ML20056F569

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Effluent & Waste Disposal Semiannual Rept for First Half of 1993
ML20056F569
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 06/30/1993
From:
BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20056F567 List:
References
NUDOCS 9308300084
Download: ML20056F569 (23)
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Text

CALVEltT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPOltT SUPPLEMENTAL INFORMATION 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 noble gases in gaseous effluents shall not result in a site bounday dose rate greater than 500 mrem & car to the whole body or greater than 3000 mrem / year to the skin (Technical Spe6fication 3/4.11.2.1).
2. Gaseous Radwaste Treatment System and the Ventilation Exhaust Treatment System shall be used to reduce gaseous emissions when the calculated gamma-air dose due to gaseous effluents exceeds 1.20 mrad or the calculated beta-air dose due to gaseous effluents exceeds 2.40 mrad at the site boundag in a 92 day period (Technical Specification 3/4.11.2.4).
3. The air dose at the site boundary due to nobic gases released la gaseous effluents shall not exceed (Technical Specification 3/4.11.2.2):

10 mrad /qtr, gamma-air i 20 mrad /qtr, beta. air 20 mradlycar, gamma-air 40 mradlycar, beta. air

4. A!! of the above parameters are calculated according to the methodology specified in the Offsite Dose Cakulation Manual (ODCM).

B. Indines and Particulates with Half Lives Greater than Eicht Days

1. The instantaneous release rate of iodines and particulates in gaseous i

effluents shall not result in a site boundary dose in excess of 1500 mrem / year to any organ (Technical Specification 3/4.11.2.1).

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 L8 mrem to any organ in a 92 day period at or beyond the site boundary (Technical Specification 3/4.11.2.4).
3. The dose to a member of the public at or beyond the site boundary from iodine-131 and particulates with half lives greater than eight days in gaseous effluents shall not exceed (Technical Specification 3/4.11.2.3):

15 mrem /qtr, any organ i

PDR ADOCF 930826 930830000(05000317 2 5

R PDR ll 1

  • 30 mrem / year, any organ l less than 0.1rc of the above limits as a result of burning contaminated  :

oil. l

4. Ali of the above parameters are calculated according to the methodology i specified in the ODCM. l C. Liquid Effluents
1. The concentrations of radionuclides in liquid effluents from the plant shall '

not exceed the values specified in 10 CFR Part 20, Appendix B, for unrestricted areas (Technical Specification 3/4.11.1.1).  ;

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2. The liquid radwaste treatment system shall be used to reduce the concentration of radionuclides in liquid effluents from the plant when the calculated dose to unrestricted areas exceeds 0.36 mrem to the whole body, or 1.20 mrem to any organ in a 92 day period (Technical Specification 3/4.11.1.3).
3. The dose to a member of the public in unrestricted areas shall not exceed l (Technical Specification 3/4.11.1.2):

3 mrem /qtr, total body  ;

10 mrem /qtr, any organ 6 mrem / year, total body 20 mrem / year, any organ .f

4. All of the liquid dose parameters are calculated according to the methodology specified in the ODCM. I M AXIMUM PElofISSillLE CONCENTRATIONS

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A. Fission and Activation Gases 1

Prior to the batch release of gaseous effluents, a sample of the source is collected and  ;

analyzed by gamma spectroscopy for the principal gamma emitting radionuclides. l The identified radionuclide concentrations are evaluated and an acceptable release l rate is determined to ensure that the dose rate limits of Technical  :

Specification 3/4.11.2.1 are not exceeded. l i

B. Iodines and Particulates with Half Lives Greater than Eicht Days j t

Compliance with the dose rate limitations for iodines and particulates is  !

demonstrated by analysis of the charcoal and particulate samples of the station main  !

vents. The charcoal sampics are analyzed by gamma spectroscopy for quantification of any release of radiciodines. The particulate samples are analyzed by gamma j spectroscopy for quantification of particulate radioactive material. All of the above parameters are calculated according to the methodology specified in the Offsite Dose  ;

Calculation Manual (ODCM).

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C. Liauid Effluents  !

