ML20056G547
| ML20056G547 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 06/30/1993 |
| From: | Baehr W, Gowdy G SOUTH CAROLINA ELECTRIC & GAS CO. |
| To: | |
| Shared Package | |
| ML20056G546 | List: |
| References | |
| NUDOCS 9309030254 | |
| Download: ML20056G547 (14) | |
Text
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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT I
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FOR THE OPERATING PERIOD
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January 1,1993 - June 30,1993 i
August 1993 l
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V. C. SUMMER - NUCLEAR STATION SOUTH CAROLINA ELECTRIC-AND GAS CGMPANY-L Prepared by:
Reviewed and approved by:
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W M-G. M.f2owdy, Staff Health Phys //
'W.R. Baeht/, Mp'and Rad wa(ste 5'ervices hager
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Health Physic's itist a
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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT
. Janusry - June,1993 VirgilC. Summer Nuclear Station South Carolina Electric & Gas This report is being submitted as a sumrnary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the Virgil C. Summer Nuclear Station.
This report satisfies the requirements in Sections 6.9.1.8 and 6.14.2 of Technical Specifications, Section 1.6.2 of the Offsite Dose Calculation Manual (ODCM) and 10CFR50.36(a). Also included is an assessment of radiation doses from plant releases.
A brief discussion of the Supplemental Information and Tables 2 through 6 is presented in Sections A through D. An evaluation of the radiological impact on man due to operation of the Virgil C. Summer Nuclear Station is presented in Section E and Table 1. Changes made to the Offsite Dose Calculation Manual during the first half of 1993 are presented in Section F and Attachment 1.
A.
SupplementalInformation Regulatory limits for doses and maximum permissible concentrations presented 1
in Supplemental information are from the Virgil C. Summer Nuclear Station Technical Specifications and 40 CFR 190. Average energy (E) is not a aplicable to the method for determining release rate limits for fission anc activation gaseous effluents; therefore, it has been omitted.
B.
Gaseous Effluents Gaseous effluents released from ground level are summarized in Tables 2 and
- 3. An elevated release pathway does not exist at Virgil C. Summer Nuclear Station. The errors for gaseous effluent totals are given as the square root of j
the sum of squares of counting errors and flow or volume measurement errors.
A systematic error of 15% has been added to estimate total error. Cumulative doses are discussed in Section E.
C.
Liquid Effluents Liquid effluents are summarized in Tables 4 and 5. Estimated total errors are expressed as in Section B above.
D.
Solid Waste Shipments Solid waste shipments are summarized in Table 6. Curie content of radioactive waste packages is determined by dose rates and/or analysis of samples by l
gamma spectroscopy.
The total error for each type of Curie content determination is conservatively estimated to be the sum of a 15% systematic error and a 20% photon response error for the detector used.
E.
Radiological Impact on Man Potential doses to the maximum exposed individual in the unrestricted area were calculated using measured plant gaseous effluent and meteorological data in accordance with the Offsite Dose Calculation Manual. The source term included three (3) waste gas decay tank (WGDT) batch releases, a 1.2-day PORV release,16.4 days of 6-inch and 45.1 days of 36-inch Reactor Building purge releases and a continuous six month main plant vent release. Doses are i
summarized in Table 1. The total activities released are presented in Tables 2 Page1 4
SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT J'anua~ry ; June,1993 Virgil C. Summer NuclearStation South Carolina Electric & Gas and 3. Air doses to the maximum exposed individual due to noble gases were I
1.75E-2 and 4.54E-2 mrad for gamma and beta, respectively. The maximum organ dose attilbuted to the releases was 8.33E-2 mrem for the six month period.
Measured plant liquid effluent data was used to calculate estimates of doses to individuals in accordance with the Offsite Dose Calculation Manual. The source term consisted of the isotopic contents cf 254 Waste Monitor Tank batch releases, 21.1 days of Steam Generator Blowdown release and a continuous Turbine Building Sump release. Doses are summarized in Table 1 and total radioactivity released is described in Tables 4 and 5. The total body dose to the maximally exposed individual due to the release of radioactive liquid was 2.25E-2 mrem. The maximum organ dose was 3.21E-2 mrem to the thyroid during the six month period.
