RC-94-0227, Semiannual Effluent & Waste Disposal Rept for Period of Jan-June 1994

Semiannual Effluent & Waste Disposal Rept for Period of Jan-June 1994

ML20072N335
Person / Time
Site:	Summer
Issue date:	06/30/1994
From:	Baehr W, Gowdy G, Gabe Taylor SOUTH CAROLINA ELECTRIC & GAS CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RC-94-0227, RC-94-227, NUDOCS 9409060076
Download: ML20072N335 (15)

Text

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• South Carolina Electric & Gas Company Gary J. Taylor Virgil C. Summer Nuclear Station General Manager P. O. Bor 86 Nuclear Plant Operations Jerknsville, SC 29065 (803) 345-4344 A SC.~ *s".Comrsny August 26, 1994 Refer to: RC-94-0227 U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

Subject:

VIRGIL C. SUMMER NUCLEAR STATION DOCKET NO. 50/395 OPERATING LICENSE NO. NPF-12 SEMI-ANNUAL EFFLUENT AND WASTE i DISPOSAL REPORT (SA 300)

Enclosed is the South Carolina Electric & Gas Company (SCE&G) Semi-Annual Effluent and Waste Disposal Report as required by 10CFR50.36a, Sections 6.9.1.8 and 6.14.2 of the Virgil C. Summer Nuclear Station Technical Specifications, and Section 1.6.2 of t

the Offsite Dose Calculation Manual (ODCM).

i Should there be any questions, please contact us at your convenience. ,

Very truly yours, s '

dW

~

SBR: Icd .

Enclosure c: O. W. Dixon R. R. Mahan (w/o attachments)

R. J. White S. D. Ebneter '

G. F. Wunder NRC Resident inspector J. B. Knotts Jr.

NSRC Central File System RTS (SA 300) i File (818.02-1) 3100c3 Q NUCLEAR EXCELLENCE- A SUMMER TRADITIONI e i

94o906oo76 94o63o PDR ADOCK 0500o395 R. _PDR:

. S 4

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT FOR THE OPERATING PERIOD i january 1,1994 - June 30,1994 August,1994 so.

V. C. SUMMER NUCLEAR STATION l SOUTH CAROLINA ELECTRIC AND GAS COMPANY l

Prepared by: Reviewed and approved by:

1

$ ru G. M. Gov 0dy G Staff HealthPhysicist W. R. Baehr, Manager Health Physics and Radwaste Services

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January- June,1994 VirgilC. Summer Nuclear Station South Carolina Electric & Gas This report is being submitted as a summary 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 Dase 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. Section F provides information on one reportable incident occurring during the period. No changes were made to the Offsite Dose Calculation Manual during the period.

A. Supplementallnformation Regulatory limits for doses and maximum permissible concentrations presented 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 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 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. Radiologicalimpact 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 ODCM. The source term included three (3) waste gas decay tank ('NGDT) batch releases. 5.88 days of 6-inch and 8.39 days of 36-inch Reactor Building purge releases and a continuous six month main plant vent release. Doses are summarized in Table 1. The total activities released are Page 1

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT

. January - June,1994 VirgilC. SummerNuclearStation South Carolina Electric & Gas presented in Tables 2 and 3. Air doses to the maximum exposed individual due to noble gases were 1.02E-3 and 2.18E-3 mrad for gamma and beta, respectively. The maximum organ dose attributed to the releases was 6.49E-3 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 of 146 Waste Monitor Tank batch releases,8.61 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 5.56E-3 mrem. The maximum organ dose was 6.84E-3 mrem to the gastrointestinal tract, lower large intestine (GILU) during the six month period.

