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Evaluation of Onsite & Offsite Accident,Worker & Member of Public Dose Scenarios
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Issue date:	05/28/1999
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NEXTEPenvironmental l

Evaluation of Onsite and Offsite Accident, Worker, and Member of the Public Dose Scenarios Prepared for:

Kerr-McGee Cushing Facility Cushing, OK Prepared by:

)

NEXTEP Environmental, Inc.

May 28,1999

{IS" loo $!Eooao U

c.

l.

TABLE OF CONTENTS ON-SITE AND OFF-SITE ACCIDENT SCENARIOS..................................B-3 Off-Site Radiological Accident Scenario-Cleanup Worker...................B-3 Off-Site Radiological Accident Scenario-Member of the Public............B-7 On-Site Radiological Accident Scenario-Radiation Worker.................B-8

)

J WORKER DOSE EVALUATION-CUSHING FACILITY..............................B-13 PUB LIC RADIATION DOS E ESTIMATE................................................B-15 1

Cushing Decommissioning Plan B-2 Response to General Comment #2 e

ON-SITE AND OFF-SITE ACCIDENT SCENARIOS Introduction Cushing has evaluated the potential for exposure from conditions occurring both on-site

]

and off-site and has. determined that transportation accidents are the most credible for j

public and employee exposures occurring off-site, while accidents involving spillage of j

radioactive. waste: are the most credible for on-site exposures.

These evaluations provide upper bounding scenarios for the types of exposures expected to occur as a result of the decommissiening operations at Cushing.

)

Assumptions:

.1) Shipment contains 450 ft' of contaminated soil (representing approximately 17 yards of waste material within an intermodal container).

2) For the off-site scenario, the transport vehicle is involved in an accident, and the 2

entire shipment is assumed to'be spilled over an area of 900 ft. The average depth of the spill is 6 inches (15 cm).

)

3) - Exposure pathways include inhalation of suspended particulates and direct exposure.

- 4) The time to clean up the off-site spill is 1 day (24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ), while the time to clean up the on-site spill is 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

5)' The average concentrations of total U and Th-232 in the shipment are assumed to be

)

200 pCi/g.

-)

6) Thorium-228 is _in secular equilibrium with Th-232.

Off-Site Radiological Accident Scenario-Cleanup Worker Emission Rate (E) = 0.01 [a A K C L' V'] based upon Reference 1.

Where:

E = Annual emission rate in tons / acre-y.

a = Fraction of total wind erosion losses that could be measured as suspended particulates (assume 0.41 for fine soil per Reference 1).

l = Soil erodability in tons / acre-y (assume 52 for fine soil per Reference 1).

. K = Surface Roughness factor (assume 1.0 for smooth pile per Reference 1).

C = Climate factor (assume 20 for Oklahoma City per Reference 1).

L' = Field width factor (0.7 per Reference 1).

V' = Vegetation factor (1.0 for no vegetation present per Reference 1).

E = (0.01)(0.41)(52)(1.0)(20)(0.7)(1.0) = 2.98 tons / acre-y The ' surface area emission rates for total uranium, Th-232,' and Th-228 (i.e., Q..u. Q..w 232, and Q..w2a) for fugitive dust due to wind are therefore:

Cushing Decommissioning Plan -

B-3 L

' Response to General Comment #2 i

Q..u = Q..wu2 = Q..wns = (2.98 tons / acre-y)(2000 lb/ ton)(454 g/lb)(200 pCi/g) 2 2 2 2

(900 ft )(0.0929 m /ft )(acre /4050 m )(y/3.15E7 s)

= 0.35 pCi/s.

Calculation of the volumetric emission rate for total U, Th-232, and Th-228 (Qv.v. Qv.w and Q,.w22s) from the cleanup, hauling, and containerization of soil can be u2, calculated using the estimate for suspended particulates from Reference 1, which is 0.38 lbs/yd'. This factor is applicable to front end loader movement of topsoil, and is also assumed to represent any soil movement using shovels or other tools.

Q,.u = Q.wu2 = Qv.w22: = [(0.38 lbs/yd')(yd'/27 ft')(45 Y)(454 g/lb)(200 pCi/g)]

+ ((1 day)(24h/ day)(3600s/h)] = 6.7 pCi/s.

The total source term emission rates for total U, Th-232, and Th-228 are calculated as follows:

Qu = Q..u + Q,.u = 7.1 pCi/s total U Qwn2 = Q..wu2 + Qv.wn2 = 71 PCi/s Th-232 1

1 Qw22: = Q w 22: + Qv.w22: = 7.1 pCi/s Th-228 An extremely conservative estimate of dose to the cleanup worker can be made by assuming that the area immediately above the spilled soil has a " lid" at a height of 2 m, which is the height for the breathing zone of the worker. Wind at a speed of 1 m/s is assumed to blow the suspended particulates across the spilled waste to the breathing zone of the worker, who is assumed to stand continuously downwind at the edge of the spill. The worker is assumed to be present for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and breathes at a rate of 1.2 m'/ hour. By imposing the dispersion " lid" at a height of 2 m, there can be no dispersion above this height. Likewise, it is also assumed that there is no atmospheric dispersion at right angles to the wind direction. Thus, the model portrays a worst case 2

scenario. Assuming a circular area of 900 ft, the diameter of the spill, D, will be:

D = (4A/n)u2 = {[(4)(900 ft )jf3}v2 = 33.9 ft.

2 The concentration of airborne radioactive material above the spill will be limited by the steady state emissions and the wind speed. The time, t, required for a particle at the leading edge to traverse the spill and reach the hypothetical worker at the trailing edge is:

Cushing Decommissioning Plan B-4 Response to General Comment #2

t = 33.9 ft + (1m/s)(1.0 ft/0.3348m) = 10.3 s.

Thus, the steady state average concentration, C, of total uranium, Th-232, and Th-228 over the spill area can be calculated as follows:

4

Cu = Cwu2 = Cw22: = [(7.1 pCi/s)(10 Ci/pCi)(10.3 s)]

+ [(900 ft )(0.0929 m /ft )(2 m)(10 mL/m')]

2 2 2 6

= 4.4 E-13 pCi/mL This concentration is an extreme overestimate of the actual concentration due to the fact that the wind causing the dust emission is not considered to carry and disperse the suspended soil particles outside the bounds of the spill area.

Assuming a 1.2 m'/ hour inhalation rate for the worker (Reference 2, p. 216), a 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months work period, and using the most conservative dose conversion factors (DCFs) from Reference 3, the hypothetical effective dose due to inhalation of the total uranium, Th-232, and Th-228 will be:

CEDEu = (4.4 E-13 Ci/mL)(1.2 m'/ hour)(24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months )(10 mL/m')(3.58 E-05 Sv/Bq) 6 (3.7 E+09 mrem /pCi per Sv/Bq) = 1.7 mrem CEDEmu2 = (4.4 E-13 pCi/mL)(1.2 m'/ hour)(24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months )(10 mL/m')

6 (4.43 E-04 Sv/Bq)(3.7 E+09 mrem /pCi per Sv/Bo)

= 20.8 mrem CEDF+22s = (4.4 E-13 pCi/mL)(1.2 m'/ hour)(24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months )(10' mL/m')

(9.23 E-05 Sv/Bq)(3.7 E+09 mrem / Ci per Sv/Bq) i

= 4.3 mrem CEDE, = CEDEu + CEDEmu2 + CEDE

= 26.8 mrem S 22:

The dose du.c to direct exposure can be estimated using the dose conversion factors from Reference 4, Table E.2. For volume sources with a thickness of 6 inches (15 cm), the DCFs are as follows:

U-234:1.85 E-16 Sv/d per Bq/m' U-235:3.24 E-13 Sv/d per Bq/m' Cushing Decommissioning Plan B.5 Response to General Comment #2

U-238i4.76 E-17 Sv/d per Bq/m'

- Th-232:

2.40 E-16 Sv/d per Bq/m' Th-228:~

3.60 E-15 Sv/d per Bq/m' l

Ac-228:

2.38 E-12 Sv/d per Bq/m' Bi-212:

'4.63 E-13 Sv/d per Bq/m' Pb-212:

3.13 E-13 Sv/d per Bq/m' Po-216:

4.21 E-17 Sv/d per Bq/m' Ra-224:

2.26 E-14 Sv/d per Bq/m'

~ Rn-220:

9.52 E-16 Sv/d per Bq/m' TI-208:

8.36 E-12 Sv/d per Bq/m' The DCF for U-235 will provide the most conservative estimate of dose to the worker from direct exposure to uranium, since it is three to four orders of magnitude greater than-the DCFs for U-234 or U-238. In addition, the EPA's default soil density of 1.625 E+06 g/m' (per Reference 4, Table E.2) was used. The dose calculations for direct exposure are performed as follows:

External dose from U = (200 pCi/gX0.037 Bq/pCi)(1.625 E+06g/m')

(3.24 E-13 Sv/d per Bq/m')(100 rem /Sv)

(1000 mrem / rem)(1 d) = 0.4 mrem.

The effective DCF for Th-232, including all daughters, is:

2.40 E-16 + 3.60 E-15 + 2.38 E-12 + 4.63 E-13 + 3.13 E-13 +

4.21 E-17 + 2.26 E-14 + 9.52 E-16.+ (0.35) (8.36 E-12) Sv/d per Bq/m'

= 6.11 E-12 Sv/d per Bq/m'

)

l where 0.35 is the branching fraction for TI-208.

External dose from Th-232 and all daughters, including Th-228 =

i

-(200 pCi/gX0.037 Bq/pCi)(1.625 E+06g/m')(6.11 E-12 Sv/d per Bq/m')

(100 rem /SvX1000 mrem /remX1 d) = 7.3 mrem.

Summing the external and internal doses, the estimated TEDE will be 34.5 mrem under the above worker scenario.

Thus, the-maximum projected dose to a cleanup worker from spillage of a shipment of cantaminated soils :and debris from the Cushing facility is conservatively projected to be 35 mrem TEDE. The above estimates are known to

. Cushing Decommissioning Plan.

84 Response to General Comment #2 m

i significantly overestimate the actual doses that would be received, due to the conservative assumptions utilized and the fact that no credits were assumed for the use of personal protective gear during the cleanup effort Off-Site Radiological Accident Scenario-Member of the Public

\\

The member of the public is assumed to be at a distance of 1 km from the spill, and is constantly in the plume centerline in the downwind direction. The atmospheric stability will be assumed as' extremely stable, Class F. The spill will be modeled as a point source, with emission rates as defined for the cleanup worker scenario.

The basic atmospheric dispersion equation for a ground level source at the plume centerline is:

. x = Q + (2n)(a,)(o,)(u).

J Sigma y and sigma z were picked from Figures 3-2 and 3-3 in Reference 5, using Class F atmospheric stability curves. The wind specd is assumed to be 1 m/s.

The concentration of airborne total uranium, x, is calculated:

x.= 7.1 E-12 Ci/s + (2x)(34 m)(14 m)(1 m/s) = 2.4 E-15 Ci/m' The effective dose can be calculated using the dose conversion factors from EPA Federal Radiation Guidance Report No.11 (Reference 3). The dose conversion factors for U-234, U-235, and U-238 are similar. Therefore, simplification of the problem can

__ be achieved through the use of the dose conversion factor for U-234, which is the most '

conservative.

Inhalation Class Y is assumed for the. resuspended material.

The

. breathing rate is assumed to be 9.6 m'/ day.

Effective Dose to the Member of the Public from total U

= (2.4 E-15 Ci/m') (9.6 m'/d) (1 d) (3.58 E-05 Sv/Bq) 6 (3.7 E+09 mrem /pCi per Sv/Bq)(10 pCi/Ci)

= 3 E-03 mrem CEDE i

I l

~ Cushing Decommissioning Plan '

B7 j

Response to General Comment #2

)

i

i Effective Dose to the Member of the Public from Th-232

= (2.4 E-15 Ci/m') (9.6 m'/d) (1 d) (4.43 E 04 Sv/Bq)

(3.7 E+09 mrem / Ci per Sv/Bq) (10' pCi/Ci)

= 4 E-02 mrem CEDE Effective Dose to the Member of the Public from total Th-228

= (2.4 E-15 Ci/m') (9.6 m'/d) (1 d) (9.23 E-05 Sv/Bq) 6 (3.7 E+09 mrem / Ci per Sv/Bq) (10 pCi/Ci)

= 8 E-03 mrem CEDE J

Total CEDE to the Member of the Public from all nuclides

= 5 E-02 mrem (0.05 mrem)

Note that the TEDE is equivalent to the CEDE as there is no anticipated direct exposure to a member of the public resulting from the accident scenario.

The upper estimate of dose to the member of the public is the 0.05 mrem, which is insignificant.

This estimate utilized conservative. assumptions of wind speed and stability class and placed the individual in the plume centerline for the entire duration of the cleanup. In addition, no shielding or dilution effects were considered as is normally j

done to account for shelter of the individual.

On-Site Radiolonical Accident Scenario-Radiation Worker j

This scenario assumes that a single container holding 7.5 ft' of waste soils is spilled.

The concentrations of total U, Th-232, and Th-228 within the spilled material are each 2

200 pCi/g. The spill covers an area of 15 ft to a depth of 6 inches (15 cm). The calculations can be performed utilizing' the same methodology as for the Off-Site.

Scenario-Cleanup Worker. The cleanup is assumed to take 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

Emission Rate (E) = 0.01 [a A K C L' V'] based upon Reference 1.

= (0.01)(0.41)(52)(1.0)(20)(0.7)(1.0) = 2.98 tons / acre-y Cushing Decommissioning Plan B-8 Response to General Comment #2

I t

t The surface area emission rate, Q, for fugitive dust due to wind is therefore:

2

, Q, = (2.98 tons / acre-yX2000 lb/tonX454 g/lb)(200 pCi/gX15 ft )

2 2 2

(0.0929 m /ft Xacre/4050 m )(y/3.15E7 s) = 6 E-03 pCi/s.

Calculation of the volumetric emission rate, Q,, from the cleanup, hauling, and replacement of soil into new drums can be calculated using the estimate for suspended particulates from Reference 1, which is 0.38 lbs/yd'. This factor is applicable to front end loader movement of topsoil,' and is also assumed to represent any soil movement using shovels or other tools.

Q, = [(0.38 lbs/yd')(yd'/27 ft')(7.5 ft')(454 g/lb)(200 pCi/g)]

+ [(4h)(3600s/h)] = 0.7 pCi/s.

The total source term emission rate for total U, Th-232, and Th-228, is:

Q, + Q, = 0.7 pCi/s.

An extremely conservative estimate of dose to the cleanup worker can be made by i

assuming that the area immediately above the spilled soil has a " lid" at a height of 2 m, which is the height for the breathing zone of the worker. Wind at a speed of 1 m/s is l

assumed to blow the suspended particulates across the spilled waste to the breathing zone of.the worker, who always stands downwind at the edge of the spill. The worker is assumed to be present for 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and breathes at a rate of 1.2 m'/ hour.

By imposing a " lid" at a height of 2 m, there can be no dispersion above this height.

Likewise, it is also assumed that there is no atmospheric dispersion at right angles to the' wind direction. Thus, the model portrays a worst case scenario. Assuming a 2

circular area of 15 ft, the diameter of the spill, D, will be:

D = (4A/x)v2 = ([(4X15 ft ))f3)uz = 4.4 ft.

2 The concentration of total uranium above the spill will be limited by the steady state emissions and the wind speed. The time, t, required for a particle at the leading edge to traverse the spill and reach the hypothetical worker at the trailing edge is:

t = 4.4 ft + (1m/s)(ft/0.3048m) = 1.3 s,

)

Thus, the steady. state average concentration, C, of total uranium, Th-232, and Th-228 over the spill area can be calculated as:

I Cushing Decommissioning Plan

' B.9 Response to General Comment #2 ~

C = [(0.7 pCi/s)(10~6pCi/pCi)(1.3 s)]

+ [(15 ft )(0.0929 m /ft )(2m)(10 mum')] = 3.3 E-13 pCi/mL 2

2 2 6

This co.a. centration is an extreme overestimate of the actual concentration due to the fact that wind causing the dust emission is not considered to carry and disperse the suspended soil particles outside the spill area.

