ML20087D192

From kanterella
Jump to navigation Jump to search
Semiannual Effluent Release Rept, Second Half 1983
ML20087D192
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 12/31/1983
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20087D167 List:
References
NUDOCS 8403130314
Download: ML20087D192 (17)
v • d • e


Text

_

SEMI-ANNUAL EFFLUENT RELEASE REPORT FOR CALVERT CLIFFS NUCLEAR POWER PLANT SECOND HALF - 1983 LIST OF ENCLOSURES TITLE PAGE Regulatory Limits 1 Maximum Permissible Concentration 2 Measurements and Approximation of Total Radioactivity 3 Batch Releases 7 Abnormal Releases 3 h Gaseous Effluents - Summation of Releases 9 i

Gaseous Effluents - Isotopic Breakdown 10 Liquid Effluents - Summation of Releases 12 Liquid Effluents -Isotope Breakdown 13 Solid Waste Shipments 16 I.

i:

8403130314 840301 PDR ADOCK 05000317 i R Pm

. . _ - - - _ _ _ _ _ _ - _ _ _ _ _ _ ._ J

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 1/

SUPPLEMENTAL INFORMATION Facility - Calvert Clifis Nuclear Power Plant Licensee - Baltimore Gas & Electric Company I. REGULATORY LIMITS 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 Qi (g 5

(3.85 x 10 ) (MPC):

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 1,10 CFR 20,

2. The release rates of gross gaseous activity shall not exceed 16 percent of the values specified in I.A.I. above when averaged over any calendar quarter. See Table I A, A3.
3. The release rates of gross gaseous activity shall not exceed 3 percent of the values specified in I.A.I. above when averaged over 12 consecutive months. See Table I A, A4 M Submitted in accordance with Section 5.6.1.b of Appendix B of the Environmental Technical Specifications I

)

__ _ _ _ _ _ A

B. j lodines and Particulates, Half-Lives >3 Days:

1. The release rate from the main vents of I-131 and particulates with half-s lives greater than eight days released to the environment as part of airborne effluents shall not exceed 2.0 uCl/sec.

4 1

2. The release rates of I-131 and particulates shall not exceed 3 percent of the value specified in I.B.I. above when averaged over any calendar quarter. See Table I A, B3.
3. It should be noted that "ibdines" as used here includes only iodine-131 since the Technical Specifications only refer to it specifically. Such other lodines, i.e., lodine-133, lodine-135, etc., are treated as gross 5 activh:y and are included in I.A.I. and I.A.2.

4 The release rates of I-131 and particulates shall nct exceed 4 percent of the valuc.specified in I.B.1 above when averaged over any 12 consecutivb fnonths. See Table I A, B4.

\ \

C. Liquid Effluents: N

1. The release rate of radioactive liquid effluents, excluding tritium and i

s 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 i, B, for unrestricted areas.

II. MAXIMUM PERMISSIBLE CONCENTRATIONS The MPC's used for radioative materials released in liquid and gaseous effluents are

. in accordance with Technical Specifications and/or are derived from the use of notes to Appeddix 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 1 x 10-7 uCi/ml. This limit was used as given in the notes to Appendix B, Table II, Column 2 of 10 CFR 20.

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

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

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

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

III. AVERAGE 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 ter the release.

Prior to and after the release of gas as a result of purging containment, I- samples are collected aad 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.

~" ' '

~ _ . . _ _ _ _ . _ _ _ . . _ . _ . _ . . _ _ _ .

s

. t; .

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 from 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, iodines are sampled using a charcoal filter and particulates are san; pled using a particulate filter. These filters are analyzed fur each significant isotope using a Ge(Li) detector. The total activity rele used is based on containment volume and purge rate with activity buildup while purging is being considered.

2. Continuous releases During the release of gaa 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(Li) 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 fiiters 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 rross alpha and strontium 89 and 90 are analyzed.