Table 1 GASEOUS AND LIQUID EFFLUENT DOSE

SUMMARY

First Quarter,1994 Second Quarter,1994 Sect on Gaseous Limits Dose Perc,ent Dose Perc,en,t of Limit of Limit

1. 2.3.1 a,b 5 mrad gamma /qtr. 1.01E-3 mrad 2.03 E-2 5.19E-6 mrad 1.04E-4 10 mrad gamma /yr. 1.01 E-2 1.02E-2*

(January-June total gamma air dose: 1.02E-3 mrad)

1. 2.3.1 a,b 10 mrad beta /qtr. 1.91E-3 mrad 1.91 E-2 2.70E-4 mrad 2.70E-3 20 mrad beta /yr. 9.55 E-3 1.09E-2 *

(January-June total beta air dose: 2.18E-3 mrad)

1. 2.4.1 a,b 7.5 mrem / organ /qtr. 6.44E-3 mrem 8.59E-2 5.30E-5 mrem 7.06E-4 15 mrem / organ /yr. 4.29 E-2 4.33 E-2 *

(January-June maximum exposed organ dose: 6.49E-3 mrem)

Li_ quid Limits 1.1.3.1 a,b 1.5 mrem /qtr. 2.40E-3 mrem 1.60E-1 3.16E-3 mrem 2.11 E-1 3.0 mrem /yr. 8.01 E-2 1.85E-1 *

(January-June whole body dose: 5.56E-3 mrem) 1.1.3.1 a,b 5 mrem / organ /qtr. 3.66E-3 mremt 7.32E-2 3.20E-3 mremt 6.40E-2 10 mrem / organ /yr. 3.66E-2 6.84E-2' (January-June maximum exposed organ dose: 6.84E-3 mremt)

• Includes contribution from previous quarters.

t Maximum organ dose for quarters 1 and 2 were to the gastrointestinal tract, lower large intestine (GILLI) and the liver, respectively. Max. for the six month period was to the GILLI.

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SEMlANNUAL EFFLUENT AND WASTE DISPOSAL REPORT

, January - Jun@,1994 VirgilC. Summer Nuclear Station 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 4.80E-5 and 1.03E-4 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 establish a five (5) mile limit beyond which doses from anearby plants within (plants five 5) mile areofinsignificant.

radius There Virgil C. Summer are no Nuclear uranium fuel cycle Station.

F. Offsite Dose Calculation Manual (ODCM) Reportable Incident This report is made in accordance with Section 1.2.1.1.b of the ODCM for a '

failure to aerform a quarterly surveillance of the Reactor Building Purge System Raciation Monitor, RM-A4. The verification of the low flow alarm (Table 1.2-2, item 3.d) was inadvertently deleted from the surveillance procedure in January of 1983 when the procedure was revised by the maintenance organization. During the period of noncompliance, the operability of the alarm function was still verified during the 18 month calibration of the monitor. The procedure deficiency was corrected on January 20,1994 and plant personnel confirmed that all other required surveillances were being performed in accordance with the ODCM.

G. Offsite Dose Calculation Manual The Virgil C. Summer Nuclear Station (VCSNS) Offsite Dose Calculation Manual .

was not revised during the affected six month period. '

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1994 VirgilC. SummerNuclearStation 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 radioiodines, 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 durinc any calendar quarter and 15 mrem to any organ during any caleno 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 gaseocs 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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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT i january - June,1994 VirgilC. SummerNuclear Station l South Carolina Electric & Gas '

SupplementalInformation

c. Liquid Effluents: l The concentration of radioactive materials released from the site shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table ll, Column 2 for radionuclides other than dissolved I or entrained noble gases. For dissolved or entrained noble gases, the :

concentration shall be limited to 2E-4 pCi/ml total activity (ODCM, j Section 1.1.2.1).

