ML20010F092

From kanterella
Revision as of 10:34, 17 February 2020 by StriderTol (talk | contribs) (StriderTol Bot change)
(diff) ← Older revision | Latest revision (diff) | Newer revision → (diff)
Jump to navigation Jump to search
Semiannual Effluent Release Rept,Jan-June 1981.
ML20010F092
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 08/31/1981
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20010F090 List:
References
NUDOCS 8109090358
Download: ML20010F092 (17)
v • d • e


Text

'

i

.l c , l

. i SEMIANNUAL EFFLUENT RELEASE REPORT FOR CALVERT CLIFFS NUCLEAR POWER PLANT FIRST HALF - 1981 t

LIST OF ENCLOSURES TITLE PAGE/ TABLE Regulatory Limits 1 Maximum Permissible Concentration 3

! Measurements and Approximation of Total Radioactivity 3 l

Batch Releases 8 Abnormal Releases 9 Gaseous Effluents - Sun mation of Releases IA Gaseous Effluents - Isotopic Breakdown IC l

Liquid Effluents - Summation of Releases 2A Liquid Effluents - Isotcpe Breakdown 2B L

Sofia Waste Shipments 3A l

l

~

8109090358 810831 PDR ADOCK 05000317 R PDR

4 i

CALVERT CLIFFS NUCLEAR POWER PLANT '

- EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SUPPLEMENTAL INFORM ATION - _

Facility- Calvert Cliffs 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 Oi ,

5 (3.85 x 10 )(MPC)il where Qi is the release rate in Ci/sec for isotope i and MPCI is the maximum permissible concentration of Irotope i as defined in Appendix B, Table II, Column I,10 CFR 20.

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

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

l 1 Submitted in accordance with Section 5.6.1.b ci Appendix B of the Environmental Technical Specifications

s 4 ; ,

9 Y

- 3. The release rues of gross gasecus 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 >S 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 effluents shall not exceed 2.0 uCI/sec (I-131 equivalent).

l

2. The release rates of I-131 and particulates shall not exceed 8 percent of the vdue specified in I.B.I. above when averaged over any calendar quarter.

See Table IA,B3.

! 3. It should be noted that " iodines" as used here includes only iodine-131 since l

[ the technical specifications only refer to it specifically. Such other l

iodines, i.e., iodine-133, iodine-135, etc., are treated as gross activity and are included in I. A.I. and I.A.2.

4. T;,e release rates of I-131 and particulates shall not exceed 4 percent of the e

values specified in I.B.I. above when averaged over any 12 cer;,ecutive months. See Table IA, B4.

l C. Liquid Effluents:

l. The release rate of radioactive liquid effluents, l excluding tritium and noble gases, shall not exceed 10 t

l curies per unit during any calendar quarter

2. The raficactivity release concentrations in liquid effluents from the plar c l

l shall not exceed the values specified in 10 CFR Part 20, Appendix B, for.

unrestricted areas.

F

I

)

. l l

l II.MXIMUM PERMISSIBLE CONCENTRATIONS The MPC's used for radioactive materials released in licuid 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 rastrictive (lowest)'APC found i

for each isotope is used regardless of solubi!Uy.

l The following limits were used to calculate the percent of applicable limit in T5ble 2A.

A. Fission and Activation Products - Limit used I 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 uCi/ml.

This limit 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 EN?RGY - not applicable s

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 scmple is collected and analyzed for each significant isotope using a i

Ge(Lj) detectcr. The total activity released is based on the

! pressure / volume relationship (gas laws) of the tank prior to and after the release.

i n - e v, * - - w

l l

i s

_4 s

Prior to and af ter the release of gas as a result of purging f 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 ourging 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.

l B. Iodine and Particulates:

1. Batch releases l

Total activity released from a pressurized gas decay tank as iodines t

and particulates is measured by the same methods as fission and i

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 sampled using a particulate filter. These filters are I analzed for each significant isotope using a Ge(Li) dctector. The total activity releasc:is based on containment volume and purge rate l i

with activity buildup while purging being considered. '

I i

l

~

.l l

t A

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. ".he filters are removed weekly and are analyzed for each significant isotope using a Ge(Li) detector. The total activ ty 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 l Prior to the release of 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 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 actua' volume released is based on the difference in tank levels prior to and af ter the release. A prooortional 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.

h

- (, .

