ML20112H534

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Semiannual Effluent & Waste Disposal Rept,Jan-June,1984
ML20112H534
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 06/30/1984
From: Baehr W, Cox J, Koon A
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
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ML19269A916 List:
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NUDOCS 8501170179
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SOUTH CAROLI!A ELECTRIC AND GAS CCNANY VIRGIL C. S(NMER NUCLEAR STATION SD4IANN(AL EFFLEENT AND NASTE DISPOSAL REPORT January - June, 1984 August 28, 1984 bc

-g/qW//et/

Approved By:

~

/

/Date W. R. Baehr, Manager Corporate Health Physics and Environment 2.1 Programs Approved By:

[/.

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f.2 f. sy J. W. Cox, Jr., Aq$6c. Mgr.

Date Health Physics

[ ? T-F[

Approved By:

i, A. R. Foon, Jr., As

. Mgr.

Date Regulatory Coppl s

s R

SEMIANNUP1 EFFLUENT AND NASTE DISPOSAL REPORT January - June, 1984 Virgil C. Sumer Nuclear Station South Carolina Electric & Gas This report is being subnitted as a sumary of the quantities of radio-active liquid and gaseous effluents and solid waste released from the Virgil C.

Sumer Nuclear Station. Wis report satisfies the requirenents in Sections 6.9.1.8 and 6.9.1.9 of Technical Specifications and 10CFR50.36(a). Also included is an assessnent of radiation doses frm plant releases.

A brief discussion of the supplemental Information and Tables 1 through 5 is presented in Sections A through D.

An evaluation of the radiological inpact on man due to operation of the Virgil C. Stmner mclear Station is presented.in Section E.

Changes made to the Process Control Program are presented in Section F.

A.

Supplanental Information Regulatory limits for doses and maxinum permissible concentrations presented in Supplemental Infonnation are from the Virgil C.-Sunmer mclear Station 'lechnical Specifications. 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 frm ground level are sunmarized in Tables 1 and 2.

An elevated release pathway does not exist at Virgil C. Stmner Nuclear Station. Cunulative doses are discussed in Section E.

We errors for gaseous effluent totals are given as the square root of the sum of squares of counting errors and flow or volume measurement 1

A systematic error of 15% has been added to estimate tota. error.

errors.

C.

Liquid Effluents Liquid effluents are sumarized in Tables 3 and 4.

Estimated total errors are' expressed as in Section B~above.

D.

Solid hhste Shipnents Solid waste shipnents are sumarized in Table 5.

The thirteen ship-ments during this reporting period are described on the following page.

Page 1 L

e SEMIANNLAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1984 Virgil C. Sumer Nuclear Station South Carolina Electric & Gas DATE WPSPE TYPE 01-18-84 87 55-gallon drums and 4 B-25 boxes, Class A, dry active waste; Radioactive Material-LSA.

01-26-84 1 conical bottom HIC containing dewatered resins, Class A waste; Radioactive Material-LSA.

02-03-84 1 conical bottom HIC containing dewatered resins, Class A waste; Radioactive Material-LSA.

02-10-84 1 conical bottom HIC containing dewatered resins, Class A waste; Radioactive Material-LSA

~

02-14-84 1 foam-lined conical bottom HIC containing process filters, Class C waste; Radioactive Material-LSA 02-22-84 57 55-gallon drums and 5 B-25 boxes, Class A, dry active waste; Radioactive Material-LSA 03-02-84 1 conical bottom HIC containing dewatered resins, Class A waste; Radioactive Material-LSA 03-09-84 1 conical bottom HIC containing dewatered resins, Class A waste; Radioactive Material-LSA 03-16-84 1 conical bottom HIC containing dewatered resins, Class A waste; Radioactive Material-LSA 04-11-84 120 55-gallon druns and 2 B-25 boxes, Class A, dry active waste; Radioactive Material-LSA 05-10-84 3 carbon steel liners containing solidified evaporator bottcms, Class A waste; Radioactive Material-LSA 05-16-84 3 carbon steel liners containing solidified evaporator bottczns, Class A waste; Radioactive Material-LSA 06-21-84 1 foam-lined conical bottom HIC containing process filters, Class C waste; Radioactive Material-LSA te conservative method for curie content determination is based on contact dose rates measured around the perimeter of the respective packages.

