ML20059C004

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Semiannual Effluent & Waste Disposal Rept for Jan-June 1990
ML20059C004
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 06/30/1990
From: Baehr W, Blue L, Gowdy G
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20059B956 List:
References
NUDOCS 9008300216
Download: ML20059C004 (15)
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t, SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT 1

FOR THE OPERATING PERIOD January 1,1990 June 30,1990 i

August 20,1990 l

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C i-1 V. C. SUMMER NUCLEAR STATION--

SOUTH CAROLINA ELECTRIC AND' GAS COMPANY 1

p Prepared by:

- k G M/Gowdy, c

Staff Health Phy(s)icist

' Reviewed at a oved by: Reviewed and approved by:

L' L'A. Blue, Manager W. R. Baehr, Manager l Corporate Health Physics and Chernistry and Health Physics j Environmenta1 Programs i

Reviewed and approved by:

Y G. G. Hall, Assoc. Manager Health Physics poo r 3 oca /(, 90cF ag

- pp A /7 0 o c A:. CScoo395 A, # _

. SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REf an

  1. ' January June,1990 Virgil C. 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 re Tcchnical Specifications and 10CFR50.36(a)quirements in Sections

. Also included is an assessmeist 6.9.1.8 and 6.9.1.9 o of radiation doses from plant releases.

A brief discussion of the SupplementalInformation and Tables 2 through 6 is presented in Sections A through D. An evaluation of the radiologicalimpact 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.

Section G proades information on one reportable incident occurring during the period.

A. Supplementallnformation 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 (D is not applicable to the method for determining release rate hmits for fission and activation gaseous effluents; therefore,it has been omitted.

B. Gaseous Effluents Gaseo'us 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.

C. Liquid Effluents Liquid effluents are summarized in Tables 4 and S. 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. Radiologicallmpact 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 five (S) waste gas decay tank (WGDT) releases, Page 1

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT

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January e June,1990 4 . Virgil C. Summer Nuclear Station 4 South Carolina Electric & Gas - >

18.2 days and 44.1 days of Reactor. Building purge releases through the 6-inch .

and 36 inch purge lines, respectively, and a continuous six month main plant J l

vent release. Doses are summarized in Table 1. The total Curies' released are n presented in Tables 2 and 3. Air doses to an individual due to noble gases were-

  • R 5.38E-2 and 1.32E 1- mrad for gamma and_ beta respectively. The maximum

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organ dose attributed to the releases was 5.77E-3 mrem for.the six month 4 period, a Measured plant liquid effluent da.., was used to calculate estimates of doses to individuals in accordance with the Offsite Dose Calculation Manual, '

o The source term consisted of the isotopic contents of 252 Waste Monitor Tank batch releases and continuous Turbine Building Sump and Steam Generator .

Blowdown 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- ,

o exposed individual due to the radioactive liquid released was 5.09E 2 mrem.

(- The maximum organ dose was 6.78E 2 mrem to the liver.

Table 1 l GASEOUS AND LIQUID DOSES j First Quarter,1990 Second Quarter,1990~

Tech C eet Gaseous Limits g,3, Percent Dose Percen,t of Limit of Limit 3.11.2.2a,b 5 mrad gamma /qtr. 4.53E 2 mrad 9.07E 1 - 8.41E 3 mrad 1.68E-1 10 mrad gamma /yr. 4.53E 1 5.38E-1 *

(January-June total gamma air dose: 5.38E 2 mrad) q l: -1 i' 3.11.2.2! 10 mrad beta /qtr. 1.19E-1 mrad 1.19E0 1.32E-2 mrad 1.32 E-1 l L 20 mrad betalyr. 5.95E-1 6.61 E 1

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.(January June total beta air dose: 1.32E 1 mrad) 3.11.2.3a,b' 7.5 mrem / organ /qtr. 4.20E-3 mrem 5.60E 2 1.57E-3 mrem 2.09E-2 15 mrem / organ /yr. 2.80E-2 3.85 E-2

  • i (January June maximum exposed organ dose: 5.77E 3 mrem)

Liquid Limits 3.11.1.2 a,b 1.5 mrem /qtr. 4.46E-2 mrem 2.97E0 6.28E-3 mrem 4.18E 1' L 3.0 mrem /yr. 1.49E0 1.70E0* '

(January-June whole body dose: 5.09E-2 mrem)

, i 3.11.1.2 a,b 5 mrem / organ /qtr. 5.96E-2 mrem 1.19E0 8.18E-3 mrem 1.64E-1 10 mrem / organ /yr. 5.96E-1 6.78 E- 1 *

(January-June maximum exposed organ dose: 6.78E 2 mrem)

  • Includes contribution from previous quarters.