Assuming a 1.2 m'/ hour inhalation rate for the worker (Reference 2, p. 216), a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

. work period, and using dose conversion factors (DCFs) from Reference 3, the hypothetical effective dose due to inhalation will be:

CEDEu = ( 3.3 E-13 Ci/mL)(1.2 m'/ hour)(4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months )(10 mum')(3.58 E-05 Sv/Bq) 6 (3.7 E+09 mrem / Ci per Sv/Bq) = 0.2 mrem.

CEDEwu2 = ( 3.3 E-13 pCi/mL)(1.2 m'/ hour)(4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months )(10 mum')

6 (4.43 E-04 Sv/Bq)(3.7 E+09 mrem /pCi per Sv/Bq) = 2.6 mrem.

CEDEw22s = ( 3.3 E-13 pCi/mL)(1.2 m'/ hour)(4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months )(10 mum')

6 (9.23 E-05 Sv/Bq)(3.7 E+09 mrem /pCi per Sv/Bq) = 0.5 mrem.

CEDEu = CEDEu + CEDEwu2 + CEDEw22: = 3.3 mrem The dose due to direct exposure can be estimated using the dose conversion factors from Reference 4, Table E.2.

For volume sources with a thickness of 6 inches (15

)

cm), the DCFs are as follows:

U-234:1.85 E-16 Sv/d per E t m'

/

U-235:3.24 E-13 Sv/d per Bq/m' U-238:4.76 E-17 Sv/d per Bq/m' Th-232:

2.40 E-16 Sv/d per Bq/m' Th-228:

3.60 E-15 Sv/d per Bq/m' Ac-223:

2.38 E-12 Sv/d per Bq/m' Bi-212:

4.63 E-13 Sv/d per Bq/m' Pb-212:

3.13 E-13 Sv/d per Bq/m' Po-216:

4.21 E-17 Sv/d per Bq/m' Ra-224:

2.26 E-14 Sv/d per Bq/m' Rn-220:

9.52 E-16 Sv/d per Bq/m' TI-208:

8.36 E-12 Sv/d per Bq/m' Cushing Decommissioning Plan B-10 Response to General Comment #2

The DCF for U-235 will provide the most conservative estimate of dose to the worker from direct exposure to uranium, since it is three to four orders of magnitude greater than the DCFs for U-234 or U-238. In addition, the EPA's default soil density of 2

1.625 E+06 g/m (per Reference 4, Table E.2) was used. The dose calculations for direct exposure are performed as follows:

External dose from U = (200 pCi/g)(0.037 Bq/pCi)(1.625 E+06g/m')

(3.24 E-13 Sv/d per Bq/m')(100 rem /Sv)

(1000 mrem / rem)(1 d) = 0.4 mrem.

The effective DCF for Th-232, including all daughters, is:

2.40 E-16 + 3.60 E-15 + 2.38 E-12 + 4.63 E-13 + 3.13 E-13 +

4.21 E-17 + 2.26 E-14 + 9.52 E-16 + (0.35) (8.36 E-12) Sv/d per Bq/m'

= 6.11 E-12 Sv/d per Bq/m' where 0.35 is the branching fraction for TI-208.

External dose from Th-232 and all daughters, including Th-228 =

(200 pCi/g)(0.037 Bq/pCi)(1.625 E+06g/m')(6.11 E-12 Sv/d per Bq/m')

(100 rem /Sv)(1000 mrem / rem)(1 d) = 7.3 mrem.

Summing the external and internal doses, the estimated TEDE will be 11 mrem under

)

the above worker scenario.

]

Thus, the maxhnum projected dose to a cleanup worker from spillage of a shipment of contaminated soils and debris from the Cushing facility is conservatively projected to be 11 mrem TEDE. The above estimates are known to significantly overestimate the actual doses that would be received, due to the conservative assumptions utilized and the fact that no credits were assumed for the use of personal protective gear during the cleanup effort fanclusion Three hypothetical exposure scenarios related to on-site and off-site accidents were evaluated. The off-site scenarios considered doses to workers and a member of the public resulting from the spillage of waste material in transit to a low-level waste disposal facility. The on-site scenario addressed potential exposure due to the cleanup Cushing Decommissioning Plan B-11 Response to General Comment #2

r i

r of spilled radioactive material. Conservative assumptions were utilized to generate estimated doses for the three scenarios, as follows:

Off-site Radiological Accident Scenario-Worker:35 mrem TEDE Off-site Radiological Accident Scenario-Public: 0.05 mrem TEDE On-site Radiological Accident Scenario-Worker: 11 mrem TEDE These dose estimates are considered to represent upper bounds of dose.

The calculations demonstrate that the radiological consequences of accidents involving radioactive waste spillage are insignificant for members of the public, and will result in doses to cleanup workers that are well within the regulatory requirements.

References

1. Colorado Department of Health, Interoffice Cotamunication, Fugitive Dust Emissions, September 30,1981.

2. Radiological Health Handbook, U.S. Department of Health, Education, and Welfare, Public Health Service, Revised 1970.

3. Environmental Protection Agency, " Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and I

Ingestion," EPA-520/1-88-020, Federal Guidance Report No.11, September,1988.

4.- U.S. NRC, NUREG/CR-5512, PNL-7994, " Residual Radioactive Contamination from Decommissioning", Volume 1, Reprinted June,1994.

5. Turner, D.

B.,

" Workbook of Atmospheric Dispersion Estimates," U. S.

Department of Health, Education, and Welfare, Cincinnati, OH,1%9.

I Cushing Decommissioning Plan B 12

. Response to General Comment #2

Worker Dose Evaluation-Cushing Facility

- A conservative estimate of dose to on-site radiological workers is made using the

- following assumptions:

1). Cleanup is performed in RMA-11 and/or Pit 4.

2) Isotopes include U-234, U-235, U-238, and Th-232 in equilibrium with Th-228.

3) Airborne activity levels range from 0-10% DAC above background and average 5%

DAC during times when activities affecting airborne activity are performed.

4) Activities affecting radiological airborne quality are performed 40% of the time spent in RMA-11 and 15% of the time spent in Pit 4 (based upon 8 weeks spent in the thorium contaminated area of Pit 4).

i

5) The working year is 2000 hoo s.

6) Assume reference man physiology and ICRP30 models.

7) Maximum anticipated exposure rates are 0.5 mR/h and 0.1 mR/h above background in RMA-11 and Pit #4, respectively for up to 2% of the time spent in the areas.

The average exposure rates during other work times are assumed as 10 micro-R/h above background.

External Dose Estimates The annual external dose is estimated as follows:

DDE = (0.5 mR/h x 40h) + (0.010 x 1960) = 39.6 mR (RMA-11)

DDE = (0.1 mR/h x 40h) + (0.010 x 1960) = 23.6 mR (Pit #4)

Internal Dose Estimates The internal dose for RMA-11 is estimated as follows:

(0.05 DAC) (0.40) (2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months ) = '40 DAC-hours CEDE = 40 DAC-hours x (5 rem CEDE /2000 DAC-hours)

= 0.1 rem = 100 mrem Note: : Only the SALI dose is calculated as it is less than 1 rem. (Reference Regulatory Guide 8.34, Section 5)

The internal dose for Pit 4 is estimated as follows:

(0.05 DAC) (0.15) (2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months ) = 15 DAC-hours Cushing Decommissioning Plan B-13 Response to General Comment #2

p 1

CEDE = 15 DAC-hours x (5 rem CEDE /2000 DAC-hours)

= 0.038 rem = 38 mrem l

Note: Only the SALI dose is calculated as it is less than 1 rem. (Reference Regulatory Guide 8.34, Section 5)

Estimation of TEDE -

The TEDEs for RMA-11 and Pit 4 are estimated as follows:

TEDE,ux.ii = DDEaux.i, + CEDEaux.ii = 140 mrem.

TEDEpi,4 =. DDEpi,4 + CEDEpi,4 = 62 mrem.

Each of these dose estimates is less than 10% of the annual dose limits for radiation workers.

4 i

I i

- Cushing Decommissioning Plan B-14 Response to General Comment #2 1

q i

j Public Radiation Dose Estimate Kerr-McGee Corporation Cushing, Oklahoma Facility Dose. to the public from operations at the Kerr-McGee. Corporation Cushing facility

~

under USNRC license SNM 1999 was calculated for 1998.~ This paper describes the methods used and documents the results for public radiation dose during 1998. The content of this evaluation was originally published.as Health Physics Technical Evaluation #12, "Public Radiation Dose for 1998 from the Ket:r-McGee Corporation Cushing, Oklahoma Facility."

Limits for effluents are delineated in 10Cl

'O Appendix B Table 2.' This table applies to airborne and liquid effluents, and each nit assumes a 50 millirem (mrem) annual dose. The 50 mrem limit for deep dose is provided in 10CFR20.1302(b)(2)(ii).

The environmental media data used to calculate the total effective dose equivalent included surface water sample results, airborne radioactivity sample results and thermoluminescent dosimeter (TLD) results. The total effective dose equivalent for the annual public dose is the sum of the calculations resulting from these environmental pathways.

Data used in the calculations are attached.

Egblic Dose due to Liauid Effluen_ts Annual surface water sample data was used to calculate public dose from liquid effluents. Nuclides measured for calculating public dose from surface water effluents

- are U-234, U-235, U-238 and Th-232. To determine background concentrations, Skull Creek is sampled as it enters the site at location B145E30S40.

Background

concentrations were subtracted from the concentrations at the sample location where the maximum surface water activity exits the site to calculate public dose.

'ihe, net concentration exiting the site is assumed to be continuous.

This is a conservative approach because currently, there are no processes that allow for dose calculations as individual releases are made. Liquid effluent releases for this time period only occurred during precipitation events.

Method -

liquid efHuent dose (mrem) = g ((sample point conc., - background conc.,) / APP B Table 2 limit,) * $0 where *u* i2 the nuclide of interest Cushing Decommissioning Plan B-15 Response to General Comment #2 i(

]

l

p Results 1998 liquid effluent dose 0.66 mrem -

q Public Dose due to Airborne Effluents Environmental airborne sample data was used to calculate public dose from airborne effluents. The average concentration above background was used to calculate the dose to the public. - The limit for Th232 from 10CFR20 Appendix B Table 2 was used to.

calculate public dose. Th232 has the most restrictive limit of the Cushing site nuclide distribution.

' The average concentration at Environmental Sample Location 003 (ENV003) was used to define' background due to its location in Unaffected Area 3 and its distance from licensed operations.

Method airborne effluent dose (mrem) =

((average conc. my w,w,,e - average conc. mye) / App B Table 2 limit) * $0 Results 1998 airborne dose (mrem) 0.00 millirem Public Dose from External Radiation Sources -

Locations used in determining public dose were the 5 TLD locations at the northern and northeastern boundary of the site. These TLDs measure dose at the site boundary closest to the public. The TLD locations were averaged for each quarter and that j

average was used to calculate the. deep dose contribution to annual dose.

.TLD. location AMO12 in Unaffected Area ~ 3 was used for background radiation i."

measurement due to its distance from licensed operations and location in this unaffected area.

J F

i Cushing Decommissioning Plan B-16 Response to General Comment #2' u

Method DDE (mrem) =

[(quarterly TLD result (average mrem /wk), - quarterly background TLD result (mrem /wk),)

13 wk/qtr where "n" is the quarter of the year (i.e.; 1,2,3 or 4)

Results 1998 TLD results (mrem) 17.4 millirem Public Dose The annual total effective dose equivalent (TEDE) to the public is the sum of the doses from the above mentioned pathways.

1998 Public Dose TEDE = 0.66 mrem ' O.00 mrem + 17.4 mrem = 18 mrem.

The public dose of 18 mrem is insignificant and is well within the 100 mrem annual dose limit established by 10 CFR 20.

Cushing Decommissioning Plan B-17 Response to General Comment #2 i.-

m

- 1998 Public Dose Data Summary Liquid nuclide U233/234 U235 U238 Th228 Th232

)

maximum concentration (pCi/ml) 3.02E-09 1.27E-10 2.17E-09 0.00E+00 0.00E+00 background (pCi/ml).

7.14E-10 2.60E-11 6.21E-10 0.00E+00 0.00E+00 not concentration (pCl/ml) 2.31E-09 1.01E-10 1.55E-09 0.00E+00 'O.00E+00

{

10CFR20 Appendix B limit (pCi/ml) 3.00E-07 3.00E-07 3.00E-07 2.00E-07 3.00E-08 dose = (not concentration / limit)*50 mrom 3.84E-01 1.68E-02 2.58E-01 0.00E+00 0.00E+00 total dose (mrom) 0.66 Airborne average concentration (pCi/ml) 1.43E-15 average background (UCi/ml) 1.47E-15 average not concentration (pCl/ml)

-3.38E-17 10CFR20 Appendix B limit (pCL/ml Th232) 6.00E-15 dose = (average not concentration / limit)*50 0.00 Deep Dose Equivalent quarter 1st 2nd 3rd 4th average environmental TLD (mrom/ week) -

0.75 1.28 1.35 2.31 background (mrem / week) 0.22 0.97 1.45 1.81 not mrom/ week by quarter 0.53 0.31

-0.10 0.50 public dose by quarter (mrom) 6.84 4.06 0.00 6.53 DDE (mrom) 17.42 1998 public dose (mrem) 18.1 Cushing Decommissioning Plan B-18 Response to General Comment #2

r l

Responses to Requist for Additional Information KMC Cushing Site Decommissioning Plan Attachment C -

Imse ApeTa;;; Pmperties Kerr-McGee/Notti Gathering Co, Inc.

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Attachment D Annual Environmental Sample Data 1996 - 1998

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Environmental Ra Attachm Environmental groundwater, surface wa 1995 through 1 1995 data is included because some samples ona= not analyzed Attachment D1 Page

plogical Data nt D 1 Br, vegetation and soil sample data for

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(5 pages)

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' i 8.19E4G130E.01'D 12!98 surfac water results (pC6't)

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M3 1.40E4)2 1.60E4)2 1.20E42 2.10E41 6 60E 42 3.40E42 4 00E41 1.10E 01 8 000 42 8.50E42 4 90E42 5.40E 02 MGO.6XM]

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1. lGE + 00 4.00E4)I 2.00E41 1.10E + 00 4.(X)E-01 3 00E41 9 00E-01 4.00E41 2.00E41 NE,E 5 I MkMCMeMMMMU NMMEN 1.00E41 1.00E41 2.00E41 1.40E + 00 5.00E4)I 2.00E4)1 1.40E + 00 5 00E41 4.00E41 9 00E41 4 00E4)!

3.00E 41 IMEM MDMMf13.00b.DMMOMEEMME N Md 2.00E41 2 00E41 2.00E41 1.30E + 00 5 00E-01 2.00E41 1.30E + 00 5 00E4)I 3.00E4)I 1.00E + 00 4 00E4)1 2.00E41 dMMNMEMMIDM[.

3MMDMDMCM M E N ((U M N O 00E +00 100F 01 100E41 1.60E + 00 5 00E41 3 00E4)!

! 30E + 00 4.00E41 2 00E41 9 00E4)!

3.00E 01 2.00E41 FMFM1M.ll M G M I D M)@ C IJMG,0064GML

%M12MGMed 0.00E + 00 1.00E 01 1.00E 01 1.00E + 00 4 00E.01 3 00E-01 1.20E + 00 5 00E41 4 00E41 1.00E + 00 4.00E41 2.00E41 QQGQ MOMC M MD M MO@C DM1MO@GME BMOLQMM,MG 1.00E-01 l.00E41 1.00E41 9.00E41 4 00E41 1.00E41 1 4GE + 00 5 00E41 2 00E 01 1.00E + 00 4.00E41 2.0)E41 b2h S of S

'~~

Environmental Radiological Data Attachment D2 Environmental air sample data for 1996 through 1998.