Table 1 GASEOUS AND LIQUID EFFLUENT DOSE
SUMMARY
First Quarter,1993 Second Quarter,1992 M
Gaseous Limits Se t on Pergeqt g
Pergeqt of Limit of Limit 1.2.3.la,b 5 mrad gamma /qtr.
1.75E-2 mrad 3.50E-1 3.68E-5 mrad 7.37E-4 10 mrad gamma /yr.
1.75E-1 1.75 E-1 *
(January-June total gamma air dose: 1.75E-2 mrad) 1.2
- a,b 10 mrad beta /qtr.
4.49E-2 mrad 4.49E-1 5.03E-4 mrad 5.03E-3 20 mrad betalyr.
2.24 E-1 2.27 E-1 *
(January-June total beta air dose: 4.54E-2 mrad)
)
1.2.4. l a,b 7.5 mrer1/ organ /qtr.
8.10E-2 mrem 1.08E + 0 2.35E-3 mrem 3.13 E-2 15 mrem /organlyr.
5.40E-1 5.55 E-1 *
(January-June maximum exposed organ dose: 8.33E-2 mrem)
Liquid Limits 1.1.3.1 a,b 1.5 mrem!qtr.
1.36E-2 mrem 9.11 E-1 8.83E-3 mrem 5 89E-1 3.0 mrem /yr.
4.5 5 E-1
- 7. 50E-1
- j (January-June whole body dose: 2.25E-2 mrem) 1.1.3.1 a,b 5 mrem / organ /qtr.
2 60E-2 mremt 5.20E-1 1.71E-2 mremt 3.42 E-1 4
10 mrem' organ /yr.
2.60E-1 3.21 E-1 *
(January-June maximum exposed organ dose: 3.21 E-2 mremt)
- Includes contribution from previous quarters.
Max. organ dose for quarters 1 and 2 were to the thyroid and gastrointestinal tract, lower t
larger intestine (GILLI), respectively. Max. for the six month period was to the thyroid.
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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT
. january - June,1993 VirgilC. SummerNuclearStation South Carolina Electric & Gas Dose rates and concentrations were below the limits specified in Supplemental Information, Section 2a, b and c during all the effluent releases.
Radiation doses from radioactive effluents to workers at the Fairfield Hydro Station were calculated for the six-month period to be 8.23E-4 and 2.14E-3 mrad for gamma and beta, respectively.
Radiation doses from nearby uranium fuel cycle sources were not assessed.
ODCM, Sections 1.3.1 and B/1.3 es+.ablish a five (5) mile limit beyond which doses from nearby plants are insignificant. There are no uranium fuel cycle plants within a five (5) mile radius of Virgil C. Summer Nuclear Station.
F.
Offsite Dose Calculation Manual The Virgil C. Summer Nuclear Station Offsite Dose Calculation Manual (ODCM) was revised once (Rev.17) during the affected six month period. A copy of the manual including the revision is included as Attachment 1.
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SEMIANNUAL EFFL,UENT AND WASTE DISPOSAL REPORT January - June,1993 VirgilC SummerNuclear Station South Carolina Electric & Gas Supplementalinformation 1.
Regulatory Limits:
a.
Fission and Activation Gases:
The air dose to an individual due to noble gases released in gaseous effluents shall be limited to less than or equal to 5 mrad for gamma radiation and 10 mrad for beta radiation during any calendar quarter and 10 mrad for gamma radiation and 20 mrad for beta radiation during any calendar year (ODCM, Section 1.2.3.1).
b.
lodines, Particulates (half-lives > 8 days) and Tritium:
The dose to an individual from radiciodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days in gaseous effluents shall be limited to less than or equal to 7.5 mrem to any organ during any calendar quarter and 15 mrem to any organ during any calenc ar year (ODCM, Section 1.2.4.1).
c.
Liquid Effluents:
The dose or dose commitment to an individual from radioactive materials in liquid effluents released shall be limited to less than or equal to 1.5 mrem to the total body and 5 mrem to any organ during any calendar quarter and 3 mrem to the total body and 10 mrem to any organ during any calendar year (ODCM, Section 1.1.3.1).
d.