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January Juna,1990 Virgil C. Summer Nuclear Station South Carolina Electric & Gas Dose rates and concentrations were below the limits specified in SupplementalInformation, 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 7.37E-3 and 1.81E-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?y plants are insignificant.

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

Summer Nuclear Station F. Process Control Program The Virgil C. Summer Nuclear Statior (VCSNS) Process Control Program (PCP) was modified one (1) time during the affected six month period. Revision 8, Change A (2/12/90) involved adding Section 7.0, Revision Summary, to the PCP to comply with the administrative procedure for procedure development, SAP-139. The overall conformance of the solidified waste product to existing criterie for solid wastes has not been adversely affected by the changes incorporated in the VCSNS PCP. Per Technical Specification requirement 613.2.1.c, the PSRC has reviewed and approved the revision which is enclosed as Attachment 1. See the chance and Procedure Development Form - A,Section IX, for the PSRC approval signature.

G. Technical Specification Reportable incident Pursuant to Section 3.3 3 9.b of Technical Specifications, the iodine channel of the main plant vent monitor (RM-A3) was inoperable for more than thirty (30) days during this six (6) month period. On 4/9'90, during a maintenance check of the iodine channel, the unit was found to give no response to the normal check source. A maintenance work order was processed for repair of the channel, however, due to the heavy outage maintenance schedule, the repair to the check source was not completed until 5/10'90 During the inoperable period, continuous samples were taken and analyzed for this channel as required by the Technical Specifications.

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.- SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1990  ;

Virgil C. Summer Nuclear Station  ;

South Carolina Electric & Gas t SupplementalInformation l- 1. Regulatory Limits: ,

a. Fission and Activation Gases:

The air dose to an individual due to noble gases released in gaseous j effluents shall be limited to less than or equal to 5 mrad for gamma radiation i 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  :

(Technical Specifications, Section 3.11.2.2).

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

1 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 c;uarter 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, 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).

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! 2. Maximum Permissible Concentrations:

a. Fission and Activation Gases:

e The dose rate in unrestricted areas due to radioactive materials I

released in gaseous effluents shall be limited to less than or equal to 500 mrem / year to the total body and less than or e skin (Technical Specifications, Section 3.11.2.1) qual to 3000 mrem / year to the

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 (Technical Specifications, Section 3.11.2.1).

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," .  : SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT-i January June,1990 Virgil C. Summer Nuclear Station South Carolina Electric & Gas 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 ofTotal Radioactivity:
a. Fission and activation gases: Gamma spectrometry [C$(s u or HPGel-

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

c. Particulates: _ Gamma spectrometry [Ge(Li) or HPGel, beta propor-tional counting, alpha proportional counting
d. Tritium: Liquid scintillation
e.  ; Liquid ef9uents: Gamma spectrometry (Ge(Li) or HPGe], licluid -

scintillation (H 3), beta proportional counting, alpha proportional counting

5. Batch Releases:
a. Gaseous:
1. Number of batch releases: 5
2. Total time period for batch releases: 2.86E + 3 min.
3. Maximum time period for a batch release: 1.05E + 3 min.
4. Average time period for a batch release: 5.72 E + 2 min.
5. Minimum time period for a batch release: 2.89E + 2 min, b Liquid:
1. Number of batch releases:

157 for first quarter,1990 95 for second quarter,1990 Page5

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[ ., .- SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1990- ,

Virgil C. Summer Nuclear Station l South Carolina Electric & Gas a

-t Supplementallnformation 1

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~ 2. Total time period for batch releases:

1.08E + 4 min, for first quarter,1990 6.52E + 3 min. for second quarter,1990 i

3. Maximum time period for a batch release:

9.60E + 1 min. for first quarter,1990 -

9.30E + 1 min. for second quarter,1990

4. Average time period for batch releases:

6.85E + 1 min, for first quarter,1990 '

6.86E + 1 min. for second quarter,1990

- 5. Minimum time period for a batch elease: , .

