ML20212H270

From kanterella
Jump to navigation Jump to search
Semiannual Effluent Release Rept,Calvert Cliffs Nuclear Power Plant,Second Half - 1986
ML20212H270
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 12/31/1986
From: Tiernan J
BALTIMORE GAS & ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 8703060059
Download: ML20212H270 (13)
v • d • e


Text

..

SEMI-ANNUAL EFFLUENT RELEASE '1EPORT CALVERT CLIFFS NUCLEAR POWER PLANT

' SECOND HALF - 1986 P

TABLE OF CONTENTS

. I. REGUL ATORY LIMITS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 A. Fission and Activation Gases. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . I '

B. Iodines and Particulates with Half Lives Greater than Eight Days ........ ...1 C. L i quid E f f l uen ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 II. MAXIMUM PERMISSABLE CONCENTRATIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 A. Fission and Activation Gases. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 B. Iodines and Particulates with Half Lives Greater than Eight Day:, . . . . . . . . . . . 3 C. Li q uid E f fluen t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 III. ODCM REPORTING REQUIREMENTS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 IV. AVERAG E EN ERG Y . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 V. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY ....... 3 A. Fission and Activation Gases. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3

1. B at ch R elea ses . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3
2. Continuous R eleases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 B. . Iodine and Particulates . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
1. B a t ch R el ease s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
2. Con tinuous R eleases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 C. Liq ui d E f fluen ts . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
1. Ba tch R eleases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4
2. Continuous Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5 D. Estimation of Total Error . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5

, 1. Liquid..........................................................5

2. Gases...........................................................5 VI. BATCH RELEASES A. Liquid..............................................................6 B. G as eo us . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 VII. ABNORM AL RELE ASES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 A. Liquid..............................................................6 B. G a s eo u s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 TABLE _S I A - Gaseous Ef fluents - Summation of Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 IC - Gaseous Ef fluents - Ground Level Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 2A - Liquid Effluents - Summations of All Releases . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9 2B - Liq uid E f fluen t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 3A - Solid Waste and Irridated Fuel Shipments. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 11 0703060059 B61231 7 PDR ADOCK 0500 R - 9 ,

1

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SUPPLEMENTAL INFORMATION Facility - Calver: Cliffs Nuclear Power Plant Licensee - Baltimore Gas & Electric Company I. REGULATORY LIMITS A. Fission and Activation Gases -

1. The instantaneous release rate of noble gases in gaseous effluents shall not result in a site boundary dose rate greater than 500 mrem / year to the whole body or greater than 3000 mrem / year to the skin.
2. The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce gaseous emmissions when the calculated gamma dose due to gaseous effluents exceeds 1.20 mrad or the calculated beta dose due to gaseous effluents exceeds 2.40 mrad at the site boundary in a 92 day period.
3. The air dose at the site boundary due to noble gases released in gaseous effluents shall not exceed:

'- 10 mrad gamma radiation / quarter 20 mrad beta radiation / quarter 20 mrad gamma radiation / year 40 mrad beta radiation / year

4. All of the above parameters are calculated according to the methodology specified in ^he Offsite Dose Calculation Manual (ODCM).

B. Iodines and Partichlates with Half Lives Greater than Eight Days

1. The instantaneous release rate of lodines and Particulates in gaseous effluents shall' not result in a site boundary dose in excess of 1500 mrem / year to any organ.
2. The Gaseous Rad-Waste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gascous effluents when calculated doses exceed 1.8 mrem to any organ in a 92 day period at the site boundary.

I

\

Q ;o .

m -

" ~

'~

3. The' dose to a. member of the public at the site boundary from lodine-131

- and: Particulates with half lives is greater than eight e days in gaseous

' effluents shall not exceed:

'15 mrem to any organ per quarter s= 30 mrerr , any organ per year less than .1% of the above limits as a result of burning contaminated oil

4. - All of the above parameters are calculated according to the methodology specified in the ODCM.

. C. Liquid Effluents

1. The concentrations of radioactive isotopes in liquid effluents:from the

-- ' plant shall not exceed the values specified in 10 CFR, Part 20, Appendix B,

' for unrestricted areas.-

2. The liquid radwaste treatment system shall . be used to reduce the radioactive isotopes in liquid effluents from the plant when the calculated -

~

doses to unrestricted areas exceeds .36 mrem to the whole body, or 1.20 mrem to any organ in a 92 day period.