(15 pages) 4 Attachment D2 Page 1 of 15

g Environmental Radiological Data 1998 Airborne radioactivity monitorine In 1998, there were a total of 5 air sampling stations used to collect environmental air samples. Samples were collected at weekly sampling periods, and there were a total of 13 samples that were invalid due to power outages and equipment failures. Summary data for the samples are as follows:

Total number of samples 252 Maximum concentration 2.51E-15 pCi/cc Average concentration 1.31E-15 pCi/cc Average MDA 1.94E-16 pCi/cc 1997 Airborne radioactivity monitorine In 1997, there were a total of 5 air sampling stations used to collect environmental air samples. Environmental station 4 was placed in service on 04/22/97, and environmental station 5 was placed in service on 12/12/97. Samples were collected at weekly sampling periods. Summary data for the samples are as follows:

Total number of samples 191 Maximum concentration 2.74E-15 pCi/cc

. Average concentration 1.26E-15 pCi/cc Average MDA 1.91E-16 pCi/cc 1996 Airborne radioactivity monitorine In 1996, there were a total of 3 air sampling stations used to collect environmental air samples. Samples were collected at weekly sampling periods. Summary data for the samples are as follows:

Total number of samples 155 Maximum concentration 7.93E-15 pCi/cc Average concentration 1.80E-15 Ci/cc Average MDA 2.03E-16 pCi/cc 1998 data:

Air Sample ID Air Sample End Date Person or Place Activity MDA Number pCi/cc pCi/cc AS010698 001 01/06/98 Environmental 1 9.80E-16 1.93E-16 AS011398 002 01/13/98 Environmental 1 2.15E-15 1.55E-16 AS012098 002 01/20/98 Environmental 1 1.79E-15 2.07E-16 AS012798 006 01/27/98 Environmental 1 2.10E-15 1.76E-16 AS020398 002 02/03/98 Environmental 1 1.85E-15 1.62E-16 AS021198 003 02/11/98 Environmental 1 1.90E-15 1.21E-16 J

Attarhrr.<nt D2 Page 2 of 15

a gupJousuouivI ysptoloSiovI aviv y!J Svutd o ta y!J serud a 3uP G'18 doJsou oJ dI'08 V31!MIA WGV l

l NuqaJ da!/os d3!/33 VSOZIL68 007 ORIL/68 3upmutuounI I I*0Z3-IS IF83-19 VSOZEt68 OOZ ORtt/68 3upJouruouivI I

! W 3-IS IV53-19 YSOE0168 001 0E/OI/68 3upJousuounI I

'6'863-19 TOL3-19 VSOEl068 007 0E/!0/68 3upJousuounI I 6*ttS-19 6*6S3-IL VSOCIL68 001 0E/lL/68 3upJomauni I I'853-IS IVI3-19 VSOEtt68 OI8 0E/tt/68 au JousuounII I* 163-IS l'SS3-19 VSOCET68 OIZ 0E/EI/68 3upmusuounI !

6'9L3-19 IV03-19 VS090468 006 09/OL/68 3upmmauni I l*Sta-IS IV53-19 YSOtit68 009 0)/{p/68 guA!JoinuounI i L*t63-19 IVL3-19 YSOD168 OIO 09/EI/68 3upJousuouni I I'983-IS l'L03-19 VS0tt868 OOZ 0)/78/68 3upJoinuou.1 I I*ES3-IV t'iL3-19 VSOS0568 OOL 05/05/68 3up m m ouselI I'IE3-IS T.7 3-19 t

YSOSit68 OIO OS/II/68 3uMJ028MII l'093-15 t'it3-19 f

YSOSI668 00E 05/16/68 3uyJouruou1'l I I'IE3-IS TPE3-19 YSOSt968 007 OS/t9/68 3upaousuou181 I l'ES3-IS I *EE3-19 VS090268 OOL 09/0R68 3upaousuou181 i I'OC3-IS l'L03-19

-YS090668 OOC 09/06/68 3upmmamiI l'863-19 I'673-19 VS091968 009 09/19/68 3upJousuouivI I 8'983-19 I'EL3-19 VS09tE68 00#

09/ZE/68 3upaousuou1'l I l't83-19 t'E83-19 VSOL0168 00E OL/01/68 3upmuutsunI I E'043-19 i'963-19 VSOL0468 00E OL/OL/68 3upJoummi I I'993-IS TE13-19 VSOLIt68 007 0L/19/68 3upJousuouni I I

IP3-IS tF93-19 YSOLZE68 007' OL/tt/68 3u iousuouniI I*0E3-IS I'963-19 YSOL7868 00E 0L/78/68 3upJousuouni I I*SS3-IS TEt3-19 YS08Oi68 007 08/09/68 3upmutuomi I I'IE3-IS t'0I3-19 VS081168 007 08/II/68 3upaomouiul I I'St3-IS

!*463-19 VS081868 007 08/18/68 3upJousuoutal I I'403-IS t'L83-19 VS09tS68 007 08/7S/68 3uAjmuutoutul I l't93-IS T653-19 VS060168 007 06/01/68

.guA!m m o miI IV93-IS ZV93-19 YS060868 OOZ 06/08/68 3uM30m*MII T063-15 TE83-19 VS06IS68 00E 06/IS/68 3upJomaunI I I* 183-IS TSL3-19 VS06tt68 001 06UR68 3u murusuivII 6'763-19 l *LIH-19 VS067668 007 06/t6/68 3upmusuomi I IV63-IS T573-19 VSl00968 007 i0/09/68 3upJouutaunI I 8'SI3-19 TEta-19 VSi0IE68 007 10/IE/68 3upaousuouni I I'Z03-IS I'L03-19 VSl07068 007 10/70/68 3upaou w uni I I W 3-IS I'8Z3-19 VSl07L68 007 10/tL/68 3upJo m u181T I'SS3-IS IV53-19 VSll0068 007 II/0E/68.

3upaousuouiul I I'IE3-IS 7953-19 VSllI068 OOZ II/10/68 3upJomou1'l I I'993-IS 7163-19 VSIIIL68 007 II/IL/68 3upJousuomi I I'SI3-IS l'LI3-19 VSlit968 OOZ

!!09/68 3u pJ m uouiul I I'913-IS I'893-19 VSIZ0t68 007 IR0468 3uA]J m uouniI I'LL3-IS I'663-19 VSIZ0868 001

!t/08/68 3u JousuomiI I'I63-IS TOI3-19 VSItiS68 007' IZ/IS/68 3uA!Jousuouni I IVS3-IS EF93-19 y$(({(6g QQ{-

{g/Z(/63 guA]Jousuouni I I'813-IS I'L03-19 VSltt668 007' 1t/76/68 3upJouutouiul I 70E3-IS T053-19 YSOi0566 OOZ 01/0S/66 3upmmami I TEL3-IS EVE 3-19 ynvolnuout 04' d883 E oj Ig

e Environmental Radiological Data Air Sample ID Air Sample End Date Person or Place Activity MDA Number pCi/cc Ci/cc ASO10698 002 01/06/98 Environmental 2 9.95E-16 2.03E-16 AS011398 003 01/13/98 Environmental 2 2.51E-15 1.99E-16 AS012098 003 01/20/98 Environmental 2 1.50E-15 2.18E-16 AS012798 007 01/27/98 Environmental 2 1.81E-15 1.84E-16 AS020398 003 02/03/98 Environmental 2 1.57E-15 1.62E-16 AS021198 004 02/11/98 Environmental 2 1.75E-15 1.15E-16 AS021798 003 02/17/98 Environmental 2 1.09E-15 1.42E-161 AS022498 003 02/24/98 Environmental 2 1.39E-15 1.45E-16 AS030198

-002 03/01/98 Environmental 2 1.01E-15 2.09E-16 AS031098 003 03/10/98 Environmental 2 9.24E-16 8.72E-17 AS031798 002-03/17/98 Environmental 2 1.73E-15 1.27E-16 AS032498 -

019 03/24/98 Environmental 2 1.01E-15 1.55E-16 AS033198 013 03/31/98 Environmental 2 8.59E-16 1.34E-16 I

AS040798 010 04/07/98 Environmental 2 1.23E-15 1.41E-16

' AS041498 007 04/14/98 Environmental 2 6.21E-16 1.47E-16 AS042198 011 04/21/98 Environmental 2 1.33E 1.88E-16 AS042898 003 04/28/98 Environmental 2 1.31E-15 2.17E-16 AS050598 -

008 05/05/98 Environmental 2 1.03E-15 2.21E-16 AS051298 011

'05/12/98 Environmental 2 9.34E-16 1.92E-16 as051998 004 05/19/98 Environmental 2 1.30E-15 2.72E-16 L AS052698 003 05/26/98 Environmental 2 1.41E-15 1.42E-16 AS060298 008 06/02/98 Environinental 2 1.11E-15 1.66E : AS060998.'

004 06/09/98 Environmental 2 8.57E-16 2.06E-16 AS061698 -

'007 06/16/98 Environmental 2 9.27E-16 1.49E-16 i

AS062398 005 06/23/98 Environmental 2-7.89E-16 2.27E-16 AS070198 003-

-07/01/98 Environmental 2 2.42E-16 1.62E-16 i

AS070798 004 07/07/98 Environmental 2 1.21E-15 2.20E-16

" AS071498 -

003, 07/14/98 Environmental 2 1.11E-15 2.58E-16 AS072398 ?

003 07/22/98 Environmental 2 7.66E-16 1.69E-16 AS072898 004 07/28/98 Environmental 2 1.32E-15 2.24E-16 AS080498 003 08/04/98 Environmental 2 1.49E-15 1.93E-16 AS081198 003 08/11/98 Environmental 2 1.32E-15 1.79E-16 AS081898 003 08/l8/98 Environmental 2 1.21E-15 2.48E-16 AS082598 003 08/25/98 Environmental 2 1.02E-15 '

2.81E-16 AS090198 003 09/01/98 Environmental 2 1.24E-15 2.34E-16

~ ASO90898 003 09/08/98 Environmental 2 1.54E-15 2.21E-16 AS091598 004 09/15/98 Environmental 2 1.04E-15 3.24E-16 ASO92298--

002 09/22/98 Environmental 2 1.03E-15 1.71 & l6

)

ASO92998 003 09/29/98 -

Environmental 2 1.03E-15 2.41E-16 AS100698 003 10/06/98 Environmental 2 7.20E-16 2.24E-16 As101398.

003-10/13/98 Environmental 2 8.18E-16 1.62E-16

AS102098

.003 10/20/98 Environmental 2 1.33E-15 1.74E-16

' ' ' AS102798 ~

003-10/27/98 Environmental 2 1.13E-15 1.38E-16 T:

ASI10398 003 11/03/98' Environmental 2 8.87E-16

.2.53E-16 AS111098 003 11/10/98 Environmental 2 1.39E-15 2.08E-16 AS111798:

003 11/17/98 Environmental 2 1.45E-15 1.55E-16

)

ASI12498.

003 11/24/98 Environmental 2 1.46E-15 1.70E-16 1

1 o.

Attachment D2 Page 4 of 15

'L'_.

t Environmental Radiologicc1 Data Air Sample ID Air Sample End Date Person or Place Activ'.y MDA Number pCi/cc pCi/cc AS120298 003 12/02/98 Environmental 2 1.75E-15 1.81E-16

. AS120898

,002 12/08/98 Environmental 2 1.02E-15 2.01E-16 AS121598 003 12/15/98 Environmental 2 1.37E-15 2.23E-16 AS122398 002 12/23/98 Environmental 2 1.65E-15 1.79E-16 AS122998 003 12/29/98 Environmental 2 1.77E-15 2.06E-16 AS010599 003 01/05/99 Environmental 2 2.06E-15 2.44E-16 AS010698 003 01/06/98 Environmental 3 9.19E-16 2.03E-16 AS011398 004 01/13/98 Environmental 3 1.88E-15 1.63E-16 AS012098 -

004 01/20/98 Environmental 3 1.79E-15 2.06E-16 AS012798 008 01/27/98 Environmental 3 2.19E-15 1.94E-16

' AS020398 004 02/03/98 Environmental 3 1.82E-15 1.78E-16 AS021198 005 02/11/98 Environmental 3 2.14E-15 1.24E-16 AS021798 004 02/17/98 Environmental 3 1.77E-15 1.56E-16 AS022498 004 02/24/98 Environmental 3 1.79E-15 1.52E-16 AS030198 003 03/01/98

- Environmental 3 1.02E-15 2.20E-16 AS031098 004 03/10/98 Environmental 3 9.46E-16 9.16E-17 AS031798 003 03/17/98 Environmental 3 1.62E-15 1.33E-16 AS032498 020 03/24/98 Environmental 3 1.12E-15 1.55E-16 AS033198 014 03/31/98 Environmentr.13 9.43E-16 1.55E-16 AS040798 011 04/07/98 Environmental 3 -

1.81E-15 1.44E-16 AS041498 008 04/14/98 Environmental 3 1.16E-15 1.61E-16 AS042198 012 04/21/98 Environmental 3 -

1.28E-15 1.57E-16

.AS042898 004 04/28/98 Environmental 3 2.00E-15 2.492-16 AS050598 009 05/05/98 Environmental 3 9.31E-16 2.33E-16 AS051298 012 05/12/98 Environmental 3 1.07E-15 1.%E-16 AS051998 005 05/19/98 Environmental 3

- 2.41E-15 3.86E-16 AS052698 004 05/26/98 Environmental 3 1.57E-15 1 A9E-16 AS060298 009 06/02/98 Environmental 3 1.65E-15 '

1.74E-16 AS060998 -

005 06/09/98 Environmental 3 9.53E-16 1.82E-16 AS061698 008 06/16/98 Environmental 3 4.38E-16 1.64E-16 AS070198 004 07/01/98 Environmental 3 2.64E-16 1.73E-16

{

AS071498 004 07/14/98 Environmental 3 1.15E-15 2.71E-16 AS072398 004 07/22/98 Environmental 3 1.35E-15 1.61E-16 AS072898 005 07/28/98 Environmental 3 2.15E-15 2.45E-16 AS080498 004 08/04/98 Environmental 3 1.39E-15 1.93E-16 AS082598 004 08/25/98 Environmental 3 8.85E-16 2.95E-16 AS090198 004 09/01/98 Environmental 3 1.41E-15 2.58E-16 ASO90898 004 09/08/98 Environmental 3 2.17E-15 2.20E-16

~

ASO91598 005 09/15/98 Environmental 3 1.12E-15 2.56E-16 ASO92298 003 09/22/98 Environmental 3 1.16E-15 1.79E-16 AS092998 004 09/29/98 Environmental 3 1.48E-15 2.41E-16 AS100698 004 10/06/98 Environmental 3 7.91E-16 2.36E-16 AS101398 004 10/13/98 Environmental 3 1.15E-15 1.87E-16 AS102098 004 10/20/98 Environmental 3 1.65E-15 2.01E-16

'AS102798 004 10/27/98 Environmental 3 1.50E-15 1.52E-16 AS110398 004 11/03/98 Environmental 3 1.07E-15 2.79E-16 AS111098 004 11/10/98 Environmental 3 1.41E-15 2.08E-16 j

Attachment D2 Page 5 of 15

l Environmental Radiological Data Air Sample ID Air Sample End Date Person or Place

' Activity-MDA I

Number pCi/cc pCi/cc ASI11798 004 11/17/98 Environmental 3 1.92E-15 1.70E-16.

' AS112498 004 11/24/98 Environmental 3 1.70E-15 1.87E-16

~ AS120298 004 12/02/98 Environmental 3 2.07E-15 1.9)E-16 AS120898.