. 4.50E + 1 min. for first quarter,1990 5.00E + 1 min. for second quarter,1990

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

2.70E + 6 gpm for first quarter,1990 3.73E 4 6 gpm for second quarter,1990 '

6. Abnormal Releases:

'al Gaseous: ,

K 1. Number of releases: 0'

2. Total activity released: O p b .- Liquid:
1. Number of releases: 0
2. Total activity released: 0 -

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT d January June,1990 Table 2 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES i

First Second- Est. Total Quarter Quarter Error, %

  • A. Fission & activation gases
1. Total release Ci 6.36E + 2 6.56E + 1 2.49E + 1
2. Average release rate fur period pCi/sec 8.18E + 1 - 8.34E0
3. Percent of technical specification limit *
  • B. lodines , .
1. Total iodine-131 Ci 2.97E 4 1.02E 4 2.11 E + 1 .
2. Average release rate for period pCi/sec 3.83E 5 1.30E 5  !
3. Percent of technical specification limit ** **

C. Particulates

1. Particulates with half lives > 8 days Ci 2.81 E-6 1.18 E-4 2.36E + 1 l'
2. Average release rate for period pCi/sec 3.62E 7 1.50E 5
3. Percent of technical specification limit  %
4. Gross alpha radioactivity Ci 0 0 D. Tritium q
1. Total release Cl 1.21 E-2 1.07 E-2 2.31E + 1
2. Average release rate for period pCi/sec 1.56E-3 1.36E-3
3. Percent of technical specification limit  % i Calculated as a percent of dose limits found in SupplementalInformation, Section la. First I c uarter values were 9.07E-1% and 4.53E 1% of the quarterly and cumulative annual gamma c ose limits, respectively and 1.19E-1% and 5.95E-1% of the quarterly and cumulative annual  ;

beta dose limits, respectively. Second quarter values were 1.68E 1% and 5.38E 1%t of the

, quarterly and cumulative annual gamma dose limits, respectively, and 1.32E-1% and l 6.61E-1%t of the quarterly and cumulative annual beta dose limits, respectively.

Calculated as a percent of dose limits found in SupplementalInformation, Section 1b. The sum of these values for the first quarter was 5.60E-2% and 2.80E-2% of the quarterly and cumulative annual organ dose limits, respectively. The sum of these values for the second quarter was 2.09E-2% and 3.85E-2%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 i

to annual dose limits..

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.* SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1990 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 I Krypton 55 Ci 3.71 t- 1 0 7.25t 1 4.54 t- 1 Krypton-85m Ci 2.20E 1 2.00E-1 0 9.62E 4 Krypton-87 Ci 5.95E 3 1.93E 1 0 0 .

Krypton 88 Ci 1.41 E 1 0 0 8.84 E-4 j Xenon 133 Ci 5.93 E + 2 6.11 E + 1 1.08E + 1 1.24 E -1 i Xenon 135 Ci- 2.60E t 1 7.02E 1 3.32 E-4 1.70E-2 i l Xenon 135m Ci 0 0 0 0 l Xenon 138 Ci 0 0 0 0 Others: Argon-41 Ci 3.38E 1 2.75E0 0 0 i Xenon 131rn Ci 9.67E-1 0 2.04E-1 1.67 E-2 Xenon-133 rn Ci 3.53E0 0 2.52E 2 1.87E 3 Unidentified Ci 0 0 0 0  !

Total for period Ci 6.24E + 2 6.50E + 1 1.18E + 1 6.15 E-1  ;

2. todines lodine 131 Ci 2.9 / t-4 1.02t 4 0 0 lodine-132 Ci 4.50E-5 4.90E-4 0 0 lodine 133 Ci 1.45 E-4 0 0 0 lodine 134 Ci 1.75E 5 0 0 0 lodine 135 Ci 7.91 E-5 . 0 0 0 Total for period Cs 5.84 E-4 5.91 E-4 0 0 _
3. Particulates Strontium 89 Ci 0 0 0 0 Strontium-90 Ci 0 0 0 0 Cesium 134 Ci 9.11 E-7 0 0 0 Cesium 137 Ci 1.45 E-6 5.03 E-7 0 0 Barium-Lanth.-140 Ci 0 0 0 0 Others: Cr 51 Ci 0 3.13 E-5 0 0 Co-58 Ci 0 5.85 E-5 0 0 Co-60 Ci 4.57 E-7 1.64E-5 0 0 Zr 95 Ci 0 3.19E-6 0 0 Nb-95 Ci 0 3.94E-6 0 0 Rb 88 Ci 6.54E 3 0 0 0 Ru 103 Ci 0 3.77E-6 0 0 Cs-138 Ci 0 2.90E-4 0 0 Unidentified Ci 0 0 0 0 Total for period Ci 6.54E-3 4.08 E -4 0 0 Page 8

