ML20246J637

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Nonproprietary Semiannual Effluent & Waste Disposal Rept for Operating Period Jan-June 1989
ML20246J637
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 06/30/1989
From: Baehr W, Blue L, Gowdy G
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
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ML19292J520 List:
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NUDOCS 8909050225
Download: ML20246J637 (14)
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' dEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT FOR THE OPERATING PERIOD january 1,1989 . June 30,1989 August 21,1989

[ M h l A

V. C. SUMMER NUCLEAR STATION SOUTH CAROLINA ELECTRIC AND GAS COMPANY Prepared by:

l t G.M/Gowdy,

$taff Health Ph Licist Reviewed and approved by: Reviewed and approved by.

la1/e &

L A. Bl6e, Manager

~

a W. R. Baehr, Manager Corporate Health Physics and Chemistry and Health Physics Environmental Programs Reviewed and approved by:

J.

9hJ62

. Cox, Jr., Assoc.@ nager

- s909050225 690829 Hlr Ith Physics PDR ADOCK0500g5 t _. _ __ _ _ . _ . _. _ . _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT Janunry- June,1989 Virgil C. Summer Nudesr 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 re Technical Specifications and 10CFR50.36(a)quirements in Sectionsradiation

. Alsoincludedisan assessmentof 6.9.1.8 and 6.9.1.9 doses from plant releases.

A brief discussion of the SupplementalInformation and Tables 1 and 3 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 Process Control Program are presented in Section F.

A. Supplementalinformation Regulatory limits for doses and maximum permissible concentrations presented in Sup alemental information are from the Virgil C. Summer _. Nuclear Station Technica Specifications and 40 CFR 190. Average energy (E) is not applicable to the method for determining release rate limits for fission and 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. Cumulative doses are discussed in Section E.

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, s

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 weste 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. 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.

Included in the source term were seven (7) waste gas decay tank (WGDT) releases, 23.4 days of Reactor Building purge releases (36-inch line), and a Page 1

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT J nu;ry -Jun2,1989 Virgil C. Summer Nudear Station E , South Carolina Electric & Gas continuous six month main plant vent relear,e. Doses are summarized in Table

1. The total Curies releasec are presented in Tables 2 and 3. Air doses to an individual due to noble gases were 7.03E-2 and 1.75E-1 mrad for gamma and beta respectively. The maximum organ dose attributed to the releases was 5.75E-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 Offsita Dose Calculation Manual.

The source term consisted of the isotopic contents of one (1) Nuclear Blowdown Monitoring Tank and 351 Waste Monitor Tank batch releases and continuous Turbine Building Sump and Steam Generator 8 lowdown releases.

Doses are summarized in Table 1. The total radioactivity released is described in Tables 4 and 5. The total body dose to the maximally exposed individual due to the radioactive liquid released was 2.44E-2 mrem. The maximum organ dose was 7.11E-2 mrem to the Thyroid.

Table 1 GASEOUS AND LIQUID DOSES First Quarter,1989 Second Quarter,1989 ect Gaseous umits go,, Percen,t Dose Percen,t of Limit of Limit 3.11.2.2 3,b S mrad gamma /qtr. 1.51E-2 mrad 3.03E-1 5.52E 2 mrad 1.10E + 0 10 mrad gamma /yr. 1. 51 E-1 7.03 E-1 *

(January-June total gamma air dose: 7.03E 2 mrad) 3.11.2.2a,b 10 mrad beta /qtr. 3.70E 2 mrad 3.70E-1 1.38E-1 mrad 1.386 + 0 20 mrad betalyr. 1.85E-1 8.76 E-1 *

(January-June total beta air dose: 1.75E-1 mrad) 3.11.2.3a,b 7.5 mrem / organ /qtr. 5.02E-4 mrem 6.69E-3 5.25E-3 miem 7.00E-2 15 mrem / organ /yr. 3.35 E-3 3.83 E-2 *

(January-June maximum exposed organ dose: 5.75E-3 mrem) 3.11.1.2a,b 1.5 mrem /qtr. 1.26E-2 mrem 8.40E-1 1.18E-2 mrem 7.90E-1 3.0 mrem /yr. 4.20E-1 8.13 E- 1 *

(January-June whole body dose: 2.44E-2 mrem) 3.11.1.2a,b 5 mrem / organ /qtr. 3.73E-2 mrem 7.46E-1 3.38E-2 mrem 6.77E-1 10 mrem / organ /yr. 3.73E-1 7.11 E-1 *

(January-June maximum exposed orc _,an dose: 7.11E-2 mrem)

Includes contribution from previous quarters.

