ML20237J409

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Semiannual Effluent Release Rept for First Half 1987
ML20237J409
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 06/30/1987
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20237J396 List:
References
NUDOCS 8709030583
Download: ML20237J409 (17)
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Text

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SEMI-ANNUAL EFFLUENT RELEASE REPORT CALVERT CLIFFS NUCLEAR POWER PLANT FIRST HALF - 1987 TABLE OF CONTENTS I. RIU M i m Y LIMITS....................................................... 1 A. Fission and Activation Gases........................................ 1 B. lodines and Particulate with Half Lives Greater than Eight Days.... 1 C. Liquid Effluents.................................................... 1 II. MNXIMM PDMI SSAN F. (DENTRATICNS . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . . . . . . . . . 2 A. Fission and Activation Gases........................................ 2 B. Iodines and Particulate with Itif Lives Greater than Eight Days.... 2 C. Liquid Effluents.................................................... 3 III. 'IIDNICAL SPIEIFICATKN REFmTIPG RfQUIRIMNTS. . . . . . . . . . . . . . . . . . . . . . . . . . 3 IV. AVERAGE ENHGV. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3 V. hEA5WfM5NTS NO APPRKImTIO6 CF TOTAL RMOIQaCTIVITY. . . . . . . . . . . . . . . . . . 4 A. Fission and Activation Cases........................................ 4

1. Batch Releases................................................... 4
2. Continuous Releases............................................. 4 B. Iodine and Particulate............................................. 4
1. Batch Releases.................................................. 4
2. Co n t i n u o u s Re l e a s e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4 C. Liquid Effluents.................................................... 5
1. Batch Releases.................................................. 5
2. Continuous Releases............................................. 5 D. Es t irm t i on o f To t a l Er r o r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5
1. Liquid.................................................. ....... 5
2. Gases........................................................... 5 VI. BATW R11 EASES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6 A. Liquid.............................................................. 6 B. Gaseous............................................................. 6 VII. NNHML Rn RASES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 A. Liquid.............................................................. 7 B. Caseous.........................,................................... 7 TABLES 1 A - Ga seou s Ef f l uent s - Stmm t i on o f Re lea se s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 8 1C - Caseous Ef f luent s - Ground Level Re lease s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 2A - Liquid Ef f luent s - Stmmt ions of Al l Re leases . . . . . . . . . . . . . . . . . . . . . . . . . 12 2B - Liquid Effluents...................................................... 14 3A - So l i d Was te and I r r ad i at ed Fuel Sh i gnen t s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 16 0709030503 PDR ADOCK  % PDR

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CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SUPPLEMENTAL INFORMATION l l

Facility - Calvert Cliffs Nuclear Power Plant Licensee - Baltimore ~ Gas & Electric Company L REGULATORY LIMITS A. Fission and Activation Gases

1. The instantaneous release rate of noble gases in gaseous effluents shall not  !

resu!t 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 i

20 mrad beta radiation / quarter 20 mrad gamma radiation / year  !

l 40 mrad beta radiation / year '

4. All of the above parameters are calculated according to the methodology  !

specified in the of fsite Dose Calculation Mar.ual (ODCM).

B. Iodines and Particulate with Half Lives Greater than Eight Days l

1. The instantaneous release rate of lodines and particulate in gaseous effluents ,

shall not result in a site boundary dose in excess of 1500 mrem / year to any organ.

2. The Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce radioactive materials in gaseous  ;

effluents when calculated doses exceed 1.8 mrem to any organ in a 92 day l period at the site bour.dary. j i

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3. The dose to a member of the public at the site boundary from Iodine 131 and j particulate with half lives is greater than eight days in gaseous effluents shall  ;

not exceed:

15 mrem to any organ per quarter l 30 mrem to 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 j unrestricted areas exceeds .36 mrem to the whole body, or 1.20 mrem to any  ;

organ in a 92 day period. t

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

3 mrem whole body dose per quarter  !

10 mrem dose to any orgc.n per quarter  ;

I 6 mrem whole body dose per year

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20 mrem dose to any organ per year l

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 gemma activities are  ;

summed. If the total does not exceed the dose rate limitations for the most limiting isotope, then the batch is released. If the most limiting isotope criteria is not met, then a detailed dose rate calculation is performed as described in the ODCM.