We estimated total error is determined to be the sum of a 15% systematic error and a 20% photon response error for the detector used.

E.

Radiological Inpact on Man Potential doses to the maxinum exposed individual in the unrestricted area were calculated using. measured plant gaseous effluent and meteorologi-cal data in accordance with the Offsite Dose' Calculation Manual. Included '

in the source term were two (2) waste gas tatch releases, five (5) contain-ment purges and a continuous six month main plant vent release. h e total curies released are presented in Tables 1 and 2.

Air doses to an individual due to noble gas were 1.28E-3 and 1.59E-3 mrad for gama and beta respec-tively. We maximtzn organ dose attributed to the releases was 1.17E-4 mrem for the six month period.

Page 2 L__

SEMIANNCAL EFFLLENT AND WASTE DISPOSAL REPORT January - June, 1984 Virgil C. Sum er IMclear Station South Carolina Electric & Gas 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 each of the 286 liquid effluent intch releases and a continuous Turbine Building Surrp release. We total radioactivity released is described in Tables 3 and 4.

The total body dose to an egosed individual due to the radioactive liquid released was 5.07E 3 mr m.

The maxinum organ dose was 2.22E-l mren (GI-LLI).

Acctznulated doses due to gaseous and liquid effluents and respective Technical Specification limits are sumerized as follows:

First Quarter, 1984 Second Quarter, 1984 Percent Percent Tech Spec Section Limit Actual of Limit Actual of Limit 3.ll.2.2a,b 5 mrad gam a/qtr.

1.16E-3 mrad 2.32E-2 1.24E-4 mrad 2.48E-3 10 mrad gama/yr.

1.16E-2 1.28E-2*

3.ll.2.2a,b 10 mrad beta /qtr.

1.46E-3 mrad 1.4 6E-2 1.29E-4 mrad 1.29E-3 20 mrad beta /yr.

7.30E-3 7.9 4E-3*

3.ll.2.3a,b 7.5 mrem / organ /qtr. 8.46E-5 mrm 1.13E-3 3.25E-5 mren 4.33 & 4 15 mrem / organ /yr.

5.64E-4 7.81E-4*

3.ll.l.2a,b 1.5 mrem /qtr.

2.76&3 mrem 1.84E-1 2.31&3 mrem 1.54E-1 3.0 mrem /yr.

9.19E-2 1.69E-l*

3.ll.l.2a,b 5 mrem / organ /qtr.

1.65E-1 mren 3.31E+0 5.65&2 mren 1.13E+0 10 mrem / organ /yr.

1.65E+0 2.22E+0*

Includes contribution frm previous quarter.

Radiation doses from nearby uranium fuel cycle sources were not assessed. Technical Specifications, Section 3/4.11.4, page B 3/411-6 establishes a five (5) mile limit beyond which doses from nearby plants are insignificant. Were are no uranium fuel cycle plants within a five (5) mile radius of Virgil C. Stmner Itclear Station.

Radiation doses frcm radioactive effluents to workers at the Fairfield Hydro Station were determined to be 1.75E-4 and 2.17F 4 mrad for gama and beta, respectively.

Page 3

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SEMIANIEL EFFLLENT AIO WASTE DISPOSAL REPORT January - June, 1984 Virgil C. Sunmer Nuclear Station South Carolina Electric & Gas Dose rates and concentrations were below the limits specified in Swplemental Information, Section 2a, b and c during all the effluent releases.

It will be noted here that the 1983 annual etmulative doses fra radioactive effluents to workers at the Fairfield Hydro Station were incorrectly reported in the previous Semiannual Effluent and itsste Disposal Report. W e doses reported were to the maximum exposed individual, uncorrected for the X/Q for the Fairfield Hydro Plant. W e correct annual canulative doses for 1983 are 1.60E-3 and 1.53E-2 mrad for ganea and beta, i

respectively, i

F. - Process (bntrol Program te Virgil C. Sun 1mer Nuclear Station (VCSNS) Process Control Program (PCP) was modifled in April,1984 to enconpass 10 CFR 61 requirements and to reflect changes in the PCP employed by the VCSNS vendor - Chem Maclear

-Systems, Inc (CNSI). We previously approved VCSNS PCP (July 12, 1983) did Since CNSI's PCP is now supported by sufficient.

not canply with 10 CPR 61.

waste form testing.to comply with 10 CFR 61, South Carolina Electric & Gas mis Coupany (SCEEG) has revised the VCSNS PCP to match that of CMI.

updates the VCSNS PCP to full conpliance with 10 CFR 61 requirements and allows SCEEG to process waste in ccupliance with both the CIEI and VCSNS PCPs.

