ML20041D939

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Semiannual Effluent Release Rept for Jul-Dec 1981.
ML20041D939
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 02/26/1982
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20041D937 List:
References
NUDOCS 8203090577
Download: ML20041D939 (17)
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6 SEMIANNUAL EFFLUENT RELEASE REPORT FOR CALVERT CLIFFS NUCLEAR POWER PLANT SECOND HALF - 1981 LIST OF ENCLOSURES ETLE PAGE Regulatory Limits 'I Maximum Permissible Concentration 3.

Measurements and Approximation of Total Radioactivity 3 4

Batch Releases 8 t'

Abnormal Releases 9 Gaseous Effluents - Summation of Release- ,

10 Gaseous Ef fluents - Isotopic Breakdown 11 Liquid Effluents - Summation of Releases . 12 Liquid Ef fluents - Isotope Brealddown 13 Solid Waste Shipments . 15 f

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B203090577 B20226 PDR ADOCK 05000317 R PDR , 1

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORTM SUPPLEMENTAL INFORMATION Pacility .. Calvert Cliffs Nuclear Power Plant Licensee - Baltimo e Gas & Electric Company I. REGULATORY LJM1TS A. Fission and Activation Gases:

1. The instantaneous release rate of gross activity, except for I-131 and particulates with half-lives longer than eight days shall not exceed Oi d

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(3.85 x 10 )(MPC)i l

where Qi is the release rate in C1/sec for isotope i and MPCI is the maximum permissible concentration of isotope i as 'defined in Appendix B, Table II, Column i,10 CFR 20.'

2. The release rates of gross gaseous activity shall not exceed 16 percent of .

the values specified in I.d.i. above when averaged over any calendar quarter. See Table IA, A3.

j-1], Submitted in accordance with Section 5.6.1.b of Appendix B of the Environmental Technical Specifications

3. The .elease rates of gross gaseous activity shall not exceed 8 percent of the values specified in I.A.I. above when averaged over 12 consecutive months. See Table IA, A4. '

B. Iodines and Particulates, Half-Lives 8 Days:

1. The release rate from the main vents of I-131 and particulates with half-lives greater than eight days released to the environs.as part of airborne eifluents shall not exceed 2.0 uCl/sec (1-131 equivalent).
2. The release rates of I-131 and particulates shall not exceed 8 percent of the value specified in I.B.I. above when averaged over any calendar quarter.

See Table IA,B3.

3. It should be noted that "lodines" as used here includes only lodine-131 since the Technical Specifications only refer to it specifically. Such other lodines, i.e., lodine-133, lodine-135, etc., are treated as gross activity and are included in I.A.I. and I.A.2.
4. The release rates of I-131 and particulates shall not exceed 4 percent of the values specified in I.B.I. above when averaged over any 12 consecutive months. See Table IA, B4.

C. Liquid Ef fluents:

1. The release rate of radioactive liquid effluents, excluding tritium and noble gases, shall not exceed 10 curies per unit during any calendar quarter
2. The radioactivity release concentrations in liquid effluents from the plant shall not exceed the values specified in 10 CFR Part 20, Appendix B, for unrestricted areas.

II. MAXIMUM PERMISSIBLE CONCENTRATIONS The MPC's used for radioactive materials released in liquid and gaseous effluents are in accordance with Technical Specifications and/or are derived from the use of notes to Appendix B,10 CFR Part 20. In all cases the most restrictive (lowest) MPC found for each isotope is used regardless of solubility.

The following limits were used to calculate the percent of applicable limit in Table 2A.

A. Fission and Activation Products - Limit used I x 10~7 uCl/ml. This limit was used ai given in the notes to Appendix B, Table II, Column 2 of 10 CFR 20.

B. Tritium - Limit used 3 x 10 3 uCl/rnt.

This limit was used as given in Appendix B, Table 11, Column 2 of 10 CFR 20.

C. Dissolved and Entrained Gases - Limit used 3 x 10-6 uCl/ml.

This limit was used as given in Appendix B, Table II, Column 2 of 10 CFR 20.

III. AVER ACE ENERGY - not applicable IV. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY A. Fission and Activation Gases:

1. Batch Releases Prior to each batch release of gas from a pressurized gas decay tank, a sample is collected and analyzed for each significant isotope using a Ge(LI) detector. The total activity released is based on the pressure / volume relationship (gas laws) of the tank prior to and af t.:r the release.