All Sources:
The annual dose equivalent shall not exceed 25 mrem to the whole body,75 mrem to the thyroid and 25 mrem to any other organ (40 CFR 190).
2.
Maximum Permissible Concentrations:
a.
Fission and Activation Gases:
The dose rate in unrestricted areas due to radioactive materials released in gaseous effluents shall be limited to less than or equal to 500 mrem / year to the total body and less than or equal to 3000 mrem / year to the skin (ODCM, Section 1.2.2.1).
b.
lodines, Particulates (half-lives > 8 days) and Tritium:
The dose rate in unrestricted areas due to radioactive materials in effluents shall be limited to less than or equal to 1500 mrem / year to any organ (ODCM, Section 1.2.2.1).
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1 SEMIANNUAL EFFL,UENT AND WASTE DISPOSAL REPORT i
[anuary - June,1993 VirgilC. SummerNuclearStation South Carolina Electric & Gas SupplementalInformation c.
Liquid Effluents:
The concentration of radioactive materials released from the site shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table 11, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 pCi/ml total activity (ODCM, Section 1.1.2.1).
3.
Average Energy:
Not Applicable 4.
Measurements and Approximations of Total Radioactivity:
a.
Fission and activation gases: Gamma spectrometry [HPGe]
b.
lodines: Gamma spectrometry [HPGe]
c.
Particulates:
Gamma spectrometry [HPGe], beta proportional counting, alpha proportional counting l
d.
Tritium: Liquid scintillation Liquid effluents: Gamma spectrometry [HPGe], liquid scintillation (H-e.
3), beta proportional counting, alpha proportional counting 5.
Batch Releases:
a.
Gaseous:
1.
Number of batch releases: 3 2.
Total time period for batch releases: 9.87E + 2 min.
3.
Maximum time period for a batch release: 4.17E + 2 min.
4.
Average time period for a batch release: 3.29E + 2 min.
5.
Minimum time period for a batch release: 2.70E + 2 min.
b.
Liquid:
1.
Number of batch releases:
160 for first c uarter,1993 94 for seconc quarter,1993 Page 5 L
SEMIANNUAL EEFL,UENT AND WASTE DISPOSAL REPORT Januhry - June,1993 VirgilC. SummerNuclearStation South Carolina Electric & Gas SupplementalInformation 2.
Total time period for batch releases:
1.29E +4 min. for first quarter,1993 7.87E + 3 min. for second quarter,1993 3.
Maximum time period for a batch release:
3.05E + 2 min, for first quarter,1993 9.60E + 1 min. for second quarter,1993 4.
Average time period for batch releases:
8.05E + 1 min. for first quarter,1993 8.38E+ 1 min. for second quarter,1993 5.
Minimum time period for a batch release:
5.70E + 1 min. for first quarter,1993 6.50E + 1 min. for second quarter,1993 6.
Average stream flow during periods of release of effluent into a flowing stream:
2.74E+ 6 gpm for first quarter,1993 3.82E+ 6 gpm for second quarter,1993 6.
Abnormal Releases:
a.
Gaseous:
1.
Number of releases:
0 2.
Total activity released: 0 b.
Liquid:
1.
Number of releases:
0 1
2.
Total activity released: 0 1
Page 6 i
SEMIANNUAL El' FLUENT AND WASTE DISPOSAL REPORT January - June,1993 Table 2 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES First Second Est. Total Quarter Quarter Error, %
A. Fission & activation gases
- 1. Total release Ci 2.42 E + 2 1.39 E + 0 1.71 E + 1
- 2. Average release rate for period pCi/sec 3.11 E + 1 1.77E-1
- 3. Percent of technical specification limit
- 3. lodines
- 1. Totat iodine-131 Ci 4.14 E-3 1.16 E-4 2.11 E + 1
- 2. Average release rate for period pCi/sec 5.33 E-4 1.48E-5
- 3. Percent of technical specification limit C. Particulates
- 1. Particulates with half-lives > 8 days Ci 7.81 E-5 5.35 E-5 5.35E + 1 1
- 2. Average release rate for period pCi/sec 1.00E-5 6.81 E-6
- 3. Percent of technical specification limit
- 4. Gross alpha radioactivity Ci 0
0 D. Tritium
- 1. Total release Ci 2.24 E + 0 0
3.98E + 1
- 2. Average release rate for period pCi/sec 2.89E-1 0
- 3. Percent of technical specification limit Calculated as a percent of dose limits found in Supplemental Information, Section la. First c uarter values were 3.50E-1% and 1.75E-1% of the quarterly and cumulative annual gamma c ose limits, respectively and 4.49E-1 % and 2.24E-1% of the quarterly and cumulative annual beta dose limits, respectively. Second quarter values were 7.37E-4% and 1.75E-1%t of the quarterly and cumulative annual gamma dose limits, respectively, and 5.03E-3% and 2.27E-1% t of the quarterly and cumulative annual beta dose limits, respectively.