We 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. Since' almost all changes were made in a conservative manner and all changes were supported by the waste form testing required by 10 CPR 61, overall conformance is better denonstrated by the present revision (Rev. 3) than the previously approved one (Rev. 2).

See.

references 3.17, 3.18, and 3.19 of Attachment I for support of these statements.

Per Technical. Specification requirement 6.13.2.1.c, the PSRC has See

' reviewed and approved the revision (Rev. 3) enclosed as Attachment I.

page 1, the Procedure Developnent Form'- A,Section VII, for PSRC approval e

signature.

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SEMIANNCAL EFFLUENT AND WASTE DISPOSAL REPORT January - June, 1984 Virgil C. Sumer Nuclear Station South Carolina Electric & Gas Supplanental Infonnation 1.

Regulatory Limits:

a.

Fission and Activation Gases:

The air dose to an individual dm to noble gases released in gaseous effimnts shall be limited to less than or equal to 5 mead for gama radiation and 10 mrad for beta radiation during any calendar quarter and 10 mrad for ganna radiation and 20 mrad for beta radiation during any calendar year (Technical Specifications, Section 3.11.2.2),

b.

Iodines, Particulates (half-lives > 8 days) and Tritim:

We dose to an individual fran 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 calendar year (Technical Specifications, Section 3.11.2.3).

c.

Liquid Effimnts:

'Ibe dose or dose ccmnitment to an individual fran radioactive materials in liquid effluents released shall be limited to less than or equal to 1.5 mrsn to the total body and 5 mren to any organ during any calendar qmrter and 3 mrem to the total body and 10 mrem to any organ during any calendar year (Technical Specifications, Section 3.11.1.2).

2.

Maximum Permissible Cbncentrations:

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 squal to 500 mren/ year to the total body and less than or equal to 3000 mren/ year to the skin (Technimi specifications, Section 3.11.2.1),

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

We dose rate in unrestricted areas due to radioactive materials in effluents should be limited to less than or equal to 1500 mrem / year to any organ (Technical Specifications, Section 3.11.2.1).

Page 5

SEMIANNCAL EFFLUENT AND WASTE DISPOSAL REPORT January - June, 1984 Virgil C. Sumer Nuclear Station South Carolina Electric & Gas Supplemental Information

+

c.

Liquid Effluents:

The concentration of radioactive materials released fran the site shall be limited to the concentrations specified in 10 CFR 20, Appendix B, Table II, Colum 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2E-4 uC1/ml total.

activity (Technical Specifications, Section 3.11.1.1).

3.

Average Energy:

Not Applicable 4.

Measurements and Approximations of Total Radioactivity:

a.

Fission and activation gases: Gama spectrometry (GeLi or HPGe) b.

Iodines: Gama spectronetry (GeLi or HPGe) c.

Particulates: Gama spectrometry (GeLi or HPGe), beta proportional counting, alpha proportional co2nting d.

Tritiun: Liquid scintillation e.

Liquid effluents: Gama spectrcmetry (GeLi or HPGe), liquid scintillation (H-3), beta proportional counting, alpha proportional counting 5.

mtch Releases:

a.

Liquid:

1.

Number of batch releases:

134 for first quarter,1984 152 for second quarter,1984 2.

Total time period for batch releases:

7306 min for first quarter,1984 8516 min. for second quarter,1984 Page 6

SIMIANNUPL EFFLIENT AND WASTE DISPOSAL REPORT January - June, 1984 Virgil C. Sumer Nuclear Station South Carolina Electric & Gas Supplemental Information 3.