B. Iodines and Particulate with Half Lives Greater than Eight Days Compliance to the dose rate limitations from Iodines and particulate 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 wit.wut exceeding the limits of 1.B.3. t i

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, . j C. Liquid Effluents ]

The. MPCs used for radioactive materials released in liquid effluents are in i 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. l 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 uCl/ml. This limit was' l used as given in the notes to Appendix B, Table II, Column 2 of 10 CFR 20. l B. Tritturn - Limit used 3 x 10~3 uCl/ml.

IIL TECHNICAL SPECIFICATION REPORTING REQUIREMENTS (Section G.9.1.8) <

A. Previous Calendar Year (1986) Dose Assessment Summary

  • During 1986 liquid releases from Calvert Cliffs resulted in a maximum organ dose of 0.38 mrem and a maximum whole body dose of 0.018 mrem. This was less than 2%  ;

of the allowable Technical Specification organ dose limit and less than 1% of the allowable Technical Specification whole body dose limit for the year. This dose was ,

calculated using ODCM methodology (Adult Fish and Shellfish Pathways). The l Gastro-Intestinal Tract was the maximum organ dose pathway.  !

Gaseous Noble Gas Releases resulted in a maximum of 0.21 mrad gamma and 0.58  !

mrad beta exposure. ' Particulate releases from Calvert Cliffs resulted in a  !

maximum organ exposure of 0.42 mrem via the Thyroid Pathway. All gaseous release pathways were below 2% of their allowable Technical Specification limits for 1986, i

B. 40 CFR 190 Total Dose Compliance <

1 Using the maximum doses listed in Section 3A and ODCM calculation the maximum l exposed individual would receive less than 3% of any of the allowable doses defined '

by 40 CFR 190.

C. Solid Waste Reporting Requirements In 1987, radioactive resin was dewatered and shipped for disposal in high integrity containers. Some oil was absorbed using a commerical granular fired clay product and some using petroset brand oil solidification agent.

D. ODCM and PCP Changes No changes were made to the PCP and ODCM during the first half of 1987. i IV. AVERAGE ENERGY Not Applicable 3

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Y._ MEASUREMENTS AND APPROXIMATIONS AND TOTAL RADIOACTIVITY A. Fission and Activation Gases l

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 gaseous isotope using a Ge l detector. The total activity released is based on the pressure / volume j relationship (gas laws) of the tank. l 1

Prior to and af ter the release of gas as a result of purging containment, samples are collected and analyzed for each significant gaseous isotope using a Ge detector. The total activity released is based on containment volume and purge rate. Activity.bulldup while purging is also considered.  ;

2. Continuous Releases During the release of gas from the main vents, samples are collected and analyzed at least weekly for each significant gaseous isotope using a Ge detector. The total activity released for the week is based on the total sample activity decay corrected to the midpoint of the sample period and multiplied by the main vent flow for the week.

B. Iodine and Particulate  !

1. Batch Releases The total activity released from a pressurized gas decay tank, containment purges and containment vents as lodines and particulate is accounted for by 1 the main vent lodine and particulate continuous samplers.
2. Continuous Releases During the release of gas from the main vents, samples of lodines and particulate are collected using a charcoal and particulate filter respectively.  ;

The filters are removed weekly and are analyzed for each significant gamma isotope using a Ge 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. 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.

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C. ' Liquid Effluents ]

. l. Batch Releases Prior to th'e release of ' liquid from a . waste tank, a sample is collected and i analyzed for the concentration of each significant gamma energy radionuclides j to demonstrate compliance with Section 1.C.1 above using the water flow rate l 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 after the release. A proportional composite sample is also withdrawn for each release 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.

When steam generator blowdown is discharged to the circulating water i conduits, it is sampled daily and these samples are used in turn to prepare a-  !

weekly blowdown composite based on each da.y's ' blowdown. The' weekly  !

composite 'Is analyzed for each significant isotope using a Ge 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  !

l D. Estimation of Total Error *

-l 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 j to sample geometry systematic error during gamma counting was determined. This  !

included an estimate of sample volume error and sample pipetting error. More j 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. I
c. Error in containment purge release . flow. <
d. Error in gas decay tank pressure.