003 12/08/98 Environmental 3 1.08E-15 2.01E-16 AS122398 003 12/23/98 Environmental 3 1.91E-15 1.78E-16 AS122998 ~

004 12/29/98 Environmental 3 2.15E-15 2.06E-16 AS010599 004 01/05/99 Environmental 3 218E-15 2.43E-16 A3010698 004 01/06/98 Environmental 4 1.04E-15 1.93E-16 AS011398 005 01/13/98 Environmental 4 2.08E-15 1.60E-16 AS012098' 005 01/20/98 Environmental 4 1.68E-16 2.09E-17 AS012798 009 01/27/98 Environmental 4 1.27E-15 1.80E-16 AS020398 005 02/03/98

Environmental 4 1.27E-15 1.58E-16 I

AS021198 006 02/11/98 Environmental 4 1.03E-15 1.10E-16 AS021798 005 02/17/98 Environmental 4 7.77E-16 1.41E-16 AS022498 005 02/24/98 Environmental 4 7.32E-16 1.04E-16

. AS031098 005 03/10/98 Environmental 4 6.92E-16 9.15E-17

- AS031798 004 03/17/98 Environmental 4 1.03E-15 1.27E-16 AS032498 021 03/24/98 Environmental 4 6.39E-16 1.26E-16 AS033198 015 03/31/98 Environmental 4 7.51E-16 1.34E-16 AS040798 012 04/07/98 Environmental 4 8.13E-16 1.61E-16

. AS041498 009 04/14/98 Environmental 4 6.23E-16 1.78E-16

. AS042198 013 04/21/98 Environmental 4 8.61E-16 1.97E-16 AS042898 005-04/28/98 Environmental 4 ~

1.14E-15 2.49E-16 '

)

AS050598 010 05/05/98 Environmental 4 4.90E-16 2.36E-16 AS051298 013 05/12/98 Environmental 4 6.34E-16 1.75E-16 AS051998 006 05/19/98 Environmental 4 1.27E-15 2.90E-16

'.AS052698 005 05/26/98 Environmental 4 1.27E-15 1.46E-16 l

AS060298 010 06/02/98 Environmental 4 8.93E-16 1.66E-16 AS060998 006 06/09/98 Environmental 4 6.94E-16 1.87E-16 AS061698 009 06/16/98 Environmental 4 5.86E-16 1.50E-16 As062398 006 06/23/98 Environmental 4 6.53E-16 2.37E-16 AS070798 005 07/07/98-Environmental 4 1.35E-15 2.30E-16

'AS071498 005 07/14/98 Environmental 4 6.59E-16 2.71E-16 AS072398 005 07/22/98 Environmental 4 1.07E-15 1.95E-16 AS072898 006 07/28/98 Environmental 4 1.42E-15 2.33E-16

' AS080498 005.

08/03/98 Environmental 4 1.33E-15 2.59E-16 AS082598 005 08/25/98 Environmental 4 8.35E-16 2.94E-16

~

ASO90198 005 09/01/98 Environmental 4 9.60E-16 2.84E-16 ASO90898 -

005 09/08/98 Environmental 4 1.45E-15 2.38E-16 j

ASO91598 006 09/15/98 Environmental 4 1.00E-15 2.71E-16

. ASO92298 004 09/22/98 Environmental 4 1.11E-15 1.71E-16 ASO92998 005 09/29/98

. Environmental 4 1.10E-15 1.77E-16

- AS100698.

005 10/06/98 Environmental 4 8.19E-16 2.26E-16 1AS101398:

005 10/13/98-Environmental 4 :

7.84E-16 1.%E-16 AS102098 005 10/20/98 Environmental 4 9.69E-16 2.01E-16

- AS102798 005 10/27/98 Environmental 4 1.39E-15 1.52E AS110398 '

005 11/03/98 Environmental 4-1.23E-15 2.65E-16 i

Attachment D2 Page 6 of 15 t.,

Environmental Radiological Data

. Air Sample ID Air Sample End Date Person or Place Activity MDA Number pCi/cc pCi/cc AS111098 005' 11/10/98 Environmental 4 1.33E-15 1.86E-16 AS111798 005 11/17/98 Environmental 4 1.48E-15 1.62E-16 ASI12498-005 11/24/98 Environmental 4 1.23E-15 1.97E-16 AS120298 -

005 12/02/98 Enviromnental 4 1.46E 1.99E-16 AS122398 004 12/23/98 Environmental 4 1.36E-15 1.78E-16 AS122998 005 12/29/98 Environmental 4 1.54E-15 1.%E-16 AS010599 005 01/05/99 Environmental 4 1.33E-15 2.03E-16 AS010698 005 01/06/98 Environmental 5 8.76E-16 2.03E-16 AS0ll398 006 01/13/98 Environmental 5 1.99E-15 1.56E-16

- AS012098 006 01/20/98 Environmental 5-1.71E-15 2.18E-16 AS012798 010 01/27/98 Environmental 5 2.42E-15 2.04E-16 AS020398 006 02/03/98 Environmental 5 1.93E-15 1.79E-16 AS021198 007 02/11/98 Environmental 5 1.63E-15 1.18E-16 AS021798 006 02/17/98 Environmental 5 1.42E-15 1.49E-16 AS022498 006 02/24/98 Environmental 5 1.60E-15 1.53E-16 AS030198 004 03/01/98 Environmental 5 1.26E-15 2.09E-16 AS031098 006 03/10/98 Environmer.tal 5 8.40E-16 9.15E-17 A5031798 005 03/17/98 Environmental 5 1.59E-15 1.33E-16 AS032498 022 03/24/98 Environmental 5 1.06E-15 1.37E-16 AS033198 016' 03/31/98 Environmental 5 9.20E-16 1.47E-16 AS040798 013 04/07/98 Environmental 5 1.63E-15 2.13E-16 AS041498 010 04/14/98 Environmental 5 1.34E-15 1.62E-16 AS042198 014 04/21/98 Environmental 5 1.44E-15 1.70E-16 AS042898 006 04/28/98 Environmental 5 1.66E-15 2.37E-16 AS050598 011 05/05/98 Environmental 5 8.76E-16 2.21E-16 AS051298 014 05/12/98 Environmental 5 1.04E-15 1.79E-16 AS051998 007 05/19/98 Environmental 5 -

2.04E-15 3.09E-16 AS052698 006 05/26/98 Environmental 5 1.49E-15 1.46E-16 AS060298 011 06/02/98 Environmental 5 1.31E-15 1.70E-16 AS060998 007 06/09/98 Environmental 5 1.04E-15 1.%E-16 AS061698 010 06/16/98 Environmental 5 8.05E-16 2.21E-16 AS062398 007 06/23/98 Environmental 5 7.98E-16 2.38E-16 AS070198 005 07/01/98 Environmental 5 3.86E-16 1.94E-16 AS070798 006 07/07/98 Environmental 5 1.42E-15 2.18E-16

)

AS071498 006 07/14/98 Environmental 5 1.39E-15 2.84E-16 d

AS072398 006 07/22/98 Environmental 5 1.30E-15 1.77E-16 AS072898 007 07/28/98 Environmental 5 1.53E-17 3.26E-18 As080498 006 08/04/98 Environmental 5 1.45E-15 2.11E-16 AS081198 005 08/11/98 Environmental 5 1.81E-15 2.05E-16 AS081898 004 08/l8/98-Environmental 5 1.59E-15 2.65E-16 AS082598 006 08/25/98 Environmental 5 1.60E-15 2.80E-16 AS090198 006 09/01/98 Environmental 5 1.54E-15 2.84E-16 ASO90898 006 09/08/98 Environmental 5 2.31E-15 2.32E-16 AS091598 -

007 09/15/98 Environmental 5 1.47E-15 2.34E-16 AS100698 006 10/06/98 Environmental 5 6.91E-16 2.48E-16 AS101398 006 10/13/98 Environmental 5 1.09E-15 2.07E-16 AS102098 006 10/20/98 Environmental 5 1.28E-15 1.91E-16 Attachment D2 Page 7 of 15

Environmental Radiological Data Air Sample ID Air Sample End Date Person or Place Activity MDA Number pCi/cc pCi/cc AS102798 006 10/27/98 Environmental 5 1.54E-15 1.45E-16

. AS110398 006 11/03/98 Environmental 5 1.05E-15 2.79E-16 AS111098 006 11/10/98 Environmental 5 1.46E-15 1.86E-16 AS111798 006 11/17/98 Environmental 5 1.85E-15 1.71E-16 AS112498 -

006 11/24/98 Environmental 5 1.83E-15 1.86E-16 AS120298 006 12/02/98 Environmental 5 1.81E-15 2.00E-16

~ AS120898 005 12/08/98 Environmental 5 1.04E-15 2.01 E-16 AS121598

-006 12/15/98 Environmental 5 1.58E-15 2.46E-16 AS122398 005 12/23/98 Environmental 5 1.78E-15 1.78E-16 AS122998 006 12/29/98 Environmental 5 2.38E-15 2.05E-16 AS010599 006 01/05/99 Environmental 5 2.10E-15 2.43E-16 1997 data Air Sample ID Air Sample - End Date Person or Place Activity MDA Number Ci/cc pCi/cc AS010797 001 1/7/97 Environmental 1 1.21E-15 1.76E-16 AS011497 004 1/14/97 Environmental 1 2.17E-15 1.41E-16

'AS012197 001 1/21/97 Environmental 1 1.70E-15 1.85E-16

~ AS012897 005 1/28/97 Environmental 1 1.28E-15 1.76E-16 j

AS020497 003 2/4/97 Environmental 1 1.17E-15 1.38E-16 AS021297

'001-2/12/97 Environmental 1 1.23E-15 1.27E-16 AS021897 001 2/18/97 Environmental 1 1.09E-15 2.19E-16 AS022597 001 2/25/97

' Environmental 1 7.97E-16 1.43E-16 AS030497 002 3/4/97 Environmental 1 6.%E-16 2.33E-16 AS031197.

001 3/11/97 Environmental 1 5.63E-16 2.58E-16 AS031897 002 3/18/97 Environmental 1-9.76E 1.46E-16 AS032597 004 3/25/97 Environmental 1 1.07E-15 1.60E-16 AS040197 002 4/1/97-Environmental 1 7.53E-16 1.66E-16 AS040897 001 4/8/97 Environmental 1 7.70E-16 1.57E-16

' AS041597 003 4/15/97 Environmental 1 1.04E-15 2.42E-16 AS042297 001 4/22/97 Environmental 1 9.72E-16 1.49E-16 AS042997 002 4/29/97 Environmental 1 1.03E-15 1.88E-16 AS050697 003 5/6/97 Environmental 1 1.58E-15 1.78E-16 AS051497 001-5/14/97 Environmental 1 8.17E-16 1.53E 4 AS052097.

004 5/20/97 Environmental 1 8.59E-16 2.21 E-16 AS052797 002 5/27/97 Environmental 1 9.94E-16 2.05E-16 AS060397 005 6/3/97 Environmental 1 9.42E-16 1.71E-16

' AS061097 001 6/10/97 Environmental 1 1.03E-15 1.45E-16 AS061797 004 6/17/97 Environmental 1 8.46E-16 1.94E-16 AS062497 '

004 6/24/97 Environmental 1 1.04E-15 2.14E-16 AS070197 003 7/1/97 Environmental 1 1.21E-15 2.06E-16 i

AS070897 002 7/8/97 Environmental 1 9.91E-16 1.69E-16 AS071597 005' 7/15/97 Environmental 1 1.39E-15 1.98E-16 AS072297 002 7/22/97 Environmental 1 2.14E-15 3.45E-16 AS072897 006 7/28/97 Environmental 1 1.59E-15 2.61E-16 Attachment D2 Page 8 of 15

Environmental Radiological Data Air Sample ID Air Sample Erxl Date Person or Place Activity MDA Number pCi/cc pCi/cc AS080597 001 8/5/97 Er.vironmental 1 1.70E-15 1.35E-16 AS081297 001 8/12/97 Environmental 1 1.18E-15 2.21E-16 AS081997 001 8/19/97 Environmental 1 9.72E-16 2.74E-16 AS082697 005 8/26/97 Environmental 1 1.51E-15 2.90E-16 AS090397 002 9/3/97 Environmental 1 1.60E-15 1.90E-16 AS090997 003' 9/9/97 Environmental 1 1.61E-15 2.89E-16 AS091697 006 9/9/97 Environmental 1 1.84E-15 2.13E-16 AS092397 001 9/23/97 Environmental 1 1.49E-15 2.48E-16 ASO93097 006 9/30/97 Environmental 1 8.13E-16 2.00E-16 AS100797 001 10/7/97 Environmental 1 1.91E-15 1.40E-16 AS101497 004 10/14/97

~ Environmental 1 1.26E-15 1.70E-16 AS102197 002 10/21/97-Environmental 1 1.99E-15 2.04E-16 AS102897 001 10/28/97 Environmental 1 1.82E-15 1.89E-16 AS110497 005 11/4/97 Environmental 1 9.80E-16 1.98E-16 as111197 002 11/11/97 Environmental 1 1.87E-15 1.88E-16 AS111897 001 11/18/97 Environmental 1 1.34E-15 1.41E-16 ASil2597 002 11/25/97 Environmental 1 2.04E-15 2.13E-16 AS120297 001 12/2/97 Environmental 1 1.72E-15 1.75E-16 AS120997 004 12/9/97 Environmental 1 1.18E-15 1.76E-16 AS121697 001 12/16/97 Environmental 1 1.70E-15 1.64E-16 AS123097 002 12/30/97 Environmental 1 1.40E-15 1.02E-16 AS010797 002 1/7/97 Environmental 2 1.21E-15 1.76E-16 AS011497 002 1/14/97 Environmental 2 2.17E-15 1.49E-16 AS012197 002 1/21/97 Environmental 2 1.53E-15 1.70E-16 AS012897 006 1/28/97 Environmental 2 1.28E-15 1.76E-16 AS020497 004 2/4/97 Environmental 2 8.54E-16 1.45E-16 AS021297 002 2/12/97 Environmental 2 1.11E-15 1.21E-16 AS021897 002 2/18/97 Environmental 2 1.13E-15 2.04E-16 AS022597-002 2/25/97 Environmental 2 8.5SE-16 1.43E-16 AS030497 003 3/4/97 Environmental 2 5.83E-16 2.33E-16 AS031197 002 3/11/97 Environmental 2 6.16E-16 2.58E-16 AS031897 003 3/18/97 Environmental 2 1.14E-15 1.83E-16 AS032'97 005 3/25/97 Environmental 2 9.63E-16 1.45E-16 AS040197 003 4/1/97 Environmental 2 7.45E-16 1.50E-16 AS040897.

002 4/8/97 Environmental 2 1.11E-15 1.73E-16 AS041597 004 4/15/97 Environmental 2 9.75E-16 1.75E-16

- AS042297 002 4/22/97 Environmental 2 1.36E-15 1.85E-16

. AS042997 003 4/29/97 Environmental 2 1.05E-15 2.17E-16 AS050697 004 5/6/97 Environmental 1.81E-15 1.78E-16 AS051497 002 5/14/97 Environmental 2 1.04E-15 1.65E-16 AS052097 005 5/20/97 Environmental 2 9.53E-16.

2.21E-16 AS052797 003 5/27/97 Environmental 2 8.13E-16 1.92E-16 AS060397 006 6/3/97 Environmental 2 9.91E-16 1.73E-16 AS061097 002 6/10/97 Environmental 2 8.51E-16 1.52E-16 AS061797 005 6/17/97 Environmental 2 9.63E-16 1.85E-16 AS062497 005 6/24/97 Environmental 2 9.70E-16 2.36E-16 AS070197 004 7/1/97 Environmental 2 1.23E-15 2.21E-16 Attachment D2 Page 9 of 15 tz

Environmental Radiological Data

. Air Sample ID - Air Sample

. End Date Person or Place Activity MDA Number pCi/cc pCi/cc

- AS070897 003 7/8/97 Environmental 2 9.17E-16 1.63E-16 AS071597.'

