ML20104B266

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Amended VC Summer Nuclear Station Semiannual Effluent & Waste Disposal Rept,Jan-June 1992
ML20104B266
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 06/30/1992
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SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20104B263 List:
References
NUDOCS 9209150208
Download: ML20104B266 (14)
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SEMIANNUAL. EFFLUENT AND WASTE DISPOSAL RE' ORT l FOR THE OPER ATING PERIOD January 1,1992 - June 30,1992 3-August 1992 -

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

?$ h G. M.' Gowdy, f Staff Health Physicist _

Reviewed and approved by: Reviewed and approved by:

/ p, 90 /m@

. M/Rollint

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/m h li. G. Hall, Associate Manager Sr. Staff Heal *S Physicist Health Physics Reviewed and approved by:

W. RTBae r, Manager 9209150208 920904 PDR ADOCK 05000395 R PDR

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SEMlANNUAL EFFLUENT AND WASTE DISPOSAL REPORT

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January June,1992 Virgil C. Summer NuclearStation 4

South Carolina Electnc & Gas e

This report is being submitted as a summary of the quantitles of radioactive liquid and gaseous effluents and solid waste released from the Virgil C. Summer Nuclear Station.

This report satisfies the requirements in Sections 6.9.1.8 and 6.14.2 of Technical Specifications, Section 1.6.2 of the Offsite Dose Calculation Manual (ODCM) and 10CFR50.36(a). Also included is an assessment of radiation doses from plant releases.

i A brief discussion of the Supplemental information and Tables 2 through 6 is presented in Sections A through D. An evaluation of the radiologicalimpact on man 3 due to operation of the Virgil C. Summer Nuclear Station is presented in Section E and Table 1. Changes made to previous reports are presented in Section F and Appendix 1.

A. Sopplementallnformation
Regulatory limits ior doses and maximum permissible concentrations presented in Supplemental informatic,n are from the Virgil C. Surgmer Nuclear Station Techmcal Specifications at;d 40 CFR 190. Average energy (E)is not applicable to

, the method for determmin j gaseous effluents; therefore,g it hasrelease rate limits for fission and activation been omitted .

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B. Gaseous Ef fluents Gaseous effluents released from ground lev?l are summarized in Tables 2 and
3. An elevated release pathway does not exist at Virgil C. Summer Nuclear Station. The errors for gaseous effluent totals are given as the souare root of the sum of squares of counting errors and flow or volume measurement errors.

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

doses are discussed in Section E.

C. Liquid Effluents

} Liquid effluents are summanzed in Tables 4 and 5. Estimated total errors are expressed as in Section 8 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 datector used.

E. Radiologicalimpact on Man Potential doses to the maximum exposed individual in the unrestncted area .

were calculated using measured plant gaseous effluent and meteorological data in accordance with the Offsite Dose Calculation Manual. The source term included four (4) waste gas decay. tank (WGDT) batch releases,1.45 days of 6-inch and 4.77 days of 36-inch Reactor Building purge releases and a continuous six month main plant vent release. Doses are summarized in Table

1. The total activities released are presented in Tables 2 and 3. Air doses to the Page1
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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT

. January - June,1992 1

\/irgil C Summer Nuclear Station South Carolina Electric & Gas i

I maximum exposed individual due to noble gases were 2.09E-2 and 5.41E-2 mrad for gamma and beta, respectively. The maximum or 4

to the releases was 3.66E-3 mrem for the six month period. gan dose attributed 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 concisted of the isotopic contents of 201 Waste Monitor Tank batch

+

releases,34.3 days of Steam Generator Blowdown _ release and a continuous i Turbine Building Sump release. Doses are summarized in Table 1 and total l radioactivity released is described in Tables 4 and 5. The total body dose to the I maximally exposed individual due to the release of radioactive liquid was i 1.08E 2 mrem. The maximum organ dose was 3.01E-2 mrem to the thyroid during the six month period.

