ML060330668

Semi-Annual Effluent Release Report for the Second Half of 1995

ML060330668
Person / Time
Site:	Calvert Cliffs
Issue date:	02/29/1996
From:	Baltimore Gas & Electric Co (BGE)
To:
Shared Package
ML060330666	List: ML060330667 ML060330668
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+kBR1SISP20060313 NUDOCS 9603060157
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CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SUPPLEM[ENTAL 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 boundary dose! rate greater than 500 mrem/year to the whole body or greater than 3000 mrem/year to the skin (Technical Specification 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 boundary in a 92 day period (Technical Specification 3/4.11.2.4).

3. The air dose at the site boundary due to noble gases released in gaseous effluents shall not exceed (Technical Specification 3/4.11.2.2):

10 mrad/qtr, gamma-air 20 mrad/qtr, beta-air 20 mrad/year, gamma-air 40 mrad/year, beta-air

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

B. lodines and Particulates with HIlf Lives Greater than Eight Days

1. The instantaneous release rate of iodines and particulates in gaseous 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 1.8 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 wilh half lives greater than eight days in gaseous effluents shall not exceed (Technical Specification 3/4.11.2.3):

15 mrem/qtr, any organ 9603060157 960229 PDR ADOCK 05000317 R Pnp

30 mrem/year, any organ less than 0.1% 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 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).

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 (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

4. All of the liquid dose parameters are calculated according to the methodology specified in the ODCM.

II. MAXIMUM PERMISSIBLE CONCENTRATIONS A. Fission and Activation Gases 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. The identified radionuclide concentrations are evaluated and an acceptable release rate is determined to ensure that the dose rate limits of Technical Specification 3/4.11.2.1 are not exceeded.

B. lodines and Particulates with Half Lives Greater than Eight Days 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 samples are analyzed by gamma spectroscopy for quantification of any release of radioiodines. The particulate samples are analyzed by gamma 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. Liquid 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 Part 20, Appendix B, including applicable table notes. In all cases, the more restrictive (lower) MPC found for each radionuclide is used regardless of solubility.

m. TECHNICAL SPECIFICATION REPORTING REQUIREMENTS A. Calvert Cliffs Nuclear Power Plant (CCNPP). Technical Specification 6.9.1.8

1. Second Half 1995 Dose Assessment Summary During the second half of 1995, liquid releases from Calvert Cliffs resulted in a calculated maximum annual organ dose of 0.02 mrem and a maximum whole body dose of 0.0005 mrem. These doses are less than 0.1 % of the Technical Specification yearly organ dose limit and less than 0.01 % of the Technical Specification yearly dose limit for the whole body. The controlling pathway was the fish and shellfish pathway with adult as the controlling age group, and the gastrointestinal tract representing the organ with the highest calculated dose during the second half of 1995.

Gaseous Releases of noble gases resulted in a maximum, quarterly, gamma air dose of 0.0003 mrad and a maximum, quarterly, beta air dose of 0.0003 mrad.

lodines and particulates in gaseous effluents from Calvert Cliffs resulted in a maximum organ dose of 0.0005 mrem for the second half of the year via the child-infant-thyroid pathway. These doses were calculated using ODCM methodology. For the second half of 1995, calculated off-site doses via the gaseous release pathways were below 1 % of their allowable Technical Specification limits.

2. 40 CFR 190 Total Dose Compliance Based upon the second half releases of 1995 and the ODCM calculations, the maximum exposed individual would receive less than 1% of the allowable dose.

During the second half of calendar year 1995, there were no on-site sources of direct radiation that would have contributed to a significant or measurable off-site dose. The direct radiation contribution is measured by both on-site and off-site thermoluminescent dosimeters (TLDs). The results of these measurements did not indicate any statistical increase in the off-site radiation doses attributable to on-site sources. Therefore, no increase in the calculated offsite dose is attributed to the direct exposure from on-site sources. A more detailed evaluation will be reported in the Annual Radiological Environmental Operating Report.