Where errors could be estirnated they were usually considered additive.

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VI. BATCliRELEASES _

1987 IST 2ND QUARTER QUARTER A. Liquid

1. Number of batch releases 5.00 E+01 7.50 E+01
2. Total time period for batch releases (hours) 4.07 E+02 1.69 E+02
3. Maximum time period for a batch release (min) 1.93 E+03 6.37 E+02
4. Average time period for batch releases (min) 4.89 E+02 1.36 E+02
5. Minimum time period for a batch release (min) 1.20 E+01 1.50 E+01
6. Average stream flow during periods of effluent into a flowing stream (liters / min of dilution water) 4.51 E+06 4.51 E+06 B. Gaseous:
1. Number of batch releases 2.60 E+01 3.20 E+01
2. Total time period for batch releases (min) 3.67 E+04 1.26 E+05
3. Maximum time period for a batch release (min) 1.00 E+04 1.03 E+04
4. Average time release (min) period for batch 1.41 E+03 3.94 E+03
5. Minimum time period for a batch release (min) 5.00 E+00 4.00 E+00

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l IST 2ND QUARTER QUARTER I

VIL ABNORMAL RELEASES A. Liquid

1. Number of releases 2. Total activity released (Curies) 4 B. Gaseous
1. Number of releases 2. Total activity releases (Curies) -

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TABLE 1 A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF - 1987 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES  :

IST 2ND EST. TOTAL -

A. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER ERROR,%

1. Total Release C1 2.46E+03 1.19E+02 2.15E+01
2. Average release rate for period uCi/sec 3.13E+02 1.51 E+01
3. Percent of tech. spec. limit (1)  % 4.47E-02 2.09E-03
4. Percent of tech. spec. limit (2)  % 1.79E-02 8.35E-04 l
5. Percent of tech. spec. limit (3)  % 6.60E-01 3.10E-02
6. Percent of tech. spec. limit (4)  % 3.30E-01 1.55E-02
7. Percent of tech. spec. limit (5)  % 9.38E-01 4.49E-02 i
8. Percent of tech. spec. limit (6)  % 4.69E-01 2.25E-02 B, IODINES
1. Total lodine - 131 C1 2.48E-02 1.10E-02 1.84E+01
2. Average release rate for period uCl/sec 3.16E-03 1.40E-03
3. Percent of tech. spec. limit (7)  % 7.51E-03 3.33E-03
4. Percent of tech. spec. limit (8)  % 7.98E-01 3.54E-01 i
5. Percent of tech. spec. limit (9)  % 3.99E-01 1.77E-01 C. PARTICULATE
1. Particulate with haJf lives greater than 8 days Cl 1.40E-05 2.92E-05 1.84E+01
2. Average release rate for period uCi/sec 1.78 E-06 3.71 E-06
3. Percent of tech. spec. limit (7)  % 4.23E-06 8.81 E-06
4. Percent of tech. spec. limit (8)  % 4.51 E-04 9.40E-04
5. Percent of tech. spec. limit (9)  % 2.25E-04 4.70E-04
6. Gross alpha radioactivity Ci < 2.llE-09 5.37 E-06 l

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a TABLE l A - REG GUIDE 1.21 (Cont.)_

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF - 1987 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES IST 2ND EST. TOTAL D. TRITIUM UNITS QUARTER QUARTER ERROR,%

1. Total Release Ci 6.92 E-02 3.35E-01 2.18E+01
2. Average release rate for period uCl/sec 8.80E-03 4.26E-02 NOTES TO TABLE l A (1) Percent of 1.A.1 whole body dose rate limit (500 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) q (5) Percent of I.A.3 beta quarterly dose limit (20 mrad)

(6) Percent of I.A.3 beta yearly dose limit (40 mrad) i (7) Percent of I.B.1 organ dose limit (1500 mrem / year)

-(8)- Percent of 1.B.3 quarterly dose limit (15 mrem)

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

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l TABLE IC - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT  !