The MPCs used for radioactive materials released in liquid effluents are in  !

accordance with Technical Specification 3/4.11.1.1 and the values from 10 CFR 20, Appendix B, including applicable table notes. In all cases, the more restrictive (lower) MPC found for each radionuclide is used regardless of solubility.

III. TECIINICAL SPECIFICATION REPORTING REOUIREMENTS (Section 6.9.1.8)

A. Previous Calendar Year (1992) Dose Assessment Summary I This section is only required for the semi-annual reports submitted within 60 days of January 1 of each year.  :

B. 40 CFR 190 Total Dose Compliance C

This section is only required for the semi-annual reports submitted within 60 days of j January 1 of each year.

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C. Solid Waste Report Requirements l 1

During the first half of 1993, the types of radioactive solid waste shipped from Calvert Cliffs were radioactive resin, which was dewatered and shipped in a high integrity  ;

container; dry compressible waste, which was shipped as LSA waste in Sealand containers; and contaminated plant equipment, which was shipped in a high-integrity i steel container. Appendix A provides a detailed breakdown of the waste shipments for the first half of 1993 per the categories specified in Technical Specification j 6.9.1.8.  !

I D. ODCM and Process Control Procram (PCP) Chances One change was made to the ODCM during the first half of 1993. The change was reviewed by POSRC and approved by the Plant General Manager, Calvert Cliffs l Nucicar Power Plant, prior to imp!cmentation. Tne scope and basis for this change is  ;

discussed in Appendix B. In keeping with the requirement of the Technical ,

Specification 6.17, a copy of the approved change to the CCNPP ODCM is enclosed  !

in Attachment 1. j No changes were made in the PCP in the first half of 1993.  !

E. Radioactive Gaseous Effluent Monitorine Instrumentation _

t None of the Technical Specification effluent monitors were out of service for greater  :

than 30 days. l t

IV. AVERAGE ENERGY l

Not Applicable. f 3

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I V. MEASUREN!ENTS AND APPROXIMATIONS AND TOTAL RADIOACTIVrIY  !

A. Fission and Activation Gases f
1. Batch Releases t

Prior to each batch release of gas from a pressurized waste gas decay tank, a  !

sample is collected and analyzed by gamma spectroscopy using a Germanium  !

(Ge) detector for the principal gamma emitting noble gas radionuclides. The  !

j total activity released is based on the pressure / volume relationship (gas laws) {

i of the tank. ,

Prior to and after each containment purge, a gas sample is collected and l 3 analyzed by gamma spectroscopy using a Ge detector for the principal gamma l cmitting noble gas radionuclides. The total activity released is based on  !

containment volume and purge rate. Activity buildup while purging is also considered. <

2. Continuous Releases j A gas sample is collected at least weekly from the main vents cod analyzed by i gamma spectroscopy using a Ge detector for the principal game.a emitting noble gas radionuclides. The total activity released for the week is based on  !

the total sample activity decay corrected to the midpoint of the sample period j

multiplied by the main vent flow for the week.  ;

A monthly composite sample is collected from the main vents and analyzed by l i liquid scintillation for tritium. The total tritium release for the month is based  ;

on this sample analysis and the vent flow. 1 B. Iodine and Particulates l

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1. Batch Releases  !

The total activities of radiciodines and particulates released from pressurized r waste gas decay tanks, containment purges, and containment vents are  !

accounted for by the continuous samplers on the main vent.

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2. Continuous Releases j a

I During the release of gas from the main vents, samples of iodines and i particulates are collected using a charcoal and particulate i lter, respectively. ,

The filters are removed weekly and are analyzed by gan.ma spectroscopy  !

using a Ge detector for significant gamma emitting radiornelides. The total

. activity released for the week is based on the total sampic activity decay  :

l corrected to the midpoint of the sample period multiplied by the main vent  ;

flow for the week. These weekly particulate filters are then composited to -

i form monthly and quarterly composites for the gross 9pha and strontium 89 l and 90 analyses. ,

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C. Liauid Effluents

1. Batch Releases Prior to the release of liquid from a waste tank, a sample is collected and analyzed by gamma spectroscopy for the principal gamma emitting radionuclides. To demonstrate compliance with the requirements addressed in Section I.C.1 above, the measured radionuclide concentrations are compared with the allowable MPCs; dilution in the discharge conduit is considered, and an allowable release rate is verified.