2. Continuous releases Steam generator blowdown is sampled daily and these samples are used in turn te prepare a weekly blowdown composite based on each day's blowdown. The weekly composite is analyzed for each significant Isotope using a Ge(U) detector and these results are multiplied by the actual quantity of blowdown to determine the total i

L activity released. The weekly composite is also used to crepare monthly and quarterly con ~", sites for use in analyses of tritium, gross i

aloha, and strontium 89 and 90.

l i D. ' Estimation of Total Error l

Total error on all releases was estimated using as a minimum the l

! random counting error associated with typical releases. In addition to l

l the random error the detector to sample geometry systematic error during gamma counting was determined. This included an estimate of f sample volume error and sample 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 period.

L

. . _ . _ ~ .-.

s I

.7.

2. Gases t

l a. Error in main vent release flow.

l

b. Error in sample flow rate.
c. Error in containment purge release flosv.

, d. Error in gas decay tank pressure.

l Where errors could be estimated they were usually considered j additive.

l l

l l

l l

--- ~,

. . _ . - - ~ ~ - _ - _

~

i r

I l V. BATCH RELEASES, *

.A. Liquid:

1st 2nd Quarter Quarter

1. Number of batch releases 4.70E+01 6.60Et 0!
2. Yotal time period for batch '3.83E+02 2.68E+ 02 l release (hours) l.

l 3. Maximum time period for a 1.79E+03 1.06E+03 batch release (min) l

4. Average time period for batch 4.89E+02 2.44E+02 releases (min)
5. Minimum time period for a 2.80E+01 2.50E+01 -

batch release (min)

\

l 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:

Ist. 2nd Quarter Quarter

1. Number of batch releases 1.20E+01 2.00E+01
2. Total time period for batch '

7.34E+04 1.25E+04 releases (min) '

3. Maximum time period for a batch 6.44 E+04 4.32E+03 release (min)
4. Average time period for batch 6.13E+03 6.25E+02 release (min)
5. Miniraum time period for a batch 9.80E+01 1.30E+01 I

release (min)

I I

)

'l

.- . - .. -, .. + , , , ,__ .._ . - . . . . . . . . . _ . , . _ _ . - - . . . _ , . . . , , . - . . _ , . .

VI. ABNORMAL RELEASES A. Liquid:

1st 2nd Quarter Quarter

1. Number of releases 2. Total activity released (CuriesN 2_/ Excluding tritium and dissolved gases B. Gaseous 1st 2nd l Ouarter Ouarter I
1. Number of releases l
2. Total activity releases (Curies) l I

f I

~

TABLE l A - REG. GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF - 1981 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES ist 2nd Est. Total A. Fission and activation gase; Units Quarter Quarter Error, %

1. Total Release C1 2.92E+02 4.93E+02 2.15E+01
2. Average release rate for period uCI/sec 3.71 E+01 6.26E+01
3. Percent of tech spec. limit (1)  % 2.09E-01 3.48E-01
4. Percent of tech. spec. limit (2)  % 3.23E-01 3.94E-01 B. lodines
1. Total lodine - 131 Ci 990E-03 1.95 E-02 1.84E+01 l
2. Average release rate for period uCi/sec 1.26E-03 2.47id-03
3. Percent of tech. spec. limit (3)  % 7.94E-01 1.59 E+00
4. Percent of tech. spec. limit (4)  % 1.14E+00 2.29E+00 i

C. Particulates

! 1. Partichtes with half lins 8 days Ci 9.64E-04 1.12E-03 1.84+01

~

2 Average release rate for period uCi/sec 1.22E-04 1.42 E-04

3. Percent of tech spec. limit (5)  % 7.94E-01 1.59E+00 4 Gross alpSs radioactivity Ci 1.33E-06 1.52E-06 D. Tritium l 1. Total Release Ci 3.50E+00 2.00E+00 2.18E+01
2. Average release cate for period uCi/sec 4.44 E-01 2.54 E-01

- 3. Percent of tech. spec. limit (6)  % 2.09E-01 3.94E-01 (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 I.B.3 for previous 12 months