Calculated as a percent of dose limits found in Supplemental information, Section 1b. The 1
sum of these values for the first quarter was 1.08% and 5.40E-1% of the quarterly and cumulative annual organ dose limits, respectively. The sum of these values for the second quarter was 3.13E-2% and 5.55E-1%t of the quarterly and cumulative annual organ dose limits, respectively.
t Note: Second quarter values are the sum of the first and second quarter values compared to annual dose limits.
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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT
' January - June,1993 Table 3 G ASEOUS EFFLUENTS-GROUND-LEVEL RELEASES Continuous Mode Batch Mode First Second First Second i
Nuclides Released Unit Quarter Quarter Quarter Quarter 1.
Fission gases IKrypton-85 C
0 0
0 1.19 E + 0 Krypton-85m Ci 1.38E-1 0
2.36 E-3
- 0 Krypton-87 Ci 0
0 2.34 E-3
- O Krypton-88 Ci 8.63 E-2 0
4.00E-3
- 0 Xenon-133 Ci 2.29 E + 2 0
2.35 E-2
- 9.3 5 E-2 Xenon-135 Ci 7.86 E + 0 8.14 E-2 8.67 E-3
- 3.52E-4 Xenon-135m Ci 0
0 1.81 E-3
- 0 Xenon-138 Ci 0
0 4.14 E-3
- O Others:
Ar-41 Ci 5.97 E-1 0
4.64 E-4
- 0 Xe-131 rn Ci 8.36 E-1 0
0 2.17 E-2 Xe-133m Ci 2.62 E + 0 0
8.08 E-4
- 5.91 E-4 Unidentified Ci 0
0 0
0 lotal for period Ci 2.41 E + 2 8.14 E-2 4.81 E-2
- 1.30 E + 0 2.
lodines lodine-131 Li 9.146-4 1.16 t-4 3.2 3 t-3 "
O lodine-132 Ci 1.42 E-4 0
1.4 5 E-4
- O lodine-133 Ci 1.08 E-4 0
1.29 E-3
- 0 lodine-134 Ci 0
0 0
0 3
lodine-135 Ci 0
0 1.73 E-4
- O Total for period Ci 1.16E-3 1.16 E-4 4.84 E-3
- O 3.