The total activity released in each batch is determined by multiplying the volume released by the concentration of each radionuclide. 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 the gross alpha, strontium 89 and 90, and tritium analyses.

Beginning with the reporting period January 1 to June 31,1993, CCNPP will begin reporting the Fe-55 activity in liquid batch releases discharged from the liquid radioactive waste processing system. The Fe-55 analysis frequency will be " quarterly." The quarterly composite samples -- which are already analyzed for Sr-89 and Sr will be analyzed for Fe-55.

2. Continuous Releases Prior to discharge of any continuous releases, a sample is collected and analyzed by gamma spectroscopy fo the principal gamma emitting radionuclides. The measured radionuclide concentrations are compared with the allowable MPC concentrations in the discharge conduit, and an allowable release rate is verified.

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 sample based on each day's blowdown. The weekly composite sample is analyzed by gamma spectroscopy for the principal gamma emitting radionuclides. These results are multiplied by the actual I

quantity of blowdown to determine the total activity released. The weekly composite is also used to prepare monthly composites for tritium and gross alpha analyses.

During periods of primary-to-secondary leakage, the secondary system becomes contaminated and subsequently, contaminates the turbine building sumps. He low-level activity water (predominantly tritium) contained in the turbine building sumps is released directly to the Chesapeake Bay. This water I

is sampled at least weekly and composited. These samples are added to a composite based on the amount released during that week. The composite sample is analyzed at least monthly for tritium and principal gamma emitting radionuclides, The results are multiplied by the actual quantity of liquid released to determine the total activity released.

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D. Estimation of Total Error  ;

Total error for all releases was estimated using, as a minimum, the random counting

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error associated with typical releases. In addition to this random error, the following - i systematic errors were also examined.

1. Liquid a) Error in volume of liquid released prior to dilution during batch releases, f b) Error in volume ofliquid 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. f b) Error in sample flow rate. '

c) Error in containment purge release flow.

-i d) Error in gas decay tank pressure.

l Where errors could be estimated they are usually considered additive. i f;

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i VI. II ATCl! HELEASES l l

1993 j IST 2ND l OUARTER OUARTER-A. Liould

1. Number of batch releases 4.80E+01 5.50E+01
2. Total time period for batch releases (min) 1.34E+04 1.49E+04  !

3 Maximum time period for a batch release (min) 1.85E+03 1.42E+03

4. Average time period for batch l releases (min) 2.80E+02 2.72E+02  ;
5. Minimum time period for a {

batch release (min) 2.00E+00 1.00E+00

6. Average stream flow during periods of effluent into a flowing stream (liters / min of dilution water) 4.29E+06 4.13E+06
11. Gaseous i
1. Number of batch releases 1.20E+01 1.50E+01
2. Total time period for batch releases (min) 9.20E+03 1.29E+04
3. Maximum time period for a batch release (min) 2.02E+03 3.15E+03
4. Average time period for batch  ;

release (min) 7.66E+02 8.62E+ 02  !

5. Minimum time period for a batch l release (min) 1.00E+01 5.50E+01

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VII. AllNORMAL RELEASES ,

1993 l IST 2ND OUARTER OUARTER i

A. Liould

1. Number of releases 0- .O_ j t
2. Total activity released (Curies) 0- II. Gaseous .
1. Number of releases  !
2. Total activity releases (Curies)  !

