ML20237L815

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Semiannual Effluent & Waste Disposal Rept for Jan-June 1987
ML20237L815
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 06/30/1987
From: Baehr W, Cox J, Gowdy G
SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML19292H705 List:
References
NUDOCS 8708280267
Download: ML20237L815 (17)
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Text

m SEMIANNUAL EFFLUENT.AND WASTE DISPOSAL REPORT l

FOR THE OPERATING PERIOD January 1,1987 - June 30,1987 1 i

August 21,1987 N

T - .- - .

l

-%*g>y<

%_. m j V. C. SUMMER NUCLEAR STATION l SOUTH CAROLINA ELECTRIC AND GAS COMPANY i

Prepared by:

l eu '/

'G.M 46wdy,. ,

Staff Health Ph sicist Reviewed and approved by: Reviewed an approved by:

?bb W. R. B'aehr, Manager J. W

. ' V' Mr x, Jr., Aisoc.phnager Corporate Health Physics Heat Physics and Environmental Programs 8708290267 870824 PDR ADOCK 05000395 R PDR h

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT

- January - June,1987 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 requirements in Sections 6.9.1.8 and 6.9.19 of Technical Specifications and 10CFR50.36(a). Also included is an assessment of radiation doses from plant releases.

A brief discussion of the Supplemental Information and Tables 1 and 3 through 7 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 l presented in Section E and Table 2. Changes made to the Process Control Program are presented in Section F. Corrections to previous reports are given in Section G.

Abnormal releases are detailed in Section H.

A. SupplementalInformation 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 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 3 and 4. 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 rneasurement errors. A systematic error of 15% has been added to estimate total error.

C. Liquid Effluents Liquid effluents are summarized in Tables 5 and 6. Estimated total .l errors are expressed as in Section B above.- I D. Solid V/aste Shipments Solid waste shipments are summarized in Table 7. The sixteen (16) j shipments during this reporting period are described on the following page in Table 1.

i SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1987 Virgil C. Summer Nuclear Station South Carolina Electric & Gas a

Table 1 SOLID WASTE SHIPMENTS l

l DATE WASTE TYPE  !

l l

02-13-87 1 (one) 8-120B cask containing a 6-80 high integrity container (HIC)  ;

with process filters, Class C waste; Radioactive Material-LSA l 02-25-87 1 (one)14-195 carbon steel liner cornaining (cement) solidified evaporator bottoms and 6 (six) B-25 boxes with dry active waste l (DAW), Class A waste; Radioactive Material-LSA j 03-14-87 1 (one) 8-120B cask containing an 8-120 HIC with dewatered resins, Class A waste; Radioactive Material-LSA t 03-18 87 12(twelve) B 25 boxes containing DAW, Class A waste; Radioactive Material-LSA  !

03-20-87 1 (one) 8-120B cask containing an 8-120 HIC with dewatered resins, Class A waste; Radioactive Material-LSA 04-08-87 2(two)14-195 carbon steel liners containing (cement) solidified evaporator bottoms and 3 (three) B-25 boxes with DAW, Class A ,

waste; Radioactive Material-LSA l C4-10-87 2 (two)14-195 carbon steel liners containing (cement) solidified evaporator bottoms and 3 (three) B-25 boxes with DAW, Class A waste; Radioactive Material-LSA 04-14-87 2 (two)14-195 carbon steel liners containing (cement) solidified evaporator bottoms and 3 (three) B-25 boxes with DAW, Class A waste; Radioactive Material-LSA i

04-16-87 9 (nine) demineralized vessels,1 (one)14-195 carbon steel liner containing (cement) solidified evaporator bottoms and 4 (four) B-25 boxes with DAW, Class A waste; Radioactive Material-LSA 04-24-87 1 (one) 8-120B cask containing an 8-120 HIC with dewatered resins, J Class C waste; Radioactive Material-LSA l 05-05-87 1 (one)14-195 carbon steel liner containing dewatered powdex resin and 2 (two) B-25 boxes with DAW, Class A waste; Radioactive l Material-LSA '

1 l

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1987 ]

Virgil C. Summer Nuclear Station South Carolina Electric & Gas ]