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7 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT

'?i J nuary-Juns, $989 Virgil C. Summer Nuclear Station South Carolina Electric & Gas Dose rates and concentrations were below the limits specified in Supplemental Info mation, Section 2a, b and c during all the effluent releases.

Radiation doses from radioactive effluents to workers at the Fairfield Hydro Station were calculated to be 9.60E-3 and 2.39E-2 mrad for gamma and beta, respectively.

Radiation doses from nearby uranium fuel cycle sources were not assessed. Technical Specifications, Section 3/4.11.4, aage B 3/411-6 establishes a five (5) mile limit beyond which doses from near ay plants are insignificant.

There are no uranium fuel cycle plants within a five (5) mile radius of Virgil C.

Summer Nuclear Station.

F. Process Control Program The Virgil C. Summer Nuclear Station (VCSNS) Process Control Program (PCP) was modified three (3) times during the affected six month period.

Revision 7, Change D (2/11/89) involved updating Attachment IV (Chem-Nuclear Systems, Inc. (CNSI) procedure FO-AD-002, Rev. M) to reflect the discontinuation of use of sealant materials on the threads of High integrity Container (HIC) lids. Revision 7, Change E (2/11/89) involved updating Attachment 111 (CNSI procedure SD-OP-003, Appendix B, pages 15 and 16, revision 10/5/88 ) to allow for a change in the sample preparation procedure for LOMI solidification of resin beads. The final change for the six-month period, Revision 7, Change F (3/15/89), also involved a change in Attachment lli (CNSI procedure SD-OP-003, Appendix B, page 1 revision 1/25/89). This change removed unnecessary information about boron content greater than 21,000 ppm. The overall conformance of the solidified waste product to existing criteria for solid wastes has not been adversely affected by the changes incorporated in the VCSNS PCP. Per Technical Specification requirement 6.13.2.1.c, the PSRC has reviewed and approved the revisions which are enclosed as Attachment 1. See the changes and each Procedure Development Form - A,Section IX, for the PSRC approval signatures.

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SSMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT

,.?

January -June,1989 L

v Virgil C. Surnmer Nuclear Station South Carolina Electric & Gas Supplementallnformation 1

I~

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 l

gamma radiation and 20 mrad for beta radiation during any calendar year (Technical Specifications, Section 3.11.2.2).

b. lodines, Particulate (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 during any calendar quarter and 15 mrem to any organ during any calendar year (Technical Specifications, Section 3.11.2.3)

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 ec ual to 1.5 mrem to the total body and 5 mrem to any organ during any ca endar quarter and 3 mrem to the total body and 10 mrem to any organ during any calendar year (Technical Specifications, Section 3.11.1.2).

d. AAll 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 mremiyear to the skin (Technical Specifications, Section 3.11.2.1).

b. lodines, Particulate (half-lives > 8 days) and Tritium:

The dose rate in unrestricted areas due to radioactive materials in effluentr, shall be hmited .x less than or equal to 1500 mrem / year to any organ (Technical Specifications, Section 3.11.2.1).

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M  : SEMIANNUAL SFFLUENT AND WASTE DISPOSAL REPORT -

e x' 7-January -June,1989 1

.- Virgil C. Summer Nuclear Station Sou't h Carolina Electric & Gas v

, e Supplementallnformation

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/mi total activity (Technical Specifications, Section 3.11.1.1).