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TAllLE I A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT F1RST IIALF- 1993 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES I

IST 2ND EST. TOTAL i A. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER ERROR, %

1. Total Release Ci 1.54E+02 8.09E +00 1.20E+01
2. Average release rate for period uCi/sec 1.98E+ 01 1.03E+00  ;
3. Percent of Tech. Spec. limit (1)  % 2.71E-03 1.85E-04
4. Percent of Tech. Spec. limit (2)  % 4.89E-03 1.72E 04
5. Percent of Tech. Spec. limit (3)  % 3.97E-02 2.49E-03
6. Percent of Tech. Spec. limit (4)  % 1.98E-02 1.25E-03
7. Percent of Tech. Spec. limit (5) G 5.90E-02 5.24E-03 ,
8. Percent of Tech. Spec. limit (6) 9c 2.95E-02 2.62E-03
1. Total Iodine - 131 Ci 1.10E-02 1.13E-03 i1.10E+ 00
2. Average release rate for period uCi/sec 1.427E-03 1.44 E-04
3. Percent of Tech. Spec. limit (7) Fc 3.41 E-03 3.45E-04 i
4. Percent of Tech. Spec. limit (8) 9c 2.11E+00 2.16E-01 i
5. Percent of Tech. Spec. limit (9) fc 1.06E+00 1.08E-01 l C. PARTICULATES l
1. Particulates with halflives greater than 8 days Ci 7.56E-03 4.46E-06 2.80E+01

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2. Average release rate for period uCi/sec 9.73E-04 5.67E-07 .
3. Percent of Tech. Spec. limit (7)  % 1.37E-04 7.55E-08
4. Percen1 of Tech. Spec. limit (8) rc 8.77E-02 4.90E-05
5. Percent of Tech. Spec. limit (9) C7c 4.39E-02 2.45E45
6. Gross alpha radioactivity Ci (10) 5.36E+01 l (10) i 9

TABLE 1 A - REG GUIDE 1.21 (Cont.)

CALVERT CLIFFS NUCLEAR POWER PLANT i EFFLUENT AND WASTE DISPOSAL SEATI-ANNUAL REPORT  ;

F1RSTIIALF- 1993 GASEOUS EFFLUENTS - SU51NTATION OF ALL REl. EASES IST 2ND EST. TOTAL '

D. TRIT 1Uh1 UNITS QUARTER QUARTER ERROR, %

1. Total Release Ci 5.64E +00 3.02E+00 11.32E+01 lr
2. Average release rate for period uCi/sec 7.10E-01 3.80E-01  ;

NOTES TO TAllLE 1A (1) Percent of LA.1 whole body dose rate limit (500 mrem / year) i (2) Percent ofI.A.1 skin dose rate limit (3000 mrem / year)

(3) Percent of I.A3 gamma quarterly dose limit (10 mrad) l l

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

(5) Percent ofI.A.3 beta quarterly dose limit (20 mrad) l, (6) Percent of I.A.3 beta yearly dose limit (40 mrad)  !

(7) Percent ofI.B.1 organ dose rate limit (1500 mrem / year) >

(8) Percent of LB.3 quarterly organ dose limit (15 mrem) I (9) Percent of LB3 yearly organ dose limit (30 mrem) 4 (10) Less than minimum detectable activity which meets the LLD requirements of 1 Technical Specification Surveillance Requirement 4.11.2.1.2. l l

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l TAllLE IC REG GUIDE 1.21 i

CALVERT CLIFFS NUCLEAR POWER PLANT i EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT j FIRSTIIALF- 1993 l t

G ASEOUS EFFLUENTS - GROUND LEVEL RELEASES i

i' CONTINUOUS MODE IIATCII MODE i

IST 2ND IST 2ND i I FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER QUARTER QUARTER  !

Argon -41 Ci (2) (2) 7.05E-03 2.91E-03 Knpton -85 Ci 3.13E+ 00 (2) 6.05E-01 4.91E+00  ;

l Knpton -85m Ci 3.01E-01 (2) 2.32E-04 1.07E-04 I

}%pton ~87 Ci (2) (2) (2) (2)

Krypton -88 Ci (2) (2) (2) (2)

Xenon -131m Ci 1.71 E+00 (2) 1.29E-02 6.8 4E-03 ,

e Xenon -133 Ci 137E+02 1.21E+00 8.31E+ 00 4.55E-01  !