3. Average Energy:

Not Applicable

4. Measurements and Approximations of Total Radioactivity:  ;

i

a. Fission and activation gases: Gamma spectrometry [Ge(Li) or HPGe] I

b. lodines: Gamma spectrometry [Ge(Li) or HPGe]

c. Particulates: Gamma spectrometry (Ge(Li) or HPGe], beta propor-tional counting, alpha proportional counting

d. Tritium: Liquid scintillation

e. Liquid effluents: Gamma spectrometry [Ge(Li) or HPGe], liquid scintillation (H-3), beta proportional counting, alpha proportional counting l 1

5. Batch Releases:

l l

a. Gaseous:

1. Number of batch releases: 3 l

2. Total time period for batch releases: 7.70E + 2 min. l

3. Maximum time period for a batch release: 4.70E + 2 min.

4. Average time period for a batch release: 2.57E + 2 min.

5. Minimum time period for a batt . release: 1.40E + 2 min.

b. Liquid:

1. Number of batch releases:

66 for first quarter,1994 80 for second quarter,1994 Page5 l

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1994 VirgilC. SummerNuclear Station South Carolina Electric & Gas Supplementalinformation

2. Total time period for batch releases:

5.19E + 3 min. for first quarter,1994 5.79E + 3 min. for second quarter,1994

3. Maximum time period for a batch release:

1.64E + 2 min. for first quarter,1994

• 8.30E + 1 min. for second quarter,1994

4. Average time period for batch releases: -

7.86E + 1 min. for first quarter,1994 7.24E+ 1 min.for second quarter,1 e4

5. Minimum time period for a batch release:

5.70E + 1 min. for first quarter,1994 6.20E + 1 min. for second quarter,1994

6. Average stream flow during periods of release of effluent into a flowing stream:

6.03E + 6 gpm for first quarter,1994 4.78E + 6 gpm for second quarter,1994 .

6. Abnormal Releases:

a. Gaseous: ,

1. Number of releases: 0

2. Total activity released: 0

b. Liquid: t

1. Number of releases: 0 ,

2. Total activity released: 0 l

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT j

. January - June,1994

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Table 2  ;

GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES l First Second Est. Total Quarter Quarter Error, %

A. Fission & activation gases

1. Total release Ci 7.50E + 0 7.11 E-1 3.13E + 1 pCi/sec l

2. Average release rate for period 9.65E-1 9.05E-2

3. Percent of technical specification limit  % *

• B. lodines

1. Total iodine-131 Ci 0 2.78E-6 5.35E + 1

2. Average release rate for period pCi/sec 0 3.54E-7

3. Percent of technical specification limit  % ** **

C. Particulates

1. Particulates with half-lives > 8 days Ci 0 0 N/A

2. Average release rate for period pCi/sec 0 l

0

3. Percent of technical specification limit  % ** **

4. Gross alpha radioactivity Ci 0 0 D. Tritium

1. Totai release Ci 1.22E + 1 8.36E-5 1.87E + 1 pCi/sec l

2. Average release rate for period 1.57 E + 0 1.06E-5

3. Percent of technical specification limit  % ** **

Calculated as a percent of dose limits found in Supplemental Information, Section la. First c uarter values were 2.03E-2% and 1.01E-2% of the quarterly and cumulative annual gamma c ose limits, respectively and 1.91E-2% and 9.55E-3% of the quarterly and cumulative annual beta dose limits, respectively. Second quarter values were 1.04E-4% and 1.02E-2%t of the quarterly and cumulative annual gamma dose limits, respectively, and 2 70E-3% and 1.09E-2%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 sum of these values for the first quarter was 8.59E-2% and 4.29E-2% of the quarterly and cumulative annual organ dose limits, respectively. The sum of these values for the second guarter was 7.06E-4% and 4.33E-2%t of the quarterly and cumulative annual organ dose hmits, 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,1994 Table 3 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES Continuous Mode Batch Mode First Second First Second Nuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission gases Krypton-85 C 0 0 0 6.69 t- 1 Krypton-85m Ci 0 0 0 0 JKrton-87 Ci 0 0 0 0 Krypton-88 Ci 0 0 0 0 Xenon-133 Ci 6.3 5E + 0 1.21 E-5 0 3.62 E-2 Xenon-135 Ci 1.07 E + 0 0 0 0 Xenon-135m Ci 0 0 0 0 Xenon-138 Ci 0 0 0 0 Others: Ar-41 Ci 8.52E-2 8.55E-5 0 0 Xe-131 m Ci 0 0 0 5.99E 3 Unidentified Ci 0 0 0 0 T otal for period Ci 7.50E + 0 9.76E-5 0 7.11 E- 1