3. Solid Waste Report Requirements During the second half of 1995, the types of radioactive solid waste shipped from Calvert Cliffs was dry compressible waste, dewatered resins and dry mechanical filters which were shipped in; High Integrity Containers(HICs) within NRC approved casks, Sealand containers, and steel boxes. Appendix A provides a detailed breakdown of the waste shipments for the second half of 3

1995 per the categories specified in Technical Specification 6.9.1.8. At CCNPP, methods of waste and materials segregation are used to reduce the volume of solid waste shipped offsite for processing, volume reduction and burial. Since the Barnwell Site reopened in July 1995, Calvert Cliffs resumed shipment and burial of its low level radioactive waste during the time period of this report.

4. Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP)

Changes No changes were made to the ODCM during the second half of 1995. Changes were made to the interdepartmental procedure RP 101 that contains discussion of the PCP. The PCP guidance was improved to better describe the requirements for shipping wet waste. A copy of the Interdepartmental Procedure RP 101 is included as Appendix B.

B. Radioactive Gaseous Effluent Monitoring Instrumentation None of the Technical Specification effluent monitors were out of service for greater than 30 days during the second half of 1995.

C. Independent Spent Fuel Storage Installation (ISFSI). Technical Specification 6.3 One cask of spent fuel was transferred to the ISFSI during the second half of 1995. The cask was sealed within the confines of the Calvert Cliffs Auxiliary Building prior to transfer to the ISFSI facility. No quantity of radionuclides were released to the environment during the ISFSI operation in the second half of 1995. Additional information regarding the ISFSI radiation monitoring program will be included in the Annual Radiological Environmental Operation Report.

IV. AVERAGE ENERGY Not Applicable.

V. MEASUREMENTS AND APPROXIMATIONS AND TOTAL RADIOACTIVITY A. Fission and Activation Gases

1. Batch Releases Prior to each batch release of gas from a pressurized waste gas decay tank or containment, a sample is collected and analyzed by gamma spectroscopy using a Germanium (Ge) detector for the principal gamma emitting noble gas radionuclides. The total activity released is based on the pressure/volume relationship (gas laws) of the tank.

2. Continuous Releases A gas sample is collected at least weekly from the main vents and analyzed by gamma spectroscopy using a Ge detector for the principal gamma emitting noble gas radionuclides. The total activity released for the week is based on the total 4

sample activity decay corrected to the sample time multiplied by the main vent flow for the week.

Prior to and after each containment purge, a gas sample is collected and analyzed by gamma spectroscopy using a Ge detector for the principal gamma emitting noble gas radionuclides. The total activity released is based on containment volume and purge rate. Activity buildup while purging is also considered.

A monthly composite sample is collected from the main vents and analyzed by liquid scintillation for tritium. The total tritium release for the month is based on this sample analysis and the vent flow.

B. Iodine and Particulates I1. Batch Releases The total activities of radioiodines and particulates released from pressurized waste gas decay tanks, containment purges, and containment vents are accounted for by the continuous samplers on the main vent.

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.

The filters are removed weekly and are analyzed by gamma spectroscopy using a Ge detector for significant gamma emitting radionuclides. The total activity released for the week is based on the total sample activity decay 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 form monthly and quarterly composites for the gross alpha and strontium 89 and 90 analyses.

C. Liquid Effluents I. 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, iron 55, strontium 89 and 90, and tritium analyses.

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2. Continuous Releases To account for activity from continuous releases, a sample is collected and analyzed by gamma spectroscopy for 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 at a minimum of three times per week 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 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. The low-level activity water (predominantly tritium) contained in the turbine building sumps is released directly to the Chesapeake Bay. This water is sampled at least three times per week and composited. 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.

D. Estimation of Total Error Total error for all releases was estimated using, as a minimum, the random counting error associated with typical releases. In addition to this random error, the following systematic errors were also examined:

I1. 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 are usually considered additive.