'3. Average Energy:

' Not Applicable

. 4.- Measurements and Approximations of Total Rad!oactivity:

a. Fission and activation gases: Gamma spectrometry [Ge(Li) or HPGe]
b. lodines: Gamma spectrometry [Ge(Li) or HPGe]
c. Particulate: Gamma spectrometry {Ge(Li) or HPGe], beta propor-tional counting, alpha proportional counting
d. Tntium: Liquid scintillation
e. Liquid effluents: Gamma spectrometry.(Ge(Li) or HPGe], liquid scintillation (H-3), beta proportional counting, alpha proportional counting
5. Batch Releases:
a. Gaseous:
1. Number of batch releases: 7
2. Total time period for batch releases: 3.33E + 3 min.
3. Maximum time period for a batch release: 1.11E + 3 min.
4. Average time period for a batch release: 4.75E + 2 min.
5. Minimum time period for a batch release: 2.28E + 2 min,
b. Liquid:
1. Number of batch releases:

144 for first quarter,1989 207 for second quarter,1989 Page 5

c.

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT v

lanuary -June,1989

. Virgil C. Summer Nucicar Station South Carolina Electric & Gas l

Supplementallnformation

2. Total time period for batch releases:

1 9.30E + 3 min. for first quarter,1989 l 1.39E + 4 min. for second quarter,1989

3. Maximum time period for a batch release:

7.60E + 1 min. for first quarter,1989

l. 8.00E + 1 min. for second quarter,1989
4. Average time period for batch releases:

6.45E + 1 min. for first quarter,1989 6.70E + 1 min.for second quarter,1989

5. Minimum time period for a batch release:

7.00E + 0 min. for first quarter,1989 5.70E + 1 min. for second quarter,1989

- 6. ' Average stream (Iow during periods of release of effluent into a flowing stream:

3.84E t 6 gpm for first quarter,1989 3.61E + 6 gpm for second quarter,1989

6. Abnormal Releases:
a. Gaseous:
1. Number of releases: 0
2. Total activity released: 0
b. Liquid:
1. Number of releases: 0
2. Total activity released: 0 Page 6

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT

. January - June,1989 Table 2 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES i

First Second Est. Total Quarter Quarter Error, %

A. Fission & activation gases

1. Total release Ci 1.92E + 2 7.04E + 2 2.04E + 1
2. Average release rate for period pCi/sec 2.47E + 1 8.95 E + 1
3. Percent of technical specification limit *
  • I B. lodines
1. Total iodine-131 Ci 3.57E-5 3.64 E-4 3.30E + 1
2. Average release rate for period pCi/sec 4.59E-6 4.63 E-5
3. Percent of technical specification limit ** **

C. Particulate

1. Pa tticulates with half-lives > 8 days Ci 7.77 E-7 4.80E-7 3.75E + 1
2. A' erage release rate for period pCi/sec 9.99E-8 6.11 E-8
3. Pucent of technical specification limit ** **
4. Grass alpha radioactivity Ci 0 0 D. Tritium
1. Total release Ci 2.30E-2 2.74E-2 6.14E + 1
2. Average release rate for period pCi/sec 2.96E-3 3.48 E-3
3. Percent of technical specification limit  %

Calculated as a percent of dose limits found in SupplementalInformation, Section la. First quarter values were 3.03E-1% and 1.51E-1% of the quarterly and cumulative annual gamma dose limits, respectively and 3.70E-1% and 1.85E-1% of the quarterly and cumulative annual beta dose limits, respectively. Second quarter values were 1.10% and 5.52E-1% of the quarterly and cumulative annual gamma dose limits, respectively, and 1.38% and 6.90E-1%

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 6.69E-3% and 3.35E-3% of the quarterly and cumulative annual organ dose limits, respectively. The sum of these values for the second quarter was 7.00E-2% and 3.50E-2% of the quarterly and cumulative annual organ dose limits, respectively.

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT

. January -June,1989 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 Ci 0 0 1.38 E-1 1.49E0 Krypton-85m Ci 9.28E-2 2.92 E-1 0 0 "

Krypton-87 Ci 1.09E-1 0 0 0 '

Krypton-88 Ci 2.25E-1 8.16 E-2 0 0 Xenon-133 Ci 1.77E + 2 6.17E + 2 3.83E-1 3.16E + 1 Xenon-135 Ci 1.17E + 1 4.81 E + 1 1.43 E-4 5.11 E-3 Xenon-135m Ci 9.26 E-2 0 0 0 Xenon-138 Ci 0 0 0 0 Others: Xenon-131m Ci 1.98E + 0 9.17 E-1 1.69 E-3 7.00 E-1 Xenon-133m Ci 1.85E-1 3.44E + 0 3.62 E-3 9.13 E-2 Unidentified Ci 0 0 0 0 Total 1or period C 1.91 E + 2 6.70E + 2 5.26E-1 3.39E + 1