, (5) Percent of technical specification limits for iodines including particulate 8 days (6) Percent of technical specification limits for gases includes tritium l

L TABLE IC REG. GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT FIRST HALF - 1981 GASEOU3 EFFLUENTS- GROUND LEVEL RELEASES Continuous Mode Batch Mode 1st 2nd 1st 2nd l

1. Fission and activation gases Unit Quarter Quarter Ouarter Quarter krypton - 85m Ci 5.86E-02 3.30E-02 krypton - 88 Ci 9.80E-03 4.10E-03 xenon - 131m Ci 3.60E-03 1.00E+20 xenon - 133 C1 2.13 E+02 3.30E+02 7.70E+01 1.60E+00 xenon - 133m Cl 8.40E-02 2.20E-01 xenon - 135 Ci 1.90E+00 2.20E+00 argon - 41 C1 4.90E-03 2.60E-02 total for period Ci 2.13E+02 3.30E+02 7.91 E+01 1.63E+02 i '
2 Halogens iodine - 131 Ci 5.51 E-03 1.81E-02 -4.39E-03 1.40E-03 lodine - 132 Ci 1.10E-06 1.20E-03 l

lodine - 133 Ci 2.66E-03 4.72E-03 8.40E-03 lodine - 135 Cl 8.20E-06 bromine - 82 Ci 1.2'0E-05 3.30E-05 total for period Ci 8.17 E-03 2.28E-02 5.24 E-03 2.60E-03

3. Particulates  ;

strontium - 89 Ci 5.71 E-05 7.75E-05

! strontium - 90 Ci 2.00E-05 4.05 E-05 cerium - 141 Cl 5.40E-08 5.30E-07 ruthenium - 103 Ci rubidium - 88 Ci 5.80E-04 1.00E-03 cobalt - 60 Ci 3.00E-04 cesium - 138 Cl 5.80E-06 3.70E-06 cobalt - 58 Cl 9.80E-07 total for period Ci 7.81E-05 1.19E-04 8.86E-04 1.00E-03 m

TABLE 2A REG. GUIDE.1.21 CALVERT CLIFFS Nt1CLI:AR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF - 1981 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES ist 2nd Est. Total A. Fission and activation products Units Quarter Quarter Error, %

1. Total release (not including tritium, gases, alpha) Ci 1.27E+00 4.31 E-01 2.16E+01
2. Average diluted concentration during period uCi/ml 2.41-09 7.52E-10
3. Percent of applicable limit  % 2.41 +09 7.52E-01 B. Tritium
1. Total release Cl 1.67 E+02 2.41 E+02 1.81 +01
2. Average diluted concentration during period uCi/mi 2.82E-07 4.21 E-07
3. Percent of applicable limit  % 9.40E-03 1.40 E-03 C. Dissolved and entrained gases
1. Total release Cl 2.69E-01 1.12E+00 2.00E+01
2. Average diluted concentration during period uCl/ml 4.54 E-10 1.95E-09
3. Percent of applicable limit  % 5.73 E-02 6.52E-02 D,' Gross alpha radioactivity
1. Total release Ci 4 4.81 E-04 < l.21E+03 3.00E+00 E. Volume of Waste Releases (prior to dilution) liters 1.13E+07 9.23E+06 3.00E+00 F. Volume of dilution water used during period liters 5.93E+11 5.73E+ 11 1.40E+01

..r , _ - e e-

TABl.E 213 REG. GillnE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1981 LIOUID EFFLUENTS Continuous Mode (1) Batch Mode Ist 2nd 1st 2nd Nuclides Released Units Quarter Quarter Ouarter Ouarter strontium - 89 Ci <, 2.05 E-0 5 <l.21.E-05 1.17 E-02 3.89E-04 strontium - 90 Ci ( 2.10 E-05 < l .24 E-0 5 9.35 E-04 3.35 E-04 cesium - 134 Ci 1.13 E-02 2.12E-03 cesium - 137 Cl 1.90E-02 3.53 E-03 lodine - 131 C1 ( 3.19E-03 ( l.92E-03 5.50 E-02 2.15E-02 cobalt - 58 Ci 8.0sii-01 1.89E-01 cobalt - 60 Cl 9.34 E-02 8.28 E-02 manganese - 56 Ci 3.90E-06 3.98E-06

