ML060330725

Independent Spent Fuel Storage Installation - Semi-Annual Effluent Release Report Supplemental Information

ML060330725
Person / Time
Site:	Calvert Cliffs
Issue date:	08/26/1994
From:	Baltimore Gas & Electric Co (BGE)
To:	Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
Shared Package
ML060330718	List: ML060330720 ML060330725
References
+kBR1SISP20060313 NUDOCS 9409020316
Download: ML060330725 (21)

Text

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 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 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 Trealment 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 mradlyear, gamma-air 40 mrad/year, beta-air 4. All of the above parameters are calculated according to the methodology specified in the Offsite Dose Calculation Manual (ODCM).B. Iodines and Particulates with Half 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 1.3 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 9409020316 940626 PDR ADOCK 05oo03171 R PDR 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. Iodines 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).2 C. Liquid Effluents The MPCs used for radioactive materials released in liquid effluents are in accordance with Technical Specification 3/4.11.1.

I 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.

III. TECHNICAL SPECIFICATION REPORTING REQUIREMENTS A. Calvert Cliffs Nuclear Power Plant (CCNPP). Technical Specification 6.9.1.8 1. First Half 1994 Dose Assessment Summary During the first half of 1994, liquid releases from Calvert Cliffs resulted in a calculated maximum first half organ dose of 0.41 mrem and a maximum whole body dose of 0.02 mrem. These doses are less than 2.0 % of the Technical Specification yearly organ dose limit and less than 0.3 % 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 first half of 1994.Gaseous Releases of noble gases resulted in a maximum, quarterly, gamma air dose of 0.001 mrad and a maximum, quarterly, beta air dose of 0.004 mrad.Iodines and particulates in gaseous effluents from Calvert Cliffs resulted in a maximum organ dose of 0.002 mrem for the first half of the year via the child-infant-thyroid pathway. These doses were calculated using ODCM methodology.

For the first half of 1994, 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 all releases for the first half of 1994 and the ODCM calculations, the maximum exposed individual would receive less than 2% of the allowable dose.During the first half of 1994, 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 first half of 1994, the types of radioactive solid waste shipped from Calvert Cliffs were radioactive resin, which was dewatered and shipped in high integrity containers; dry compressible waste, which was shipped as LSA waste in Sealand containers and steel boxes; and assorted fuel pool processing filters, which were shipped in a high integrity container.

Appendix A provides a detailed breakdown of the waste shipments for the first half of 1994 per the categories specified in Technical Specification 6.9.1.8. At CCNPP, methods of waste 3 supercompaction and materials segregation are used to reduce the volume of solid waste (as defined by IOGFR part 61) buried off-site.

As a result, the volume of waste actually buried is included in this report. Subsequent reports will also include the volume of solid waste buried as appropriate.

4. ODCM and Process Control Program (PCP) Changes No changes were made to the ODCM or PCP during the first half of 1994.5. Radioactive Gaseous Effluent Monitoring Instrumentation None of the Technical Specification effluent monitors were out of service for greater than 30 days.B. Independent Spent Fuel Storage Installation (ISFSI). Technical Specification 6.3 One cask of spent fuel was transferred to the ISFSI during the first half of 1994. 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 first half of 1994. 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, 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.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.

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 V sample activity decay corrected to the midpoint of the sample period multiplied by the main vent flow for the week.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 I1. 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.5

%# w 2. Continuous Releases Prior to discharge of any 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 as 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 blowdcwn 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.

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.D. Estimation of Total Error Total error for all releases was estimated using, as a minimum, the random counting error associated with typical releases.

Ea addition to this random error, the following systematic errors were also examined: 1. Liquid a. Error in volume of liquid released prior to dilution during batch releases.b. Error in volume oil 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.4 6 "I VI. BATCH RELEASES 1994 Ist 2nd QUARTER QUARTER A. Liquid 1. Number of batch releases 4.30E+01 3.70E+01 2. Total time period for batch releases (min) 1.32E+04 1.21E+04 3 Maximum time period for a batch release (miin) 1.93E+03 2.65E+03 4. Average time period for batch releases (min) 3.06E+02 3.28E+02 5. Minimum time period for a batch release (miin) 2.1OE+O1 2.50E+01 6. Average stream flow during periods of effluent into a flowing stream (liters/min of dilution water) 6.07E+06 7.65E+06 B. Gaseous 1. Number of batch releases 2.70E+01 2.60E+01 2. Total time period for batch releases (min) 5.66E+04 2.64E+04 3. Maximum time period for a batch release (miin) 7.76E+03 2.91E+03 4. Average time period for batch release (min) 1.74E+03 1.02E+03 5. Minimum time period for a batch release (min) 2.80E+01 1.25E+02 7 VII. ABNORMAL RELEASES 1994 1st 2nd QUARTER QUARTER A. Liquid 1. Number of releases 2. Total activity released (Curies)B. Gaseous 1. Number of releases 2. Total activity releases (Curies)-0 --0--0--0--0 --0--0--0-8 TABLE IA -REG GUIDE 1.21I CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF -1994 GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES 1ST 2ND EST. TOTAL A. FISSION AND ACTIVATION GASES 'UNITS QUARTER QUARTER ERROR, %1. Total Release Ci 5.24E+O1 2.98E+01 +1.20E+01 2. Average release rate for period uCi/sec 6.67E+00 3.83E+00 3. Percent of Tech. Spec. limit(l) % 1.30E-03 7.50E-04 4. Percent of Tech. Spec. limit(2) % 1.72E-03 8.91E-04 5. Percent of Tech. Spec. limit(3) % 1.83E-02 1.04E-02 6. Percent of Tech. Spec. limit(4) % 9.16E-03 5.21E-03 7. Percent of Tech. Spec. limit(5) % 2.17E-02 1.41E-02 8. Percent of Tech. Spec. limit(6) = 1.09E-02 7.06E-03 B. IODINES 1. Total Iodine -131 Ci 9.44E-04 1.80E-03 +/-6.50E+00 2. Average release rate for period uCi/sec 1.21E-04 2.29E-04 3. Percent of Tech. Spec. limit(7) % 2.88E-04 5.50E-04 4. Percent of Tech. Spec. limit(8) % 1.81E-01 3.45E-01 5. Percent of Tech. Spec. limit(9) % 9.04E-02 1.72E-01 C. PARTICULATES