Xenon -133m Ci 5.8SE-01 (2) 1.02E-02 4.90E-03 i i

Xenon -135 Ci 239E+00 1.49E+00 1.19E-02 5.76E-03 Xenon -138 Ci (2) (2) (2) (2)  !

Total for Period Ci 1.45E+02 2.70E+ 00 8.95E+00 539E+00 [

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2. IIALOGENS  !

Iodine -131 Ci 9.18E-03 1.13E-03 1.84E-03 (1) l

=

lodine -133 Ci 339E-03 1.76E-03 (1) (1) i Total For Period Ci 1.26E-02 2.89E-03 1.84E-03 (1) 4 i

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TAllLE IC - REG GUIDE 1.21 (Cont.)  ;

CALVERT CLIFFS NUCLEAR POWER PLANT [

EFFLUENT AND WASTE DISPOSAL SE311-ANNUAL REPORT  !

FIRST IIALF- 1993 i G ASEOUS EFFLUENTS - GROUND LEVEL RELEASES i

CONTINUOUS MODE IIATCII MODE j IST 2ND IST 2ND

3. PARTICULATES UNITS QUARTER QUARTER QUARTER QUARTER Manganese -54 Ci (2) (2) (1) (1) l Iron -59 Ci (2) (2) (1) (1)  :

t Cobalt -58 Ci (2) (2) (1) (1)

Cobalt -60 Ci (2) (2) 1.33E-05 (1) l Zine -65 Ci (2) (2) (1) (1)  !

Strontium -89 Ci (2) (2) (1) (1) l Strontium -90 Ci (2) (2) (1) (1) l Molybdenum -99 Ci (2) (2) (1) (1) t Cesium -134 Ci (2) (2) 3.3SE-03 (1) [

t Cesium -137 Ci 1.07E-05 4.46E-06 4.16E-03 (1)

Cerium -141 Ci (2) (2) (1) (1)

Cerium -144 Ci (2) (2) (1) (1) i Gross Alpha Radioacthity Ci (2) (2) (1) (1) i Total For Period Ci 1.07E-05 4.46E-06 7.55E-03 (1)  ;

NOTES TO TAllLE IC i

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

i (2) Irss than minimum detectable activity which meets the LLD requirements of j Technical Specification Surveillance Requirement 4.11.2.1.2. 1 I

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TAllLE 2A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT i FIRST 11ALF- 1993 l

LIOUID EFFLUENTS - SUMMATION OF ALL RELEASES ,

l IST 2ND EST. TOTAL  !

A. FISSION AND ACflVATION PRODUCTS UNITS QUARTER QUARTER ERROR, % [

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1. Total Release (not including l tritium, gases, alpha) Ci 7.35E-01 4.98E-01 1.03E+ 01 -

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2. Average diluted concentration  ;

during period uCi/ml 3.42E-09 2.12E-09

3. Percent of Tech. Spec. limit (1)  % 9.76E-01 1.76E+ 00  ;
4. Percent of Tech. Spec. limit (2)  % 4.8SE-01 8.81E-01

, 5. Percent of Tech. Spec, limit (3)  % 2.35E+00 4.17E+ 00 ,

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, 6. Percent of Tech. Spec. limit (4)  % 1.17E+ 00 2.09E+00 l

11. T R rfl U M
1. Total Release Ci 1.61E+02 1.78E+02 1.04E+01
2. Average diluted concentration during period uCi/ml 7.50E-07 7.59E-()7 l
3. Percent of applicable limit (5)  % 2.50E-02 2.53E-02 .

C. DISSOLVED AND ENTRAINED GASES  ;

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1. Total Release Ci 4.72E-02 1.72E-02 11.20E+01 ,
2. Average diluted concentration l during period uCi/ml 2.20E-10 7.31 E-11 .

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TAllLE 2A - REG GUIDE 1.21 (Cont.)  ;

1 CALVERT CLIFFS NUCLEAR POWER PLANT l EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST IIALF- 1993 LIOUID EFFLUENTS - SUMMATION OF ALL RELEASES f

IST 2ND EST. TOTAL !