Maxinun time period for a batch release:

101 min for first quarter,1984 87 min, for second quarter,1984 4.

Average time period for batch releases:

55 min. for first quarter,1984 56 min. for second quarter,1984 5.

Minimtzn time period for a batch release:

15 min. for first quarter,1984 14 min, for second quarter,1984 6.

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

2.55E+6 gpn for first quarter,1984 4.14E+6 gpn for second quarter,1984 b.

Gaseous:

1.

NLmber of batch releases: 7 2.

Total time period for intch releases:

5698 min.

3.

Maxinum time period for a batch release:

1423 min.

4.

Average time period for a tntch release:

814 min.

5.

Mininum time period for a batch release:

2 min.

6.

Abnormal Releases:

a.

Liquid:

1.

NLmber of releases: NONE 2.

Total activity released: ME Page 7

i l

SEMIANN(AL EFFLIENT AND WASTE DISPOSAL REPORT January - June, 1984 Virgil C. Summer Nuclear Station South Carolina Electric & Gas b.

Gaseous:

1.

Mmber of releases: EtE 2.

Total activity released: TONE I

1

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1 Page 8

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SEMIANNERL EFFLEENT AND WASTE DISPOSAL REPORT January - June,1984 Table 1 GASEOUS EFFL(ENTS-SCM4ATION OF ALL RELEASES First Second Est. Total Quarter Quarter Error, %

A.

Fission & activation gases

l. Total release Ci 4.25E+0 4.26E-1 1.91E+1 l
2. Average release rate for period uCi/sec 5.40E-1 5.41E-2
3. Percent of technical specification limit B. Iodines
1. Total iodine-131 Ci 0

1.88E-6 3.38E+1 l

2. Average release rate for period uCi/sec 0

2.39E-7_

3. Percent of technical specification limit C. Particulates
l. Particulates with half-lives > 8 days Ci 0

2.08E-6 5.28E+1 l

2. Average release rate for period uCi/sec 0

2.65E-7

3. Percent of technical specification limit
4. Gross alpha radioactivity Ci 0

0 D. Tritiun Ci 1.60E-1 0

2.99E+1 l

l. Total release

__ 2. Average release rate for period uCi/sec 2.04E-2 0

3. Percent of technical specification limit Calculated as a percent of dose limits found in Supplemental Inforation, Section la.

First quarter values were 2.32E-2% and 1.16E-2% of the quarterly and etmulative annual gama dose limits, respectively and 1.46E-2% and 7.30E-3% of the quarterly and cumilative annual beta dose limits, respectively. Second quarter values were 2.48E-3%

and 1.28E-2% of the quarterly and ctznulative annual gama dose limits, respectively, and 1.29E-3% and 7.94E-3% of the quarterly and ctmulative annual beta dose limits, respectively.

    • Calculated as a percent of dose limits found in Supplemental Information, Secti'on lb.

We sun of these values for first quarter was 1.13E-3% and 5.64E-4% of the quarterly and cumulative annual organ dose limits, respectively. We stun of these values for second quarter was 4.33E-4% and 7.81E-4% of the quarterly and ctznulative annual organ dose limits, respectively.

Page 9

i SEMIANNLAL EFFLUENT AND WASTE DISPOSAL REPORP January - June, 1984 Table 2 GASEOUS EFFLIENTS-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 0

0 krypton-85m Ci 0

0 0

0 krypton-87 Ci 0

0 0

2.63E-3

~

krypton-88 Ci 0

0 0

1.40E-2 xenon-133 Ci 7.00E-1 0

5.86E-1 2.18E-1 xenon-135 Ci 2.77E+0 0

4.63E-2 1.75E-1 xenon-135m Ci 0

0 0

0 xenon-138 Ci 0

0 0

0 Others: Xe-133m Ci 1.28E-2 0

1.96E-2 6.30E-3 Ar-41 Ci 4.43E-2 0

6.81E-2 9.89E-3 unidentified Ci 0

0 0

0 Total for period Ci 3.53E+0 0

7.20E-1 ! 4.26E-1 2.

Iodines iodine-131 Ci 0

1.88E-6 0

0 iodine-133 Ci 0

0 0

0 iodine-135 Ci 0

0 0

0 Total for period Ci 0

1.88E-6 0

0 3.

