ML20112K113

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Semiannual Effluent & Waste Disposal Rept,Jan-June 1983
ML20112K113
Person / Time
Site: Summer South Carolina Electric & Gas Company icon.png
Issue date: 06/30/1983
From: Dixon O
SOUTH CAROLINA ELECTRIC & GAS CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8504090339
Download: ML20112K113 (13)
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SEMIANNUAL EFFLUENT AND iGSTE DISPOSAL REPORT January - June,1983 '

Virgil C. Sumer Nuclear Station South Carolina Electric & Gas his report is being subnitted as a sunnary of the quantities of radio-active liquid and gaseous effluents and solid waste released from the Virgil C.

Sunner Nuclear Station. h is report satisfies the requirements in Sections 6.9.1.8 and 6.9.1.9 of Technical Specifications and 10CFR50.36(a).

A brief discussion of the Supplemental Information and Tables 1 through 5 i is presented in Sections A through D. An evaluation of the radiological inpact

, which operation of the Vigil C. Sumer Naclear Station has had on man is presented in Section E. Changes made to the Process Control Program are presented in Section F.

, A. Supplemental Information

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Regulatory limits for doses and maxinum permissible concentrations presented in Supplemental Information are from the Virgil C. Sumner M2 clear Station Technical 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 from ground level are sumarized in Tables 1 and 2. An elevated release pathway does not exist at Virgil C. Summer Nuclear Station. Omulative doses are discussed in Section E.

Se errors for gaseous effluent totals are given as the square root of the sum of squares of counting errors and flow or volume measurenent

errors. A systenatic error of 15% has been added to estimate total error.

C. Liquid Effluents

! Liquid effluents are sumarized in Tables 3 and 4. Estimated total

errors are expressN1 as in Section B above.

l D. ' Solid Waste Shipments Solid waste shipments are summrized in Table 5. The shipnent i

consisted of 119 55-gallon druns and two B-25 boxes.

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. SEMIANNUAL EFFLIENT AND WASTE DISPOSAL REPORT January _. June, 1983 a

Virgil C. Sumer Nuclear Station

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South Carolina Electric & Gas i

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. Since the method for curie content determination is based on contact dose rates 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. Radiological Inpact on Man

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Potential doses to the maximurn em=d individual in the unrestricted area were. calculated uPing measured plant gaseous effluent and meteorological data in accordance with the Offsite Dose Calculation tenual.

Included in the source term were two (2) waste gas batch releases, two~(2)

! containment' purges and a continuous six month main plant vent release. The total curies released are presented in Tables 1 and 2. Air doses to an

, individual due to noble gas were 9.22E-3 and 1.08E-1 mrad for gama and beta, respectively.

Measured plant liquid effluent data was used to calculate estimates of l doses to individuals in accordance with the Offsite Dose Calculation Manual. The source term consisted of the isotopic contents of each of the 326 liquid effluent batch releases and a continuous Turbine Building Sunp release. The total radioactivity released is described in Tables 3 and 4.

i The total body dose to an e-ad individual due to the radioactive liquid

released was 2.39E-3 mrem. . The maximum organ dose was 9.01E-4 mre (thyroid) during the first quarter and 6.85E-3 mre (GI-LLI) during the second 4

quarter.

! Accumulated doses due to gaseous and liquid effluents and respective l Technical Specification limits are sumarized as follows:

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First Quarter, 1983 second Quarter, 1983 l Tech Spec- Percent Percent Section Limit Actual of Limit Actual- of Limit 3.11.2.2a 5 mead gama/qtr. 9.22E-3 mead' 1.84E-l' l.17E-6 mrad 2.33E-5 10 mrad gama/yr. 9.22E 9.22E-2*

t 3.11.2.2a .10 mrad beta /qtr. 1.08E-1 mrad 1.08 .8.97E-7 mrad 8.97E-6

20 mrad beta /yr. 5.'4E-1 5.4E-1
  • i l 3.ll.2.3a' 7.5' mrenVorgary'qtr. 3.23E-4 mrem 4.31E-3 .1.26E-4 mrem 1.69E-3 l ~15 mem/ organ /yr. 2.15E-3 3.0E-3
  • i 3.ll.l.2a 1.5 mrenVqtr. 5.41E-4 mrem 3.61E-2 1.85E-3 mrem 1.23E-1

!- 3.0 'mrenVyr. 1.81E-2 7.97E-2*

" 3.ll.l.2a 3 5 mrem /orgarv'qtr. 9.01E-4 mrem .1.8E-2 6.85E-3 mrem 1.37E-1 10 mrem /orgarv'yr. 9.0E-3 7.755-2*

  • includes contribution from previous quarter.. 3 9

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SEMIANMJAL EFFIDENP AND WASTE DISPOSAL REPORT January - June, 1983 1

Virgil C. Sunmer Nuclear Station

, South Carolina Electric & Gas Radiation doses from radioactive effluents to workers at the Fairfield

' Hydro Station were determined to be 1.26E-3 and 1.48E-2 mrad for gamma and beta, respectively.

t Dose rates and concentrations were below the limit.s specified in Supplemental Information, Section 2a, b and c during all the effluent

releases.