- 54 Ci

~

manganese 1.77 E-01 1.59E-02

~

chromium - 51 Ci 1.28E-02 7.32 E-03 zirconium - 95 Ci 2.45 E-03 1.19E-02 niobium - 95 Ci 9.74 E-03 4.29 E-04 molybdenum - 99 Ci 1,'IE-03 1.97 E-0 5 barium -140 Ci 9.6 t E-04 antimony - 124 Ci 6.93E-0I cobalt - 57 Cl 8.61Fe04 tin - 113 Ci 3.15E-04 2.94 E-03 ruthenium - 103 Ci 4.45 E-04 lodine - 133 Cl 5.23 E-03 2.87 E-03 antimony - 125 Ci 4.62 E-02 2.47E-02 zirconium - 97 Ci 5.36E-04 cerium - 144 Ci 2.87 E-03 ruthenium - 106 Ci 1.07E-02 cerium - 141 Ci 6.58E-06 silver - 110m C1 3.85 E-03 1.14 E-02 lanthanum - 140 Ci 7.27 E-05 2.86E-02 unidentified Ci ( 3.90E-03 < 2.30E-03 5.54 E-05 5.42E-03 Total for period Ci 7.13-03 4.24 E-03 1.26E+00 4.27E-01

a

.. ) -

TABLE-2B REG. GU10E 1.21

~

. CALVERT CLIFFS NtICLEAR POWER PLANT l EFFLUENT AND WASTE DISPOSAL SCMIANNUAL REPORT t FIRST HALF - 1981 ~

1

-LIOUID EFFLUENTS Cor.tinuous Mode (1) Batch Mode 1st .2nd 1st 2nd Nuclides Released Unit Quarter Quarter, Quarter Ouarter

! Xenon - 133 Ci 5.67 E-03 3.42E-03 2.55E-01 1.llE+00 l .p Xenon - 135 Ci 8.88 E-03 6.01 E-03 l Xenon - 133m Ci 2.77E-03 (1) Continuous mode releases, i.e. nucides released, t e less than " unidentified' unless otherwise noted.

i l

I i

l l

i

\

an t- - - ,,- -- ,-

TABLE 3A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT -

FIRST HALF - 1981 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLIO WASTE SHIPPED OFFSITE FOR BURIAL ON DISPOSAL (NOT IRRADIATED FUEL) 6-Month Est. Total

1. Type of Waste Unit Period Error %
a. Spent resin, filter sludge, . m3 3.85E+01 2.00E+01 evaporator bottoms, etc. Cl 8.35E+01 i
b. Dry compressible waste, m3 2.2SE+02 5.00E+0i contaminated equipment, etc. C1 2.20E+00
c. Irradiated components, control m3 1.25E+02 5.00E+01 rods, etc. Ci 7.11 E-02 l
d. Other (describe) - - -
2. Estimate of major nuclides (by type of waste)

Units

a. Cobalt - 58  % 2.52E+01 Cesiu . - 137  % 2.34E+01 Cesium - 134  % 1.87 E+01 Manganese - 54  % 1.61d+01 Cobalt - 60  % 1.60E+01
b. Cobalt - 60  % 7.23E+01 Cobalt - 58  % 1.60E+01 Cesium - - 137 %_ 6.38E400 Cesium - 134  % 2.26E+00 Manganese - 54  % l66E+00 Niobium - 95  % 1.03E+00 c.- Cesium - 137  % 3.53E+01 Cobalt - 60  % 2.21E+01 Cobalt - 58  % 1.72 E+01 Cesium - 134  % 7.28E+00 .

Niobium - 95  % 6.68E+00 l 3.96500 Antimony - 125  %

Manganese - 54  % 3.79E+00 l Chromium - 51  % 2.30E+00 Zirconium - 95  % 1.36E+00 j

d. --- - -

j I

TABLE 3A (CONTINIUED)

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 30 Motor surface transit Barnwell, S. C.
Retrieved from "https://kanterella.com/w/index.php?title=ML20010F092&oldid=2473736"