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Table 4 LIQUID EFFLUENTS- SUMMATION OF ALL RELEASES First Second Est. Total Quarter Quarter Error, %

A.L Fission & activation products

1. Total release (not including tritium, gases, Ci 1.88E 1 5.07E-2 1.91 E + 1 alpha)
2. Average diluted concentration during pCi/ml 4.89E 10 2.39E-10 period 3, Percent of applicable limit  %

B. Tritium

1. Total release Ci 1.67E + 2 7.39E + 1 1.86E + 1 -
2. Average diluted concentration during pCi/ml 4.35 E-7 3.49 E-7 period
3. Percent of applicable limit *
  • C. Dissolved and entrained gases
1. Total release Ci 2.71 E-1 6.96E-2 1.83E + 1
2. Average diluted concentration during pCi/ml 7.06E-10 3.29E-10 period
3. Percent of applicable limit  % *
  • D. Gross alpha radioactivity
1. Total release Ci 0 0. N/A E. Volume of waste released (prior to dilution) liters 5.33E + 7 3.29E + 7 3.00E + 0

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F. Volume of dilution water used during period liters 3.84E + 11 2.12E + 11 4.30E + 0

  • See following page.

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  • os 1 . ; SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1990

, - Table 4 LlQUID EFFLUENTS SUMMATION OF ALL RELEASES Calculated as a percent of dose limits found in Supplemental Information, Section 1c The- l sum of these values for the first quarter was 2.97% and 1.49% of the respective quarterly and cumulative annual whole body dose limits and 1.19% and 5.96E 1% of the respective quarterly and cumulative annual organ dose limits. The sum of these values for the second quarter was 4.18E-1% and 1.70% of the respective quarterly and cumulative annual whole body dose limits and 1.64E-1% and 6.78E-1%t of the respective quarterly and cumulative ,

annual organ dose limits. Dose to the liver was the most limiting organ dose for the first and second quarters of 1990. (tNote: Second quarter values are the sum of the first and second 4 quarter values compared to annual dose limits.)

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e SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January Ta ble 5 June,1990 LIQUID EFFLUENTS Continuous Mode Batch Mode First Second hrst 5econd t Nuclides Released Unit- Quarter Quarter Quarter Quarter Strontium-59 Ci 0 0 0 1.14 E-5 Strontium 90 Ci 0 0 0 7.66E 6 Cesium 134 Ci 7.15E 4 4.07E 4 1.83E 2 6.9 3 E-4 Cesium 137 C 7.33E 4 5.71 E-4 2.59E 2 9.5 3 E-4 i lodine 131 Ci 1.36E 2 0 1.94E 2 8.2 8 E-4 Cobalt-58 Ci 0 2.llt 6 4.39E 3 1.31 E-2 Cobalt 60 Ci 0 4.90E-5 2.03E-2 7.06 E-3 tron 59 Ci 0 0 0 -4.98E 5 t

Zinc-65 Ci 0 0 4.63E 4 7.26E 4 Manganese 54 Ci 0 0 4.68E 3 1.08E 2 Chromium 51 Ci 0 0 1.92E 3 3.62E 3 Zirconium Niobium 95 Ci 0 0 1.55h-3 1. l l E 3 Molybdenum 99 Ci 0 0 9.09 E-4 0 Technetium 99m Ci 0 0 5.68E-4 7.42 E 7 -

Barium Lanth.140 Ci 0 0 5.50E 5 8.61 E 5 Cerium 141 Ci 0 0 7.42E 6 2.37E-5 Other: 'F-18 Ci 0 5.05E-6 0 0 Na24 Ci 0 0 2.89E-4 0 Fe 55 Ci 0 0 1.29 E-2 4.99 E-4