Particulates Strontium-89 C
0 0
0 0
Strontium-90 Ci 0
0 0
0 Cesium-134 Ci 4.83 E-8 0
2.19 E-5
- O Cesium-137 Ci 1.47 E-7 0
2.86 E-5
- O Barium-Lanth.-140 Ci 0
0 4.16 E-6
- O Others:
Na-24 Ci 0
0 3.02E-6*
0 Cr-51 Ci 0
1.60E-5 0
0 hon-54 Ci 0
1.82 E-6 0
0 Co-58 Ci 2.10 E-7 2.10 E-5 0
0 3
Co-60 Ci 0
1.02 E-5 2.44 E-7
- O Br-82 Ci 2.13 E-6 0
0 0
Rb-88 Ci 5.16E-4 0
0 0
Nb-95 Ci 0
4.33 E-6 0
0 Zr-95 Ci 0
1.50E-7 1.41 E-5
- O hoo-99 Ci 0
0 7.10 E-6
- O Tc-99m Ci 1.25 E-6 0
0 0
Cs-136 Ci 0
0 9.07 E-6
- O Unidentifica Li 0
0 0
0 i otal for period L
- 5. 20 E-4 5.35b-5 8.82 t-5 '
O i
- Activities From PORV release 1/12-1/13/93 4
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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1993 Table 4 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES First Second Est. Total Quarter Quarter Error, %
A. Fission & activation products
- 1. Total release (not including tritium, gases, Ci 9.53 E-2 7.92 E-2 2.70E + 1 alpha)
- 2. Average diluted concentration during pCi/ml 2.76E-10 2.26E-10 period
- 3. Percent of applicable limit B. Tritium
- 1. Total release Ci 3.36E + 2 3.68 E + 1 1.85E + 1
- 2. Average diluted concentration during pCi/ml 9.73 E-7 1.05 E-7 penod
- 3. Percent of applicable limit C. Dissolved and entrained gases
- 1. Total release Ci 2.81 E + 0 1.90E-3 1.90E + 1
- 2. Average diluted concentration during pCi/ml 8.15E-9 5.42E-12 period
- 3. Percent of applicable limit D. Gross alpha radioactivity
- 1. Total release Ci 0
0 N/A l
l E. Volume of waste released (prior to 5.80E + 7 3.29E + 7 3.00E + 0 dilution) liters F. Volume of dilution water used during 3.45E + 11 3.50E + 11 4.30E + 0 period liters
- See following page.
Page 9
SEMIANNUAL EFFLUENT AND. WASTE DISPOSAL REPORT January - June,1993 Table 4 LIQUID EFFLUENTS-SUMM ATION OF ALL RELEASES Calculated as a percent of dose limits found in Supplemental Information, Section 1c. The sum of these values for the first quarter was 9.11E-1% and 4.55E-1% of the respective quarterly and cumulative annual whole body dose limits and 5.20E-1% and 2.60E-1% of the respective quarterly and cumulative annual organ dose limits. The sum of these values for the second quarter was 5.89E-1% and 7.50E-1%t of the respective quarterly and cumu!ative annual whole body dose limits and 3.42E-1% and 3.21E-1%t of the respective quarterly and cumulative annual organ dose limits. Dose to the thyroid was the most limiting organ dose for the first quarter and first six (6) months of 1993. Dose to the gastrointestinal tract, lower larger intestine (GILLI) was the most limiting for the second quarter of 1993.
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Note: Second quarter values are the sum of the first and second quarter values compared to 1
annual dose limits.
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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT
' January - June,1993 Table S LIQUID EFFLUENTS Continuous Mode Batch Mode First Second First becond i Nuclides Released Unit Quarter Quarter Quarter Quarter Strontium-89 0
0 0
0 0
i Strontium-90 Ci 0
0 1.34 E-5 0
Cesium-134 Ci 5.20E-5 2.50E-4 9.42 E-4 2.59 E-4 i