2. lodines lodin e- 1.31 Li _

.e 2.78E-6 0 0 lodine-132 Ci 0 0 0 0 lodine-133 Ci 0 2.56E-6 0 0 lodine-134 Ci 0 0 0 0 lodine-135 Ci 0 0 0 0 Total for period Ci 0 5.34E-6 0 0

3. Particulates 5trontium-89 Li 0 0 0 0 Strontium-90 Ci 0 0 0 0 Cesium-134 Ci 0 0 0 0 Cesium-137 Ci 0 0 0 0 Barium-Lanth.-140 Ci 0 0 0 0

. Others: none Ci 0 0 0 0 Unidentified Ci 0 0 0 0 Total f or period Li 0 0 0 0 Page 8

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1994 Table 4 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES First Second Est. Total Unit Quarter Quarter Error, %

A. Fission & activation products

1. Total release (not including tritium, gases, Ci 2.59E-2 2.41 E-2 2.15E + 1 l alpha)

2. Average diluted concentration during pCi/ml 7.05E-11 6.74E-11 -

period

3. Percent of applicable limit  %

• B. Tritium 1.Totai release Ci 2.04E + 2 2.62E + 2 1.83E + 1 l

2. Average diluted concentration during pCi/ml 5.54E-7 7.31 E-7 period

3. Percent of applicable limit  %

• C. Dissolved and entrained gases

1. Total release Ci 1.67E-2 2.13E-2 3.87E + 1

2. Average diluted concentration during pCi/ml l 4.53E-11 5.96E-11 period

3. Percent of applicablelimit  % *

• D. Gross alpha radioactivity l 1. Total release lCi l 0 0 N/A E. Volume of waste released (prior to dilution) liters 3.00E + 7 1.79E + 7 3.00E + 0 b

F. Volume of dilution water used during period liters 3.67E + 11 3.58E + 11 4.30E + 0

• See following page.

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT

. January - June,1994 Table 4 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES 0

Calculated as a percent of dose limits found in Supplemental Information, Section 1c. The sum of these values for the first quarter was 1.60E-1% and 8.01E-2% of the respective quarterly and cumulative annual whole body dose limits and 7.32E-2% and 3.66E-2% of the respective quarterly and cumulative annual organ dose limits. The sum of these values for the second quarter was 2.11E-1% and 1.85E-1%t of the respective quarterly and cumulative annual whole body dose limits and 6.40E-2% and 6.84E-2%t of the respective c uarterly and cumulative annual organ dose limits. Dose to the gastrointestinal tract, iower larger intestine (GILLI) was the most limiting organ dose for the first quarter and first six (6) months of 1994. Dose to the liver was the most hmiting orgaa Jose for the second quarter of 1994. <

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 l January - June,1994 Table 5  :