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Prior to and after the release of gas as a result of purging containment, samples are collected and analyzed for each significant isotope using a Ge(Li) detector. The total activity released is based on containment volume and purge rate with activity buildup while purging is being considered.

. 2. Continuous releases During the release of gas from the main vents, samples are collected and analyzed at least weekly for each significant isotope using a Ge(Li) detector. The total activity released for the week is based on the weekly result multiplied by the main vent flow for the week.

B. Iodine and Particulates:

1. Batch releases Total activity released f rom a pressurized gas decay tank as iodines and particulates is measured by the same methods as fission and activation gases.

Prior to and after the release of gas as a result of purging containment, lodines are sampled using a charcoal filter and particulates are sampled using a particulate filter. These filters are analzed for each significant isotope using a Ge(Li) detector. The total activity released is based on containment volume and purge rate with activity buildup while purging being considered.

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2. Continuous releases During the release of gas from the main vents, samples of iodines and particulates are collected using a charcoal and particulate filter respectively. The filters are removed weekly and are analyzed for each significant isotope using a Ge(L1) detector. The total activity released for the week is based on the activity found on the filters multiplied by the main vent flow for the week. The activity on the filters is corrected for decay and buildup during the sample period.

These weekly particulate filters are then composited to form monthly and quarterly composites at which time gross alpha and strontium 89 and 90 are analyzed.

C. Liquid Effluents:

1. Batch releases Prior to the release of liquid from a monitor tank, a sample is collected and analyzed for the coricentration of each significant gamma energy peak to demonstrate compliance with Section 1.C.1 above using the water flow rate in each discharge conduit into which the effluent is discharged at the time of discharge. The total activity released in each batch is determined by multiplying the volume released times the concentration of each isotope. The actual volume released is based on the difference in tank levels prior to and af ter the release. A proportior.al composite sample is also withdrawn for each week's releases, and this is used in turn to prepare monthly and quarterly composites for use in analyses of gross alpha and strontium 89 and 90.
2. Continuous releases Steam generator blowdown is sampled daily and these samples are used in turn to prepare a weekly blowdown composite based on each day's blowdown. The weekly composite is analyzed for each significant isotope using a Ge(LI) detector and these results are multiplied by the actual quantity of blowdown to determine the total activity released. The weekly composite is also used to prepare monthly and quarterly composites for use in analyses of tritium, gross alpha, and strontium 89 and 90.

D. Estimation of Total Error

Total error on all releases was estimated using as a minimum the random counting error associated with typical releases. In addition to the random error the detector to sample geometry systematic error
during gamma counting was determined. This included an estimate of
sample volume error and sampic pipetting error. More specifically the following other systematic errors were also examined
1. Liquid
a. Error in volume of liquid released prior to dilution during batch releases.
b. Error in volume of liquid released via steam generator blowdown.
c. Error in amount of dilution water used during the reporting l

period.

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2. Gases
a. Error in main vent release flow,
b. Error in sample flow rate.
c. Error in containment purge release flow.
d. Error in gas decay tank pressure. t Where errors could be estimated they were usually considered additive.

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V. BATCH RELEASES A. Liquid:

3rd 4th Quarter Quarter

1. Number of batch releases 3.00E+01 2.60E+01
2. Total time period for batch 2.96E+02 2.71E+02 release (hours)
3. Maximum time period for a 1.56E+03 6.75E+02

. batch release (min)

4. Average time period for batch 5.91E+02 6.25E+02 releases (min)
5. Minimum time period ior a 2.70E+01 5.50E+01 batch release (min)
6. Average stream flow during periods 4.64E+06 4.64E+06 of effluent into a flowing stream (liters / min of dilution water)

B. Gaseous:

3rd 4th Quarter ,Q uarter

1. Number of batch releases 2.10E+01 1.10E+01
2. Total time period for batch 2.29E+04 1.69E+03 releases (min)
3. Maximum time period for a batch 8.37E+03 3.55E+02 release b'M
4. Average time period for batch 1.09E+03 1.54E+02 release (min)
5. Minimum time period for a batch 5.50E+01 5.00E+00 release (min)

_9-VI. ABNORMAL RELEASES A. Liquid:

3rd 4th Quarter Quarter

1. Number of releases 2. Total activity released (Curies)2]

B. Gaseous 3rd 4th Quarter Quarter _

l. Number of releases 1
2. Total activity releases (Curles) 3.86E+01 2/ Excluding tritium and dissolved gases i