Particulates strontitzn-89 Ci 0

0 0

0 strontitzn-90 Ci 0

0 0

0 cesitun-134 Ci 0

0 0

0 cesitzn-137 Ci 0

0 0

0 baritzn-lanthantun-140 Ci 0

0 0

0 Otherst Co-58 Ci 0

2.08E-6 0

0 unidentified Ci 0

0-0 0

Total for period Ci 0

2.08E-6 0

0 Page 10

SEMIANNUP1 EFFLUENT AND NPSfE DISPOSAL REPORT January - Jtine,1984 Table 3 LIQUID EFFLLENTS-Sl1HATION OF ALL RELEASES First Second Est. Total Unit Quarter Quarter Error, %

A.

Fission & activation products

1. Total release (not including tritium, Ci 1.45E+0 2.08E+0 1.93E+1 qases, alpha)
2. Average diluted concentration during period uCi/ml 4.70E-9 6.68E-9
3. Percent of applicable limit B. Tritiun Ci 6.llE+1 4.38E+1 1.80E+1 l
1. Total release
2. Average diluted concentration during period uCi/ml 1.98E-7 1.41E-7
3. Percent of applicable limit C. Dissolved and entrained gases Ci 6.64E-3 1.93E-3 3.82E+1 l
l. Total release
2. Average diluted concentration during period uCi/mi 2.15E-11 6.19E-12
3. Percent of applicable limit D. Gross alpha radioactivity L
1. Total release l

Ci 1 0

l 0

l 3.81E+1 l E. Volume of waste released (prior to

-dilution) liters 4.80E+7 4.44E+7 3.00E+0 F. Volume of dilution water used during liters 3.08E+11 3.llE+11 4.30E+0 period o see following page.

Page 11

SEMIANN(AL EFFLUENT AND WASTE DISPOSAL REPORT January - June, 1984 Table 3 LIQUID EFLLENTS-StMRTION OF ALL RELEASES Calculated as a percent of dose limits found in Supplemental Infonnation, Section Ic.

The stan of these values for first quarter was 1.84E-l% and 9.19E-2% of the respective quarterly and ctmulative annual whole body dose limits and 3.31% and 1.65% of the The stzn of these valtes respective quarterly and cumulative annual organ dose limits.

for the second quarter was 1.54E-l% and 1.69% of the respective quarterly and ctmulative annual whole body dose limits and 1.13% and 2.22% of the respective Ibse to the GI-LLI was tiie niost quarterly and cimilative annual organ dose limits.

limiting organ dose for first and second quarters.

Page 12

SEMIANNCAL EFFLUENT AND WASTE DISPOSAL REPORT January - June, 1984 Table 4 LIQUID EFFLtENTS Continuous Mode Batch Mode First Second First Second Nuclides Released i Unit Quarter Quarter Quarter Quarter strontian-89 Ci 0