3. The dose to a member of the public in unrestricted areas shall not exceed:

3 mrem whole body dose per quarter 10 mrem dose to any organ per quarter 6 mrem whole body dose per year 20 mrem dose to any organ per year

4. All of the liquid dose parameters are calculated according to the methodology specified in the ODCM II. MAXIMUM PERMISSABLE CONCENTRATIONS A. Fission and Activation Gases Prior to the batch release of gaseous effluents, the gas activities are summed.

If the total does not exceed the dose rate lim *,tations for the most limiting isotopes, then the batch is released. If the most limiting isotope criteria is not met, then the detailed dose rate calculation is performed as described in the ODCM.

2

Yp:

b.

3 B. Iodines and Particulates with Half Lives Greater than Eight Days Compliance to the dose rate limitations from lodines and Particulates is demonstrated by calculating the maximum quantity that could be seen on a weekly sample. This is reduced by factor of 0.5 for conservatism. As long as the I-131 (most limiting isotope) releases in a seven day period do not exceed 12.5 Ci, then no further analysis are needed to verify compliance without exceeding the limits of 1.B.3.

C. Liquid Effluents The MPCs used for radioactive materials released in liquid 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 1. x 10-7 uC1/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.

Ill. ODCM REPORTING REQUIREMENTS No changes were made to the ODCM during the second half of 1986.

IV. AVERAGE ENERGY Not applicable V. 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 coll 6cted and analyzed for each significant gaseous isotope using a Ge(L1) detector. The total activity released is based on the pressure / volume relationship (gas laws) of the tank.

3

+ +- -- - -- -- - - -

y ' , ,p

+

t.1 7

)Q '*- , -

g

- Prior'to and after the release of gas as a result of purging containment,

._ samples are collected and analyzed for each'significant gaseous isotop-

, -using; a L Ge(LI). detector. The total activity -released is based on- '

r;

. . containment volume and purge rate with activity buildup while purging is ~

being conside red. .

. i

2. ,; Continuous ibileases -

During the release of gas from the main vents, samples are collected and -

analyzed at lenst weekly for each significant ,aseous_ isotope using a Ge(LI)l 7 detector.1 The total activity released for 4 e week is based on the total.-

sample activity multipl.ed by the main vent flow for the week.

~

m B. Iodine and Particulates. s

1. . l Batch Releases 1The total activity released from a pressurized gas decay tank, containment purges and containment vents as lodines and particulates is accounted for by the main vent ledine and particulate continuous samplers.
2. Continuous Releasei During the release of gas from the main vents, samples of lodines and

. particulates ~ are callected "using a charcoal and ' particulate filter respectively. The filters are removed. weekly and are analyzed for each C significant isotope utng a Ge(L1) detector. The total activity released for -

the week is based on the total sample activity found on the filters decay corrected to the midpoint of the sample period and multiplied.by the main vent flow for the week. The activity on the filters is corrected for decay

,- and buildup during the cample 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 waste tank, a sample is collected and

, analyzed for- the concentration of each significant gamma energy radionuclide to demonstrate compliance with Section I.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 i batch ' is 'determlncd 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 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, strontium 89 and 90, and Tritium.

t i

4 i

L, . 4- ,-_..,,--,_--,_,m,,-_..m.___ -.-,~__,,,m-,...,__.-__-.,__.,,,,.~._~,,_.--

r- ..

,, . ;a ~ -

o ,

N; s

[When steam generator blowdown is discharged to the circulating water

= . conduits, it 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. -

- 2. ' Continuous Releases None 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 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.
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.

Where errors could be estimated they were usually considered additive.