006 7/15/97 Environmental 2 1.09E-15 1.89E-16 AS072297.

003 7/22/97 Environmental 2 1.55E-15 3.06E-16 AS072897 007 7/28/97 Environmental 2 1.19E-15 2.61E-16 AS080597 002 8/5/97 Environmental 2 1.08E-15 1.35E-16 AS081297 002 8/12/97 Environmental 2 1.11E-15 2.21E-16 AS081997 002 8/19/97 Environmental 2 6.28E-16 2.74E-16 AS082697-006 8/26/97 Environmental 2 1.24E-15 2.89E-16 ASO90397 003 9/3/97 Environmental 2 1.48E-15 1.68E-16 AS090997 004 9/9/97 Environmental 2 1.09E-15 2.62E-16 ASO91697 007 9/9/97 Environmental 2 1.31E-15 1.89E-16 AS092397 002 9/23/97 Environmental 2 1.16E-15 2.26E-16 ASO93097 007 9/30/97 Environmental 2 7.56E-16 2.00E-16 AS100797 002 10/7/97 Environmental 2 1.24E-15 1.30E-16 AS101497 005 10/14/97 Environmental 2 1.16E-15 1.66E-16 AS102197

'003 10/21/97 Environmental 2 1.62E-15 1.94E-16 AS102897 002 10/28/97 Environmental 2 1.41E-15 1.89E-16 AS110497 006

-11/4/97 Environmental 2 1.06E-15 2.07E-16 ASI11197 003 11/11/97 Environmental 2 1.47E-15 1.88E-16 AS111897 002 11/18/97 Environmental 2 1.61E-15 1.41E-16 AS112597 003 11/25/97 Enviromnental 2 1.81E-15 1.74E-16 AS120297 002-12/2/97 Environmental 2 1.64E-15 1.67E-16 AS120997 005-12/9/97-Environmental 2 1.29E-15 1.76E-16 AS121697 002 12/16/97 Environmental 2 '

1.83E 1.47E-16 AS123097 003 12/30/97 Environmental 2 1.30E-15 1.07E-16 AS010797 003 1/7/97 Environmental 3 1.42E 1.76E-16 AS011497-003 1/14/97 Environmental 3 2.35E-15 1.42E-16 AS012197-003 1/21/97 Environmental 3 2.09E-15 1.73E-16 AS012897-007 1/28/97 Environmental 3 1.54E-15 1.86E-16 AS020497 005 2/4/97 Environmental 3 1.39E-15 1.39E-16 AS021297 -

003.

2/12/97 Environmental 3 1.27E-15 1.27E-16 AS021897 003 2/18/97 Environmental 3 1.06E-15 2.14E-16 AS022597 -

003-2/25/97 Environmental 3 9.42E-16 1.43E-16

~ AS030497 004 3/4/97 Environmental 3 5.10E-16 2.33E-16 AS031197 003 3/11/97 Environmental 3 8.14E-16 2.58E-16.

AS031897 004 3/18/97 Environmental 3 1.05E-15 1.45E-16 AS032597 006-3/25/97 Environmental 3 1.40E-15 1.60E-16

.' AS040197 004 4/1/97 Environmental 3 1.00E-15 1.66E-16 AS040897 003 4/8/97 Environmental 3 8.71E-16 1.73E-16

' AS041597 005 4/15/97 Environmental 3 1.07E-15 1.86E-16 AS042297 003 4/22/97 Environmental 3 1.12E-15 1.88E-16 AS042997.

004-4/29/97 Environmental 3 1.33E-15 2.06E-16 AS050697 005' 5/6/97 Environmental 3 2.42E-15 1 %E-16 AS051497 003 5/14/97 Environmental 3 1.17E-15 1.68E-16

- AS052097 006-5/20/97 Environmental 3 1.20E-15 2.33E-16 AS052797 004-5/27/97 Environmental 3 8.83E-16 '

2.07E-16

' AS060397 007 6/3/97 Environmental 3 7.17E-16 1.88E-16 t

Attachment D2 ' Page 10 of 15

p Environmental Radiological Data Air Sample ID1 Air Sample End Date Person or Place Activity MDA Number pCi/cc pCi/cc AS061097 003 6/10/97 Environmental 3 1.11E-15 1.47E-16 AS061797 006 6/17/97 Environmental 3 1.01E-15 1.94E-16 AS062497 006 6/24/97 Environmental 3 1.20E-15 2.25E-16

. AS070197 005 7/1/97 Environmental 3 1.20E-15 2.20E-16 AS070897 004 7/8/97 Environmental 3 1.26E-15 1.63E-16 AS071597 007-7/15/97 Environmental 3 1.22E-15 2.00E-16 AS072297 004=

7/22/97 Environmental 3 9.55E-16 2.26E-16 AS072897 008 7/28/97 Environmental 3 1.31E-15 2.87E-16 AS080597 003 8/5/97 Environmental 3 1.48E-15 1.45E-16 AS081297 003 8/12/97 Environmental 3 1.32E-15 2.43E-16 AS081997.

003 8/19/97 Environmental 3 6.67E-16 2.74E-16 AS082697 007 8/26/97 Environmental 3 1.54E-15 2.89E-16 ASO90397.

004 9/3/97 Environmental 3 1.51E-15 1.86E-16 ASO90997 005 9/9/97 Environmental 3 1.38E-15 2.81E-16 AS091697 008 9/9/97 Environmental 3 1.38E-15 1.93E-16 ASO92397 003 9/23/97 Environmental 3 1.52E-15 2.48E-16 ASO93097 008 9/30/97 Environmental 3 9.14E-16 2.15E-16 AS100797 003 10/7/97 Environmental 3 2.18E-15 1.39E-16 AS101497 006 10/14/97 Environmental 3 1.13E-15 1.70E-16 AS102197 004 10/21/97 Environmental 3 1.07E-15 2.16E-16 AS102897 003 10/28/97 Environmental 3 1.32E-15 1.99E-16 AS110497 007 11/4/97 Environmental 3 1.24E-15 2.17E-16 as!!!!97 004.

11/11/97-Environmental 3 2.15E-15 1.98E-16 ASI11897 003 11/18/97 Environmental 3 1.72E-15 1.34E-16 AS112597 004 11/25/97 Environmental 3 2.74E-15 1.51E AS120297-003 12/2/97 Environmental 3 1.68E-15 1.75E-16 t

AS120997 006 12/9/97 Environmental 3 1.45E-15 1.76E-16 AS121697 003 12/16/97 Environmental 3 1.31E-15 1.64E-16

' AS123097 004-12/30/97 Environmental 3 1.38E-15 1.06E-16 AS042297 004 4/22/97 Environmental 4 6.32E-16 1.74E-16 AS042997 005 4/29/97 Environmental 4 9.56E-16 2.08E-16 AS050697 006 5/6/97 Environmental 4 7.71E-16 1.96E-16 AS051497 004 5/14/97 Environmental 4 7.89E-16 1.63E-16 AS052097 -

007 5/20/97 Environmental 4 7.86E-16 2.27E-16

AS052797 005 5/27/97 Environmental 4 6.19E-16 2.05E-16 AS060397 008 6/3/97 Environmental 4 6.78E-16 1.93E-16 AS061097 004 6/10/97 Environmental 4 1.00E-15 1.68E-16

)

'AS061797 007 6/17/97 Environmental 4 1.00E-15 1.94E-16

' AS062497 007 6/24/97 Environmental 4 1.21E-15 2.48E-16 AS070197-006 7/1/97 Environmental 4 8.92E-16 2.08E-16 j

AS070897

'005 7/8/97 Environmental 4 7.92E-16 1.63E-16 i

AS071597

- 008 7/15/97 -

Environmental 4 8.13E-16 2.00E AS072297:

005 7/22/97 Environmental 4 1.04E-15 2.21E-16 AS072897 009 7/28/97 Environmental 4 1.16E-15 2.75E-16 L

'AS080597 004 8/5/97 Environmental 4 6.99E-16 1.39E-16 AS081297 004 8/12/97 Environmental 4 1.21E-15 1.91E-16 i

AS081997 )

004 8/19/97 Environmental 4 7.84E-16 2.61E-16 j

1 Attachment D2 Page 11 of 15 w

l

Environmental Radiological Data Air Sample ID Air Sample End Date Person or Place Activity MDA Number pCi/cc pCi/cc AS082697 008 8/26/97 Environmental 4 7.02E-16 2.52E-16 ASO90397 005 9/3/97 Environmental 4 1.11E-15 1.87E-16 AS040997 006 9/9/97 Environmental 4 1.42E-15 1.81E-16 ASO91697 009 9/16/97 Environmental 4 9.68E-16 2.03E-16 ASO92397 004 9/23/97 Environmental 4 1.34E-15 2.48E-16 ASO93097 009 9/30/97 Environmental 4 6.56E-16 2.00E-16 AS100797 004 10/7/97 Environmental 4 1.28E-15 1.71 E-16 AS101497 007 10/14/97 Environmental 4 1.20E-15 1.70E-16 AS102197 005 10/21/97 Environmental 4 7.76E-16 2.05E-16 AS102897 004 10/28/97 Environmental 4 1.27E-15 1.%E-16 AS110497 008 11/4/97 Environmental 4 8.97E-16 2.07E-16 as111197 005 11/11/97 Environmental 4 1.36E-15 1.98E-16 ASill897 004 11/18/97 Environmental 4 1.05E-15 1.%E-16 ASI12597 005 11/25/97 Environmental 4 2.38E-15 1.58E-16 AS120297 004 12/2/97 Environmental 4 1.49E-15 1.52E-16 AS120997 007 12/9/97 Environmental 4 1.11E-15 1.60E-16 AS121697 004 12/16/97 Environmental 4 1.21 E-15 1.49E-16 AS123097 005 12/30/97 Environmental 4 8.15E-16 1.01E-16 AS121697 005 12/12/97 Environmental 5 1.93E-15 1.47E-16 AS123097 006 12/30/97 Environmental 5 1.36E-15 1.07E-16 1996 data Air Sample ID Air Sample End Date Person or Place Activity MDA Number Ci/cc pCi/cc AS0102%

002 1/2/%

Environmental 1 3.15E-15 1.81E-16 AS0108%

001 1/8/%

Environmental 1 3.65E-15 2.05E-16 AS0115%

001 1/15/%

Environmental 1 1.41E-15 1.72E-16 AS0122%

001 1/22/96 Environmental 1 1.95E-15 1.76E-16

' AS012996 001 1/29/%

Environmental 1 1.15E-15 1.75E-16 AS0205%

003 2/5/%

Environmental 1 1.76E-15 1.70E-16 AS0212%

003 2/12/%

Environmental 1 1.19E-15 1.60E-16 AS021996 001 2/19/%

Environmental 1 1.478-15 1.72E-16 AS0226%

003 2/26/%

Environmental 1 1.33E-15 1.55E-16 AS030496 001 3/4/96 Environmental 1 1.49E-15 1.38E-16 =

AS0311%

002 3/11/%

Environmental 1 1.57E-15 2.10E-16 AS031896 003 3/18/96 Environmental !

1.50E-15 1.36E-16 I

AS032596 001 3/25/96 Environmental 1 1.57E-15 1.86E-16 AS0401%

002 4/1/%

Environmental 1 1.83E-15 1.81E-16 q

AS0403%

003 4/8/%

Environmental 1 2.13E-15 1.43E-16 i

AS041596 002 4/15/%

Environmental 1 1.25E-15 2.24E-16 AS0422% -

003 4/22/%

Environmental 1 1.04E-15 1.98E-16 AS042996 002 4/29/%

Environmental 1 7.06E-16 2.19E-16 AS0506%

006 5/6/%

Environmental 1 1.53E-15 2.01E-16 i

AS0513%

001 5/13/96 Environmental 1 9.60E-16 1.62E-16

- AS052096 001 5/20/%

Environmental 1 1.09E-15 2.llE-16 Attachment D2 Page 12 of 15 j

Environmental Radiologicel Data 4

- Air Sample ID. Air Sample End Date Person or Place Activity MDA Number pCi/cc pCi/cc AS0528%

003-5/28/96 Environmental 1 9.48E-16 2.05E-16 AS0603%

003 6/3/96 Environmental 1 8.43E-16 3.59E-16 AS061096 005 6/10/%

Environmental 1 1.16E-15 2.30E-16 '

AS0617%.

001

' 6/17/%

Environmental 1 1.10E-15 2.18E-16 AS0624%

'006 6/24/%

Environmental 1 7.38E-16 2.56E-16 AS0701%

001 7/1/96

. Environmental 1 1.42E-15 2.08E-16 AS0708%

004 7/8/96 Environmental 1 1.92E-15 2.24E-16

. AS0715%

001.

7/15/%

Environmental 1 1.33E-15 2.33E-16 AS0722%

001 7/22/96 Environmental 1 3.47E-15 2.52E-16

. AS072996 001 7/29/96 Environmental 1 4.72E-15 2.26E-16 AS0805%

005 8/5/96 Environmental 1 6.55E-15 1.97E-16

. AS081296 001 8/12/%

Environmental 1 1.18E-15 2.57E-16 AS081996 -

006 8/19/%

Environmental 1 1.66E-15 2.75E-16 AS0827%

006 8/27/%

Environmental 1 1.01E-15 1.66E-16 ASO903%

006 9/3/%

Environmental 1 1.56E-15 1.98E-16 ASO90996 005 9/9/96 Environmental 1 2.74E-15 2.83E-16 ASO917%

001 9/17/%

Environmental 1 2.37E-15 2.20E-16 AS0923%

005 9/23/%

Environmental 1 1.74E-15 2.62E-16

' AS1001%

005 10/1/96 Environmental 1 4.%E-16 3.25E-16 AS1014%

003 10/14/96 Environmental 1 9.34E-16 2.64E-16 AS102296 004 10/22/ %

Environmental 1 1.68E-15 3.74E-16 AS1031%

007 10/31/96 Environmental 1 1.47E-15 4.04E-16 AS1105%

005 11/5/96 Environmental 1 1.59E-15 2.09E-16 ASI112%

001 11/12/ %

Environmental 1 1.88E-15 1.57E-16 AS111996 005 11/19/96 Environmental 1 '

2.48E-15 2.16E-16 AS112696 001' 11/26/96 Environmental 1 2.34E-15 1.64E-16 AS1203%

002 12/3/96 Environmental 1 1.76E-15 2.02E-16 AS121096 001 12/10/ %

Environmental 1 1.72E-15 2.05E-16

. AS121796 -

001 12/17/96 Environmental 1 2.27E-15 1.88E-16 AS1231%

002-12/31/96 Environmental 1 1.41E-15 8.95E-17 AS0102%

003 1/2/96 Environmental 2 2.70E-15 1.81E-16 AS010896 002 1/8/96 Environmental 2 2.83R-15 2.05E-16 AS011596 002 1/15/96 Environmental 2 1.08E-15 1.72E-16

- AS0122%

002 1/22/96 Environmental 2 1.22E-15 1.76E-16 AS012996 002 1/29/%

Environmental 2 1.37E-15 1.76E-16 AS0205%

004 2/5/%

Environmental 2 1.73E-15 1.69E-16 AS0212% -

004 2/12/%

Environmental 2 1.19E-15 1.60E-16

' AS021996 002 2/19/96 Environmental 2 1.11E-15 1.72E-16 AS022696 004

. 2/26/%

Environmental 2 9.92E-16 1.55E-16 AS0304%

002 3/4/96 Environmental 2 1.13E-15 1.23E-16 AS0311%

003' 3/11/96 Environmental 2 1.38E-15 2.00E-16 AS031896 004 3/18/96 Environmental 2 1.54E-15 1.30E-16 AS0325%

002 3/25/96 Environmental 2.