? TABLE 1 A - REG. GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF - 1981 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 3rd 4th Est. Total A. Fission and activation gases Units Quarter Quarter Error, %

1. Total Release Ci 6.00E+02 7.92E+02 2.15E+01
2. Average release rate for period uCi/sec 7.61 E+01 1.01 E+02
3. Percent of tech. spec. limit (1)  % 3.71E-01 5.37E-01
4. Percent of tech, spec limit (2)  % 3.90E-01 4.20E-01 B. lodines
1. Total iodine - 131 Ci 3.79E-03 4.00E-03 1.84E+01
2. Average release rate for period uCi/sec 4.81E-04 5.08E-04
3. Percent of tech. spec. limit (3)  % 3.97 E-01 3.38E-01
4. Percent of tech. spec, limit (4)  % 2.42E+00 1.88E+00 C. Particulates
1. Particulates with half lives > 8 days Ci 4.88E-05 7.54E-03 1.84+01
2. Average release rate for period uCi/sec 6.19E-06 9.57 E-04
3. Percent of tech. spec. limit (3)  % 3.97 E-01 5.37E+01
4. Gross alpha radioactivity Ci <.2.84E-06 43.53E-06 D. Tritium
1. Total Release Ci 2.56E-01 5.68E-02 2.13E+01
2. Average release rate for period uCi/sec 3.25E-02 7.20E-03
3. Percent of tech. spec. limit (6)  % 3.71E-01 5.37E-01 l

(1) Percent of I.A.2 for each quarter (2) Percent of I.A.3 for previous 12 months (3) Percent of I.B.2 for each quarter (4) Percent of 1.B.3 for previous 12 months l

l (5) Percent of Technical Specification limits for iodines including particulates>8 days l

(6) Percent of Technical Specification limits for gases includes tritium

. TABLE IC REG. GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT SECOND HALF - 1981 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode 3rd 4th 3rd 4th

1. Fission and activation gases Unit Quarter Quarter Quarter Quarter krypton - 85m Ci 1.12E+01 4.58E+01 krypton - 88 Ci 6.12E-02 4.42E-01 xenon - 131m Ci 2.90E+00 7.41E+00 xenon - 133 Ci 2.65E+02 4.84 E+02 2.94E+02 1.97E+02 xenon - 133m Ci 2.43E+01 9.76E-01 xenon - 135 Ci 2.84E+00 3.52E+01 argon - 41 Cl 1.36E-01 9.18E-01 krypton - 87 C1 2.28E-02 2.60E-01 total for period C1 2.65E+02 4.84E+02 3.35E+02 3.08E+02
2. Halogens lodine - 131 Ci 3.76E-03 4.00E-03 2.70E-05 2.83E-07 lodine - 132 Ci 3.60E-04 4.00E-05 1.21 E-08 lodine - 133 Ci 1.71E-03 2.l lE.03 2.25E-05 1.78E-07 lodine - 135 Ci 3.20E-04 1.56E-03 4.16E-08 bromine - 82 Ci 1.49E-07 total for period Ci 6.15E-03 7.67E-03 8.95E-05 6.64 E-07 I
3. Particulates strontium - 89 Ci 7.07E-07 6.14 E-07 strontium - 90 Ci 8.43E-07 7.82E-07 rubidium - 88 Ci 7.06E-03 cobalt - 60 C1 2.14E-07 cesium - 138 Ci 8.96 E-06 7.03E-05 barium - 140 Ci 3.40E-06 1.28E-04 1.00E-05 lanthanum - 140 Ci 1.76E-05 2.76E-04 bromine - 82 C1 2.76E-06 barium - 139 Ci 1.58E-08 cesium - 134 Ci 6.10E-07

! cerium - 139 Ci 1.08E-07 cesium -137 Ci 1.52E-06 total for period Ci 2.46E-05 4.05E-04 2.42E-05 7.13E-03

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TABLE 2A REG. GUIDE.1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEM1 ANNUAL REPORT SECOND HALF - 1981 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 3rd 4th Est. Total A. Fission and activation products Units Quarter Quarter Error, %