LIQUID EFFLUENTS Continuous Mode Batch Mode First becond First 5econd l tNuclides Released Unit Quarter Quarter Quarter Quarter l 5trontium-89 Li 0 0 0 0 Strontium-90 Ci 0 0 0 0 Cesium-134 Ci 0 0 1.37E-5 5.44E-5 Cesium-137 Ci 0 0 7.08E-5 1.54E-4 lodine-131 Ci 0 6.7 3 E-6 1.20E-6 2.65E-5 Lobalt-56 Li 0 0 3.b l t-3 1.52 t-2 Cobalt-60 Ci 8.59E-5 0 1.37 E-2 2.78E-3 tron-59 Ci 0 0 9.33 E-5 1.60E-5 Zinc-65 Ci 0 0 5.69E-5 0 Manganese-54 Ci 0 0 2.22E-3 6.96E-4 Chromium-51 Ci 0 0 3.78E-4 5.32 E-6 zirconsum-Ntobium-95 Li O O 9.3 6 t-4 1.bbt-5 Molybdenum-99 Ci 0 0 0 0 Technetium-99m Ci 0 0 0 0 Barium-Lanth.-140 Ci 0 0 4.26E-5 8.29E-6 Cerium-141 Ci 0 0 0 0 Other: Na-24 Li 2.22 t-5 2.b9t-5 0 5.40t-6 Fe-55 Ci 0 0 3.54E-3 3.08E-3 Co-57 Ci 0 0 5.89E-5 2.72 E-5 Ag-110m Ci 0 0 2.90E-5 0 Sn-113 Ci 0 0 6.25E-6 0 Sb-124 Ci 0 0 4.59 E-6 2.48 E-4 Sb-125 Ci 0 0 7.3 6E-4 1.59E-3 1-132 Ci 6.94E-5 3.62E-5 0 1.66E-6 l-133 Ci 6.96E-5 3.73E-5 0 0 1-134 Ci 4.7 7 E-5 3.51 E-5 0 2.02E-6 1-135 Ci 9.67 E-5 5.16E-5 0 0 Cs-138 Ci 3.80E-5 0 0 1.61 E-5 l Unidentified l Ci l 0 l 0 l 0 l 0 l l Total for period (above) Ci l 4.30E-4 1.94E-4 2.55E-2 l l l l 2.39E-2 l Page 11

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT

. January - June,1994 Table 5(continued)

LIQUID EFFLUENTS Continuous Mode Batch Mode First Second First Second tNuclides Released Unit Quarter Quarter Quarter Quarter Xenon-133 Ci 0 0 1.19E-2 1.99E-2 Xenon-135 Ci 0 0 6.65E-6 5.20E-6 Other: Kr-85 Ci 0 0 4.07E-3 1.19E-3 Xe-131m Ci 0 0 5.93E-4 1.18E-4 Xe-133m Ci 0 0 0 9.89E-5 Xe-135m Ci 5.63E-5 0 0 0 Total entrained gases Ci 5.63E-5 0 1.66E-2 2.13 E-2 i Tritium not included. See Table 4 for tritium nembers.

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT 4 January - June,1992 Table 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

1. Type of waste Unit 6-month Est. Total Penod Error,%

a. Spent resins, filter sludges, evaporator m3 1.76E + 1 bottoms, etc. Ci 1.10E + 0 3.50E + 1

b. Dry compressible waste, contaminated m3 1.53E + 1 eq uip., etc. Ci 7.50E-1 3.50E + 1

c. Irradiated components, control rods, etc. m3 0 Ci 0 N/A 3

d.Other (describe) m 0 Ci 0 N/A

2. Estimate of major nuclide composition (by type of waste)

a. Fe-55  % 3.06E + 1 Co-60  % 2.50E + 1 Co-58  % 1.53 E + 1 Ni-63  % 1.25 E + 1 Mn-54  % 7.14E + 0 Cs-137  % 2.25E + 0 Sb-125  % 1.14E + 0

b. Fe-55  % 5.08E + 1 Co-60  % 2.31 E + 1 Ni-63  % 1.04E + 1 Cs-137  % 6.10E + 0 Mn-54  % 3.50E + 0 Cs-134 _

% 2.20E + 0

c. None  % N/A

d. None  % N/A

• All nuclides with concentrations above 10% are listed in descending order by activity level

3. Solid Waste Disposition (6 month period)

Number of Shipments Mode of Transportation Destination 43t Truck Barnwell, SC tNote: 42 of these are partial shipments of DAW from waste processor to Barnwell, SC.

B. lrradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A Page 13