks X 7 days X 20 hours X 60 min 4.2E+04 min week day hour -4.54E+07 x 4.2E+Q4/8.49E+ll (1 -e ) = 0.89 ~/-* -Isotope A A . . oi X 0.89 = l , -'-------... Co-60 2.63E+04 X 0.89 = 2.34E+04 --*cg-~134-- 8.85E+03 X 0.89 = 7.88E+03 Cs-137 4.01E+04 X 0.89 3.57E+04 Mn-54 4.51E+Ol X 0.89 = 4.0lE+Ol C. D = tFM~ A. DF. i l l where: D = Dose commitment to the total body or critical organ from liquid effluents for the time period t, in mrem. t = The length of the time period over which C. and Fare l averaged for all liquid releases, hours. m = The mixing ratio (reciprocal of the dilution factor) at the point of exposure, dimensionless, 0.2 from Appendix llA~ Surry UFSAR. F = The inverse ~f the total dilution volume for the time period t, cc . A. = The total activity, µCi of isotope l i, released from pond. DF.= The site related ingestion dose commitment factor to l the total body or GI-LLI of an adult from ODCM Table 4.0, mrem/hr per µCi/cc. t 5 weeks x 7 days x 20 hours= 7.00+02 hours week day m 0.2 F = 1/(2 x 2.0E+OS gal x 63.09 cc-min x 2.52E+06 sec) F l.57E-14 -1 cc min gal-sec 45/2/DC/CAT , ... I* l D. Total Body Dose . Isotope A,(µCi) X DF. (mrem/hr) = mrem-cc l. l. µCi/cc hr Co-60 2.34E+04 X 3.82E+03 8.94E+07 Cs-134 7.88E+03 X l.33E+04 = l.05E+08 Cs-137 3.57E+04 -*X 7.85E+03 = 2.80E+08 Mn-54 4. OlE+Ol .-*' l.35E+03 5.41E+04 X = .,-" I: = 4.75E+08 *-'-. = 7.00E+02 (hr) x l.57E-14(cc-

1) x 4.75E+08(mr~;-cc)

....__,_~- D(Total Body) --~ ............... h ** D(Total Body)= 5.22E-03 mrem E. GI-LLI Dose Isotope A.(µCi) X DF. (mrem/hr) = mrem-cc l. l. µCi/cc hr Co-60 2.34E+04 X 3.25E+04 = 7. 61E+08 Cs-134 7.88E+03 X 2.85E+02 = 2.25E+06 Cs-137 3.57E+04 X 2.32E+02 = 8.28E+06 Mn-54 4. OlE+Ol X 2.16E+04 = 8.66E+05 I: = 7.72E+08 D(GI-LLI) = 7.00E+02 (hr) X -1 7. 72E+08 (mrem-cc) l.57E-14(cc ) X hr D(GI-LLI) 8.48E-03 mrem 45/2/DC/CAT Nuclide Co-60 Cs-134 Cs-137 Mn-54 e D. INHALATION OF RESUSPENDED RADIONUCLIDES IN AIR I. Problem Determine the total body and critical organ dose to the member(s) of the general public and the Company worker from inhalation of radionuclides resuspended in air. II. Assumptions

1) All contaminated soil activity is deposited on the surface of the dredge spoils pond. _..,_ ------iy' ---Tlie entire dredge spoils pond surface area is used for the disposal of the contaminated soil. 3) Reg. Guide 1.109 assumptions are valid. 4) The resuspension factor L~y4558-MS-LASL, Surface m , is valid. for moderate Contamination activity Decision conditions from Levels, l.OOE-05 5) Calculations pertain to the adult total body and teen for critical organ (lung). 6) The member of the general public is estimated to occupy the vicinity of the dredge spoils pond approximately one month throughout the year and the Company worker is estimated to occupy the dredge spoils pond approximately 2000 hours throughout the year. III. Calculations A. Total surface area of dredge spoils pond: 2700 ft x 600 ft = l.62E+06 ft 2 l.62E+06 ft 2 X 9.29E-02 m 2 = l.51E+05 m 2 12" B. Concentration in Air Surface Activity Surface Area Contamination