It will be noted here that.an error was found in the previous Semi-annual Effluent and Waste Disposal Report. An incorrect X/Q' value was used in the calculation for determining dose attributed to tritium in the gaseous effluent, thereby resulting in an under-estimation by 3.2E-8 mrem; a dose considered to be insignificant. 'Ihe correct organ dose should be 1.59E-7 mrem.

F. Process Control Program There were no changes made to the Process Control Program (PCP).
Virgil C. Sumer Maclear Station was awaiting NRC review and approval of the PCP for. the cement solidification systen in accordan'
e with Facility i Operating License No. NPF-12, Section 2C (20).*

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t This approval was received from the NRC on July 12, 1983.

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SEMIANNUAL EFFLIENT AND WASTE DISPOSAL REPORT January - June, 1983 Virgil C. Sununer Nuclear Station i South Carolina Electric & Gas i

Supplemental Information

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 nrad for ganna radiation and 10 mrad for beta radiation during any calendar quarter and 10 nrad for gruana radiatic,n ard 20 mrad for beta radiation during any calendar year (Technical Specifications, Section 3.11.2.2).

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

1 h e dose to an indivudual from radiciodines, tritium and radioactive materials in particulate form with half-lives greater .than 8 i 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 meem to any organ
during any calendar year (Technical Specifications, Section 3.11.2.3).-

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c. Liquid Effluents:

1 ne dose or dose conunitment to an individual frczn radioactive materials in liquid effluents released shall be limited to less than or equal to 1.5 mrsn to the total body and 5 mean to any organ during any calendar quarter and 3 meem to the total body and 10 nrem to any organ during any calendar year (Technical Specifications, Section 3.11.1.2).

l 2. Mad mum Permissible Concentrations:

I a. Fission and Activation Gases:

l The dose rate in unrestricted areas due to radioactive

! materials released in gaseous effluents shall be limited to less than or equal to 500 mren/ year to the total body and less than or equal to-3000 mean/ year to the skin (Technical Specifications, Section 3.11.2.1).

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1 b. Iodines, Particulates (half-lives >8 days) and Trititzn I ne dose rate in unrestricted areas due to radioactive i materials in effluents should be limited to less than or. equal'

-to 1500 mren/ year to any organ (Technical Specifications, Section 3.11.2.1).

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SEMIANNUAL EFFLLENE AND WASTE DISPOSAL REPORT January - June, 1983 Virgil C. Sumer Nuclear Station 4 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, Column 2 for radionuclides other than dissolved or entrained no* ole gases. For dissolved or entrained noble gases, the concentration shall be '.imited to 2E-4pCi/ml total activity (Technical Specifications, Section 3.11.1.1).

3. Average Energy:

Not Applicable

4. Measurements and Approximations of 'Ibtal Radioactivity:
a. Fission and activation gases: Gama spectrometry (GeLi)
b. Iodines: Gamma spectrometry (GeLi)
c. Particulates: Ga,Tma spectrometry (GeLi), beta proportional counting, alpha proportional counting
d. Tritiun: Liquid scintillation
e. Liquid effluents: Gama spectranetry (GeLi), liquid scintillation (H-3), beta proportional counting, alpha proportional counting

! . 5. Batch Releases:

a. Liquid:
1. tunber of batch releases:

164 for first quarter,1983 162 for second quarter, 1983

2. Total time period for batch releases:

10053 min. for first quarter, 1983 9245 min for second quarter,1983

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F SEMIANNIAL EFFLUENT AND WASTE DISPOSAL REPORT January - June, 1983 Virgil C. Sumner Nuclear Station South Carolina Electric & Gas Supplanental Information

3. Maximum time period for a batch release:

130 min, for first quarter, 1983 150 min for second quarter,1983

4. Average time pariod for batch releases:

61 min, for first quarter,1983 57 min, for second quarter, 1983

5. Minimun time period for a batch release:

1 min. for first quarter,1933 0.17 min, for second quarter,1983

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

1.36E6 gpn for first quarter,1983 1.56E6 gpu for second quarter,1983

b. Gaseous:

1 tinnber of batch releases: 4

2. Total time period for batch releases
1802 min.
3. Maximum time period for a batch release: 1035 min.
4. Average time period for a batch release: 451 min.
5. Minimum time period for a batch release: 120 min
6. Abnormal Releases:
a. Liquid:
1. 1&nnber of releases: LONE
2. Total activity released: IONE
b. Gaseous:
l. NLunber of releases: LONE
2. Total activity released: NONE '

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SEMIANMJAL EFFLUENT AIO WMiTE DISPOSAL REPORT January - June, 1983 Table 1 i,

l GASEOUS EFFLUENTS-SLBMATION OF ALL RELEASES s.

1 First Second Est. Total Quarter Quarter Error, %

t A. Fission ~8 activation gases 1

1. Total release- C1 3.80E+2 2.86E-3 2.83&1 l
2. Average release rate for period uC1/sec 4.89E+1 3.63E-4
3. Percent of technical specification limit  % *

i i 1. Total iodine-131 Ci 4.88E-7 0.00EX) 1.82&2 l l 2. Average release rate for period pCi/sec 6.27E-8 0.00E0

3. -Percent of technical specification limit  % ** **

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t l C. Particulates

1. Particulates with half-lives >8 days Ci 0.00E0 2.02E-6 1.07&2 l
2. Average release rate for period uCi/sec 0.00E0 2.57E-7
3. Percent of technical specification limit  % ** **

! 4. Gross alpha radioactivity Ci 0.00E0 0.00E0 1

D. Tritium

1. Total release C1 2.50EX) 1.00E0 2.28&l l
2. Average release rate for period uCi/sec 3.22E 1.28E-1

-3. Percent of technical specification limit  % ** **

  • Calculated as a percent of dose limits found in Supplemental Information, Section la.

, First quarter values were 1.84E-l% and 9.22E-2% of the quarterly and annual' ganea dose

(. limits, respectively and 1.084 and 5.4E-l% of the quarterly and annual beta dose

limits, respectively. Second quarter values were 2.33E-5% and 9.22E-2% of the I

quarterly and annual ganma dose limits, .respectively and 8.97E-6% and 5.4E-l% of the quarterly and annual beta dose limits, respectively.

    • Calculated asia percent of dose limits found in Supplemental Information,- Section lb.

The sum of these values for first quarter was 4.31E-3% and 2.15-34 of the quarterly and annual organ dose limits, respectively. . Ttve sum of these values for second quarter was 1.69E-3% and 3.0s-34 of the quarterly and annual organ dose limits, respectively.

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SD4IANNIAL EFFLUENT AND WASTE DISPOSAL REPORT January - June, 1983 Table 2 GASEOUS EFFLIENTS-GROUND-LEVEL RELEASES Continuous Mode Batch Mode First Secord First Second Nuclides Released Unit Quarter Quarter Quarter Quarter

l. Fission gases krypton-85 Ci 2.65E+2 0.00E0 0.00E0 0.00E0 krypton-85m Ci 0.00E0- 0.00E0 0.00E0 0.00E0 krypton-87 Ci 0.00E0 0.00E0 0.00E0 0.00E0 krypton-88 Ci 0.00E0 0.00E0 0.00E0 0.00E0 xenon-133 Ci 6.41E+1 0.00E0 4.41E+1 1.49E-3 xenon-135 Ci 8.26E-1 0.00E0 5.50E0 8.48E-4 xenon-135m Ci 0.00E0 0.00E0 0.00E0 0.00E0 xenon-138 Ci 0.00E0 0.00E0 0.00E0 0.00E0 Others (specify) Ar-41 Ci 0.00E0 0.00E0 0.00E0 5.15E-4 i Ci . E . E . E . E Ci . E . E . E . E unidentified Ci 0.00E0 0.00E0 0.00E0 0.00E0-l Total for period Ci 3.30E+2 0.00E0 4.96E+1 2.86E-3 l
2. Iodines l

! iodine-131 Ci 4.88E-7 0.00E0 0.00E0 0.00E0 lodire-133 Ci 2.66E-7 0.00E0 0.00E0 0.00E0 iodine-135 Ci 0.00E0 0.00E0 0.00E0 0.00E0 Total for period l Ci 7.54E-7 0.00E0 0.00E0 0.00E0