Table 1 (continued) ']

l DATE WASTE TYPE 05-12-87 1 (one) 6-80-2 cask containing a 6-80 HIC with DAW, Class A waste; Radioactive Material-LSA 05-19-87 14 (fourteen) B-25 boxes containing DAW, Class A waste; )

Radioactive Material-LSA i 05-21-87 1 (one) 6-80-2 cask containing a 6-80 HIC with process filters, Class C l waste; Radioactive Material-LSA. )

05-27-87 16 (sixteen) demineralized vessels and 9 (nine) B-25 boxes with DAW, i Class A waste; Radioactive Material-LSA l 06 04-87 6 (six) demineralized vessels and 9 (nine) B-25 boxes with DAW, Class A waste; Radioactive Material-LSA The conservative method for curie content determination is based on contact dose rates measured around the perimeter of the respective packages. The 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. RadiologicalImpact on Man l

Potential doses to the maximum exposed individual in the l 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 eleven (11) waste gas batch releases,12.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> of Reactorhours Buildingof purge Reactor Building releases (purge 36-inch line), releases (6-inchsix and a continuous line),1515 month main plant vent release. Doses are summarized in Table 2. The total j curies released are presented in Tables 3 and 4. Air doses to an individual due to noble gases were 3.99E-2 and 1.14E-1 mrad for gamma and beta re-spectively. The maximum organ dose attributed to the releases was 8.28E-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 each of the 246 liqu'id effluent batch releases from Waste Monitor Tanks, Steam Gen-erator Blowdowns, Condensate Demineralized Backwash, and a continuous Turbine Building Sump release. Also included was one abnormal release detailed in Section H. Doses are summarized in Table 2. The total radioactivity released is described in Tables 5 and 6. The total body dose to the maximally exposed individual due to the radioactive liquid released was 4.38E-2 mrem. The maximum organ dose was 5.57E-2 mrem to the Liver.

Page 3 -

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT '

Jenuary - June,1987 Virgil C. Summer Nudear Station South Carolina Electric & Gas i

Table 2 GASEOUS AND LIQUID DOSES

~

First Quarter,1987 Second Quarter,1987_

Tech Spec Gaseous Limits Section Perc,en,t Percen,t Dose _

Dose _ of Limit of Limit 3.11.2.2a,b 5 mrad gamma /qtr. 3.95E-2 mrad 7.90E-1 4.51 E-4 mrad 9.03 E-3 10 mrad gamma /yr. 3.95E-1 3.99 E-1 *

(January-June total gamma airdose: 3.99E-2 mrad) 3.11.2.2a,b 10 mrad beta /qtr. 1.13E-1 mrad 1.13 E + 0 1.25E-3 mrad 1.25E-2 20 mrad beta /yr. 5.65E-1 5.69 E-1 *

(January-June total beta air dose: 1.14E-1 mrad) l 3.11.2.3a,b 7.5 mrem / organ /qtr. 7.65E-3 mrem 1.02 E-1 6.37E-4 mrem 8.49E-3 1

15 mrem / organ /yr. 5.10E-2 5.52 E-2 *

(January-June maximum exposed organ dose: 8.28E-3 mrem)

Liquid Limits 3.11.1.2a,b 1.5 mrem /qtr. 2.98E-2 mrem 1.99E + 0 1.40E-2 mrem 9.33E-1 3.0 mrem /yr. 9.95 E-1 1.46E + 0*

(January-June whole body dose: 4.38E-2 mrem) 3.11.1.2 a,b 5 mrem / organ /qtr. 3.83E-2 mrem 7.65E-1 1.75E-2 mrem 3.50E-1 10 mrem / organ /yr. 3.83 E-1 5.57E .1 *

(January-June maximum exposed organ dose: 5.57E-2 mrem)

  • Includes contribution from previous quarters.