D. GROSS ALPIIA RADIOACTIVITY UNITS QUARTER QUARTER ERROR, %

1. Total Release Ci (6) (6) j E. VOLUME OF WASTE RELEASED t

(prior to dilution) liters 3.64E+07 4.15E+07 130E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 2.15E +11 235E+11 it.64E+01 I

NOTES TO TAllLE 2A (1) Percent of LC.3 Quarterly Organ Dose Limit (10 mrem) to maximum exposed organ -

(2) Percent of LC.3 Yearly Organ Dose Limit (20 mrem) to maximum exposed organ (3) Percent of LC.3 Quarterly Whole Body Dose Limit (3 mrem) i (4) Percent of LC.3 Yearly Whole Body Dose Limit (6 mrem) l l

(5) Limit used is 3 x 10-3 uCi/ml (6) Irss than minimum detectable activity which meets the LLD requirements of Technical Specification Surveillance Requirement 4.11.1.1.1.

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l TAllLE 2H - REG GUIDE 1.21 CALVERT CLIITS NUCLEAR POWER I 1 ANT j EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 1 FIRST I1ALF- 1993 LIOUID EFFLUENTS CONTINUOUS MODE IIATCII MODE 1ST 2ND IST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER i Sodium -24 Ci (1) (1) (1) 2.13E-04 Chromium -51 Ci (1) (1) (1) 2.16E-02 Manganese -54 Ci (1) (1) 1.69E-03 1.83E-03 Iron -55 Ci (2) (2) 2.52E-02 6.39E-02 t

Cobalt -57 Ci (1) (1) 6.87E-04 (1)

Cobalt -58 Ci (1) (1) 4.79E-01 7.81 E-02 ;

1ron -59 Ci (1) (1) 1.42E-03 3.30E-03 l Cobalt -60 Ci (1) (1) 5.14E-03 7.36E-03 Zine -65 Ci (1) (1) 1.82E-03 (1) i Strontium -89 Ci (1) (1) 5.39E-04 1.84E-04  !

Strontium -90 Ci (1) (1) 2.21E-04 6.31E-05 Strontium -92 Ci (1) (1) (1) (1)

Niobium -95 Ci (1) (1) 1.56E-04 7.00E-03 Zirconium -95 Ci (1) (1) 2.17E-04 3.22E-03 Niobium -97 Ci (1) (1) (1) (1)

Zirconium -97 Ci (1) (1) (1) (1)

Molybdenum -99 Ci (1) (1) (1) (1)

Technetium -99m Ci (1) (1) 1.11E-04 1.65E-04 Ruthenium -103 Ci (1) (1) (1) 2.21E-03 Ruthenium -106 Ci (1) (1) (1) (1) ,

Silver -110m Ci (1) (1) 1.15E-03 5.48E-02 Tin -113 Ci (1) (1) (1) 1.49E-03 ,

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TAllLE 2B - REG GUIDE 1.21 (Cont.)

CALVERT CLIFFS NUCLEAR POWER PIANT EFFLUENT AND WASTE DISPOSAL SES11-ANNUAL REPORT F1RSTI1ALF- 1993 LIOUID EFFLUENTS CONTINUOUS h10DE BATCII h10DE IST 2ND IST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Antimony -122 Ci (1) (1) 1.26E-04 (1)

Antimony -124 Ci (1) (1) 9.66E-04 1.49E-02 Antimony -125 Ci (1) (1) 2.85E-03 7.78E-02 Tc'.lurium -127 Ci (1) (1) (1) (1)

Tellurium -129 Ci (1) (1) (1) 7.19E-03 lodine -131 Ci 8.60E-05 (1) 3.14E-02 4.02E-03 lodine -133 Ci (1) (1) 2.73E 03 7.22E-04 lodine -135 Ci (1) (1) (1) (1)

Cesium -134 Ci 1.17E-04 9.0SE-04 7.21E-02 5.83E-02 Cesium -136 Ci (1) (1) 2.43E-03 7.0SE-05 Cesium -137 Ci 1.35E-04 1.04E-03 1.02E-01 8.66E-02 Barium -139 Ci (1) (1) (1) (1)