2. lodines lodine-131 Ci 3.57E-5 3.64 E-4 0 0

' lodine-132 Ci 0 0 0 0 lodine-133 Ci 3.87E-6 3.03 E-4 0 0 lodine-134 Ci 0 0 0 0 lodine-135 Ci 0 1.82 E-5 0 0 Total for period Ci 3.96E-5 6.85 E-4 0 0

3. Particulate Strontium-89 Ci 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: Co-58 Ci 7.7 7 E-7 4.80 E-7 0 0 Rb-88 Ci 0 7.76E-4 0 0 Cs-138 Ci 5.92E-5 0 0 0 Unidentified Ci 0 0 0 0 Total for period Ci 6.00E-5 7.76 E-4 0 0 Page 8

-4 SEMIANNUAL EFFLUENT AND WAST E DISPOSAL REPORT January - June,1989 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 1.41 E-1 1.03E 1 1.84E + 1 alpha)
2. Average diluted concentration during pCi/mi 3.51E-10 2.23 E-10 period 3.Percentof applicablelimit  % *
1. Total release Ci 6.45E + 1 2.29E + 2 1.85E + 1
2. Average diluted concentration during pCi/ml 1.60 E-'7 4.94E-7 penod
3. Percent of applicable limit  % *
  • C. Dissolved and entrained gases
1. Total release Ci 4.15E-1 1.44 E-1 1.90E + 1
2. Average diluted concentration during pCi/ml 1.03 E-9 3.11 E-10 period
3. Percent of applicablelimit  %
  • D'. Gross alpha radioactivity
1. Total release Ci 0 0 N/A E. Volume of waste released (prior to dilution liters 5.47E + 7 6.60E + 7 3.00E + 0 F. Volume of dilution water used during period liters 4.03E + 11 4.63E + 11 4.30E + 0
  • See following page.

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January -June,1989 Table 4 LlQUID EFFLUENTS-SUMMATION 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 8.40E-1% and 4.20E-1% of the respective quarterly and cumulative annual whole body dose limits and 7.46E-1% and 3.73E-1% of the respective quarterly and cumulative annual organ dose limits. The sum of these values for the second quarter was 7.90E-1% and 3.95E-1% of the respective quarterly and cumulative annual whole body dose limits and 6.77E-1% and 3.38E-1%'of the respective quarterly and cumulative annual organ dose limits. Dose to the Thyroid was the most limiting organ dose for the first and second quarters of 1989.

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1989 Table S LIQUID EFFLUENTS Continuous Mode Batch Mode First Second First Second tNuclides Released Unit Quarter Quarter Quarter Quarter Strontium-89 Ci 0 1.75 E-4 1.81 E-4 1.78 E-4 Strontium-90 C 0 4.80 E-5 3.46E-5 4.49 E-4 Cesium-134 Ci 2.66E-4 6.20E-4 7.29 E-3 1.79E-3 Cesium-137 Ci 3.06E-4 5.97 E-4 6.37E-3 2.36E-3 lodine-131 Ci 1.42 E-2 8.60E-3 5.52 E-3 3.34E-2 Cobalt-58 Ci 1.26 E-2 1.02 E-2 3.17 E-2 5.85 E-3 Cobalt-60 Ci 9.72 E-4 1.47 E-3 9.93 E-3 3.55 E-3 tron 59 Ci 0 0 5.80E-6 5.02 E-4 Zinc-65 Ci 0 0 1.74 E-4 0 Manganese-54 Ci 1.08 E-4 0 2.19E-3 6.82 E-4 Chromium-51 Ci 0 0 4.31 E-4 6.75 E-4 Zirconium-Niobium-95 Ci 0 0 1.63 E-3 4.26d-4 Molybdenum-99 Ci 0 0 6.30 E-4 4.22 E-4 Technetium-99m Ci 2.04E-4 0~ 7.56 E-4 5.07 E-4 Barium-Lanth.-140 Ci 0 0 1.3 7 E-5 8.88E-5 Cerium-141 Ci 0 0 1.37 E-6 1.65 E-6 Other: Na-24 Ci 1.68E-3 9.06 E-4 7.62E-5 2.49 E-5 Fe-55 Ci 0 0 2.51 E-3 1.31 E-2 Ni-56 Ci 0 0 0 2.37E-7