1. Total release (not including tritium, gases, alpha) Ci 6.69 E-01 3.09E-01 2.16E+01
2. Average diluted conuntration during period uCi/ml 1.18E-09 5.12E-10
3. Percent of applicable limit  % 1.18E+00 3.12E-01 B. Tritium
1. Total release Ci 2.33E+02 3.60E+02 1.81+01
2. Average diluted concentration during period uCi/mi 4.14E-07 5.99E-07
3. Percent of applicable limit  % 1.38 E-02 2.00E-02 C. Dissolved and entrained gases
1. Total release Ci 1.72E+00 8.74E-01 2.00E+01
2. Average diluted concentration during period uCi/ml 3.05E-09 1.45E-09
3. Percent of applicable limit  % 1.02E-01 4.83E-02 D. Gross alpha radioactivity
1. Total release Ci <,1.27E-01 4 1.15E-03 3.00E+00 l

l E. Volume of Waste Releases (prior to dilution) liters 1.10E+07 7.19E+06 3.00E+00 F. Volume of dilution water used during period liters 5.65E+11 6.03E+11 1.40E+01

TABLE 2B REG. GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF - 1981 LIQUID EFFLUENTS Continuous Mode (1) Batch Mode 3rd 4th 3rd 4th Nuclides Released Units Quarter Quarter Quarter Quarter strontium - 89 Ci < 4.90E-05 8.83E-03 9.99E-04 strontium - 90 Ci < 4.90E-05 2.56E-02 5.59E-05 cesium - 134 Ci 1.29E-02 2.44E-02 cesium - 137 C1 2.60E-02 5.43E-02 lodine - 131 Ci ( 2.74E-03 9.81E-02 1.32E-01 cobalt - 58 Ci 2.20E-01 5.00E-02 cobalt - 60 Ci 2.68E-02 6.27E-03 manganese - 56 C1 2.55E-04 manganesc - 54 Ci 1.82E-01 6.44E-03 chromium - 51 Ci 1.65E-02 2.72E-03 zirconium - 95 C1 3.17E-03 niobium - 95 C1 4.04E-03 2.19E-03 molybdenum - 99 Ci 5.33E-04 barium - 140 Ci 3.07E-03 antimony - 124 Ci 2.79 E-04 iodine - 133 C1 2.85E-02 2.23E-02 antimony - 125 Ci 3.08E-03 1.82E-03 cerium - 141 Ci silver .10m Ci 9.31E-04 lanthanum - 140 Ci 6.84E-03 2.21E-03 unidentified Ci ( 4.08E-03 <1.42E-03 <, 3.60E-03 Total for period Cl 6.92E-03 6.69E-01 3.09E-01

TABLE 2B REG. GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF - 1981 LIQUID EFFLUENTS Continuous Mode (1) Batch Mode 3rd 4th 3rd 4th Nuclides Released Unit Quarter Quarter Quarter Quarter Xenon - 133 Ci < 4.86E-03 1.67E4 0 8.62E-01 Xenon - 135 Ci 1.41E-02 1.04E-03 Xenon - 133m Ci 5.52E-03 6.56E-03 Xenon -131 m Ci 2.21E-02 4.74E-03 (1) Continuous mode releases, i.e. nuclides released, l are less than " unidentified" unless otherwise noted.

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TABLE 3A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF - 1981 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL ON DISPOSAL (NOT IRRADIATED FUEL) 6-Month E:,t. Total

1. Type of Waste Unit Period Error %
a. Spent resin, filter sludge m3 1.44E+01 2.00E+01 evaporator bottoms, etc. Ci 1.05E+01
b. Dry compressible waste, m3 6.66E+01 5.00E+01 contaminated equipment, etc. Ci 1.96E-01
c. Irradiated components, control m3 3.09E+01 5.00E+01 rods, etc. C1 2.10E+00
d. Other (describe) -- .- -
2. Estimate of major nuclides (by type of waste)

Units

a. Cobalt - 58  % 3.48E+01 Cesium - 137  % 2.97 E+01 Cesium - 134  % 2.03E+01 Manganese - 54  % 4.70E+00 Cobalt - 60  % 5.80E+00 Antimony - 122  % 1.12E+00
b. Cobalt - 60  % 1.74E+01 Cobalt - 58  % 2.63E+01 Cesium - 137  % 4.13E+01 l Cesium - 134  % 1.06E+01

! Manganese - 54  % 2.60E+00

c. Cobalt - 60  % 1.98E*01 l Cobalt - 58  % 2.18E+01 l Antimony - 122  % 2.80E+00 i Niobium -95  % 6.30E+00 Antimony - 125  % 4.31E+01 i Manganese - 54  % 3.30E+00
d. - -- --

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TABLE 3A (CONTINUED)

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 12 Motor surface transit Barnwell, S. C.

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