3. Particulates l strontium-89 Ci 0.00E0 0.00E0 0.00E0 0.00E0 strontium-90 Ci 0.00E0 0.00E0 0.00E0 0.00E0 cesite-134 Ci 0.00E0 0.00E0 0.00E0 0.00E0 cesium-137 Ci 0.00E0 0.00E0 0.00E0 0.00E0 barium-lanthanum-140 Ci 0.00E0 8.70E-7 0.00E0 0.00E0 Others (specify) Co-58 Ci 0.00E0 1.15E-6 0.00E0 0.00E0 Ci . E . E . E . E Ci . E . E . E , E

! unidentified Ci 0.00E0 0.00E0 0.00E0 0.00E0

'Ibtal for period 'Ci 0.00E0 2.02E-6 0.00E0 0.00E0 Page 8 of 12

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SH4IANNUAL EFFLUENT AND WASTE DISPOSAL REPORT January - June, 1983 Table 3 LIQUID EFFLUENES-SLNMATION OF ALL RELEASES First Second Est. Total Unit Quarter Quarter Error, %

A. Fission & activation products

.l. Total release (not including tritium, gases, alpha) Ci 2.93E-2 4.00E-1 2.34E+1

2. Average diluted concentration during period pCi/ml 1.12E-10 1.55E-9 -
3. Percent of applicable limit  % *

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1. 'Ibtal release Ci -2.87E+1 3.78E+1 1.80E+1 l
2. Average diluted concentration during period pCi/ml 1.lE-7 1.47E-7
3. Percent of applicable limit  % *
  • 4 C. Dissolved and entrained gases l 1. Total release Ci 1.llE-3 1.38E-4 7.48E+1 l
2. Average diluted concentration during period UCi/ml 4.24E-12 5.35E-13
3. Percent of applicable limit  % *
  • f D. Gross alpha radioactivity l l 1. Total release I Ci l 0.00E0 l 2.02E-41 3.81E+1 l E. Volume of waste released (prior to

! dilution) liters 6.28E+7 6.20E+7 3.00E0 F. Volume of dilution water used during period- liters 2.62E+11 2.58E+11 4.30E0

  • See following page.

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SEMIANNERL EFFLUENT AtO WASTE DISPOSAL REPORT January - June, 1983 Table 3 LIQUID EFFLUENTS-SCNMATION OF ALL RELEASES

  • Calculated as a' percent of dose limits found in Suppleroental Information, Section Ic.

The sum of these values for first quarter was 3.61E-2% and 1.81E-2% of the respective quarterly and ennual whole body dose limits and 1.8E-2% and 9.0E-3% of the respective quarterly and annual organ dose limits. The stan of these values for second quarter was 1.23E-l% and 7.97E-2% of the respective quarterly and annual whole body dose limits and 1.37E-l% and 7.75E-2% of the respective quarterly and annual organ dose limits. Doses to the thyroid and GI-LLI were the most limiting organ doses for first and second quarter, respectively.

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= . SEMIANNLAL EFFLUENP AND WASTE DISPOSAL hEPORT January - June, 1983 Table 4 LIQUID EFFLUENTS Continuous Mode Batch Mode First Second First Second Nuclides Released Unit Quarter Quarter Quarter Quarter strontium-89 Ci 0.00E0 0.00E0 5.20E-7 7.93E-6 strontium-90 Ci 0.00E0 0.00E0 6.50E-7 9.92E-6 cesium-134 Ci 0.00E0 0.00E0 2.26E-6 1.09E-3 cesium-137 Ci 0.00E0 0.00E0 5.57E-6 0.00E0 iodine-131 Ci 0.00E0 0.00E0 4.59E-4 2.64E-6 cobalt-58 Ci 0.00E0 2.43E-5 1.65E-2 3.10E-1 cobalt-60 Ci 0.00E0 0.00E0 1.55E-3 5.37E-2 iron-59 Ci 0.00E0 0.00E0 9.55E-5 2.63E-3 zinc-65 Ci 0.00E0 0.00E0 4.22E-6 0.00E0 mancanese-54 Ci 0.00E0 0.00E0 1.09E-3 1.49E-3 chromium-51 Ci 0.00E0 0.00E0 3.96E-4 2.83E-2 zirconium-niobium-95 Ci 0.00E0 0.00E0 1.09E-5 2.33E-3 molybdenum-99 Ci 0.00E0 0.00E0 5.79E-5 0.00E0 technetium-99m Ci 0.00E0 0.00E0 2.88E-4 0.00E0 barium-lanthanum-140 Ci 0.00E0 0.00E0 2.61E-4 2.43E-5 cerium-141 Ci 0.00E0 0.00E0 0.00E0 0.00E0 Other (specify) I-133 Ci 0.00E0 0.00E0 1.42E-3 0.00E0 Ce-144 Ci 0.00E0 0.00E0 9.00E-5 0.00E0 W-187 Ci 0.00E0 0.00E0 9.92E-4 6.04E-5 Na-24 Ci 0.00E0 0.00E0 5.75E-3 5.90E-5 Zr-97 Ci 0.00E0 0.00E0 2.61E-6 0.00E0