Table 1 3 GASEOUS AND LlQUID EFFLUENT DOSE

SUMMARY

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First Quarter,1992 Second Quarter,1992 OD A ge n Gaseous Limits Dose Percent Percent of Limit Dose of Limit 1.2.3 la,b 5 mrad gamma /qtr. '

- 6.76E-3 mrad 1.35E 1 1,41E 2 mrad 2.82E 1 10 mrad gamma /yr. 6.76E 2

2.09 E-1 *
(January lune total gamma air dose
2.09E-2 mrad)
1. 2.3. t a.b 10 mrad betalqtr 161E 2 mrad 1.61E 1 3.80E 2 mrad 3.80E-1 20 mrad beta /yr. 8.05E 2 2.71 E-1 '

(January-June total beta air dose: 5.41E 2 mrad) 12.4 la.b 7 5 mrem / organ /qtr- 7 93E 4 mrem 1.06E42 2.87E-3 mrem 3.83E 2 9 15 mrem / organ /yr. 5.29E 3 2.44E 2*

(January June maximum exposed organ dose: 3.66E 3 mrc:n) 3

' Liould Limits i 1 1.3.1a,b 1.5 mremiqtr. 1.89E 3 mrem 1.260-1 8.93E 3 mrem 5.96E 1

3.0 mremlyr. 6.30E-2 3.61E P (Januarv Junewhole bodydose
1.08E 2 mrem)

L1.3.1a.b 5 mremforgan/qtr. 6 97E 3 mremt 139E-1 2.32E 2 mremt 4 63E-1 10 mrem /orgarVyr. 6 97E 2

. 3.01 E 1 *

(January-June maximum exposed organ dose: 3.01E-2 mremt)

  • Includes contnbution from previous quarters.

t Maximum organ dose for quarters 1 and 2 was to the thyroid.

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1992 Virgil C. Summer Nuclear Station South Carolina Electric & Gas Dose rates and concentrations were below the limits specified in Supplemental iniormation, See. tion 2a, b and c during all the ef fluent releases.

4 Radiation doses from radioactive effluents to workers at the Fairfield Hydro Station were calculated for the six month penod to be 1.89E 3 and 4.86E 3 mrad for gamma and beta, respectively.

Radiation doses from nearby uranium fuel cycle sources were not assessed.

ODCM. Sections 1.3.1 and B/1.3 establish a five (5) mile limit beyond which doses from nearby plants are insignificant. There are no uranium fuel cycle plants within a five (5) mile radius of Virgii C. Summer Nuclear Station.

F. Offsite Dose Calculation Manual The ODCM was not revised during the affected six month period.

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dEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1992 Virgil C. Summer Nuclear Station South Carolina Electric & Gas Supplementalinformation 1

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 talendar quarter and 10 mrad for gamma radiation cnd 20 mrad for beta radiation during any calendar year (ODCM, Section 1.2.3.1).

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

The dose to an indivioual from radiciodines, tntium and radioactive i materials in particulate form with half-lives greater than 8 days in gaseous effluents shr.il 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 (ODCM, Section 1.2.4.1).

c. Liquid Effluents:

The dose or dose commitment to an individual from radioactive materials in liquid effluents released shall be limited to less than or equal to 1.5 mrem to the total body and 5 mre: to any organ during any calendar quarter and 3 mrem to the totai;. ,dy and 10 mrem to -

any organ during any calendar year (ODCM, Section 1.1.3.1).

d All Sources:

The annual dose equivalent shall not exceed 25 mrem to the whole body,75 mrem to the thyroid and 25 mrem to any other organ (40 CFR 190).

2.

Maximum Permissible Concentrations:

a.

Fission and Activation Gases:

The dose rate in unrestricted areas due to radioactive materials released in 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 (ODCM, Section 1.2.2.1).

b.

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

The dose rate in unrestricted areas due to radioactive materials in effluents shall be limited to less than or equal to 1500 mrem / year to any organ (ODCM, Section 1.2.2.1).

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1992 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, 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 (ODCM, Section 1.1.2.1).

, 3. Average Energy:

Not Applicable 4.

Measurements and Approximations of Total Radioactivity:

a.

Fission and activation gases: Gamrna spectrometry [Ge(Li) or HPGel b.

lodines: Gamma spectrometry [Ge(Li) or HPGel

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

Liquid effluents: Gamma spectrometry (Gt (Li) or HPGe], liquid scintillation (H-3), beta proportional counting,

, alpha proportional cour

  • ng
5. Batch Releases;
a. Gaseous:

1.

Number of batch releases: 4 2.

Total time period for batch releases: 1.02E + 3 min.

3.

Maximum time period for a batch release. 3.97E + 2 min.

4.

Average timo period for a batch release: 2.54E + 2 min.

5.