  • Co 57 Ci 4.69E-6 0 8.59E 5 3.37 E-5 Zr 97 Ci 0 0 4.74E 6 0 Ru 103 Ci 0 0 6.47E 5 1.70 E-4 Ru-106 Ci 0 0 2.48E 3 4.09E 4 Ag 110m Ci 0 0 3.83 E-4 1.40E-4

'5n 113 Ci 0 0 1.58E-4 3.51 E-5

'5b 122 Ci 0 0 5.05 E-4 1.45 E-5

'5b-124 Ci 0 0 4.10 E-4 9.41 E-4

' 5 b- 12 5 Ci 0 0 7.92 E-3 4.5 5 E-3

'5b 126 Ci O' 0 3.78E-5 2.76E-5 Te-132 Ci 0 0 1.74E-4 9.80E-5 l-132 Ci 8.91E 3 1.45 E-3 1.87 E-4 2.37 E-4 1-133 Ci 1.88E 2 1.35E 3 3.11 E-4 0 1134 Ci 4.67E-3 3.15 E-4 8.24 E-6 0 1-135 Ci 1.39 E-2 0 6.00E-6 0 Cs-136 Ci 9.49E 5 0 8.99 E-5 0 Cs 138 Ci 4.44E-4 0 0 8.41 E-6 Ce-144 Ci 0 0 1.07 E-3 3.29E-4 Np 239 Ci 0 0 0 4.5 3 E-6 Page 11

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT

- January - June,1990 I Table 5 (continued) ,

LIQUID EFFLUENTS Continuous Mode Batch Mode First Second First Second 1Nuclides Released Unit Quarter Quarter Quarter Ouarter Unidentified l Cl l 0 l 0 l 0 l 0  ;

Total f or period (above) Ca. 6.20E 2 4.16 E -3 1.26E-1 4.65E-2

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Xenon 133 Cs 5.3 5 E-4 0 2.66E 1 6.79E 2 -

L. Xenon 135 Ci 1.46E 3 0 9.3 5 E-5 0 Other: Kr 85m Ci 0 0 5.85E-7 0

Kr 87 Ci 0 0 2.06E-6 0 Xe-131m Ci 0 0 1.2 5 E-3 1.50E 3 Xe-133m Ci 0 0 2.38E 3 2.40 E-4 '

Total entrained gases - Ci 1.99E 3 0 2,69 E- 1 6.96E-2 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 c{uantity of these isotopes comprised only 5.5E-3 % and 7.6E-3 % of the total curies released' (including tritium) during the first and second quarter, respectively.

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,e SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1990 Table 6 - i SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

- A. Solid Waste Shipped Offsite for Buriai or Disposal (Not irradiated fuel)

1. Type of waste Unit 6 month Est. Total Period Error,Bo
a. Spent resins, filter sludges, evaporator m3 1.51 E + 1

,. bottoms, etc. Ci 2.03E + 1 3.50E + 1 L

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b. Dry compressible waste, contaminated m' 5.71 E + 1 equip., etc. Ci 1.44E + 1 3.50E + 1
c. Irradiated components, control rods, etc. me O Ci 0 N/A

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d.Other (describe) m 3 0

Ci 0 N/A L 2. Estimate of major nuclide composition (by type of waste)

a. Fe-55 to 4.3 5 E + 1

'o 1.85E + 1 Co 60 ,

Cs 137 So 1.12 E + 1 Cs-134  % 9.82E + 0 Ni-63  % 9.44E + 0

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Co 58 90 2.40E + 0

b. Fe-55  % 4.77E + 1

% 2.23E + 1 Co 58 Co 60  % 7.89E + 0

% 6.22E + 0 Cs-134 Cs 137 So 5.33E + 0 Cr 51  % 3.80E + 0

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

All nuclides with concentrations above 2.0% are listed.

3. Solid Waste Disposition (6 month period)

Number of Shipments Mode of Transportation Destination .

28t Truck Barnwell, SC i tNote: 23 of these are partial shipments of DAW from waste processor to Barnwell, SC.

l l B. trradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination l

None N/A N/A Page 13

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V. C. SUMMER NUCLE AR STATION PROCESS CONTROL PROGRAM 1

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