1.32E-15 1.86E-16 AS040196 003-4/1/96 Environmental 2 1.92E-15 1.81E-16 AS0408%

004 4/8/96 Environmental 2 1.71E-15 1.30E-16 AS041596 003 4/15/96 Environmental 2 1.06E-15 2.13E-16 AS042296 004-4/22/%

Environmental 2.

1.01E-15 1.88E-16 Attachment D2 Page 13 of 15

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l

Environmental Radiological Dita

' Air Sample ID Air Sample End Date Person or Place Activity MDA Number pCi/cc pCi/cc AS0325%

003 3/25/%

Environmental 3 1.56E-15 1.78E-16

. AS040196 004 4/1/%

Environmental 3 2.02E-15 1.81E-16 AS0408%

005 4/8/%

Environmental 3 2.30E-15 1.36E-16 AS0415%

004 4/15/96 Environmental 3 1.33E-15 2.04E-16 AS0422%

005 4/22/96 Environmental 3 8.38E-16 1.89E-16 AS042996 004 4/29/%

Environmental 3 9.34E-16 2.41E-16 AS0506%

008-5/6/%

Environmental 3

- 1.50E-15 2.11E-16 AS0513%

003 5/13/%

Environmental 3 7.45E-16 1.53E-16 AS052096 003 5/20/%

Environmental 3 1.09E-15 2.23E 16 AS0528%

005 5/28/%

Environmental 3 1.07E-15 2.16E-16 AS0603%

005.

6/3/%

Environmental 3 9.91E-16 3.42E-16 AS061096 007 6/10/%

Environmental 3 9.76E-16 2.30E-16 AS0617%.

003 6/17/%

Environmental 3 1.61E-15 2.18E-16 AS0624%

008 6/24/%

Environmental 3 1.10E-15 2.56E-16 AS0701%

003 7/1/%

Environmental 3 1.34E-15 1.98E-16 AS0708%

006 7/8/%

Environmental 3 1.39E-15 2.04E-16 AS0715%

003 7/15/%

Environmental 3 1.36E-15 2.33E-16 AS0722%

003 7/22/96 Environmental 3 2.05E-15 2.25E-16 AS072996 003 7/29/96 Environmental 3 7.93E-15 2.25E-16 AS0805%

007 8/5/%

Environmental 3 6.52E-15 1.87E-16 AS0812%

003 8/12/96 Environmental 3 1.37E-15 2.57E-16 AS081996 008 8/19/%

Environmental 3 1.77E-15 2.62E-16 AS0827%

008 8/27/%

Environmental 3 1.40E-15 1.66E-16 ASO903%

008 9/3/% -

Environmental 3 1.50E-15 1.88E-16 ASO90996 007 9/9/%

Environmental 3 2.61E-15 2.56E-16

. AS0917%

003 9/17/96 Environmental 3 2.86E-15 2.09E-16 ASO923%

007 9/23/%

Environmental 3 2.36E-15 2.62E-16 AS1001%

007 10/1/%

Environmental 3 2.13E-15 1.65E-16 AS1008%

003 10/8/%

Environmental 3 3.10E-15 1.99E-16 AS1014%

005 10/14/96 Environmental 3 2.45E-15 2.36E-16 AS1022%

006 10/22/ %

Environmental 3

.1.52E-15 1.97E-16 AS1031%

009 10/31/ %

Environmental 3 1.70E-15 2.00E-16 AS1105%

007 11/5/%

Environmental 3 1.89E-15 2.09E-16 ASI112%

003 11/12/96 Environmental 3 1.81E-15 1.72E-16

. AS111996 007 11/19/ %

Environmental 3 2.39E-15 1.92E-16 ASI126%

003 11/26/ %

Environmental 3 2.27E-15 1.65E-16 AS1203%

004 12/3/96 Environmental 3 1.71E-15 1.95E-16 AS121096 003 12/10/ %

Environmental 3 2.02E-15 2.13E-16 AS1217%

003 12/17/96 Environmental 3 2.88E-15 1.97E-16 AS1231%

004 12/31/96 Environmental 3 1.78E-15 8.94E-17

(

i Attachment D2 Page 15 of 15

Envirofunental Radiological Data Attachment D3 Environmental thermolumineescent dosimeter data for 1996 through 1998.

(3 pages) i

)

Attaciunent D3 Page 1 of 3

I Environmental Radiological Data The Kerr-McGee Corporation monitors the Cushing site with Thermoluminescent dosimetry. There were 38 locations onsite for the years 1996 through 1998. The dosimeters were placed on the boundaries of the Radioactive Materials Areas, in site buildings and offices for environmental monitoring, and various other locations onsite to collect additional information. Of the 38 locations,29 dosimeters were used to measure deep dose at the 16 RMA boundaries and 3 of the environmental air sampling locations.

The first quarter of 1996 included some measurements taken inside the RMAs. TLD numbers for these dosimeters are as follows:

AM022 AM023 I

AM026 AM027 AM028 AM029 AM032 AM033 The current locations for these dosimeters are shown in the data. During the first quarter of 1997, the dosimeter at environmental air sampler 001 (AM007) was involved in a piping radiography at the NGC Tank Farm. The measurements from these dosimeters are not included in the summary below, but are included in the data following the summary. There was no result from dosimeter AM034 for the first quarter of 1997.

_. Location. _

Average net mR/ week

. Average _ net mR/ year _ _

._ _ _ _._ _27 RMA boundary monitors and environmental air 1 29 67'10 sample.locatipns 001, 002 and_003_ _._. _ _ _

_ i.

1.

Note: The values in the table above are net (gross reading minus mail control dosimeter reading) mR/ week and year, and are not adjusted for exposure from natural sources.

f Data:

TLD Location Block East South % 2nd 3rd 4th 97 2nd 3rd 4th 98 2nd 3rd 4th

average Bld A 9 Front o'fficc area ~~

1st ist 1st mR/wk

~

g I.10 1.23!0.90'0.92 1.01 0.99 0.71 2.51 0.59 1.16'0.93 1.51 1.13 4

40

-10 0.97 i l.69 ) l.35 l 1.32 ! !.32 ! !.161.22 l 3.14 l 0.91 ! 1.28 1.40 2.50 1.52 AM002 {RMA-ll North fence AM003 RMA-Il East fence l4 0, 50 '0.93ll.50l1.11l1.22 1.36 l 1.05,1.33 l 2.73 l 0.86 l 1.161.40 1.98 1.39 l 0.86 1.49 ' l.26 ' 1.13 1.25 { l.01 l 1.0812.83 j 0.80 l 1.211.54 l 2.02 1.37 AM004 RMA-1 South fence l5 95 : 45 AM005 RMA-3 North fence

! 11 80 0 i0.83 1.48 1.11 1.03 1.37 l 1.25 l 1.47 2.42 i 0.76 i 1.35 1.33!2.57 1.41 AM006 RMA-8 South fence f 82 95 40 '0.63 1.35,0.90 1.07 1.20 l 0.99 ' t.392.10 1.36II.13 0.99 f 2.00 1.26 AM007 Env. Air Sampler 001 l 77 10 ' 80 l 0.70 1.08 0.80 0.93 E l.99 0.80 j 2.24 0.88 1.04 0.68I2.18 1.21 0.73 f l.95 AM008 RMA-10 North fence l102'10 30 0.79 1.18 l 0.90 : 0.91 l 1.08 ; 0.90 1.36 I 2.47 1.00 1.11 1.20 AM009 'RMA-13 North fence

!129 60 70 l1.15 1.20 { 0.98 l 1.15 1.11 f 1.02 l 1.00 f 3.10 0.89,1.29 0.93 l 1,91 1.31

! 2.00 1.27 { l.10 l 1.17 l 1.21 1.14 ' O.92 2.60 0.94 l 1.11 j 0.72 ! 1.89 1.34 AM010 RMA-12 West fence 69 0

32

{0.921.27 0.94 l 1.06 j 1.25 2.82 1.04 l 1.110.76 l 1.30 AM011 {RMA-10 West fence 1.18 1.02 0.72 101 40 70 AM012 lEnv. Air Sampler 003 165 90 l 60 ' O.68 1.16 0.66 ) 0.62 { 0.93,0.85 j 0.65 1.85 0.22 l 0.97 1.45 1.81 0.99 i

Attachment D3 Page 2 of 3 i

L J

Environmental Radiological Data TLD location Block East South % 2nd 3rd 4th 97 2nd 3rd 4th 98 2nd 3rd 4th

average

- 1st.

. 1st 1st mR/wk

!95l30 l1.05!1.47 1.07 j l.30 l 1.32 f l.41 ; 1.50 3.14 j 0.81 AM014 RMA-4 South fence 39 1.35 1.74 2.16 1.53 l 0.78 1.25 ! 1.14 ! 0.91 l 1.17 1.18 l 0.95 l 3.24 0.86,1.28 1.14 1.82 AM015 S A En&dge room

~

1.31 w,

AM016 jB AW M sd O.75 f 1.11 0.90 0.941.11 0.84 0.66 3.51 ' 0.69 l 1.28 0.44 1.76 1.17 AM017 -Bldg A-9 office west wall l

}0.86j1.37;1.16f1.17 0.81 2.93 ! 0.93 l 1.28 i 0.70 1.57 1.24 2.03 1.34 AM018 Trailer 'A' middle room l l

0.61 l 0.9910.77 i 0.65 0.98 0.79 0.38 2.58;0.37 1.00!0.22 1.60 0.91

! !.83 l1.48 l l.06 l 1.14 AM019 RMA-12 North fence I $7 5 i 50 0.90 2/18f 0.72 1.14 l 0.621,61 1.27 1.37 1.19 AM020 Bldg 73 north wall -

l

{ 0.56 i 0.86 l 0.49 j 0.63 0.97 0.55 0.22 ! 2.03 ; 0.37 0.76 l 1.14 1.95 0.88 i

i (0.79 1.09 0.80'l.20 1.13 0.93 0.68 1.63 i 1.89 l 1.03 ! 1.30 1.86 1.19 AM021 Bldg A-9 North fence 1.26 l 0.59 AM022 RMA-2 South fence 30 75, 70 1.39,1.09 1.16 1.12 1.38 0.88 2.33 0.88 2.30 1.31 0 1 70 1,28 ! 1.14 j 1.17 l 1.28 1.40 0.93 1.85 0.67 1.13 1,69 1.95 1.32 AM023 {RMA-4 North fence 28 r 0

'0.87 1.32l 1.15 1,44 2.25 1.23.

10 !0.88 1.32 l 1.14 ! 1.17 ' l.11 1.23 0.89 a 1.59,0.64 AM024 lRMA-2 North fence

!7 50 1.02 f 1.21 1.16 l 1.050.86 2.00 f 0.81 I

AM025 {RMA-5 East fencel42 65 1.07 1.82 2.28 1.29 1

AM026 ;RMA-6 West fence l 64 80 32 FT1.411.25l1.241.31l1.0l!!.02 2.1010.90 1.34 1.79 2.70 1.46

[ ? 1.29 ; 1.40 f 1.13 1.29 l 1.35 0.98 2.34 l 0.83 AM027 lRMA-7 North fencel 81 95 40 1.64 1.46 2.50 1.47 94 5, 40," 1.23 j l.08 i l.03 1.08 1.00 l 0.83 1.83'O.54 1.09 1.23 1.65 1.14 AM028 RMA-9 North fence j

AM029 ;RMA-8 North fence 83 10 10

~l~: 1.24i0.94'0.97 1.85 0.%l0.95 1.70 0.76 1.11 1.28 1.33 1.19

0[79)l.19f0.92 1.24 1.41 0.21 0.90 2.36 0.57 1.05 1.27 1.60 1.13 AM030 RMA-7 5outh fence 81 ' 95, 80 90l70 {0.78 1.37 l 0.921.10 1.29 1.11 0.91 2.60 0.55, 1.33 1.41 1.98 1.28 AM031 RMA-9 South fence i 93 AM032.Env. Air Sampler 002 12l80j.23 lS.77 1.13 l 0.77 1.02 1.39 0.86 0.62 2.13 0.61 0.92 1.11 1,55 1.10 AM033 f RMA-2 South fence 21 40 i 40 l 6.88 1.35 l 0.97 1.04 1.57 0.% 0.80 2.21 0.77 1.19 1.57 2.03 1.31 AM034 l Bid A-9 Rad storage south i

!1.25l1.11 1.03 1.59 2.76 2.56 4.15 0.71 1.62i1.63 1.79 1.84 I.82 l 1.270.89 l 1.13 AM035 RMA-6 West fence 76 i 90 l 20 0

1.68 1.12 0.84 2.33- 0.76 1.31 1.33 1.98 1.29 AM036 Trailer "B" North wall l

0.58 l 0.84 0.53 l 0.54 1.05 0.64 0.40 1.50 0.19 0.98 0.98 1,41 0.80 AM037 RMA-5 North fence 17 l70l70 0.86 l 1.140.89 l0.871.62 1.05 0.79 2.19 0.69 1.34 1.26 1.60 1.19 AM038 lRMA-3 North fence l 10 5}O l 1.02 l 1.30 1.31 l 0.931.86 1.50 0.48 1.80 0.67 1.40 1.45 2.18 1.33 Note:

Average values include light shaded values, but dark shaded values are omitted from the average as (lescribed in the text.

J l

Attachment D3 Page 3 of 3 l

I j

1 r-r n-Responses to Request for Additional Information KMC Cushing Site Decommission' g Plan.

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Responses to Request for Additional Information KMC Cushing Site Decommissioning Plan l

l Attachment F Revisions to Section 3 Cushing Site Decommissioning Plan Attachment F includes revisions of:

1.

Section 2.4.6.1 2.

Section 3.2.2.4 3.

Section 3.2.2.5 4.

Section 3.3.3.1 -

l 5.

- A portion of Section 3.3.9 j

l 6.

Section 3.5 i

7.

Figure 3.5 8.

Figure 4.1 These pages should replace the equivalent pages in the August 17,1998 submittal.

' In addition, Attaciunent F includes the following new figures:

j 1.

Figure 3.5A l

2.

Figure 3.5B

/

3.

Figure 3.5C These pages should be added to the August 17,1998 submittal following the revised Figure 3.5.

)

i i

j

nov, t August.1ees i

Isotopic ratios were calculated using the 1990 and 1994 groundwater analytical

h..

data for U2" and U*. None of the U*: U2" ratios calculated from existing analytical data exceeded 4.4 and therefore do not likely indicate the presence of licensed materials (Grant Environmental,1996).

Th: rrrn' :t!:n: M Th" :nd '30"' chruM be cert; 0;2:! in n:tur:! : !'

' Mr;;::::, d";:::::: 5 i; r!d!!T:: Of 5 r t;; nur!!d:: Oh00!d y!:'d ft: ; ::' :

n'- M ::d! r != Se ; end ;;t : tS:n $0:!cm Typ!- "y, $5 d!"crene: !: en 5:

d:: Of 1^^ t: 1,^^^ tin ;==:0 : d!cm 5:n Scrium (ME",1^*5). M:::::::, $0:

- ;:2 d 'g::und:::t;: & =l:':; ::n :":~' 2: ::!:'! : r!2itt; d thr:

eslienwelisles:

Existing site data show that thorium exceeds radium in samples from several locations, including presumed background locations. There is no consistent pattern between concentrations and ratios of radionuclides and proximity to RMAs, refinery wastes or unimpacted areas.

The data suggest that the natural variability of radionuclides in soil and their relative leaching characteristics may be responsible for observed concentration differences in groundwater rather than leaching from licensed material.

2.4.6.2 Well Location Trends The groundwater data was also examined to determine if typical concentrations can be established for radionuclides in background wells or for other wells, based on their proximity to RMAs. It might be expected that radionuclide concentrations in the groundwater in background wells would be lower than radionuclide concentrations in wells within or down-gradient from RMAs. However, no such general relationship was identified.