Minimum time period for a batch release: 150E + 1 min.

b. Liquid:

1.

Number of batch releases:

98 for first quarter,1992 103 forsecond quarter,1992 Page 5 I

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SEMIANNUAL EFFl.UENT AND WASTE DISPOSAL REPORT january June,1992 Virgil C. Summer Nuclear Station South Carolina Electric & Gas Supplerrentalinformation

2. Total time period for batch releases:

7).7E + 3 min. for first quarter,1992 7.88E + 3 mm. for second quarter,1992

3. Maximum time period for a batch release:

8.80E + 1 min for first quarter,1992 9.60E + 1 min. for second quarter,1992

4. Average time period for batch releases:

7.42E + 1 min. for first quarter,1992 7.65E + 1 min. for second quarter,1992

5. Minimum time period for a batch release:

4.50E + 1 min. for first quarter,1992 5.40E + 1 min for second quarter,1992 6.

Average stream flow during periods of release of effluent k into a 11owing stream:

2.85E + 6 gpm for first quarter,1992 3.51E + 6 gpm for second quarter,1992

6. Abnormal Releases:
a. Gaseous:
1. Numberof releases: 0 I
2. Total activity released: 0
b. Liquid:
1. Numberof releases: 0
2. Total activity released: O Page 6

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June,1992 Table 2 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES 4

First Second Est. Total

[

Quarter Quarter Error, %

A. Fission & activation gases

' 1. Total release Ci 8.12E + 1 1.96E + 2 2.34E + 1

2. Average release rate for period pCi/sec 1.04E + 1 2.50E + 1
3. Percent of technical specification limit  % *
  • B. lodines 1.Totat iodine 131 Ci 4.12 E-5 1.45 E-4 2.66E e 1-
2. Average release rate for period pCi/sec 5.30E 6 1.84E-5 -
3. Percent of technical specification limit  % ** **

C. Particulates

1. Particulates with half lives > 8 days lCi 0 0 N/A l
2. Average release rate for penod "Ci/sec 0 0
3. Percent of technical specification limit a
4. Gross alpha radioactivity 0 0 l Ci D. Tritium
1. Totai release Ci 0 2.47 E-1 3.09E + 1
2. Averagc release rate for period pCi/sec 0
3. Percent of technical specification limit **

3.14E-2 c

Calculated as a percent of dose limits found in SupplementalInformation, Section Ia. First c

uarter values were 1.35E-1% and 6.76E-2% of the quarterly and cumulative annual gamma ose !imits, respectively and 1.61E 1% and 8.05E-2% of the quarterly and cumulative annual beta dose limits, respectively. Second quarter values were 2.82E 1% and 2.09E-1%t of the quarterly and cumulative annual gamma dose limits, respectively, and 3.80E-1% and 2.71E-1% t of the qucrterly 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 1.06E 2% and 5.29E-3% of the quarterly and cumulative annual organ dose limits, respectively. The sum of these values for the second quarter wasctively.

limits, respe 3.83E-2% and 2.44E 2%t of the quarterly end cumulative annual organ dose t Note:

Second quarter values are the sum of the first and second quarter values compared to annual dose limits.

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT

, January - June,1992 i

Table 3 GASEOUS EFFLUENTS-GROUND-LEVEL RELEASES Continuous Mode Batch Mode

First Second First Second Nuclides Released Unit Quarter Quarter Quarter Ouarter
1. Fission oases Krypton-85 Ci 0 0 1.0SE-1 7.73 E- 1 Krypton 8Sm Ci 0 5.17'E-2 0 0 Krypton-87 Ci 0 0 0 0 Krypton 68 Ci 0 1.18E 3 0 0 Xenon-133 Ci 7.3 7 E + ) 1.85E + 2 2.12 E -4 2.09 E- 1 1 lenon-135 Ci 7.41 E + 0 7.77E + 0 7.74E-6 5.13E-5 Xenon-135m Ci 0 0 0 0 Xenon-138 Ci 0 0 0 ,

0 Others: Ar-41 Cs 0 1.64E 2 0

)

0 l Xe-131m Ci 0 '3.00 E- 1 0 1.3 5 E-2  !