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 FairfieldHydro Station were determined to be 5.45E-3 and 1.56E-2 mrad for gamma and beta, respectively, l

l Page 4 i

SEMlANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1987 Virgil C. Summer Nuclear Station South Carolina Electric & Gas 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. 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 five (5) times during the affected six month period. Revision 5, Change H (1/16/87) and Revision 6 (3/26/87) involved updating Attachment 11 to the PCP to reflect thanges to the Chem-Nuclear Systems,Inc. (CNSI) procedure FO-OP-023 providing operating guidelines for use of bead resin / activated carbon dewatering system for 14-195 or smaller  ;

l liners. Revision 6 also involved combining changes A-H of Revision 5 into the main body of the PCP. Revision 6, Change A (4/8/87) provided for adding CNSI procedure FO-AD-004 (Rev. G), " Operating Guidelines for Use of Fiberglass Reinforced Plastic High Integrity Containers," to the PCP. Revision 6, Change B (4/8/87) involved replacing CNSI procedure FO-OP-004 attached -

to the PCP with new CNSI procedure FO-OP-025, " Dewatering Procedure for CNSI 24 inch Diameter Pressure Vessels". Finally, Revision 6, Change C (6/11/87) provided for updating Attachment Vill to the PCP to reflect I changes in CNSI operating procedure FO-AD-004. The overall conformance of the solidified waste product to existing criteria for solid wastes has not j been adversely affected by the changes incorporated in the VC5NS PCP. Per j Technical Specification requirement 6.13.2.1.c, the PSRC has reviewed and i approved the revisions which are enclosed as Attachment 1. See the changes )

i and each Procedure Development Form - A, Section Vll, for the PSRC  ;

approval signatures. ,

G. Corrections to Previous Reports in the last Semiannual Effluent and Waste Disposal Report (July-December,1986), two numbers were reported incorrectly. In Table 3, page 9, the fourth quarter fission and activation gas total release was 1.11E + 1 Ci, not 1.74E + 1 Ci. In Table 5, page 11, the fourth quarter volume of waste  !

released (prior to dilution) should be 7.60E + 7 liters instead of the reported 6.52E + 8 liters. No other sections of the report are affected by these changes.

H. Abnormal Releases  !

i in February,1987 a fire service deluge valve opened allowing approximately 17,000 gallons of water to pour through a slightly activated i charcoal plenum. This water was mainly collected in the Auxikary Building sump, however, approximately 2500 gallons escaped under a rollup door to - l the adjacent ground. Subsequently analyses of soil in the area and

~

sediments and liquids contained in the nearest yard drain and its outfalls were aerformed. No radioactive material was detected in the yard drain or outsic e the protected area. Some slight soil contamination was noted in the Page 5 w___.--___--______________-_______.___-__-__

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1987 Virgil C. Summer Nuclear Station South Carolina Electric & Gas-area adjacent to the door. Analysis of free standing water around the rollup -

door indicated levels of Co-58 and Co-60 of 1.5E-8 and 3.5E-8 pCi/ml, respectively. Thus only about 0.47 pCi of total activity can conservatively be assumed released during this event. Assuming all 2500 gallons were instantaneously introduced into the Broad River and the river water drunk -

by the maximum exposed individual at the.1 mile exclusion boundary, insignificant doses to the public are found. Doses to the public were calculated to be 5.9E-10 mrem .whole body and 5.0E-9 mrem to the maxirum organ of the maximum exposed individual.

4 l

j l

Page 6 i

. s. l

____._______1_______________________ '

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1987 -

Virgil C. Summer Nuclear Station South Carolina Electric & Gas SupplementalInformation

1. Regulatory Limits:
a. Fission and Acti'vation 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 (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 guarter 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).

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 e skin (Technical Specifications, Section 3.11.2.1) qual to 3000 mrem / year to the

b. lodines, Particulate (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 org an (Technical Specifications, Section 3.11.2.1). ,

I l

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SEM! ANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1987 Virgil C. Summer Nuclear Station 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, j Table 11, Column 2 for radionuclides other than dissolved or entrained noble l gases. For dissolved or entrained noble gases, the concentration shall be l limited to 2E-4 uCi/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: Gamma spectrometry [Ge(Li) or HPGe]
b. lodines: Gamma spectrometry [Ge(Li) or HPGe]
c. Particulate: Gamma spectrometry [Ge(Li) or HPGe], beta propor. .i tional counting, alpha proportional counting
d. Tritium: Liquid scintillation j
e. Liquid effluents: Gamma spectrometry [Ge(Li) or HPGe], lic{uid scintillation (H-3), beta proportional counting, i alpha proportional counting l
5. Batch Releases:
a. Liquid:
1. Number of batch releases: )