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT

{

FIRST HALF - 1987 1

GASEOUS EFFLUENTS - GROUND LEVEL RELEASES 4

CONTINUOUS MODE BATCH MODE IST 2ND IST 2ND 1

1. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER QUARTER QUARTER argon -41 Ci --- ---

2.52E-02 1.19E-02 krypton -85 C1 -- ---

1.19E+01 1.05E+00 ,

krypton -85m Cl 1.63E+00 1.09E-01 1.92E+00 6.52E-04

.l krypton -88 C1 -- ---

7.64 E-02 ---

i xenon -127 C1 --- --- ---

1.72 E-07 xenon -131m C1 -- ---

1.31E+01 1.llE+00 l xenon -133 Ci 3.37E+02 1.89E+01 2.01E+03 9.62E+01 ,

xenen -133m C1 3.22E+00 --

3.22E+01 1.30E-01 xenon -135' C1 3.86E+01 1.69 E+00 1.21 E+01 1.72 E-02 Total For Period Cl' 3.80E+02 2.07 E+01 2.08E+03 9.86E+01 2, HALOGENS lodine -131 Ci 2.48E-02 1.10E-02 (1) (1) l lodine -133 Ci 3.22 E-02 1.22 E-02 (1) (1)

Total For Peiiod Ci 5.70E-02 2.32 E-02 (1) (1)

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

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TABLE IC ' REG GUIDE 1.21 (Cont.)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF - 1987 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES l

CONTINUOUS MODE BATCH MODE IST 2ND IST 2ND

3. PARTICULATE UNITS QUARTER QUARTER QUARTER QUARTER cobalt -58 C1 3.83 E-06 6.12 E-06 (1) (1) strontium -89 (2) Ci (2) (1) (1)

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strontium -90 (2) C1 ---

(2) (1) (1) cadmium -109 Ci --

1.59 E-0) (1) (1) cesium -137 Ci 1.02E-05 7.16E-06 (1) (1)

Total For Period Cl 1.40 E-05 2.92E-05 (1) (1)

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

(2) Does not include strontium values for 2nd quarter.

1 TABLE 2A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF - 1987 i LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES IST 2ND EST. TOTAL A. FISSION AND ACTIVATION PRODUCTS UNITS QUARTER QUARTER ERROR,% _

l. Total release (not including tritium, gases, alpha) Cl 1.59E+00 1.52 E+00 2.16E+01
2. _ Average diluted concer.: ration during period uCi/mi 2.69 E-09 2.57E-09
3. Percent of tech. spec. limit (1)  % 2.69E+00 2.57E+00
4. Percent of tech. spec limit (2)  % 2.85E+00 2.26E+00 _
5. Percent of tech. spec. limit (3)  % 1.43E+00 1.13 E +00
6. Percent of tech. spec. limit (4)  % 7.01E-01 7.28 E-01
7. Percent of tech, spec. limit (5)  % 3.51 E-01 3.64E-01 B. TRITIUM _
l. Total release C1 2.39E+02 3.16E+01 1.81E+01
2. Average diluted concentration during period uCl/ml 4.04E-07 5.35E-08
3. Percent of applicable limit  % 1.35E-02 1.78E-03 C. DISSOLVED AND ENTP.AINED GASES
1. Total Release Cl 7.09E-01 6.47E-02 2.00E+01
2. Average diluted concentration during period uCl/mi 1.20E-09 1.09E-10 f .

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TABLE 2A - REG GUIDE 1.21 (Cont.) l CALVERT CLIFFS NUCLEAR POWER PLANT I EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT i FIRST HALF - 1987 i

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES

.)

i IST 2ND EST. TOTAL j D, GROSS ALPHA RADIOACTIVITY UNITS QUARTER QUARTER ERROR,%

1. Total Release Ci < l.42E-03 < 4.22E-03 3.00E+00 E. VOLUME OF WASTE RELEASES (prior to dilution) liters 9.48 E+06 4.96E+06 3.00E+00

- F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 5.91E+11 5.91E+11 1.40E+01 i

(1) Percent of I.C.1 10 CFR 20 Limit (IE-07 uC1/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) 1 i

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L TABLE 2B - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF - 1987 .

LIQUID EFFLUENTS l CONTINUOUS MODE (1) BATCH MODE j IST 2ND IST 2ND  !

= NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER  !

sodium -24 Cl 0 0 1.27 E-05 4.73 E-04 j chromium -51 Cl 0 0 3.17E-02 7.39E-02  !

manganese -54 Cl 0 0 5.53E-03 4.89E-03 i

cobalt -57 Cl 0 0 ---

3.61E-05 cobalt -58 Ci 0 0 7.38E-01 7.28 E-01 {

iron -59 Cl 0 0 4.15E-04 1.55E-03  !

cobalt -60 Ci 0 0 4.26E-02 6.24 E-02 strontium -89 (2) Cl 0 0 < l.23E-03 (2) strontium -90 (2) Ci 0 0 8.91E-04 (2) i s

niobium -95 Cl 0 0 3.53E-02 2.65E-02 zirconium -95 Ci 0 0 2.03E-02 1.24E-02 niobium -97 Cl 0 0 1.08 E-03 ---

l technicium -99m Cl 0 0 2.86E-04 4.73E-05 i

. i ruthenium -103 Cl 0 0 1.54E-03 3.56E-03 silver -110m Cl 0 0 2.10E-02 1.44 E-02 tin -113 Cl 0 0 3.04E-03 3.34E-03 antimony -124 Ci 0 0 5.39E- 03 8.04E-03 antimony -125 Ci 0 0 1.33 E-01 1.08 E-01 1 lodine -131 Cl 0 0 9.62 E-02 1.90E-02

. Iodine -132 Ci 0 0 2.01 E-05 9.56E-05 tellurium -132 Ci 0 0 8.61 E-04 ---

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TABLE 2B .4 REG GUIDE 1.21 (Cont.)

CALVERT CLIFFS NUCLEAR POWER PLANT 4 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 4 FIRST HALF - 1987 f

LIQUID EFFLUENTS CONTINUOUS MODE (1) BATCH MODE ..

IST 2ND IST . 2ND l NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER I lodine -133 Cl 0 0 6.50E-03 6.49E-03 cesium -134 Ci 0 0 1.74E-01 1.89E-01 lodine -134 Ci 0 0 5.26E-05 ---

' lodine -135 Cl 0 0 4.84E-04 1.20E-03 ceslum -136 Cl 0 0 1.88E-03 2.43E-04 cesium -137- Cl 0 0 2.70E-01 2.61 E-01 barium -140 Cl 0 0 ' l .04 E-04 ---

lanthanum -140 Ci 0 0 7.32 E-05 ---

cerium -144 Cl 0 0 1.26E-03 1.24 E-05 Total For Period Ci 0 0 1.59E+00 1.52E+00 xenon -133 Cl 0 0 6.96E-01 6.22E-02 j xenon -133m Ci 0 0 9.llE-03 4.20E-04 )

l xenon -135 Cl 0 0 4.37E-03 1.81E-03 1 xenon -135m Cl 0 0 1.94 E-04 3.00E-04 l Total For Period Cl 0 0 7.09E-01 6.47E-02 l i

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(1) There were no continuous liquid releases during the 1st and 2nd quarters.

l (2) Does not include strontium values for 2nd quarter.

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TABLE 3A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF - 1987 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS l A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 1 6-MONTH EST. TOTAL

1. Type of Waste UNITS PERIOD ERROR %

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a. Dewatered Spent Resin m 8.80E+00 Ci 2.61 E+02 2.00E+01
b. Dry Compressible Waste, m3 7.98E+01 Contaminated Equipment, etc. C1 4.80E+00 5.00E+01
c. Irradiated Components, m3 ___

Control Rods, etc. C1 ----

5.00E+01

d. Other (CVCS Filters) m3 ____

Ci - - -

2.00E+01

2. Estimate of Major Nuclide (By Type of Waste) *
a. Manganese -54 1.70E+00 %

Cobalt -58 2.27E+01 %

Cobalt -60 3.50E+00 %

Nickel -63 9.80E+00 %

Ceslum -134 1.94E+01 %

Cesium -137 3.99E+01 %

Others 3.60E+00 %

b. Cobalt -60 2.00E+01 %

Nickel -63 1.70E+01 %

Cesium -134 1.70E+01 %

Ceslum -137 4.40E+01 %

Others 1.90E+00 %

  • Only nuclides greater than 1% were reported
3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 5 Motor Surface . Transit '

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Barnwell S.C.

1 Moto'r S'urface Transit Richland, Wash

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...

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