  • Co-57 Ci 0 0 1.44 E-4 1.42 E-5 Rb-88 Ci 0 0 0 5.3 5 E-5 Ru-103 Ci 0 0 3.58E-5 0 Ru-106 C 0 0 5.11 E-5 1.84 E-5 Ag-110m Ci 0 0 2.11 E-5 0
  • 5n-113 Ci 0 0 5.96E-6 2.81 E-6
  • 5 b-124 Ci 0 0 1.00E-3 6.71 E-4
  • Sb-12 5 Ci 0 0 1.10 E-2 4.20E-3 1-132 Cs 5.43 E-3 1.28E-3 0 0 1-133 Ci 1.56E-2 4.58E-3 8.03 E-5 2.61 E-4 1-134 Ci 1.53 E-3 2.03 E-3 0 0 1-135 Ci 6.43 E-3 1.73 E-3 1.17 E-5 0 Cs-136 Ci 0 0 1.89 E-5 4.81 E-5 Cs-138 Ci 0 1.59E-3 0 0 Ce-144 Ce 0 0 2.72 E-4 4.19E-5 Np-239 Ci 0 0 3.89E-6 0 Unidentified l Ci 0 0 0 0 l Total for period (above) l Ci l 5.93 E-2 l 3.38E-2 l 8.21 E-2 l 6.93 E-2 l Page 11

y SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1989 Table 5 (continued)

LIQUID EFFLUENTS Continuous Mode Batch Mode First Second First Second tNuclides Released Unit Quarter Quarter Quarter Quarter Xenon-133 Ci 1.56E-3 1.69 E-4 4.03 E-1 1.40E-1 Xenon-135 Ci 6.80 E-4 2.36 E-4 7.67E-5 4.92 E-4 Other: Kr-85m C 0 0 6.76E-7 5.00E-6 Kr-87 Ci 0 0 0 7.49E-7 Kr-88 Ci 0 0 7.68E-6 2.77E-6 Xe-131m Ci 0 0 8.01 E-3 2.17 E-3 Xe-133m Ci 0 0 1.75 E-3 7.74 E-4 Total entrained gases Ci 2.24E-3 4.05E-4 4.13 E-1 1.44 E-1 t Tritium not included. See Table 4 for tritium numbers.

  • Dose factors for these trace radionuclides are not included in the ODCM or Regulatory Guide 1.109, consequently the cumulative dose attributed to these isotopes is not reported. The uantity of these isotopes comprised only 1.9E-2 % and 2.1E-3 % of the total curies released q(including tritium) during the first and second quarter, respectively.

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f SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1989 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.5 pent resins, titter sludges, evaporator m3 1.51 E + 1 bottoms, etc. Ci 3.73E + 2 3.50E + 1

b. Dry compressible waste, contaminated m3 8.83E + 1 eq uip., etc. Ci 1.09E + 0 3.50E + 1
c. Irradiated components, control rods, etc. m' O Ci 0 N/A d.Other (descrioe) Process Filters m' O Ci 0 N/A
2. Estimate of major nuclide composition (by type of waste)
a. Co-58  % 4.87 E + 1 Fe-55  % 1.42E + 1 Cs-134  % 1.23E + 1 Cs-137  % 9.03E + 0 Co-60  % 6.65E + 0 H-3 'A 5.09E + 0 Ni-63  % 2.30E + 0
b. Fe-55  % 4.42E + 1 Co-60

. OE + 0 Ni-63

.20E + 0 Co-58

% 3.20E + 0 Mn-54 Pu-241 *A 1.20E + 0

c. None  % N/A
d. None  % N/A
  • All nuclides are listed in descending order by activity level.

All nuclides with concentrations above 1.0% are listed.

3. Solid Waste Disposition (6 month period)

Number of Shipments Mode of Transportation Destination 511 Truck Barnwell, SC tNote: 48 of these are partial shipments of DAW from waste processor to Barnwell.

B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination None N/d N/A Page 13

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