0 9.85E-5 2.04E-4 strontian-90 Ci 0

0 0

0 cesiun-134 Ci 0

0 4.55E-5 0

cesium-137 Ci 0

0 0

0 iodine-131 Ci 0

0 1.10E-4 1.56E-3 cobalt-58 Ci 0

0 9.33E-1 1.59E+0 cobalt-60 Ci 0

0 1.41E-1 2.89E-1 iron-59 Ci 0

0 2.75E-2 6.71E-3 zinc-65 Ci 0

0 2.27E-3 0

manganese-54 Ci 0

0 8.14E-2 4.62E-2 chranium-51 Ci 0

0 1.82E-1 4.60E-2 zirconium-niobiun-95 Ci 0

0 6.91E-2 2.21E-2 molybdenum-99 Ci 0

0 0

1.42E-4 technetian-99m Ci 0

0 9.13E-5 9.72E-4 barium-lanthanum-140 Ci 0

0 1.33E-4 0

cerium-141 Ci 0

0 0

0 Other: Na-24 Ci 0

1.99E-2 3.89E-3 2.34E-2

  • Sc-46 Ci 0

0 5.94E-5 0

Fe-55 Ci 0

0 2.53E-3 1.42E-2 Mn-56 Ci 0

0 3.97E-6 1.68E-5

  • Ni-56 Ci 0

0 3.90E-6 0

  • Co-57 Ci 0

0 2.00E-3 3.20E-3 Rb-88 Ci 0

0 0

2.04E-4

  • Nb-97 Ci 0

0 1.17E-5 0

Zr-97 Ci 0

0 0

2.07E-5 Ag-110m Ci 0

0 0

1.41E-6

  • Sn-ll3 Ci 0

0 9.43E-4 8.82E-5

  • Sb-124 Ci 0

0 1.13E-3 3.14E-3

  • Sb-125 Ci 0

0 3.37E-5 8.20E-5 I-132 Ci 0

1.85E-3 0

8.31E-4 I-133 Ci 0

2.50E-3 4.43E-4 3.83E-3 I-135 Ci 0

0 4.05E-5 2.17E-4 Ce-144 Ci 0

0 9.43E-5 2.30E-4

  • Hf-181 Ci 0

0 0

7.24E-6 W-187 Ci 0

0 0

5.94E-4 t@-239 Ci 0

0 0

7.12E-5 l

Total for period (above) l Ci l 0

l 2.42E-2l 1.45E+0l 2.06E+0 l Page 13

7 SEMIANNLRL EFFLUENT AND WASTE DISPOSAL REPORT January - June, 1984 Table 4 (Continued)

LIQUID EFFLtENTS Continuous Mode Batch Mxle First Second First Second -

Nuclides Released Unit Quarter Quarter Quarter Quarter xenon-133 Ci 0

0 4.78E-3 4.62E-4 xenon-135 Ci 0

1.41E-4 1.57E-3 1.32E-3 Other: Kr-85m Ci 0

0 8.66E-6 0

Kr-88 Ci 0

0 2.76E-4 0

t Tritium not included. See Table 3 for tritium numbers.

Dose factors for these trace radionuclides are not included in the ODO4 or O

Regulatory Guide 1.109, consequently the cunulative dose attributed to these isotopes is not reported. 'Ihe quantity of these isotopes emprised only 2.88E-lt and 3.13E-l% of the total curies released during first and second quarter, respectively.

Page 14

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1984 Table 5 SG.ID WASTE AND IRRADIATED FUEL SHIPENTS A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)

Unit 6-month Est. Total

1. Type of waste Period Error, %

mJ 6.50E+1

a. Spent resins, f11ter sludges, evaporator Ci 4.03E+1-3.50E+1 bottm s, etc.
b. Dry ccmpressible waste, contaminated mJ 8.66E+1 Ci 9.59E-1 3.50E+1 equip., etc.
c. Irradiated ccmponents, control mJ 0

Ci 0

0 rods, etc.

d. Other (describe) Process Filters mJ 4.76E+0 Ci 2.90E+1 3.50E+1
2. Estimate of major nuclide conposition (by type of waste)*
a. Co-58 5.73E+1 Co-60 1.10E+1 H-3 9.12E+0 Cr-51, Mn-54, te>-95, Ni-63, Fe-55, Zr-95 1.86E+1 C-14, Fe-59, Be-7, I-131 3.23E+0
b. Co-58 5.llE+1 Cr-51 2.34E+1 t&>-95, Co-60, Zr-95, Mn-54, Fe-59 2.07E+1 Fe-55, Ce-144, C-14, Ni-63 2.75E+0 0
c. NDE
d. La-140 3.10E+1 Co-58 2.62E+1 Fe-55 1.21E+1 Cr-51 1.15E+1 Ni-63, Co-60, Nb-95, Zr-95, Mn-54 1.48E+1 Ni-56, Fe-59, W-187, Ba-140, C-14, Ce-139 4.04E+0 All nuclides are listed in descending order by activity level.

All nuclides with concentrations above 0.25% are listed.

3. Solid waste Disposition bbmber of Shiptents Pbde of Transportation Destination 13 Truck Barnwell, S.C.

B. Irradiated Fuel Shipnents (Disposition)

Ntsnber of Shipnents Mode of Transportation Destination NDE Page 15

ATTACHbENP I V. C. SCMER NUCLEAR STATION PROCESS CONTROL PROGRAM

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