5 f

VI. BATCH RELEASES 1986 3RD 4TH QUARTER QUARTER A. Liquid -

1. Number of batch releases 5.30E+01 4.20E+01
2. Total time period for batch 3.51E+02 3.28E+02 release (hours)
3. Maximum time period for a 7.05E+02 6.25E+02 batch release (min)
4. Average time period for batch 3.98E+02 4.69E+02 releases (min)
5. Minimum time period for a 1.50E+01 1.80E+01 batch release (min)
6. Average stream flow during periods 4.54E+06 4.54E+06 of effluent into a flowing stream (liters / min of dilution water)

B. Gaseous

1. Number of batch releases 1.60E+01 2.20E+01
2. Total time period for batch 5.33E+03 7.59E+04 releases (min)
3. Maximum time period for a batch 2.83E+03 1.01E+04 rclease (min)
4. Average t!me period for batch 3.33E+02 3.30E+03 release (min)
5. Minimum time period for a batch 1.00E+01 1.00E +02 release (min)

VII. ABNORMAL RELEASES A. Liquid

1. Number of releases 2. Total activity released (Curles) B. Gaseous
1. Number of releases 2. Total activity releases (Curles) 6

TABLE 1 A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1986 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 3RD 4TH EST. TOTAL A. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER ERROR,%

1. Total Release Ci 1.04E+03 2.64E+03 2.15E+01
2. Average release rate for period uCi/sec 1.32E+02 3.36E+02
3. Percent of tech. spec. limit (1)  % 1.97E-02 5.46E-02 '
4. Percent of tech. spec. limit (2)  % 7.89E-03 2.08E-02
3. Percent of tech. spec. limit (3)  % 2.88E-01 7.93E-01
6. Percent ot tech. spec. limit (4)  % 1.44E-01 3.96E-01
7. Percent of tech. spec. limit (3)  % 4.02E-01 1.02E+00
8. Percent of tech. spec. limit (6)  % 2.01E-01 5.10E-01 B. IODINES
1. Total lodine - 131 C1 2.03E-02 2.83E-02 1.84E+01
2. Average release rate for period uCi/sec 2.58E-03 3.60E-03
3. Percent of tech, spec. limit (7)  % 6.13E-03 8.55E-03
4. Percent of tech. spec. limit (8)  % 6.53E-01 9.llE-01
5. Percent of tech. spec. limit (9)  % 3.27E-01 4.55E-01 C. PARTICULATES
1. Particulates with half lives greater than 8 days Cl 7.72E-05 5.89E-05 1.84E+01
2. Average release rate for period uCl/sec 9.82E-06 7.49E-06
3. Percent of tech. spec. limit (7)  % 2.33E-05 1.78E-05
4. Percent of tech. spec. limit (8)  % 2.49E-03 1.90E-03
5. Percent of tech. spec. limit (9)  % 1.24E-03 9.48E-04
6. Gross alpha radioactivity Ci 1.39E-06 7.59E-04 D. TRITIUM
l. Total Release Ci 2.35E-01 1.88E+00 2.18E+01
2. Average release rate for period uCi/sec 2.98E-02 2.39E-01 NOTES TO TABLE 1 A l

(1) Percent of I.A.1 whole body dose rate limit (300 mrem / year)

(2) Percent of I.A.1 skin dose rate limit (3000 mrem / year)

(3) Percent of I.A.3 gamma quarterly dose limit (10 mrad)

(4) Percent of I.A.3 gamma yearly dose limit (20 mrad)

(5) Percent of I.A.3 beta quarterly dose limit (20 mrad)

(6) Percent of I.A.3 beta yearly dose limit (40 mrad)

(7) Percent of I.B.1 organ dose limit (1500 mrem / year)

(8) Percent of I.B.3 quarterly dose limit (15 mrem)

(9) Percent of I.B.3 yearly dose limit (30 mrem)

TABLE IC REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT SECOND HALF - 1986 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH

1. FISSION & ACTIVATION GASES UNITS QUARTER QUARTER QUARTER QUARTER argon - 41 C1 -

1.58E+00 3.53E-03 8.17E-03 krypton - 85 C1 - -

1.31E+01 . 2.20E+01 krypton - 85m C1 2.04E+00 6.42E+00 1.04E-03 7.77E-02 krypton - 88 Ci -