2.4.6.3 Particle Size Effects The material outside the well. screen (e.g. permeable material, such as sandstone or limestone, or less permeable material, such as mudstone) also appears to influence the concentration of radionuclides in the groundwater. Wells screened in fine grained materials (e.g. mudstone) appear to have slightly higher radionuclide concentrations.

This suggests an association between natural radionuclide concentration and fine-grained material.

Water in low permeability materials stay in contact with the formation longer than water in more permeable materials. The longer contact time between groundwater and radionuclides in the soil or rock matrix in low permeability materials could contribute to increased leaching of radionuclides.

Water samples from wells completed in fine-grained soil are more prone to c

contamination by fine suspended soil particles. The presence of even a small amount CusNne Site r- _ _. -

g Plan Site information: 2-20 L..

o Rev.1 August,1998 Concentration limits for thorium and natural uranium wastes containing fewer O

daughters than at secular equilibrium may be calculated on a case-by-case basis using isotopic data that are applicable when appropriate.

3.2.2.3' Apolication of Radioactivity Limits to Measurement Area Average Radioactivdy Stated radioactivity limits are for average values, above background, e

applicable to affected areas:

100 m2 area for' soil radioactivity, 100 m area for exposure rate on open land, and z

100 m2 area for paved surface radioactivity.

Area-weiahted Radioactivity J. ' The average radioactivity concentration in soil must be < (100/A)t/2 times the stated limit, where A is the area of elevated radioactivity in m2. The maximum area for which this applies is 100 m2,

. Surface radioactivity on a paved surface out-of-doors that is between one h

and three times the stated limit is acceptable provided the area-weighted average radioactivity within a 100 m2 area containing the elevated activity is less than the stated limit.

Maximum Radioactivity The maximum radioactivity in soil at any location may not exceed three times the stated limit above background.

. The maximum exposure rate at any location indoors or out-of-doors may not exceed two times the stated limit above background.

3.2.2 A Apolication of Radioactivity Limits'to Subsurface Material KMC will characterize and may remove material from subsurface burials where measurements from surficial materials may or may not indicate a' need for removal.

KMC will calculate the average volumetric activity of subsurface material and apply multiples of the limits'in accordance with' guidance provided by NRC in the paper Volumetric Averaging of Thorium Contaminated Subsurface Soils, (NRC 1995),

i DC:II"/,DO0707200CI!7'f d VO!CZ : Ih:$ Z:::I 2T OCI!O CC OC CCO$

I b: i:!r S.: v !r m r.;;; :D..M :Or!;t:f Y S2d!:n 3.2.2.2. The :v:.:;: ediv' /t d :ny l7h

Czer 1T rt!: mi;r

!r= nr:t 5: !r:: th:n 1.3 !!-. O th: ltM ' !n:!!y, the Cushing See Dooommissionm0 Plan Descriptum of Planned Decommiseloning Activites ; 3-3 g

l

}

Rev.1 August, toes 1

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3.2.3 CRITERIA FOR BUILDINGS i

The following are criteria for unrestricted release of decommissioned buildings (Austin,1992; NRC,1992a; NRC,1992c).

3.2.3.1 Exoosure Rate Limit The gamma exposure rate cannot exceed 5 pR/hr above background at 1 meter J

above the floor or building surface (NRC,1981). The average and maximum radiation I

i Cushing Site Decommissioning Plan Descnphon of Planned Decommissioning ActMties : 34 L -

Rev.1 August,1996 and shipped to a licensed disposal site in 1992.

Additional characterization and h

decommissioning will be necessary at this location.

3.3.3.1 Trash Dumo Decommissionina Contaminated material will be removed to comply with the Criteria. KMC will use the following general procedures to remove contaminated soil and debris.

1.

Soll borings will be drilled on a 5 x 5 meter grid. - Samples will be collected at 0.5 meter intervals and will be analyzed in the on site gamma spectrum analyzer.

2.

Material that does not exceed criteria stipulated in Section 3.2.2.4 will either be left in' place or stored temporarily within the RMA. This material will either be used as fill dirt to help contour the area or be disposed of as Other Industrial Waste.

3.

Material that exceeds criteria stipulated in Section 3.2.2.4 will be excavated and placed in the RMSA for subsequent packaging and shipping, or will be packaged and shipped directly from the RMA.

4.

A final survey will be conducted as described in Section 6.

5.

- KMC will notify NRC. prior to backfilling excavated areas, so NRC can

. i arrange a confirmatory survey if needed.

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01 Cushing Site Decommissioning Plan Descnption of Planned Decommissioning Activities : 316

i Rev.1 August.1998 for representative measurement of volumetric radioactivity. In that circumstance, the crushed rubble would be sampled and analyzed for its radioactivity concentration.

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..rr 3.3.10 NORM Elevated concentrations of Naturally Occurring Radioactive Material (NORM)

O have 8een osserved oneite. NORu wiii oe coiiected and hendied in accordance w>th

. State requirements.

3.3.11 ESTIMATED VOLUME Actual volumes of material exceeding the Criteria are not known at this time.

However, KMC anticipates that the volumes will approach those listed in Table 3.4.

1 TABLE 3.4 ESTIMATED VOLUME OF CONTAMINATED SOIL AND DEBRIS -

Avg. Thorium'88 Avg. Uranium Location Material Volume (yd3)

Concentration (pCilg)

RMA-3

- 10,000 20 Low RMAs-2, 5,and 8 2000 15 Low RMA-11 2000 30 160 RMA-10 Buildings 100 30 160 RMA-10 Soils 450 30 160 Small RMAs 20 20 Low O

l Cushing Sne Decommissioning Plan Description of Planned Decommissioning Activities : 3-25 j

Riv.1a June 4.1999 not t release criteria will be' temporarily stored pending treatment or increased

{'

settlement time.-

A similar retention pond will be constructed ~near Pit 4 to contain stormwater collected during Pit 4 remediation activities. The same controls, water sampling and analysis, and release procedures implemented for the RMSA will be implemented for

the Pit 4'stormwater' retention pond. Water meeting the discharge criteria will be

' compared with limits in 10 CFR 20, Appendix B Table 2. Water meeting the discharge criteria will be released via a discharge pipe to Skull Creek. Water that does not meet release criteria will be temporarily stored pending treatment or increased settlement -

time. The discharge of stormwater from a RMSA or stormwater retention pond will be subject to ALARA goals. In this case any discharge of radionuclides in excess of 20%

of the Appendix B Table 2 limit will be investigated and the need for corrective measures evaluated.

3.5 GROUNDWATER INVESTIGATION j

Evaluation of potential radioactive _ groundwater. contamination is important to KMC. cleanup efforts.

Preliminary groundwater investigations were performed to develop the " Phase I Remedial Investigation Report" (Burns & McDonnell,1991). The j

groundwater investigation proposed herein supplements previous work around potential J

O sources o< <aoioactive contaminatiea.

3.5.1 OBJECTIVES The _ objectives of this investigation are:

. to determine the range of background concentrations of natural radionuclides in groundwater,

. to establish groundwater monitoring systems where licensed materials may contaminate groundwater, and e.to evaluate the potential migration of radionuclides by sampling soil and/or groundwater, as necessary, at selected RMAs.-

>These primary objectives will be achieved through the following tasks:

establish background water-quality monitoring points, collect and analyze groundwater samples, and evaksate background water e

quality, 0

, Cushing Site DecommissioninD Plan Description of Pienned Dooommissioning Activities : 3-29

F RIv.1a June 4,1999 install monitoring wells where needed at RMAs where potential radiological e

impact to groundwater is anticipated based on the results of soil sampling, and sample soil and/or groundwater at selected RMAs to identify subsurface radiological contamination.

The following sections identify the rationale and approach KMC proposes to use to characterize groundwater quality and achieve the above objectives. They explain the selection of sampling locations and include descriptions of data to be collected and how the data will determine the results of the investigation.

3.5.2 DETERMINING BACKGROUND RANGE IN GROUNDWATER AND SOIL Site groundwater quality reflects natural influeoces and, potentially, radiological and/or non-radiological impacts from previous site activities. To determine the impact l

of previous site activities, it is necessary to separate naturally occurring conditions from l

conditions related to site activities by comparing groundwater chemistry in up-gradient 1

or background wells with wells that are within or down-gradient from source areas.

Analytical results from down-gradient locations will be examined to differentiate radionuclides derived from licensed material from radionuclides leached from native soils.-

3.5.2.1 Backaround Groundwater Samplina An assessment of background water-quality is necessary to evaluate possible impact to groundwater. Wells located either hydraulically up-gradient or hydraulically isolated from RMAs provide background water-quality information. Wells located south of Skull Creek also provide background water-quality information, since shallow groundwater flows toward the creek and the RMAs are located north and west of the creek. Based on these characteristics, a list has been compiled of wells that could be expected to provide the necessary background water-quality for radiological analysis.

These wells are identified in Table 3.5 and shown on Figure 3.5.

Existina Samolina Locations l

l Twenty-three existing wells, listed in Table 3.5, are proposed for obtaining j.

background water-quality samples. The distribution of these wells between the different l

water-bearing zones is as follows:

)

1

(

Unconsolidated Soil / Upper Vanoss 9 Wells l

Lower Vanosa 13 Wells Vamoosa-Ada 1 Well

. Cushing Site Decommissioning Plan.

Description of Planned Decommissioning ActMtses : 3-30 L

]

m l

Rav.1a Juns 4,1999

'p.

One fall and one spring sampling of existing wells are planned during this v

investigation. These events are planned to characterize groundwater quality at high and low groundwater levels, respectively. Water-quality results from the different water-bearing. units will be examined for possible radionuclide impacts, or other indications of 3

contamination (e.g. pH, total dissolved solids, carbonate / bicarbonate, dissolved oxygen and specific conductance). If groundwater analyses provide evidenco of seasonal fluctuation in radionuclide concentrations, additional sampling will be performed.

3.5.2.'2 Backaround Soil Concentrations The developed soil layer, or "A" horizon, normally is present in undisturbed off-l site areas. In these areas the soil has been naturally leached and weathered, and

)

radionuclide and other constituent concentrations are'different than in the underlying, less weathered soil. Also, the application of fertilizers in agricultural areas will alter soil chemistry.

In on-site areas, the "A" horizon often has been disturbed (e.g. either is covered with fill, is absent because of excavation, or otherwise has been modified as a result of refinery land uses). Where the "A" horizon hca been disturbed (as is the case in most RMAs and many othy site areas), shallow soil chemistry might be different than where it has not been disturbW. Consequently, radionuclide measurements in undisturbed off-site "A" horizon surface soil might not be similar to the same measurements in-the disturbed surface soil in on-site areas.

Because of this, KMC believes that on-site, disturbed areas that were not

'affected by facility waste disposal operations, and have not been recently farmed,

provide the most representative " background" soil samples for comparison to soil from disturbed areas affected by_ facility operations. Existing soil sampling analytical data

~ was presented in the Unaffected Area Report (KMC,1995). In general, on-site surface soil, not affected by historic radioactive waste management, is present in unaffected areas. Soil concentration data from unaffected areas will be combined with soil sample data from offsite locations to determine the range of background soil concentrations _for site decommissioning.

Several samples in unaffected area 4 contained elevated conotiitrations of uranium due to the presence of naturally occurring radioactive (material. Soil concentration results from these locations will not be included in the background. determination.

3.5.3 EVALUATING SOURCES OF LICENSED MATERIALS.

For. most-potential source areas on the site, contamination is the result of intentional surface placement of radioactive materials containing thorium. Subsurface contamination may extend beneath these RMAs as a result of the leaching and j

subsequent downward transport of radionuclides by infiltrating water. However, the low -

L-Cushing Site Decommessioning Plan.

Desenption of Planned Decommissioning Actwitees : 3-31

R v.1a June 4.1999 em solubility of thorium and its tendency to sorb onto soil particles is expected to minimize

_ V the depth of penetration.

Subsurface soil sampling and analysis.will determine whether thorium impacted areas are potential sources of impact to groundwater. The netsd to collect groundwater data at specific RMAs will depend on the results of the soil analysis. If the soil analyses i

indicate that radionuclide concentrations are similar to background values or that affected soil does not extend to the water table, no groundwater sampling wi!I be performed at that location.

Also, if shallow groundwater is not present in the unconsolidated zone or upper part of the Vanoss, then the pathway to groundwater is I

not complete, and groundwater sampling is not necessary.

Intentional subsurface placement of radioactive materials containing uranium occurred at only a few RMAs. In these RMAs, some radioactive materials might have been placed near the groundwater level and uranium, a more soluble radionuclide than thorium, might be present in groundwater at the RMA. At these locations, groundwater sampling and analysis will determine whether groundwater is affected. The sampling strategy for each RMA is discussed in the following sections.

3.5.3.1 RMAs 1. 2. 4 Throuah 9. and 12 Throuah 16 (Surficial Thorium Ontv)

RMAs are the only probable sources for groundwater contamination from O

licensed materials. The investigation approach planned for RMAs 1,2,4 through 9, and 12 through 16 will examine radionuclide concentration with depth, and use the shallow soil results to evaluate the need for deeper sampling. This process avoids deeper sampling in areas with only surface or near-surface contamination.

l The process of soil sampling at RMAs 1,2,4 through 9, and 12 through 16 is illustrated on Figure 3.6. This process is divided into the following steps.

1.

Prior surveys established RMA boundaries and provide starting points for 1

this investigation. Locations yielding the highest surficial soil concentrations I

will be the starting locations for this analysis.

2.

Surface and near-surface sampling in each RMA will be done using either mechanized or hand-operated equipment. Samples will be analyzed for thorium at the on-site laboratory, 3.

If near-surface impacts above the normal range of background are confirmed, deeper samples will be obtained. If sampling beyond the depth of hand sampling is necessary, deeper samples will be obtained using mechanical equipment.

h 4.

Groundwater grab ramples will be collected if soil impact above normal V

background extends to the water table.

cushing She Decommissioning Plan Descnption of Planned Decommissioning ActMtes : 3-32 Y'

_.1

p-R2v.13 June 4,1999 5.

If groundwater grab samples indicate that radionuclides might have O-migrated to groundwater, investigation in these areas will include installation and sampling of monitoring wells.

. Within each RMA, KMC plans to obtain samples from 5-meter grid nodes where the results of previous soil sample analyses exceed Option 1 limits. A minimum of one sample location will be selected in each RMA and a minimum of two samples will be taken at each location. These will include the 0 to 6 inch and 6 to 12 inch depth intervals. The maximum number of surface locations to be sampled in a single RMA is

~

10. Wherever the RMA includes more than 10 5-meter square grids where the Option 1 limit is exceeded, the 10 grids with the highest measured activities will be selected for sampling.

3.5.3.2 RMAs 3.10. and 11 Conditions at RMA-3, RMA-10 and RMA-11 suggest the possibility that radionuclides could have migrated to the groundwater. As a result, a different approach to determine if radionuclide migration has occurred is planned for these RMAs.

RMA-3 (Pit 4)

Only thorium has been observed at concentrations exceeding proposed release O

criteria in Pit 4. The mobility of the thorium contained in materials disposed in this RMA could be increased because of the acidity of Pit 4.

KMC has identified two possible mechanisms that could make RMA-3 a source

- of radiological impact to groundwater. Thorium contaminated acidic water may migrate -

~ directly through the Pit 4 berm and emerge as surface seepage on the down-gradient side of the berm. As contaminated water moves away from the pit and mixes with unaffected materials, its pH will rise. As pH rises, thorium will sorb to surface or subsurface' soil. Soil samples will be collected down-gradient of the Pit 4 berm to evaluate the potential for thorium migration via seepage through the berm.

The area downgradient of Pit 4 will be used as a stormwater retention pond during the remediation of Pit 4. This portion of the evaluation can only be performed after Pit 4 remediation is complete.