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V VI. BATCH RELEASES 1995 3RD 4TH QUARTER QUARTER A. Liquid

1. Number of batch releases 3.90E+Ol 2.30E+01

2. Total time period for batch releases (min) 1.23E+04 8.97E+03 3 Maximum time period for a batch release (min) 1.49E+03 1.47E+03

4. Average time period for batch releases (min) 3.16E+02 3.90E+02

5. Minimum time period for a batch release (min) 2.60E+OI 2.70E+O0

6. Average stream flow during periods of effluent into a flowing stream (liters/min of dilution water) 9.04E+06 9.OOE+06 B. Gaseous

1. Number of batch releases 3.00E+OO 3.OOE+OO

2. Total time period for batch releases (min) 1.2 1E+03 5.25E+02

3. Maximum time period for a batch release (min) 9.80E+02 2.75E+02

4. Average time period for batch release (min) 4.05E+02 1.75E+02

5. Minimum time period for a batch release (min) 9.OOE+O 1 1.20E+02 7

W VU. ABNORMAL RELEASES 1995 3RD 4TH QUARTER QUARTER A. Liquid

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

1. Number of releases 2. Total activity releases (Curies) 8

V w TABLE 1A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1995 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 3RD 4TH EST. TOTAL UNITS QUARTER QUARTER ERROR, %

A. FISSION AND ACTIVATION GASES Ci 9.42E+00 1.40E+01 +1.20E+01

1. Total Release

2. Average release rate for period uCi/sec 1.20E+00 1.76E+00

3. Percent of Tech. Spec. limit(1)  % 2.99E-04 3.98E-04

4. Percent of Tech. Spec. limit(2) _ 2.85E-04 4.21E-04

5. Percent of Tech. Spec. limit(3)  % 4.12E-03 5.54E-03

% 2.06E-03 2.77E-03

6. Percent of Tech. Spec. limit(4)

7. Percent of Tech. Spec. limit(S)  % 4.84E-03 6.92E-03

% 2.42E-03 3.46E-03

8. Percent of Tech. Spec. limit(6)

B. IODINES C

- 1.65E-04 9.51E-05 _ +00

1. Total Iodine- 131 __Ci_

2. Average release rate for period uCi/sec 2.10E-05 1.21E-05

3. Percent of Tech. Spec. limit(7)  % 4.99E-05 2.87E-05

4. Percent of Tech. Spec. limit(8)  % 1.24E-03 7.16E-04

5. Percent of Tech. Spec. limit(9)  % 6.21E-04 l 3.58E-04 C. PARTICULATES

1. Particulates with half lives Ci 1 (10) 1.89E-05 +2.80E+01 greater than 8 days uCi/sec (10) 2.38E-06

2. Average release rate for period

3. Percent of Tech. Spec. limit(7)  % (10) 3.38E-07

% (l0j 2.18E-04

4. Percent of Tech. Spec. limit(8)

5. Percent of Tech. Spec. limit(9)  % (10) 1.09E-04

6. Gross alpha radioactivity Ci (10) I (10) N/A 9

TABLE 1A - REG GUIDE 1.21 (Continued)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1995 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 3RD 4TH EST. TOTAL D. TRITIUM UNITS QUARTER QUARTER ERROR, %

1. Total Release Ci 8.03E-01 3.73E-01 +1.32E+01

2. Average release rate for period uCi/sec 1.02E-01 4.69E-02 NOTES TO TABLE 1A (1) Percent of I.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)

(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 rate limit (1500 mrem/year)

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

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

(10) Less than minimum detectable activity which meets the LLD requirements of Technical Specification Surveillance Requirement 4.11.2.1.2.

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TABLE I - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1995 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES

_ CONTINUOUS MODE BATCH MODE 3RD I 4TH 3RD 4TH ER QUARTER QUARTER QUARTER

1. FISSION AND ACTIVATIONGASES UNITS Ci (2) (2) (2) (2)

Argon -41

-85 Ci (2 _ (2) 1.39E+00 2.05E+00 Krypton

-85m Ci (2) (2) (2) (2)

Krypton

-87 Ci (2) (2) (2) (2)

Krypton

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

Kryton (2)

Xenon -131m Ci- (2) (2) X 2)

Ci 6.08E+00 9.56E+00 (2) (2)

-133 Xenon Xenon -_133m i(2)

Ci (2) (2) 2.36E+00O2)

(2)

(2)