Barium -140 Ci (1) (1) 7.93E-06 (1)

Cerium 139 Ci (1) (1) (1) (1)

Lanthanum -140 Ci (1) (1) 2.19E-03 1.21E-03 Cerium -141 Ci (1) (1) (1) 1.45E-04 Cerium -144 Ci (1) (1) 1.14E-04 (1) i I

Tungsten -187 Ci (1) (1) (1) (1)

Total For Period Ci 3.39E-04 1.95E-03 7.34E-01 4.%E-01 I

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TAllLE 2Il- REG GUIDE 1.21 (Cont.)

CALVERT CLIFFS NUCLEAR POWER PLANT i EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT i FIRST IIALF - 1993 LIOUID EFFLUENTS I i

CONTINUOUS MODE BATCII MODE IST 2ND IST 2ND NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Xenon -131m Ci (1) (1) 3.81 E-05 (1)

Xenon -133 Ci (1) (1) 4.71E-02 1.69E-02 Xenon -133m Ci (1) (1) (1) (1)

Xenon -135 Ci (1) (1) 9.52E-05 2.84E-04 Xenon -135m Ci (1) (1) (1) (1)

Total For Period Ci (1) (1) 4.72E-02 1.72E-02 i

NOTES TO TAllLE 215 f

(1) Less than minimum detectable activity which meets the LLD requirements of Technical Specification Surveillance Requirement 4.11.1.1.1.

(2) Continuous mode efDuents are not analyzed for Fe-55. l l

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TAllLE 3A -

1 CALVERT CLIFFS NUCLEAR POWER PLANT  !

EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL kEFORT F1RSTIIALF- 1993 i i

SOLID WASTE AND IRRADIATED FUEL SIIIPMENTS j i

A. SOLID WASTE SillPPED OFFSITE FOR IlURIAL OR DISPOSAL (NOTIRRADIATED FUEL) i 6-MONTII EST. TOTAL

1. Type of Waste UNITS PERIOD ERROR %  :
a. Dewatered spent resin m3 3.41E+00 Ci 1.00E+01 2.00E+01 l

3

b. Day Compressible Waste (Shipped) m 1.19E+ 03 Contaminated Equipment, etc. Ci 3.16E+0? 15.00E+01
c. Irradiated Components, m3 0.00E+00
Control Rods, etc. Ci 0.00E+00 ,

5.00E+01 l 3

d. Other (Cartridge Filters) m 0.00E+00 Ci 0.00E+ 00 2.00E+ 01 l
2. Estimate of Major Nuclides (By Type of Waste - Only nuclides > 1 Fe are reported)  !

a.

Fe-55 5.96E+007c Co-60 5.5SE+009c  !

Ni 63 3.62E+01%

Cs-134 8.98E+00Fc 4 Cs-137 4.32E+01rc j i

b.  !

C-14 1.99E+00% i Cr-51 9.36E+00% l Fe-85 3.45E+019c  !

Co-58 1.48E+007c  !

Co-60 9.82E+007c  ;

d Ni-63 1.27E+ 01%  :

Nb-95 1.01E+007c ,

, Ru-306 2.45E+00%  !

Ag-110m 1.37E+00% l 4

Sb-125 4.62E+00% l Cs-134 2.63E+00%

Cs-137 104E+01%

Ce-144 1.97E+00% .

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TAllLE 3A I

CALVERT CLIFFS NUCLEAR POWER PIANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT ,

FIRST IIALF- 1993 i SOLID WASTE AND IRRADIATED FUEL SIIIPMENTS (Cont.)  !

A. SOLID WASTE SilIPPED OFFSITE FOR HURIAL OR DISPO-AL (NOT IRRADIATED FUEL) l i

3. Solid Waste Disposition
  • Number of Shipments Mode of Transportation Destination  !

2 Motor Surface Transit Chem Nuclear Systems, Inc. -

Barnwell, SC i i

20 Motor Surface Transit Scientific Ecology Group  !

Oak Ridge,TN  !