94 for first quarter,1987 152 for second quarter,1987

2. Total time period for batch releases:

5307 min. for first quarter,1987 9606 min. for second quarter,1987 j

3. Maximum time period for a batch release:

i 108 min. for first quarter,1987 840 min. for second quarter,1987 Page 8 i

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1987 Virgil C. Summer Nuclear Station South Carolina Electric & Gas Supplementalinformation

4. Average time period for batch releases:

56 min. for first quarter,1987 63 min. for second quarter,1987

5. Minimum time period for a batch release:

20 min. for first quarter,1987 35 min. for second quarter,1987

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

3.12E + 6 gpm for first quarter,1987 3.41E + 6 gpm for second quarter,1987

b. Gaseous:
1. Number of batch releases: 16
2. Total time period for batch releases: 1.92E + 4 min.
3. Maximum time period for a batch release: 4.04E + 3 min.
4. Average time period for a batch release: 1.20E + 3 min.
5. Minimum time period for a batch release: 1E + 0 min.
6. Abnormal Releases:
a. Liquid:
1. Number of releases: 1
2. Total activity released: 4.7E-1 pCi
b. Gaseous:
1. Numberof releases: 0
2. Total activity released: 0 Page 9

l SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1987 Table 3 GASEOUS EFFLUENTS SUMMATION OF ALL RELEASES I

l First Second Est. Total Error, %

Quarter Quarter A. Fission & activation gases

1. Total release Ci 6.22E + 2 6.47E + 0 1.82E + 1
2. Average release rate for period uCi/sec 8.01 E + 1 8.23 E-1
3. Percent of technical specification limit *
  • B. lodines
1. Total iodine-131 Ci 4.23 E-4 2.55E-5 2.09E + 1
2. Average release rate for period uCi/sec 5.44E-5 3.2 5 E-6
3. Percent of technical specification limit ** **

C. Particulate

1. Particulate with half lives > 8 days Ci 1.30 E-4 1.23 E-4 2.10E + 1
2. Average release rate for period uCi/sec 1.67E 5 1.56E-5
3. Percent of technical specification limit ** **
4. Gross alpha radioactivity Ci 0 0 i l

D. Tritium

1. Total release Ci 4.63E-1 7.97 E-2 7.77E + 1
2. Average release rate for period uCi/sec 5.96E-2 1.01 E-2
3. Percent of technical specification limit  % ** **

Calculated as a percent of dose limits found in SupplementalInformation, Section la. First quarter values were 7.90E-1% and 3.95E-1% of the quarterly and cumulative annual gamma dose limits, respectively and 1.13E% and 5.65E-1% of the quarterly and cumulative annual beta dose limits, respectively. Second quarter values were 9.03E 3% and 3.99E-1% i of the quarterly and cumulative annual gamma dose limits, respectively, and 1.25E-2% and 5.69E-1% of the quart ( tly 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 1.02E-1% and 5.10E 2% of the quarterly and cumulative annual organ dose limits, respectively. The sum of these values for the second quarter was 8.49E-3% and 5.52E-2% of the quarterly and cumulative annual organ dose limits, respectively.

a e 10

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT Januaiy - June,1987 Table 4 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES Continuous Mode Batch Mode First Second First Second Nuclides Released Unit Quarter Quarter Quarter Quarter

1. Fission gases .'

Kt v pton-85 Ci 0 0 1.06E + 0 2.31 E-1 Krypton-85m Ci 0 0 7.64E-2 0 Krypton-87 Ci 0 0 4.05 E-3 0 Krypton-88 Ci 0 0 3.95E-2 0 Xenon-133 Ci 3.61 E + 2 5.92E + 0 2.43E + 2 8.54E-3 Xenon-135 Ci 9.52 E + 0 3.06E-1 7.70E-1 1.11 E-4 Xenon-135m Ci 0 0 0 0 Xenon-138 Ci 0 0 0 0 Others: Argon-41 Ci 0 0 1.16E-2 0 Xenon-131m Ci 8.80E-1 0 3.60E + 0 5.73 E-4 Xenon-133n1 Ci 2.05E-1 0 1.76E + 0 2.30 E-4 Unidentified Ci 0 0 0 0 Total for period Ci 3.72E + 2 6.23E + 0 2.50E + 2 2.41 E-1