Xenon -135 Ci 1.95E+00 Xenon -138 Ci_ (2) (2) (2) i (2)

Ci 8.03E+00 1.19E+01 1.39E+00 2.05E+00 Total for Period

2. HALOGENS

-131 Ci 1.65E-04 9.40E-05 (1) 1.05E-06 Iodine

-133 Ci 1.16E-03 5.86E-04 (1) 1.86E-06 Iodine Ci Ci 1.33E-03 6.80E-04 (1) 2.91E-06 Total For Period 11

TABLE IC - REG GUIDE 1.21 (Continued)

CALVERT CLIFTS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1995 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH PARTICULATES UNITS QUARTER QUARTER QUARTER QUARTER 3.

Manganese -54 Ci (2) (2) (1)

Iron -59 Ci (2) (2) (1)

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

Cobalt -60 Ci (2) (2) (1)

Zinc -65 Ci (2) (2) (1) (1)

Strontium -89 Ci (2) (2) (1 1)

Strontium -90 Ci (2) (2)

Molybdenum -99 Ci (2) (2)

-134 Ci (2) 2) (1) 7.17E-06 Cesium

-137 l Ci (2) 4.42E-06 (1) 7 35E-06 Cesium Cerium -141 Ci (2) (2) (1)

Cerium -144 Ci (2) (2)

Ci (2) (2) (1) (1)

Gross Alpha Radioactivity Total

_ For Period Ci Ci (2) l 4.42E-06 (1) 1 45E-05 NOTES TO TABLE 1C (1) lodines and particulates in batch releases are accounted for with the main vent continuous samplers when the release is made through the plant main vent.

(2) Less than minimum detectable activity which meets the LLD requirements of Technical Specification Surveillance Requirement 4.11.2.1.2.

12

V w TABLE, 2A - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1995 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) Ci 3.34E-02 4.88E-02 +1.03E+01

2. Average diluted concentration during period uCi/ml 2.78E-11 4.10E-11

3. Percent of Tech. Spec. limit(l) _ 1.17E-01 3.89E-01

4. Percent of Tech. Spec. limit(2)  % 5.85E-02 1.94E-01

5. Percent of Tech. Spec. limit(3)  % 3.57E-02 3.63E-02

6. Percent of Tech. Spec. Iimit(4)  % 1.78E-02 1.81E-02 B. TRITIUM i

1. Total Release Ci 2.78E+02 2.17E+02 _1.04E+01

2. Average diluted concentration - l l during period - uCi/ml 2.32E-07 1.83E-07

3. Percent of applicable limit(5)  % 7.72E-03 6.09E-03 C. DISSOLVED AND ENTRAINED GASES

1. Total Release Ci 8.46E-03 3.1 lE-02 +1.20E+01

2. Average diluted concentration during period uCi/ml 7.05E-12 2.61E-I I 13

TABLE 2A - REG GUIDE 1.21 (Continued)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1995 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 3RD 4TH D. GROSS ALPHA RADIOACTIVITY UNITS QUARTER QUARTER ERROR, %

1. Total Release Ci (6) (6)

E. VOLUME OF WASTE RELEASED (prior to dilution) liters 2.41E+07 4.90E+07 +1.30E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 1.20E+12 1.19E+12 _1.64E+O1 NOTES TO TABLE 2A (1) Percent of I.C.3 Quarterly Organ Dose Limit (10 mrem) to maximum exposed organ (2) Percent of I.C.3 Yearly Organ Dose Limit (20 mrem) to maximum exposed organ (3) Percent of I.C.3 Quarterly Whole Body Dose Limit (3 mrem)

(4) Percent of I.C.3 Yearly Whole Body Dose Limit (6 mrem)

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

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TABLE 2B - REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1995 LIQID EFFLUENTS CONTINUOUS MODE BATCH MODE 3RD 1 4TH 3RD 4TH UNITS QUARTER QUARTER QUARTER QUARTER NUCLIDES RELEASED Ci (1) (1) (1) (1)