4.15E+00 - -

xenon - 131m C1 -

8.41E+00 1.30E+01 2.25E+01 xenon - 133 C1 3.55E+02 7.35E+02 6.14E+02 1.75E+03 xenon - 133m C1 3.13E+00 7.75E+00 1.31E+00 1.25E+01 xenon - 135 Ci 3.33E+01 6.18E+01 7.75E-01 9.60E+00 Total For Period Ci 3.94E+02 8.25E+02 6.42E+02 1.81E+03

2. HALOGENS lodine - 131 C1 2.03E-02 2.83E-02 (1) (1) lodine - 133 Ci 4.51E-02 9.64E-02 (1) (1)

Total For Period Ci 6.54E-02 1.25E-01 (1) (1)

3. PARTICULATES beryllium -7 C1 3.43E-05 4.57E-06 (2) (2) chromium - 51 Cl 4.32E-06 2.53E-05 (2) (2) cobalt - 58 Ci 6.80E-06 2.58E-05 (2) (2) cesium - 137 Ci 1.32E-05 3.27E-06 (2) (2) barium - 140 Ci 1.84E-05 -

(2) (2)

Total For Period Ci 7.72E-05 5.89E-05 (2) (2) l (1) Iodines in batch releases are accounted for with the continuous main vent samplers when j the release is made through the plant main vent.

(2) Particulates in batch releases are accounted for with the main vent continuous particulate samplers when the release is made through the plant main vent.

';6 TABLE 2A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT

- SECOND HALF - 1986 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) C1 2.00E-01 6.11E-01 2.16E+01
2. Average diluted concentration during period uCl/mi 3.36E-10 1.03E-09
3. Percent of tech. spec. limit (1)  % 3.36E-01 1.03E+00
4. Percent of tech. spec. limit (2)  % 1.72E-01 1.97E+00
3. Percent of tech. spec. limit (3)  % 8.61E-02 9.85E-01
6. Percent of tech. spec. limit (4)  % 7.00E-02 1.46E-01
7. Percent of tech. spec. limit (5)  % 3.50E-02 7.23E-02 B. TRITIUM
1. Total Release - Ci 1.59E+02 8.59E+01 1.81E+01
2. Average diluted concentration during' period uCi/mi 2.67E-07 1.44E-07
3. Percent of applicable limit  % 8.90E-03 4.80E-03 C. DISSOLVED AND ENTRAINED GASES
1. Total Release Cl 1.29E-01 1.86E-01 2.00E+01
2. Average diluted concentrati)

during period uCl/ml 2.17E-10 3.13E-10 D. GROSS ALPHA RADIOACTIVITY

1. Total Release Ci 4.39E-04 9.77E-04 3.00E+00 E. VOLUME OF WASTE RELEASES (prior to dilution) liters 9.26E+06 8.74E+06 3.00E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 5.95E+11 5.95E+11 1.40E+01 (1) Percent of I.C.1 10 CFR 20 limit (IE-07 uCi/cc)

(2) Percent of I.C.3 Quarterly organ dose limit (10 mrem)

(3) Percent of I.C.3 Yearly organ dose limit (20 mrem)

(4) Percent of I.C.3 Quarterly Whole body dose limit (3 mrem)

(5) Percent of I.C.3 Yearly Whole body dose limit (6 mrem)

r TABLE 2B REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1986 LIQUID EFFLUENTS CONTINUOUS MODE (1) BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER beryllium -7 Cl 0 0 1.52E-05 -

sodium - 24 Ci 0 0 2.93E-05 6.91E-04 chromium - 31 Cl 0 0 3.55E-04 7.14E-02 manganese - 54 Cl 0 0 2.40E-03 2.69E-03 cobalt - 38 Cl 0 0 4.61E-02 1.88E-01 cobalt - 60 Cl 0 0 1.80E-02 1.87E-02 zinc - 65 Cl 0 0 1.11E-05 -

strontium - 89 Ci 0 0 1.76E-03 8.13E-04 strontium - 90 Ci 0 0 3.61E-04 2.01E-04 niobium - 95 Cl 0 0 1.21 E-03 2.28E-02 zirconium - 95 Cl 0 0 8.30E-04 1.01E-02 molybdenum - 99 Cl 0 0 6.14E-05 -

technicium - 99m Cl 0 0 1.70E-04 4.98E-05 ruthenium - 103 Cl 0 0 2.70E-07 2.97E-03 ruthenium - 106 Ci 0 0 1.70E-04 -

silver - Il0m Cl 0 0 2.22E-03 2.60E-02 tin - 113 Ci 0 0 3.60E-04 6.70E-03 antimony - 124 Cl 0 0 8.03E-05 4.08E-02 antimony - 125 Cl 0 0 2.25E-02 8.79E-02 lodine - 131 Cl 0 0 4.24 E-02 3.20E-02 lodine - 132 Ci 0 0 2.52E-04 4.65E-04 tellurium - 132 Ci 0 0 -