2. todines lodint-131 C 4.2 2 E-4 2.55E-5 5.5 7 E-7 0 lodine-132 Ci 1.5 5 E-4 0 0 0 lodine-133 Ci 4.72 E-5 0 0 0 lodine-135 Ci 1.06 E-4 0 0 0 Total for period Ci 7.30E-4 2.55E-5 5.57E-7 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: Cr-51 Ci 1.40 E-5 2.44E-5 0 0 Mn-54 Ci 3.26E-7 1.47 E-6 0 0 Co-58 Ci 9.92E-5 8.16 E-5 0 0 Co-60 Ci 1.47 E-5 1.39 E-5 0 0 N b-95 Ci 1.56 E-6 1.34E-6 0 0 Unidentified Ci 0 0 0 0 Total for period Ci 1.3 0 E-4 1.23 E-4 0 0 Page 11

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1987 Table 5 l 1

LIQU!D EFFLUENTS-SUMMATION OF ALL RELEASES First Second Est. Total A. Fission & activation products

~

1. Total release (not including tritium, gases, Ci 1.39E-1 2.26E-1 1.80E + 1 alpha)
2. Average diluted concentration during uCi/ml 3.01 E-10 6.78E-10 penod *
  • l
3. Percent of applicable limit  %

B. Tritium 1.Totai release Ci 1.76E + 2 1.61 E + 2 1.83E + 1

2. Average diluted concentration during uCi/mi 3.81 E-7 4.83 E-7 penod
3. Percent of applicable limit  %

C. Dissolved and entrained gases

1. Total release Ci 1.01 E-2 6.31 E-4 3.16E + 1
2. Average diluted concentration during uCi/ml 2.19E-11 1.89E-12 penod
3. Percent of applicable limit  %

D. Gross alpha radioactivity

1. Total release Ci 0 l 0 N/A E. Volume of waste released (prior to dilution liters 6.176 + 7 2.72 E + 7 3.00E + 0 l

l F Volume of dilution water used during period liters 4.62E + 11 3.33E + 11 4.30E + 0 See following page.

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5EMIANNUAL EFFLUENT AMD WASTE DISPOSAL REPORT

-l January - June,1987 l Table 5 LIQUID 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 1.99% and 9.95E-1% of the respective quarterly and cumulative annual whole body dose limits and 7.65E-1% and 3.83E-1% of the respective quarterly and cumulative annual organ dose limits. The sum of these values for -

the second quarter was 9.33E-1% and 1.46% of the respective quarterly and cumulative annual whole body dose limits and 3.50E-1% and 5.57E-1% of the respective quarterly and j cumulative annual organ dose limits. Dose to the Liver was the most limiting organ dose -

for the first and second quarters of 1987.

Page 13

l SEMlANNUAL EFFLUENT AND WASTE DISPOSAL REPORT l January - June,1987 l Table 6 LIQUID EFFLUENTS l Continuous Mode Batch Mode First Second First Second a tNuclides Released Unit Quarter Quarter _

Quarter Quarter 1 Strontium-89 Ci 0 0 0 0 Strontium-90 Ci 0 0 0 0 1 Cesium-134 Ci 8.50 E-4 2.09 E-4 1.11 E-2 5.20E-3 Cesium-137 Ci 5.50 E-4 4.55 E-5 8.54E-3 4.2 8 E-3 lodine-131 Ci 2.79E-3 0 9.29 E-4 i 0 4 Cobalt-58 C1 2.14 E-5 2. 7 9 E-5 4.54 E-2 1.42 E-1 Cobalt-60 Ci 0 0 2.85 E-2 3.62 E-2 Iron-59 Ci 0 0 1.61 E-4 3.84 E-4 Zinc-65 Ci 0 0 6.93 E-5 1.67 E-4 Manganese-54 Ci 0 0 3.72 E-3 4.17 E-3 J

Chromium-51 Ci 0 0 6.51 E-3 1.45 E-2 j Zirconium-Niobium-95 Ci 0 0 9.3 5 E-4 4.9 5 E-3 ,

Molybdenum-99 Ci 0 0 0 0 Technetium-99m Ci 7.21 E-7 0 5.46E-5 7.19 E-7  !

Barium-Lanth.-140 Ci 0 0 6.65 E-6 0  !