C. Liquid Effluents:

1. Batch releases Prior to the release cf liquid from a monitor tank, a sample is collected and analyzed for the concentration of each significant gamma energy peak to demonstrate compliance with Section I.C.1 above using the water flow rate in each dischcrge 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 Jevels prior to and after the release. A proportional 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 S? 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 39 and 90.

-m umi mumm i m

_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 sample pipetting error. More specifically the following other systematic errors were also examir.ed:

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 period.

' 2. Gases I 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.

Where errors could be estimated they were usually considered additive.

l

- 7-V. ' BATCH RELEASES 3rd 4th Quarter Quarter

~ A. Liquid:

<1. - Number of batch releases 6.40E+01 4.70E+01

2. Total time period for batch 2.38E+02 3.05E+02

.. , release (hours)

n
3. Maximum time period for a -

6.50E+02 7.85E+02 batch release (min)

4. Average time peric,d for batch 2.23E+02 3.89E+02 releases (min)
5. Minimum time period for a 2.60E+01 2.50E+01 batch release (min)
6. Average stream flow during periods 4.64E+06 4.64E+06 l of effluent into a flowing stream (liters / min of dilution water)

-B. Gaseous:

'l. Number of batch releases 6.50E+01 5.20E+01

2. Total time period for batch - 1.67E+04 7.10E+04

- releases (min)

3. . Maximum time period for a batch 2.28E+03 9.72E+03 release (min)
4. Average time period for batch 2.57E+02 1.36E+03 ,

release (min)

5. Minimum time period for a batch 5.60E+01 1.30E+01 release (min) .

9 t

, - . - -,,,--e v---, ,,,v.., . ~- --- ,- .--,--,m.-- y. ----,,,,n.,-wg- < ..g.,, ,,1 -- ,,-- , -

, ,-----.,.w,v,,

U .-

. VI. ABNORMAL RELEASES 3rd 4th Quarter Quarter

- A. Liquid:

1. Number of releases 2. Total activity released (Curies) 2_/ B. Gaseous: -
1. - Number of releases - 2. Total activity releases (Curies) 2/ Excluding tritium and dissolved gases s>

-rW - - -w., n- n-,y---em we m- - , , - - - - - g -r-g-s , , , ~ .,- , - , -,-v., --av.-- . r-- +- - - , ---

TABLE l A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1983 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 3rd 4th Est. Total A, Fission and activation gases Units Quarter Quarter Error, %

1. Total Release Ci 2.25E+03 1.82E+03 2.15E+01
2. Average release rate for period uCi/sec 2.S6E+02 2.31 E+02
3. Percent of tech. spec. limit (1)  % 1.63E+00 1.44E+00
4. . Percent of tech. spec. limit (2)  % 3.38E +00 3.69E+00 B, -Iodines
1. Total iodine - 131 Ci 1.00E-02 5.52E-02 1.84E+01

-2. Average release rate for period uCi/sec 1.27E-03 7.02E-03

3. Percent of tech. spec. limit (3)  % 7.94E-01 4.39E+00
4. Percent of tech. spec. limit (4)  % 1.66E+00 3.78E+ 00

~

C, Particulates

~

1. Particulates with half lives greater than 8 days Ci 8.18E-06 1.34E-04 1.84E+01
2. ' Average release rate for period uCi/sec 1.04E-06 1.70E-05
3. Percent of tech. spec. limit (3)  % 6.50E-04 1.07E-02 4.- Percent of tech. spec. limit (4)  % 3.28E-01 2.93E-01
5. Gross alpha radioactivity Ci 3.09E-06 4.53E-05

. D. Tritium

1. Total Release Ci 2.93E+ 00 3.72E+01 2.18E+01
2. Average release rate for period uCi/sec 3.72E-01 4.73E+00
3. Percent of tech. spec. limit (1)  % 3.02E-03 3.84E 02 (1)~ Percent of I.A.2 for each quarter

-(2) Percent of I.A.3 fer previous 12 months

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

TABLE IC REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT SECOND HALF - 1983 i

GASECUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode 3rd 4th 3rd 4th

'l.- Fission and activation gases Units Quarter Quarter Quarter Quarter krypton - 85m Ci 2.13E+00 1.23E+09

-krypton - 88 Ci 4.36E-01 2.35E-01 xenon - 131m Ci 8.19E+00 4.99E+00 xenon - 133 C1 3.03E+02 5.55E+02 1.89E+03 1.22E+03 xenon - 133m Ci- 7.00E-01 1.13E+01 5.1IE+00 xenon' - 135 Ci 1.25E+01 3.59E+01 2.32E+01 4.54E+00 argon - 41 Ci 1.42E-01 1.95E-01 krypton - 87 Ci 9.48E-02 8.10E-02 krypton - 85 Ci 1.48E+00 1.50E+00 Total For Period C1 3.15E+02 5.91E+02 1.93E+03 1.23E+03

2. Halogens

. iodine - 131 Ci 9.94E-03 4.98E-02 1.16E-04 5.46E-03 iodine - 132 Ci 8.80E-03 5.36E-07 1.82E-02 iodine - 133 Ci 1.63E-02 3.43E-02 6.69E-05 1.02E-04

. lodine - 135 Ci 5.40E-03 5.19E-07 7.00E-08 bromine - 82 Ci 1.30E-05 1.91 E-06 3.97E-06 L~ Total For Period Ci - 2.62E-02 9.83E-02 1.85E-04 2.37E-02

TABLE IC REG GUIDE 1.21 (CONT'D) l CALVERT CLIFFS NUCLEAR POWER PLANT

(-

SECOND HALF - 1983 I

L GASEOUS EFFLUENTS - GROUND LEVEL RELEASES Continuous Mode Batch Mode 3rd 4th 3rd 4th

. 3. Particulates Units Quarter Quarter Quarter Quarter _

strontium - 89 Ci < 6.10E-06 <l.16E-06 strontium - 90 Ci < 9.01E-07 < 2.40E-06 rubidium - 88' Ci 1.68E-01 1.06E-02 cobalt - 38 Ci 3.83E-06 cesium - - 138* Cl 6.?8E-03 2.66E-05 cesium - 134 Ci cesium - - 137 Cl 1.18E-06 1.27E-04 Total For Period Ci <7.00E-06 <3.56E-06 1.74E-01 1.07E-02 0 Particulates with half lives less than eight days.

l TABLE 2A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1983 LIQUID EFFLUENTS - SUMM ATION 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 3.49E-01 5.40E-01 2.16E+01
2. Average diluted concentration during period uCi/ml 1.79E-09 2.96E-09 3.- Percent of applicable limit  % 1.78E+00 2.96E+00 E , Tritium
1. Total Release C1 2.40E+02 9.29E+01 1.81E+01
2. Average diluted concentration

- during period uCi/ml 1.22E-06 4.76E-07

3. Percent of applicable limit  % 's.07E-02 1.58E-02 C, ' Dissolved and entrained gases
1. Total Release Ci 7.62E-01 4.04E-01 2.00E+01
2. Average diluted concentration during period uCi/mi 3.93E-09 2.19E-09
3. Percent of applicable limit  % 1.31E-01 7.31E-02 D, Gross alpha radioactivity
1. . Total Release Ci 3.38E-04 2.09E-04 3.00E+00 E, Volume of Waste Releases (prior to dilution) liters 6.71E+06 ' 37E+06 3.00E+00 F. Volume of dilution water used during period liters 5.94E+11 5.63E+ 11 1.40E+01

TABLE 2B REG GUIDE 1.2_1_

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1983 LIQUID EFFLUENTS Continuous Mode (1) Batch Mode 3rd 4th 3rd 4th Nuclides Released Units Quarter Quarter Quarter Quarter strontium - - 89 C1 2.00E-04 <l.16E-03 strontium-  :- 90 Ci 1.07E-04 3.22E-04 cesium - 134 Ci 3.27E-02 2.33E-02 cesium - 137 Ci 5.83E-02 5.78E-02 lodine '- 131 Ci- 6.89E-02 5.61E-02 cobalt - 58 Cl 1.07E-01 2.35E-01 cobalt - 60 Cl 1.97E-02 1.93E-02 manganese - -54 Ci 1.67E-03 3,55E-03