Contaminated water could also migrate directly into the shallow groundwater below Pit 4.. KMC will install three down-gradient wells at locations indicated on Figure 3.5A. All three wells will be shallow wells, monitoring the first water-bearing interval in either the unconsolidated soil or upper Vanoss zone. Groundwater samples from these wells will' enable KMC to evaluate this mechanism as a potential source of impact to groundwater.

O

- Cushing Site Decommessioning Plan Descnphon of Planned Decommissioning Activities : 3-33

Rsv.1a Juns 4.1999 1

.< f q The sequence of sampling down-gradient of Pit 4 will be as follows:

(./

First, groundwater samples will be taken from the three down-gradient wells (CMW 44.1,45.1, and 46.1) completed in the unconsolidated soil or upper Vanoss. Results will be compared with the range of background and with samples collected from upgradient wells.

Shallow subsurface soil samples will be collected and analyzed to compare with background values. Samples will be collected every six inches from 0.5 feet deep to 2.5 feet deep. Samples will not be collected below the water table.

If soil sample analyses confirm that radionuclide concentrations are similar to background, no additional groundwater sampling will be performed.

If soil sample analyses confirm radionuclide concentrations are different from background, then additional groundwater samples might be determined to be necessary.

Such additional samples would be collected further down-gradient from Pit 4 and RMA-3.

Figure 3.7 shows a plan view of the first two sampling steps. Figure 3.8 is a schematic cross-section showing typical sample locations.

RMA-10 Both thorium and uranium are present in RMA-10.

Since uranium is more soluble and mobile than thorium and groundwater is relatively shallow in this area, uranium migration through soil to groundwater may occur. In RMA-10, the investigation will focus on groundwater quality. KMC will install two up-gradient and three down-gradient wells at locations indicated on Figure 3.5 8 to determine if groundwater-quality impacts directly attributable to this RMA have occurred. All five wells will be shallow wells, monitoring the first water-bearing interval in either the unconsolidated soil or upper Vanoss zones. KMC plans to sample these new wells four to six times over a one year period to collect the data necessary to make this determination.

RMA-11 Both thorium and uranium are present in RMA-11. Subsurface placement of radioactive materials in RMA-11 increases the potential for radionuclide impacts to groundwater. As at RMA-10, the RMA-11 investigation will focus on groundwater quality to determine if radionuclides have migrated to groundwater. KMC will install one shallow up-gradient well and one shallow down-gradient well. These wells, along with four existing wells (MW-2, 3, 8, and 9) will be sampled to evaluate whether groundwater quality impacts directly attributable to this RMA have occurred. These well locations are g

Cushing Site Decommissioning Plan Description of Hanned Decommissioning Actrvities : 3-34

RIv.In June 4,1999 indicated on Figure 3.5 C. KMC plans to sample these wells four to six times over a one year period to collect the data necessary to make this determination.

3.5.4 Soit SAMPLING AND ANALYTICAL PROCEDURES Procedures to be used during field data collection are described below and detailed in the KMC Site Sampling and Analysis Plan (SAP) (KMC,1999). Other industry-standard procedures might be used when necessary.

3.5.4.1 Soil Samplina

. Surface soil sampling will be performed at RMAs 1, 2, 4 through 9, and 12 through 16 at locations previously identified, and at selected locations in RMA-3. The thickness of unconsolidated soil underlying the site is expected to be about 10 (or less) feet in most areas. Where shallow groundwater is present, its depth ranges from near surface to about 10 feet deep. In other areas of the site, shallow groundwater is not present.

. At RMAs 1,2,4 through 9, and 12 through 16, an auger will be used to obtain samples at two-foot intervals until sampling ceases. Sampling will cease when:

4 augering refusal occurs, e

O

acomt mi# ted oiiie re ched. or the water table is reached.

e After sampling has been completed, the Lorehole either will be used for groundwater grab sampling, monitoring well installation, or will be backfilled in accordance with site abandonment procedures. Boreholes in which monitoring wells are not installed will be backfilled with uncontaminated soil if the borehole is less than 10 feet deep, or grout if the borehole is more than 10 feet deep.

3.5.4.2 Soil Laboratory Analyses Soil samples will be analyzed by the onsite MCA. The number of such analyses -

will be determined as the investigation progresses.

Use of an on-site laboratory provides quick turn-around times in support of field activities.

In addition to radionuclide concentration analyses, one or more samples representing the major subsurface soil types will be set aside for distribution coefficient analysis. Since these analyses will be used in the evaluation of the potential for

'radionuclide migration, the samples to be submitted for laboratory analysis typically will 1

be from among the deeper soil samples collected. Distribution coefficient (Kd) testing

-will be conducted using ASTM Method D-4319 (ASTM,1993). These samples will be i-j l

Cushing Ste Decommissioning Plan Description of Planned Decommissioning Activities : 3-35

)

Rw.1a June 4.1999 collected, but not analyzed if no groundwater impacts are identified from this program,

-Gq then the distribution coefficient of the soil samples will not be analyzed.

. 3.5.5 GROUNDWATER SAMPLING AND ANALYnCAL PROCEDURES Groundwater samples will be collected from both new and existing monitoring wells. Samples may also be collected from open boreholes if the need is indicated.

Analysis of groundwater samples will be performed at an offsite analytical laboratory.

3.5.5.1 Grab Samplina This sampling will consist of measuring the depth to water and collecting a grab sample from the open borehole. The sample will be submitted for radiological a,nalyses as discussed in Section 3.5.5.4.

3.5.5.2 Monitorina WellInstallation Well installation and development will be conducted according to procedures in the SAP and will comply with Oklahoma Water Resources Board standards (OWRB, 1996) for the drilling, completion, and plugging of monitor wells.

Following completion, the wells will be developed by pumping or bailing. Water produced during development of newly installed monitoring wells will be stored in an on-O site storage tank and sampled Once analytical results are received, the produced water will be disposed of in accordance with applicable regulations.

3.5.5.3 Groundwater Monitorina Well Samplina The groundwater. monitoring wells installed at RMA-3,10, and 11, and (if necessary) at other RMAs, will be sampled repeatedly to build a database of water level

. and analytical information. KMC plans to sample these wells four to six times in the year following their installation. Groundwater levels will be measured and samples collected during each sampling event. Groundwater sampling procedures are detailed in the SAP.

3.5.5.4 Groundwater Laboratory Analyses.

A list of radionuclides and field parameters for which groundwater will be analyzed is provided in Table 3.6. Radionuclide analyses will be performed at an off-site analytical laboratory selected by KMC.

The use of filtered versus unfiltered samples is important in groundwater

. sampling.

Filtered samples provide data on the concentration on radionuclides

- concentration in the groundwater, and eliminate the influences of well installation and h.

. sampling that might cause analytical results to yield higher concentrations in unfiltered groundwater samples than actually are present in groundwater. Because this is an Cushing Site Decommissioning Plan Desenption of Planned Decommissioning ActMtes : 3-36

RIv. in June 4,1999 investigative program to examine the impact of possible leaching and transport of J

dissolved radionuclides in the groundwater near the RMAs, only filtered samples will be collected and analyzed.

Filters used in this investigation will be sized to remove suspended materials while allowing dissolved and colloidal material to pass. Future sampi'ng and monitoring techniques might be adjusted depending on the results from the filteied samples.

3.5.6 DATA EVALUATION Data co!lected during this investigation will supplement existing site data to support and refine understanding of site hydrogeology, particularly in the vicinity of RMAs. Data evaluation will focus on the following topics:

Determination of the range of background groundwater quality, Evaluation of vertical extent of radiologically impacted soil, identification of the presence and movement of groundwater near RMAs, e

Estimation of the extent of radiologically impacted groundwater near RMAs, and O

summery report of investi ation reeuu.

2 e

Methods to be used to address these features are discussed in the following sections.

3.5.6.1 Vertical Extent of Radiolooically impacted Soil The vertical extent of radiologically impacted soil will be determined by the soil sampling performed in the RMAs. Information collected as part of this groundwater pathways analysis will be combined with previous analyses to estimate a Icwer vertical extent of licensed materials migration.

The estimated depths will be mapped or contoured for the RMAs examined as part of this analysis. The estimated or measured depth to groundwater, if groundwater is reached, will be included on the illustrations of vertical extent to identify those areas where the pathway to groundwater appears to be completed.

3.5.6.2 Backaround Water Quality Background water-quality samples will be collected in areas selected to identify i

naturally occurring radionuclides in the groundwater, and to distinguish impacts from licensed materials from natural concentrations. Analytical results will be evaluated to produce a statistical description of the range of background water quality. A table of these values will be compiled for comparison with other site data.

Cushing Site Decommissioning Plan Descnption of Planned Decommissioning Activities : 3-37

R3v.1a Juns 4,1999 s

3.5.6.3 Presence and Movement of Groundwater

~

Water table maps of the unconsolidated zone and Upper Vanoss Group will be refined with the addition of data from soil borings and new monitoring wells. Maps for areas near the _RMAs will show the presence or absence of shallow groundwater, and will be used to refine estimates of hydraulic gradient, direction of flow, and water-quality impacts related to RMAs. The refined interpretation of recharge and discharge zones will provide additional information about movement of groundwater,

' Water level data collected as part of this investigation will be evaluated and presented to show potential flow paths and rate of groundwater movement and influence of recharge, discharge, and dilution on the groundwater flow system.

Shallow geologic cross-sections for the vicinity of RMAs 3,10, and 11 will be

- generated from boring logs. Cross-section of other areas will be generated if impacted groundwater is indicated. The correlation of sandstone and limestone lenses in the

. Upper Vanoss Group between borings will be interpreted.

Understanding the correlation of, these zones may be important in evaluating rate and direction of groundwater flow and movement of radionuclides that'could be present in groundwater.

3.5.6.4 Extent of Impacted Groundwater p

Analytical results from down-gradient monitoring wells will first be compared with v

the range of background. llf analytical results are not statistically significantly higher than' background results, no further evaluation will be performed. However, if results are' not statistically significantly higher than background results, water quality results from down-gradient locations will be compared with those from up-gradient locations to determine if there is an increase in radionuclide concentrations due to migration via the groundwater pathway from the RMA.

3.5.6.5 Summary Reoort of Results The data collected for this groundwater investigation will refine the understanding of the ' groundwater regime in the _ vicinity of the.16 RMAs.-

The report of this investigation will include the.following:

. The range of background water-quality; e ; The vertical extent of contamination (or lack thereof) at source areas; Modifications to the groundwater monitoring system, and e

Le- ' Groundwater impacts related to source areas.

j O.

I j

I' Cushing Site Decommissioning Plan.

Description of Planned Decommissioning Activities : 3-38

r -

R;v.1a June 4,1999 i

p KMC will provide copies of analytical data to NRC and DEQ as it is received from j

the laboratory. The groundwater investigation report will be submitted approximately six I

months following receipt of data from the final round of groundwater sampling.

TABLE 3.3 QUALITY SYSTEM REQUIREMENTS Requirement ANSI Standard NQA-1 Basic Requirements Organization / Management Responsibility Section 4.1 1

Quality System / Quality Assurance Program Section 4.2 2

Instructions, Procedures, and Drawings Section 4.2 & 4.3 5

Contract Review Section 4.3 Design Control Section 4.4 3

Document and Data Control Section 4.5 6

Purchasing / Procurement Document Control Section 4.6 4&7 Product identification and Traceability Section 4.8 8

Process Control Section 4.9 9

Inspection and Testing Section 4.10 10 & 11 Control of Inspection, Testing, and Measuring Equipment Section 4.11 12 Inspection and Test Status Section 4.12 14 Controlof Nonconforming Product Section 4.13 15 g.

t Corrective and Preventative Action Section 4.14 16 Handling Storage, Packaging, Preservation &

Delivery Section 4.15 13 Control of Quality Records Section 4.16 17 Intemal Quality Audits Section 4.17 18 Training Section 4.18 -

2 3

Servicing Section 4.19 Statistical Techniques Section 4.20 t

i f']s L

1 Cushing Site Decommissioning Plan Description of Planned Decommissioning ActMties : 3-39

Rry.1a June 4,1999 j

xY TABLE 3.5 WELLS FOR BACKGROUND MONITORING Well Unit Rationale CMW 11.1 Unconsolidated Soil Located hydraulically up-gradient of RMAs CMW 11.2 Upper Vanoss Located hydraulically up-gradient of RMAs CMW 21.1 Upper Vanoss Separated from RMAs by local discharge to Skull Creek CMW 22.1 Upper Vanoss Separated from RMAs by local discharge to Skull Creek CMW 24.1 Upper Vanoss Separated from RMAs by local discharge to Skull Creek CMW 25.1 Upper Vanoss Separated from RMAs by local discharge to Skull Creek CMW 26.1 Upper Vanoss Separated from RMAs by local discharge to Skull Creek CMW 30.1 Upper Vanoss Separated from RMAs by local discharge to Skull Creek CMW 33.1 Upper Vanoss Located hydraulically up-gradient of RMAs CMW 11.3 Lower Vanoss Located hydraulically up-gradient of RMAs CMW 18.1 Lower Vanoss Located hydraulically up-gradient of RMAs CMW 18.2 Lower Vanoss Located hydraulically up-gradient of RMAs CMW 20.1 Lower Vanoss Separated from RMAs by local discharge to Skull Creek CMW 20.2 Lower Vanoss Separated from RMAs by local discharge to Skull Creek CMW 23.1 Lower Vanoss Separated from RMAs by local discharge to Skull Creek CMW 23.2 Lower Vanoss Separated from RMAs by local discharge to Skull Creek CMW 30.2 Lower Vanoss Separated from RMAs by local discharge to Skull Creek CMW 30.3 Lower Vanoss Separated from RMAs by local discharge to Skull Creek CMW 31.1 Lower Vanoss Separated from RMAs by local discharge to Skull Creek CMW 31.2 Lower Vanoss Separated from RMAs by local discharge to Skull Creek f,,

(

l CMW 32.1 Lower Vanoss Separated from RMAs by local discharge to Skull Creek CMW 32.2 Lower Vanoss Separated from RMAs by local discharge to Skull Creek CMW 29.1 Vamoosa-Ada Vertically separated from RMAs l

i

<~

V Cushing Sde Decommissioning Plan Desenption of Planned Decommissioning Activities : 3-40 l

Rev. is June 4,1999

/%

Table 3.6 GROUNDWATER ANALYTICAL PROCEDURES Radionuclides Analytical Procedure MRL I

I Gross Alpha / Beta 900.0 N/A Uranium-234, 235, 238 HASL-300 N/A Thorium-228, 230, 232 HASL-300 N/A Radium-226 -

903.0 or KMTC-205-RA-7 N/A Radium-228 904.0 N/A Radon-222*

913.0 N/A Technetium-99" HASL-300 N/A Water-Quality Parameters Analytical Proc 3 dure MRL (mg/l)

Chloride 300.0 0.02 Fluoride 340.2 0.02 Nitrate 300.0 0.02 Phosphate 365.3 0.01 Sulfate 300.0 0.02 Total Dissolved Solids 160.1 5

Total Suspended Solids 160.2 5

Aluminum 200.7 0.05 Calcium 200.7 0.05 Iron 200.7 0.02 Magnesium 200.7 0.01 C)

Potassium 200.7 2

Sodium 200.7 0.1 Ammonium 350.3 0.05 Carbonate Bicarbonate SM2320B 20 Field Parameters Procedure MRL pH RA Probe N/A Temperature Probe N/A Specific Conductivity Probe N/A Dissolved Oxygen Probe N/A Eh Probe N/A I

Analytical procedures from SW-846 or Standard Methods for the Examination of Water and Wastewater (SM).

MRL. Method Reporting Limit (detection limits for volatile and semi-volatile organic compounds vary depending on compound analyzed).

mg/l = milligrams / liter N/A = Not Applicable

Necessity for radon analyses dependent on gross alpha results.

"First round of groundwater sampling only.

O Cushing Site Decommissioning Plan Description of Planned Decommissioning Activnes : 3-41 J

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