Sodium -24 Ci (1) (1) 5.97E-04 (12 Chromium -51 Ci (1) (1) 1.52E-04 2.13E-04 Manganese -54 Ci (2) (2) 9.02E-03 1.40E-02 Iron -55 Ci (1) (1) 5.57E-06 1.64E-06 Cobalt -57 Ci (1) (1) 2.01E-03 1.79E-03 Cobalt -58 (1) (1)

-59 Ci (1) (1)

Iron Ci (1) (1) 1.58E-03 2.81E-03 Cobalt -60

-65 Ci (1) (I Zinc 2.13E-05

-89 Ci (__ (1) (1)

Strontium 1.86E-05

-90 ci (1) (1) 1.15E-05 Strontium (1)

-92 Ci (1) (1) (1)

Strontium 1.76E-04

-95 Ci (1) (1) 1.34E-03 Niobium 6.46E-04

-95 Ci (1) 6.39E-04 Zirconium 1 (1)

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

Niobium -

5.37E-05

-97 Ci (1) (1)

Zirconium (1)

Molybdenum -99 Ci 1 Technetium -99m Ci Il (1) ll (1) (1) (1)

Ci (1 (1) (1) (1)

Ruthenium -103 Ci (1) (1) (1) j 1 Ruthenium -106 i Ci (1) (1) 1.29E-03 1.70E-02 Silver -110m Ci (1) (1) 2.1 lE-04 4.53E-04 Tin -113 I'

TABLE 2B - REG GUIDE 1.21 (Continued) a CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1995 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE I 3RD 4TH 3RD 4TH UNITS QUARTER QUARTER QUARTER QUARTER NUCLIDES RELEASED 1)

-122 Ci (1) (1) 1.25E-05 Antimony (1j

-124 Ci (1) (1) 3.55E-04 Antimony 3.06E-03

-125 Ci (1) (1) 1.06E-02 Antimony (1)

-127 Ci () (1) (1)

Tellurium (1)

-129 Ci (1) (1) (1)

Tellurium 4.38E-04

-131i Ci (1) 6.58E-06 1.OOE-05 Iodine 4.16E-05

-133 Ci (1 1.85E-05 4.16E-05 Iodine (1)

-135 Ci 1 (1) (1)

Iodine 1.40E-03

-134 Ci (1) 6.41E-05 2.01E-03 Cesium

-136 Ci (1 ()()()

Cesium 2.3 1E-03

-137 Ci j 4.25E-05 3.41E-03 Cesium ()1

-139 Ci I (1) (

Barium (1)

-140 Ci (1) 5.67E-05 Barium

-139 Ci' (li (1 Cerium

-140 Ci (1) (1) (1)

Lanthanum

-141 Ci (1) (1j) (1 Cerium 1.70E-03 Cerium -144 Ci (1) (1) _(1)

Ci _ (1) (1) (1) 1.52E-03 Europium -154 Ci (1) (lj (1) 1.05E-03 Europium -155 _

Ci l (1) (1) (1) (1)

Tungsten -187 I Ci (1) 1.32E-04 3.34E-02 4.87E-02 Total For Period 16

TABLE 2B - RE;IGUIDE 1.21 (Continued)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1995 LIQUID EFFLUENTS l CONTINUOUS MODE BATCH MODE

' 3RD 4TH 3RD 4TH NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Krypton -85 Ci () l (I) (1) (1)

Xenon -131m Ci (1) (1) 4.1 IE-04 (1)

Xenon -133 Ci (1) (1) 8.05E-03 3.1 OE-02 Xenon -133m Ci (1) (1) (1) (1)

Xenon -135 Ci (1) (1) 3.26E-06 5.42E-05 Xenon -135m Ci (1) (1) (1) 4.22E-05 Total For Period Ci (1) (1) 8.46E-03 3.1 IE-02 NOTES TO TABLE 2B (1) Less than minimum detectable activity which meets the LLD requirements of Technical Specification Surveillance Requirement 4.11.1.1.1.