Xe-133m Ci 0 1.62E + 0 0 1.83E 4 Unidentifiec {

Ci 0 0 0 0 Total for period C' 8.11 E + 1 1.95E + 2 , 1.05E 1 9.95 E- 1

2. lodines
odine-131 Ci 4.12E 5 1.45 E-4 0 0 looine-132 Ci 0 0 0 0

lodine-133 Ci 1.43E 6 1.38E-5 0 0 lodine 134 Ci 0 0 0 0 locine-135 Ci 0 0 0 0 Total for period C 4.26E-S 1.59E 4 0 0

3. Particulates 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: Br-82 Ci 0 3.80E 7 0 0 Rb-88 Ci 0 5.23 E-6 0 0 Unidentified Ci 0 0 0 0 Total for period Ci 0 5.61E 6 0 ,

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January June,1992 1

4 Table 4 I LIQUID EFFLUENTS SUMMATION OF ALL RELEASES 4

First Second Est. Total '

Ouarter Quarter Error, %

A. Fission & activation products

1. Total release (not including tritium, gases, Ci 7.04E 2 7.14 E-2 1.83E + 1 alpha)
2. Average diluted concentration during pCi/mi 1.91 E- 10 1.68E 10 period
3. Percent of applicable limit  % *

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1. Total release Ci 6.50E + 1

. 1.41E 4 2 1.86E + 1

2. Average diluted concentration during pCi/mi 1.76E 7 3.31 E-7

) period

3. Percent of applicable limit  % *
  • C. Dissolved and entrained gases
1. Total release Ci 4 2.92 E-2 2.31 E- 1 1.81 E + 1
2. Average diluted concentration during pCi/mi 7.93 E-11 5.44E-10 l

i period

3. Percent of applicable lirnit  % *
  • D. Gross alpha radioactivity
1. Total release Ci 0 0 N/A

" E. Volume of waste released (prior to dilutionl liters 2.04E + 7 4.28E + 7 3.00E + 0 F. Volume of dilution water used during period liters 3.68E + 11 4.25E + 11 4.30E + 0

  • See following page.

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J SEMIANNUAL. EFFLUENT ANP '9ASTE DISPOSAL REPORT January Jua 2,1992 Table 4 i

LIQUID EFFLUENTS SUMMATION OF ALL HELEASES Calculated as a percent of dose limits found in Supplemental information, Section Ic. T; .

l sum of these values for the first quarter was 1.26E 1% and 6.30E 296 of the resoective-

quarterly and cumulative annual whole body dose limits and 1.39E 1% and 6.97E-2% of the

- respective quarterly and cumulative annual organ dose limits. The sum of these values for 4

the second ouarter was S.96E 1% and 3.61E 1% t of the respective quarterly and cumulative -

' annual whole body dose limits and 4.63E-1% and 3.01E-196 t of the respective quarterly and cumulatise annual organ dose limits. Dose to the thyroid was the most limiting organ dose j for the first quarter, second auarter and first six (6) months of 1992.

t Note
Second quarter values are the sum of the first and second quarter values compared to annual dose limits.

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT

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Januarv June,1992 Table 5 t

LIQUID FFFLUENTS Continuous Mode Batch Mode Ulfst beCond First 50Cond tNuclides Released Unit Ouarter Ouarter Quarter Ouarter Strontium 89 Ci 0 0 S.71E 7 1.00E 5 Strontium 90 Ci o o S.28E-7 9.24E-6 Cesium-134 c 0 168E 4 3. 71 E-4 Cesiu m- 13 7 Ci 0 2.5 5 E 3 __

4.12 E-4 S.43E-4 4.38E 3 loaine-131 Ci 1.77E 3 6.7 2 E-3 3.94E 3 S.51 E-3 Cobalt-58 Ci 0 0 '

3.33 E-2 9.38E-3 Cobait-60 Ci 0 0 1.38E 2 1.17E 2 f ron-59 Ci 0 0 1.72 E-4 4.04E-6 Zinc u5 Ci 0 '

O O 4.00E-5 Manaanesec4 u o 0 Chromium 51 1.39E 3 1.41 E -3 Ci 0 0 6.33E 4 1.86 E-4 Zirconium Niocium-95 n ci 0 0 Molybdenum 99 8.93E 4 1.2 2 E -3 Ci 0 0 0 2.20E-5