  • As-76 Ci 0.00E0 0.00E0 1.14E-6 0.00E0 I-132 Ci 0.00E0 0.00E0 3.43E-5 0.00E0 I-135 Ci 0.00E0 0.00E0 2.77E-4 8.63E-7 l
  • Pb-199 Ci 0.00E0 0.00E0 3.36E-7 0.00E0
  • Br-82 Ci 0.00E0 0.00E0 2.75E-6 0.00E0
  • Sb-124 Ci 0.00E0 0.00E0 0.00E0 2.04E-4 H- 3 Ci 0.00E0 0.00E0 2.87E+1 3.78E+1

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Total for period (above) l Ci l 0.00E0 l 2.43E-51 2.87E+1l 3.82E+1l xenon-133 Ci 0.00E0 0.00E0 8.08E-4 5.98E-5 xenon-135 Ci 0.00E0 0.00E0 2.99E-4 7.77E-5

  • Dose factors for these trace isotopes are not included in the ODCM or Regulatory Guide 1.109, consequently the ctmulative dose attributed to these isotopes is not reported. The quantity of these isotopes comprises only 4.85E-2% of the total curies released.

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  • SEMIANN(AL EFFLIENT Am NASTE DISPOSAL REPORT January - June, 1983 Table 5 SOLID WASTE AND IRRADIATED FUEL SilIPMENES A. Solid Waste Shipped Offsite for Burial or Disposal (m t irradiated fuel)
1. Type of waste Unit 6-month Est. Total Period Error, %
a. Spent resins, filter sludges, evaporator m3 0.00E0 bottczns, etc. Ci 0.00E0 0.00E0
b. Dry cmpressible waste, contaminated m3 3.09E+1 r equip., etc. C1 2.16E-1 3.50E+1
c. Irradiated cmponents, control m3 0.00E0-rods, etc. Ci 0.00E0 0.00E0
d. Other (describe) m3 0.00E0 C1 0.00E0 0.00E0
2. Estimate of major nuclide conposition (by type of waste)
a. TONE  % . E

% . E

% . E

b. Co-58  % 5.57E+1 Cr-51  % 2.05E+1 00-60  % 1.01E+1 Zr-95, Nb-95, Mn-54, Fe-59  % 1.37E+1

% . E

c. PONE  % . E

% . E

d. NONE  % . E

% . E

3. Solid Waste Disposition Number of Shignents 2de of Transportation Destination 1 Truck Barrwell, S.C.

B. Irradiated Fuel Shipnents (Disposition)

Number of Shipnents Mode of Transportation Destination NONE Page 12 of 12 9

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' SOUTH CAROL.INA ELECTRIC & GAS COMPANY

.ost carica 744 COLLMU : SOutre CARouMA 29218

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9. W. DixOH. JR.

v.ci an >ce r August 24, 1983 uvet .. una*ry ,

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. Mr. J . P. O'Reilly, _

Regional Administrator U. S. Nuclear Regulatory Commission Region II, Suite 2900 '

101.Marietta Street, N.W.'

Atlanta, GA 30303 -

Subject:

Virgil C. Summer Nuclear St.ation Docket No. 50/395 -

Operating Licens,e No. NPF-12 Semi-Annual Effluent and h3sta Disposal Repor't

Dear Mr. O'Reilly:

Please find attacherl South Carolina Electric and Gas, Company's (SCE&G) Semi-Annual Effluent and Waste Disposal Report as required by 10CFR50.36a and Sections 6.9.1.8 and 6.9.1.9 of the Virgil C. Summer Nuclear Station Technical Specifications.

s If there are any questions, please call us at your convenience.

Very trul you s, l

f1 7 .

O. W. Di on [

HCF:OWD/fjc Attachment -

cc: V. C. Summer G. J. Braddick T. C. Nichols, Jr./O. W. Dixon, Jr. J. C. Mille; E. H. Crews, Jr. J. L. Skolds E. C. Roberts J. B. Knotts,, - Jr.

H. N. Cy as H. G. Sheal'y Group / General Managers I&E Washington O. S. Bradham NPCF R. B. Clary File (Lic./Eng.)

C. A. Price A. R. Koon D. A. Lavigne C. L. Ligon (NSRC)

DESIcnATED ORIGINAU Coztified B y C n.-

i a- - g \ f$$5.

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