Cerium-141 Ci 0 0 0 0 l

Other: Na-24 Ci 2./8E-3 0 4.13 E-4 3.49 E-6 Fe-55 Ci 0 0 1.3 5 E-2 4.41 E-3 ha n-56 Ci 0 0 0 1.04E-6

  • Co-5 7 Ci 0 0 1.24E-4 3.7 7 E-4 l Zr-97 Ci 0 0 0 1.14 E-6 l Ru-103 Ci 0 0 0 2.19 E-6 I Ru-105 Ci 0 0 0 7.05 E-6 Ag-110m Ci 0 0 9.52 E-6 3.64E-4
  • Sn-113 Ci 0 0 1.36 E-5 7.18 E-5
  • Sb-124 Ci 0 0 2.76 E-4 2.74E-3
  • S b-12 5 Ci 0 0 2.2 7 E-3 6.38E-3 1-132 Ci 1.61 E-3 0 1.09E-5 0 1-133 Ci 3.28E-3 7.3 5 E-5 3.53 E-4 0 1-134 Ci 1.37 E-3 0 4.68E-6 0 1-135 Ci 1.99 E-3 0 9.3 7 E-5 0 Cs-136 Ci 1.05 E-6 0 2.95 E-5 3.59E-6 Cs-138 Ci 7.04E-4 0 0 0 Ce-144 Ci 0 0 1.09E-5 0 VV-18 7 Ci 0 0 0 5.85 E-6 l Total for period (above) l Ci l 1.59 E-2 l 3.56 E-4 l 1.23 E-1 l 2.26E-1 l Page 14

SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1987 Table 6 (continued)

LIQUID EFFLUENTS Continuous Mode Batch Mode l First Second First Second tNuclides Released Unit Quarter Quarter Cr arter Quarter Xenon-133 Ci 4.00 E-3 0 5.33 E-3 6.30 E-4 Xenon-135 Ci 7.55 E-4 0 5.32 E-5 1.26 E-6 Other: Kr-85m Ci 0 0 6.56 E-6 0 i 0 1.52 E-6 0 Kr-87 Ci 0

)

Total entrained gases Ci 4.76E-3 0 5.39 E-3 6.31 E-4 t Tritium not included. See Table 5 for tritium numbers. l

  • Dose factors for these trace radionuclides are not included in the ODCM or Regulator Guide 1.109, consequently the cumulative dose attributed to these isotopes is not reported. The j uantity of these isotopes comprised only 1.52E-3% and 5.94E-3% of the total curies released j g(including tritium) during the first and second quarter, respectively. 1 l

1 1

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I SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT.

January - June,1987 .,

i Table 7 '

1 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS {

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

Unit 6-month Est. Total

1. Type of waste Period Error,%

. a.5 pent resins, filter sludges, evaporator m3 7.93E + 1  ;

bottoms, etc. . Ci 4.20E + 2 3.50E + 1 j

b. Dry compressible waste, cor,taminated m3 1.81 E + 2 equip., etc. Ci 3.43E + 1 3.50E + 1 3
c. Irradiated components, control rods, m 0 etc. Ci 0 N/A l d.Other (describe) Process Filters m 3 4.70E + 0 l Ci 2.80E + 1 3.50E + 1 l
2. Estimate of major nuclide composition (by type of waste)* ,
a. H-3  % 5.55E + 1 }

% 1.94E + 1 Co-58 Co-60  % 9.31E + 0 Fe-55  % 4.93E + 0 Mn-54  % 2.43E + 0 )

Ni-63 + C-14 + Zr-95  % 4.78E + 0

b. Fe-55  % 5.03E + 1 Co-58  % 1.68E + 1 Co-60  % 1.58E + 1 Ni-63 + Mn-54 + Nb-95 + Sr-89  % 1.33E + 1

% N/A

c. None

% 5.18E + 1

d. Fe-55 Co-60  % 2.03E + 1 Co-58  % 1.68E + 1 Ni-63 + Mn-54 + Cr-51  % 8.19 E + 0 l ATI nuclides are listed in descending order by activity level.

All nuclides with concentrations above 1% are listed.

3. Solid Waste Disposition (6 month period)

Number of Shipments Mode of Transportation Destination 16 Truck Barnwell, S.C.

B. lrradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination NONE N/A N/A Page 16

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