' chromium - 51 Ci 5.41E-02 zirconium - 95 .Ci 8.00E-03 niobium - 95 Ci 3.73E-04 1.24E-02 molybdenum - 99 Ci 1.16E-03 1.51E-03 antimony - 124 Ci 5.74E-03 4.83E-03 iodine - 133 Ci 1.43E-02 6.40E-03 antimony - 125 Ci 1.96E-02 3.87E-02 cobalt Ci 4.39E-05 1.56E-05 silver - Il0m Ci 1.22E-02 9.49E-03 lanthanum - 140 Ci 7.91E-04 8.99E-04 tin ~- - 113- Ci 9.47E-04 sodium' - 24 Cl 9.69E-05 niobium- - 97 Ci 1.82E-03 2.82E-04 cesium - 136 Ci 9.38E-04

' zirconium - 97 Ci 2.61 E-04 ruthenium - 103 Ci 1.93E-03

TABLE 2B REG GUIDE 1.21 (CONT'D)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF _ 1983 LIQUID EFFLUENTS Continuous Mode (1) Batch Mode 3rd 4th 3rd 4th l Nuclides Released Units Quarter Quarter Quarter Quarter  !

antimony - 122 Ci 1.73E-04 2.39E-05 unidentified Ci <3.36E-03 < 3.69E-03 Tctal For Period Ci 3.49E-01 5.40E-01 I

t t

TABLE 2B REG GUIDE 1.21 (CONT'D)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1983 LIQUID EFFLUENTS Continuous Mode (1) Batch Mode 3rd 4th 3rd 4th Nuclides Released Units Quarter Quarter Quarter Quarter Xenon - 133 C1 2.65E-01 2.67E-01 Xenon - 135 Ci 3.90E-03 1.20E-03 Krypton - 85m Ci 7.69E-05 XGnon - 133ra Ci 7.55E-05 1.53E-03 (1)- Continuous mode releases, i.e., nuclides released, are less than " unidentified" unless otherwise noted.

TABLE 3A EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT ll SECOND HALF - 1983 I

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. ' . SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-Month Est. Total

11. Type of Waste Units Period Error %
a. - Spent resin, filter sludge m3 1.82E+01 evaporator bottoms, etc. Cj 9.05E+01 2.00E+01
b. Dry compressible waste, m 3.03E+02 contaminated equipment, etc. Cj 7.70E-01 5.00E+01 c.. trradiated components, m control rods, etc. Cj --
d. - Other (describe) m Ci

.2. .

LEstimate of major nuclides (by type of waste) la. Cobalt - - 58 2.30E+01%

Cesium - 137 3.14E+01%

.. Cesium - 134 1.66E+01%

' Manganese - 54 4.95E+00%

Cobalt - 60 1.44E+01%

Antimony - 122 1.30E+00%

, Strontium - 90 1.30E+00%

Antimony. - 125 2.14E+00%

-Zirconium - 95 1.09E+00%

Niobium - 95 3.06E+00%

- b. Cobalt - 60 2.96E+01%

Cobalt - 58 4.69E+01%

Cesium - 137 8.39E+00%

Cesium' - 134 3.69E+00%

Manganese - 54 2.59E+00%

Niobium - 95 1.75E+00%

Antimony - 125 3.30E+00%

- Zirconium - 95 1.17E+00%

Silver -llom 1.46E+00%

. 3. Solid Waste Disposition Number of Shipments Mode of Transportation. Destination 9 Motor surface transit Barnwell, S. C.

10 Motor surface transit Richland, Wash.

- _ _ _ - _ - _ _ - _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _

Retrieved from "https://kanterella.com/w/index.php?title=ML20087D192&oldid=2731871"