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

1'

TABLE3A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1995 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. Dewatered spent resin m' 2.38E+O1 Ci 3.23E+02 +2.OOE+01

b. Dry Compressible Waste (Shipped) m3 8.83E+01 Contaminated Equipment, etc. Ci 2.92E-01 +5.OOE+01 Dry Compressible Waste (Buried) mJ 1.82E+01 Contaminated Equipment, etc. Ci 7.13E-02 +5.OOE+01

c. Irradiated Components, j I 0.OOE+00 Control Rods, etc. Ci 0.OOE+00 N/A

d. Other (Cartridge Filters) mI 6.80E+00 Ci 7.64E+00 l +2.OOE+0I (b.) Volume shipped represents waste generated prior to offsite volume reduction.

2. Estimate of Major Nuclides (By Type of Waste - Only nuclides >1 % are reported)

a. Fe-55 1.20E+00%

Co-60 1.27E+00%

Ni-63 3.64E+00%

Cs-137 9.21E+01%

Ce-144 1.06E+00%

b. H-3 1.85E+00%

C-14 1.58E+00%

Cr-51 8.01E+00%

Fe-55 2.30E+01%

Co-58 1.37E+01%

Co-60 2.33E+00%

Ni-63 1.61E+00%

Nb-95 1.60E+00%

Zr-95 1.30E+00%

Cs-134 1.34E+01%

Cs-137 3.03E+01%

Ce-144 1.16E+00%

c. N/A 18

d C-14 9.96E+00%

Cr-51 3.56E+00%

Fe-55 3.94E+01%

Co-58 1.73E+01%

Co-60 7.3 3E+00%

Ni-63 6.96E+00%

Nb-95 6.02E+00%

Zr-95 3.14E+00%

Sb- 125 1.013E+00%

Ru-106 1.1 2E+00%

Sn-1 13 1.1 8E+00%

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 21 Motor Surface Transit Chem Nuclear Systems, Inc.

Barnwell, SC 2 Motor Surface Transit Scientific Ecology Group Oak Ridge, TN 1S

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1995 TYPE WASTE: DAW 10 CFR PART 61 WASTE CLASS: A SOURCE OF WASTE: Radiologically Controlled Areas SHIPPING CONTAINER: 20' & 40' Sealand Containers; 45 and 90 cubic foot Steel Boxes TOTAL CURIE QUANTITY: 0.364 Ci HOW DETERMINED: Dose to curie content, conversion by volume based on generic distribution and scaling factors TOTAL SHIPPED WASTE VOLUME: 3,764 ft3 TOTAL BURIAL WASTE VOLUME: 1805.3 ft3 HOW DETERMINED: Container volume and number of containers shipped SOLIDIFICATION AGENT OR ABSORBENT: None A-1

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1995 TYPE WASTE: Dewatered Resin 10 CFR PART 61 WASTE CLASS: A(S), B and C SOURCE OF WASTE: Liquid Waste Processing Systems SHIPPING CONTAINER: High Integrity L-.8-120 Liner (120.3)

TOTAL CURIE QUANTITY: 323.5 Ci HOW DETERMINED: Gamma scan analysis using resin sample, conversion by weight based on radionuclide distribution and scaling factors TOTAL SHIPPED WASTE VOLUME: 842.1 ft3 TOTAL BURIAL WASTE VOLUME: 842.1 ft3 HOW DETERMINED: Container volume and number of containers shipped SOLIDIFICATION AGENT OR ABSORBENT: None A-2

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1995 TYPE WASTE: Spent Fuel Pool Filters 10 CFR PART 61 WASTE CLASS: B and C SOURCE OF WASTE: Spent fuel pool and portable underwater vacuum filters.

SHIPPING CONTAINER: High Integrity L-8-120 Liners (120.3 ft 3 )

TOTAL CURIE QUANTITY: 7.64 Ci HOW DETERMINED: Dose to curie content, conversion by weight based on generic distribution and scaling factors TOTAL SHIPPED WASTE VOLUME: 240.6 ft3 TOTAL BURIAL WASTE VOLUME: 240.6 ft3 HOW DETERMINED: Container volume and number of containers shipped SOLIDIFICATION AGENT OR ABSORBENT: None A-3

APPENDIX B CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE [)ISPOSAL SEMI-ANNUAL REPORT SECOND HALF - 1995