1.44E-04 lodine - 133 Ci 0 0 1.26E-02 8.46E-03 cesium .- 134 Ci 0 0 1.43E-02 2.33E-02 lodine - 134 Ci 0 0 1.19E-04 1.49E-04 lodine - 135 Ci 0 0 3.21E-03 2.46E-03 cesium - 136 Cl 0 0 1.30E-04 1.29E-04 cesium - 137 Ci 0 0 2.81E-02 6.40E-02 cerium - 144 Ci 0 0 5.16E-04 -

Total For Period Ci 0 0 2.00E-01 6.llE-01 Krypton - 85m Ci 0 0 2.47E-05 -

Krypton - 88 Cl 0 0 8.86E-05 -

Xenon - 133 Cl 0 0 l.19E-01 1.71E-01 Xenon - 133m Cl 0 0 1.63E-03 1.03E-02 Xenon - 135 Ci 0 0 6.87E-03 1.53E-03 Xenon - 135m Ci 0 0 1.32E-03 3.57E-03 Total For Period Ci 0 0 1.29E-01 1.86E-01 (1) There were no continuous liquid releases during the 3rd and 4th quarters.

1

,. .. I l

TABLE 3A l l

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT '

SECOND HALF - 1986 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 6-MONTH EST. TOTAL

1. Type of Waste UNITS PERIOD ERROR %
a. Spent resin, filter sludge m3 5.47E+00 evaporator bottoms, etc. Cl 6.63E+01 2.00E+01
b. Dry compressible waste, m3 1.22E+02 contaminated equipment, etc. Ci 4.64E+00 5.00E+01
c. Irradiated components, m3 -

control rods, etc. C1 -

5.00E+01

d. Other (CVCS Filters) m3 -

C1 -

2.00E+ 1

2. Estimate of major nuclides (by type of waste)
a. Nickel - 63 1.20E+01 %

Cobalt - 53 1.90E+00 %

Cesium - 137 5.58E+01 %

Cesium - 134 2.70E+01 %

Manganese - 54 5.60E-01 %

Cobalt - 60 1.90E+00 %

Strontium - 90 4.46E-01 %

Othe s 2.20E-01 %

b. Cobalt - 60 2.00E+01 %

Cesium - 137 4.40E+01 %

l Cesium - 1 34 1.70E+01 %

Nickel - 63 1.70E+01 %

Strontium - 90 3.00E-01 %

l' Others 1.01E+00 %

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

3 Motor surface transit Richland, Wash.

l

' dl_

. y g

~

BALTIMORE GAS AND ELECTRIC CHARLES CENTER P. O. BOX 1475 BALTIMORE, MARYLAND 21203 JosEPN A.TIERNAN Vict Pmtseptur Nucumm ENtmOV

' February 26, 1987 U.S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk.

SUBJECT:

Calvert Cliffs Nuclear Power Plant Units Nos. 1&2; Docket Nos.. 50-317 & 50-318

' Semi-Annual ~ Effluent Release Report '

Gentlemen:

Enclosed please find the Semi-Annual Effluent Release Report in compliance with paragraph 6.9.1.8 of the Unit 1 and Unit 2 Technical Specifications.

This report contains the results for Strontium. As required, the metereorological data is on file.

Very truly yours,

/

JAT/WBC/laa Enclosure cc: D. A. Brune, Esquire J. E. Silberg, Esquire A. C. Thadani, NRC S . A . McNe il . NRC Dr. Thomas Murley, NRC T. Foley/D. A. Trimble, NRC M

9 I I

Retrieved from "https://kanterella.com/w/index.php?title=ML20212H270&oldid=3099577"