Cesium-137 Ci 3.23 E-4 4.2 6 E-4 2.19E-3 2.63 E-4 iodine-131 Ci 4.96E-3 0
1.83 E-3 3.17 E-4 Cobalt-58 0
0 1.32 E-4 1.08 E-3 2.30E-2 Cobalt-60 Ci 0
0 2.32 E-2 9.00E-3 Iron-59 Ci 0
0 8.78 E-5 2.99E-3 Zinc-65 Ci 0
0 5.17 E-5 1.39 E-4 Manganese-54 Ci 0
0 2.64 E-3 4.02 E-3 Chromium-51 Ci 0
0 2.01 E-3 1.7 7 E-2 Zirconsum-Niobium-95 0
0 0
2.22 t-4 6.22 t-3 Molybdenum-99 Ci 0
0 0
0 Technetium-99m Ci 6.73 E-3 0
2.58 E-5 0
Barium-Lanth.-140 Ci 0
0 8.02E-5 2.23 E-5 i
Cerium-141 Ci 0
0 0
0 Other:
Na-24 Ci
/./6E-3 0
5.71 E-5 1.31 E-5 l
Fe-55 Ci 0
0 6.24 E-3 3.90 E-4 i
Co-57 Ci 5.54 E-5 0
7.87 E-5 4.59E-5 Rb-88 Ci 0
0 1.71 E-4 0
Ru-103 Ci 0
0 1.15 E-5 1.19 E-4 Ru-106 Ci 0
0 2.47 E-4 5.12 E-5 Ag-110m Ci 0
0 3.91 E-4 2.38 E-4 Sn-113 Ci 0
0 0
1.85 E-4 5n-117rn Ci 0
0 6.18E-6 5.5 7 E-6 Sb-122 Ci 0
0 4.84 E-6 8.45 E-7 5b-124 Ci 0
0 1.34 E-4 1.10 E-3 Sb-125 Ci 0
0 1.59 E-3 1.20E-2 Sb-126 Ci 0
0 0
4.27 E-6 T e-132 Ci 0
0 2.09 E-5 2.56 E-6 l-132 Ci 8.85 E-4 0
5.15 E-5 1.09 E-5 l-133 Ci 1.32 E-2 1.03E-4 3.84 E-5 0
l-134 Ci 6.86 E-4 0
0 0
l-13 5 Ci 1.00 E-2 0
0 0
Cs-136 Ci 0
0 5.64 E-5 0
Cs-138 Ci 9.06 E-4 0
9.19 E-5 1.32 E-5 Ce-144 Ci 0
0 0
5.87 E-5 lunidentified l
Ci 1
0 1
0 1
0 1
0 l
ITotal for neriod (above) l Ci l
- 4. 56 E-2 I
9.13 E-4 1
4.96E-2 1
7 82E-2 l
Page 11
SEMIANNUAL EFFLUENT AND. WASTE DISPOSAL REPORT January - June,1993 Table 5 (continued)
LIQUID EFFLUENTS Continuous Mode Batch Mode First Second First Second tNuclides Released Unit Quarter Quarter Quarter Quarter Xenon-133 Ci 2,47 E-3 0
2.73 E + 0 1.86 E-3 Xenon-135 Ci 1.01 E-2 0
8.75 E-3 0
Other:
Ar-41 Ci 0
0 7.55 E-7 0
Kr-85 Ci 0
0 1.76E-3 0
Kr-85m Ci 4.42 E-4 0
2.06 E-4 0
Kr-88 Ci 0
0 4.66E-5 0
Xe-131m Ci 0
0 3.01 E-2 3.27E-5 Xe-133m Ci 0
0 2.51 E-2 0
Total entrained gases Ci 1.30 E-2 0
2.80E + u,
13!)E-3 i Tritium not included. See Table 4 for tritium numbers.
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SEMIANNUAL EFFLUENT AND. WASTE DISPOSAL REPORT j
January - June,1993 Table 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel) 6-month Est. Totcl
- 1. Type of waste Unit Penod Error,%
1
- a. 5 pent resins, filter sludges, evcporator m'
1.98E + 1 3.50E + 1
)
bottoms, etc.
Ci 9.47 E + 1
- b. Dry compressible waste, contaminated m
1.20E + 1 3.50E + 1 3
eq uip., etc.
Ci 7.90E-1
- c. Irradiated components, control rods, etc.
m 0
N/A 3
Ci 0
d.Other Idescribe) m 0
N/A 3
Ci 0
- 2. Estimate of major nuclide composition (by type of waste) a.
Fe-55 2.68E + 1 Ni-63 2.68 E + 1 Co-60 2.34 E + 1 i
Cs-137 7.69 E + 0 Cs-134 7.47 E + 0 I
Co-58 4.80E + 0
- b. Fe-55 4.99 E + 1 Co-60 1.53 E + 1 Ni-63 1.18 E + 1 Cs-137 1.05 E + 1 Cs-134 4.61 E + 0 Mn-54 2.69 E + 0 Co-58 2.44 E + 0 c.
None N/A
- d. None N/A
- All nuclides with concentrations above 1.0% are listed in descending order by activity level.
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- 3. Solid Waste Disposition (6 month period)
Number of Shipments Mode of Transportation Destination 371 Truck Barnwell, SC tNote: 33 of these are cartial shipments of DAW from waste processor to Barnwell, SC.
B. Irradiated Fuel Shipments (Disposition)
Number of Shipments Mode of Transportation Destination 0
N/A N/A Page 13
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