' Tecnnetium-99m Ci 0 0 3.23E-5 1.6 7 E-4 Barium-Lanth.-140 Ci 0 0 1.80E-5 2.36E 5 Cerium-141 l Ci 0 0 0 0 Other: F-18 C 1.08E 3 4.13 E-3 0 1 0 Na-24 Ci 4. 73 E-4 3.06E 3 4 68E-5 1.67E 4 Fe-55 'i O O 4.18 E-4 139E-3 Co-57 Ci 0 0 1.99E 4 9.98E 5

' 2n 69m Ci 0 0 2.43E 6 0 As-76 Ci 0 0 0 3.15E 6 Ru 103 Ci 0 0 0 7.95E-7

) Ru 106 Ci 0 L

1 0 8.44 E-6 0 Aa- 110m Ci 0 0 7.21E 6 1.34E-4 l Sn-113 Ci 0 0 9.60E-6 9.09E-6 i Sb-124 L Ci 0

! 0 1.92 E-4 7.64E-6 Sb-125 Ci 0

) 0 7.46E-3 4. 74 E-3 1-132 Ci S.62 E-4 1.91 E-3 0 l

' 1-133 Ci 0

1.85E-3 6.24E-3 1.73E 4 l-134 2.26 E-4 C1 1.66E-4 6.23 E-4 0 1-135 Ci 0

8.51 E-4 2.26E-3 0 Cs-136 0 Ci 0 9.97 E-5 0 5.46E-6 Cs-138 Ci 4.90E-6 2.3 7E-4 0 0 Ce-144 i Ci 0 0 4.17E-6 1.84E-5 Unidentified Ci 0 0 0 0 Total for period (abovo) Ci 6.77E-3 2.79E-2 6.37E-2 4.35 E-2 1

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT t

, January June,1992

(

Table 5 (continued) I LIQUID EFFLUENTS 3

' Continuous Mode Batch Mode i First Second First Second TNuchdes Released Unit Quarter i Quarter Quarter Quarter i 4 i 4

j Xenon-133 Ci 3.43E 3 1.62 E-3 2.51E 2 2.24E 1

Xer 1135 Ci 5.32 E-4 3.28 E-4 1.18E 5 1.56E 5 j Other
Kr-85m Ci 4 62E 5 0 9.33E 7 2.01 E-5 i

Xe 131m Ci 0 0 6.47E 5 4.66E-3

, Xe-133m Ci 0 0 1.11E 5 6.40E-4 Total entrained gases Ci 4.01 E-3

1.95E 3 2.52E 2 2.29E 1 i T

{

t Tritium not mcluded. See TaHe 4 for tritium nurnbers.

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SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT

' January - June,1992 Table 6 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS 4

I A. Sclid Waste Shicoed Offsite,for Burial or Discosal(Not irradiaied fuel) j 1. Type of waste

> Unit 6 month Est. Total Period Error,%

a. Spent resins, tilter sludges, evaporator m* _.

bottoms, etc. 6.92E + 1 Ci 1.94E + 2 3.50E + 1 i

b. Dry compressible waste, contaminated m' equip., etc. 1.24E + 1 Ci 8.07E-1 3.50E + 1 l
  • c. Irradiated components, centrol roas, etc. md 0 Ci 0 N/A d, d.Other (describe) md 0
Ci 0 N/A
2. Estimate of major nuclide composition (by tyu;nf waste) 3, g, 55 gn, So 2.20E t 1

]

~

% 1.72E + 1 Q63  %

i 1.62E + 1 Cs 134

%- 1.51 E + 1 Co 60

% 1.43 E + 1 Co-58

% 1.03 E + 1 Mn 54  %

! 2.60E + 0

b. Fe-55  % 4.12E + 1 c, 60

% 1.99E + 1 4

Cs-137

% 1.39E + 1 Cs-134

% 8.29E + 0 Ni 63

% 6.90E + 0 Mn 54 '

i  % 2.69E + 0 H-3 l  % 1.60E + 0 Co-58

% 1.57E + 0

c. None

% N/A

d. None' _ . .

,  % N/A

' All nuclides ..ith conct.ntrations above 1.0% 6re listed in descending order b .

3. Solid Waste Discosition (6 month oeriod)

Number of Shipments Mode of Transportation

, ASt Destination fruck l

Barnwell, SC tNote: 38 of these are partial shipments of DAW f.~om waste processor to Barnwell SC , .

B. Irradiated Fuel Sh',oments (Disposition)

Number of Shipments Mode of Transportation None Destination . .

N/A N/A

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