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l APPENDIX A SOLID RADWASTE SIIIPMENT DATA -l FOR  !'

SEMI-ANNUAL EFFLUENT RELEASE REPORTING FIRSTIIALF- 1993  ;

, l TYPE WASTE: DAW 10 CFR 61 WASTE CLASS: A  :

i SOURCE OF WASTE: Radiologically Controlled Areas SIIIPPING CONTAINER: 40' Sealand Containers TOTAL CURIE QUANTITY: 2.82 Ci IlOW DLTERMINED: Dose to curie content, conversion by volume based on generic  :

distribution and scaling factors TOTAL SIIIPPED WASTE VOLUME: 41600 ft 3 IlOW DETERMINED: Container volume and number of containers shipped -

SOLIDIFICATION AGENT OR AllSORilENT: None  !

w h

p f

TYPE WASTE: Dewatered Resin f 10 CFR 61 WASTE CIASS: C  !

i SOURCE OF WASTE: Miscellaneous Liquid Radwaste Processing and calibration sources  ;

e

' 3 SillPPING CONTAINER: High Integrity L-8-120 liner (120.3 ft ) l; TOTAL CURIE QUANTITY: 10 Ci  !

llOW DETERMINED: Gamma scan using sample of resin. Conversion by weight based on l radionuclide distribution and scaling factors.

TOTAL SillPPED WASTE VOLUME: 120.3 ft 3 IlOW DETERMINED: Container volume and number of containers shipped l

)

d SOLIDIFICATION AGENT OR AllSORIIENT: None

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APPENDIX A SOLID RADWASTE SIIIPMENT DATA  !

FOR l SEMI-ANNUAL EFFLUENT RELEASE REPORTING  !

FIRST ILALF - 1993 l i

TYPE WASTE: Contaminated Plant Equipment j 10 CFR 61 WASTE CLASS: C SOURCE OF WASTE: Reactor Coolant System reactor coolant pump motor rotating assembly i l

SillPPING CONTAINER: Iligh Integrity Carbon Steel Liner <

r TOTAL CURIE QUANTITY: 28.8 Ci [

llOW DETERMINED: Dose to curie content, conversion by weight based on generic h distribution and scaling factors l

[

TOTAL SHIPPED WASTE VOLUME: 300 ft 3 6

a

IIOW DETERMINED: Container volume and number of containers shipped SOLIDIFICATION AGENT OR AllSORIlANT: None t

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APPENDIX II l f

4- SU5151ARY OF CIIANGES TO TIIE CCNPP ODCM f FIRST IIALF 1993 l i

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CIIANGES TO TIIE CCNPP ODCM IN FIRST IIALF 1993 j i

SUMMARY

ANI) IIASIS  :

A minor change of the ODCM was approved on February 10,1993. The revision was controlled by I the normal procedure change process. The change was reviewed by the Plant Operations and Safety ,

Review Committee (POSRC) and was approved by the Plant General Manager, Calvert Cliffs }

Nuclear Power Plant, prior to implementation. This process meets the requirements of CCNPP  :

Technical Specification 6.17. [

Each of the items comprising this minor change are described below:

{

. t l Item 1:The words Tossil Energy Division" were changed to " Corporate Affairs Group" due to a j corporate reorganization in which Environmental Programs Section personnel - who perform the j Radiological Emironmental Monitoring Program - were moved from the Fossil Energy Division to i

the Corporate Affairs Group. This change only impacts the organizational titles of key personnel, 2

and will not affect the Radiological Emironmental Monitoring Program outlined in the ODCM.

This change will ensure the titles and organizations of key personnel are maintained accurate.  ;

l  !

Item 2: An internal commitment tracking number was added to the margin of four pages. This i internal commitment tracking system will ensure important information is not deleted from the  ;

ODCM. t j

l Item 3: An executive summary of changes was added to the ODCM. This provides a mechamsm  !

document changes to the ODCM. l i

j A copy of the revised ODCM is attached to this report. j J

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XITACIIMENT (1)

ODCM TFlT WITII CIIANGES i

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