(µCi) + (m2) = (µCi/m 2) 2.63E+04 + 1. 51E+05 = 1. 74E-01 8.85E+03 + l.51E+05 = 5.86E-02 4. 01E+04 + l.51E+05 2.66E-01 4.51E+Ol + l.51E+05 = 2.99E-04 C. Total Body and Critical Organ Dose Equation 0 D ECi x BR x DF x CF 45/4/RRA/CAT Resuspension Concentration Fac!~r in Air X (m ) = µCi/m 3 X l.OOE-05 = l.74E-06 X l.OOE-05 = 5.86E-07 X l.OOE-05 2.66E-06 X l.OOE-05 2.99E-09 It/., 'i \) JI. where: 0 D = The total body or critical organ (lung) annual dose, mrem. C. = Concentration of radionuclide~ µCi/m 3 1 BR = Breathing rate of a teen or adult, 8.00E+03m 3/yr,R.G.1.109. DF = Inhalation total body dose factor for an adult or inhalation lung dose factor for a teen, mrem/pCi,R.G.1.109. CF. ConversiorC factor, 1. OOE+06 pCi/µCi. *,*,J),. ______ Total Body Annual Dose to an Adult. 0 Ci BR DF CF D Nuclide (µCi/m 3) X (m 3/yr) X (mrem/pCi) X (pCi/µCi) = (mrem/yr) Co-60 1. 74E-06 X 8.00E+03 X 1. 85E-06 X 1.00E+06 2.58E-02 Cs-134 5.86E-07 X 8.00E+03 X 9. lOE-05 X 1.00E+06 = 4.27E-01 Cs-137 2.66E-06 X 8.00E+03 X 5.35E-05 X 1.00E+06 = 1.14E+OO Mn-54 2.99E-09 X 8.00E+03 X 7.87E-07 X 1.00E+06 = 1.88E-05 E 1.59 Member of general public: Annual dose for 744 hours occupancy = 1.35E-01 mrem. Company worker: Annual dose for 2000 hours occupancy = 3.63E-01 mrem. E. Critical Organ (Lung) Annual Dose to a Teen 0 Ci BR DF CF D Nuclide (µCi/m 3) X (m 3 /yr) X (mrem/pCi) X (mrem/µCi) = (mrem/yr) Co-60 1.74E-06 X 8.00E+03 X 1.09E-03 X 1.00E+06 = L 52E+Ol Cs-134 5.86E-07 X 8.00E+03 X 1.83E-05 X 1.00E+06 = 8.58E-02 Cs-137 2.66E-06 X 8.00E+03 X 1. 5 lE-05 X l.OOE+06 = 3.21E-01 Mn-54 2.99E-09 X 8.00E+03 X 2.48E-04 X 1.00E+06 = 5.93E-03 E = 1.56E+Ol Member of general public: Annual dose for 744 hours occupancy

1.33E+OO mrem. Company worker: Annual dose for 2000 hours occupancy

3.56E+OO mrem. 45/4/RRA/CAT E. DOSE FROM EXTERNAL.IRRADIATION FROM RADIONUCLIDES DEPOSITED ON GROUND SURFACE I. Problem Determine the annual dose to the member(s) of the general public and the Company worker from external radiation due to radionuclides deposited onto the ground surface. II. Assumptions -1.) All contaminated soil activity is deposited onto the surface of the dredge spoils pond. 2) The dredge spoils pond is a volume slab source of infinite extent having a finite thickness with self-absorption (61 cm). 3) The gamma flux is uniform throughout the volume source. 4) The equation for calculating the gamma flux for a thick slab of infinite extent with self-absorption contained in Reactor Shielding Design Manual, T. Rockwell III, is valid. 5) The density of soil is 2.2 g/cc. 6) The member (s) of the general public is estimated to occupy the vicinity of the dredge spoils pond approximately one month throughout the year and the Company worker is estimated to occupy the dredge spoils pond approximately 2000 hours throughout the year. III. Calculations A. From sample results, the following average isotopic concentrations were determined: B. 45/7 /EI/CAT Isotope Co-60 Cs-134 Cs-137 Mn-54 0 0 = Sv = Jls E2(b3) Concentration (µCi/cc) Sv 2µ s , where gamma flux, photons/cc-sec. 1 source strength, cc sec l.56E-06 5.26E-07 2.38E-06 2.68E-09 4.47E-06 -1 linear absorption coefficient, cm integral exponential function equal to 5.0E-04 for b = 3 to 10, Rockwell graph, p. 374 Rockwell Manual. e = µ x h, where his the amount of soil providing s~lf-absorption, equal to 61 cm. 1. From NBS Handbook No. 29, the i~ferpolated value ofµ for 1.33 MeV gamma photons is 9.2E-02 cm s 2. b3 = b3 = b3 = 3. Sv = Sv = 4. µs X h -1 9.2E-02 cm X 61 cm 5.61 4.47E-06µCi/cc x 3.7E+04 l.65E-01 photons/cc-sec Sv 2µ s dps/µCi 1.65 E-01 photons/cc-sec (5.0E-0 4) 2 x 9.2E-02cm-1 4.48E-04 photons/cm 2-sec 5. From ANSI 6 .1.1., the gamma ray flux to dose rate conversion factor for 1.4 MeV gamma photons is 2.51E-06 rem/hr per photon/cm 2-sec. The 1.4 MeV energy is more conservative than the actual isotopic energies.

6. Dose Rate (mrem/hr)

= 2.51E-06 x 4.48E-04 = l.12E-09 rem/hr l.12E-06 mrem/hr Member(s) of the general public: Annual dose for 744 hours (one month) occupancy = 8.33E-04 mrem Company worker: Annual dose for 2000 hours occupancy = 2.24E-03 mrem. 45/7 /EI/CAT}}

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