_1. Particulates with half lives greater than 8 days Ci 1.19E-03 (10) +/-2.80E+01 2. Average release rate for period uCi/sec 1.53E-04 (10)3. Percent of Tech. Spec. limit(7) % 2. 1E-05 (10)4. Percent of Tech. Spec. limit(8) % 1.36E-02 (10)5. Percent of Tech. Spec. limit(9) % 6.80E-03 (10)6. Gross alpha radioactivity Ci (10) (10) N/A 9 TABLE 1A -REG GUIDE 1.21 (Continued)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF -1994 GASEOUS EFFLUENTS

-SUMMATION OF ALL RELEASES 1st 2nd EST. TOTAL D. TRITIUM UNITS QUARTER QUARTER ERROR, %1. Total Release Ci 2.O1E-01 6.OOE-01 +1.32E+01 2. Average release rate for period uCi/sec 2.59E-02 7.63E-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. l1.2.1.2.10 TABLE 1C -REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST IHALF -1994 GASEOUS EFFLUENTS

-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd 1. FISSION AND ACTIVATION GASES UNITS _QUARTER QUARTER QUARTER QUARTER Argon -41 Ci (2) 2.80E-02 1.48E-02 1.40E-02 Krypton -85 Ci (2) (2) 1.72E-01 4.47E+00 Krypton -85m Ci (2) 1.55E-03 (2) 7.75E-04 Krypton -87 Ci (2) (2) (2) (2)Krpton -88 Ci _ (2) (2) (2) (2)Xenon -131m Ci (2) (2) 1.85E-02 3.68E-01 Xenon -133 Ci 1.96E+01 6.54+00 2.74E+01 1.47E+01 Xenon -133m Ci__ (2) (2) 3.16E-01 5.24E-02 Xenon -135 Ci 4.48E+00 3.57E-00 4.33E-01 2.79E-02 Xenon -138 Ci (2) (2) (2) (2)Total for Period Ci 2.41E+01 1.01E+01 2.84E+O1 1.96E+01 2. HALOGENS _Iodine -131 Ci 9.44E-04 1.80E-03 (1) 1)Iodine -133 Ci 3.36E-03 1.20E-02 (1) (1)Total For Period Ci Ci _ 4.30E-03 1.38E-02 (1)11 VBLE IC -REG GUIDE 1.21 (Continuewsi CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF -1994 GASEOUS EFFLUENTS

-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd 3. PARTICULATES UNITS QUARTER QUARTER QUARTER QUARTER Manganese

-54 Ci (2) (2) 1 Iron -59 Ci (2) (2)Cobalt -58 Ci _ 6.18E-06 (2)Cobalt -60 Ci (2) (2)Zinc -65 Ci (2) (2) ( 1)Strontium

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

-90 Ci (2) (2) (Molybdenum

-99 Ci (2) (2) (1) (1)Cesium -134 Ci__ (2) (2) 4.49E-04 (1)Cesium -137 Ci _ 1.40E-05 (2 7.17E-04 (1)Cerium -141 Ci (2) (2) (1) (l_Cerium -144 Ci(2) (2) (1) (L)Gross Alpha Radioactivity Ci (2) ( (1)Total For Period Ci (2) 2.02E-05 (2) 1.17E-03 (1)NOTES TO TABLE IC (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 1114wf TABLE 2A -REG GUIDE 1.21 CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF -1994 LIOUID EFFLUENTS

-SU:MMATION OF ALL RELEASES Ist 2nd EST. TOTAL A. FISSION AND ACTIVATION PRODUCTS UNITS QUARTER QUARTER ERROR, %1. Total Release (not including tritium, gases, alpha) Ci 2.40E-01 3.97E-01 +1.03E+01 2. Average diluted concentration during period uCi/ml 3.05E-10 3.97E-10 3. Percent of Tech. Spec. limit(l) % 7.61E-01 3.36E+00 4. Percent of Tech. Spec. liinit(2)

% 3.80E-01 1.68E+00 5. Percent of Tech. Spec. lirnit(3)

% 1.41E-01 4.70E-01 6. Percent of Tech. Spec. limit(4) % 7.03E-02 2.35E-01 B. TRITIUM -_1. Total Release Ci 2.27E+02 l.59E+02 +1.04E+01 2. Average diluted concentration during period uCi/ml 2.88E-07 1.59E-07 3. Percent of applicable limit(5) = 9.62E-03 5.35E-03 C. DISSOLVED AND ENTRAINED GASES 1. Total Release Ci 3.67E-02 5.67E-02 1.20E+01 2. Average diluted concentration during period uCi/rnl 4.66E-1 1 5.67E-l 1 13 iMiLE 2A -REG GUIDE 1.21 (Continueaj CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF -1994 LIOUID EFFLUENTS

-SUMMATION OF ALL RELEASES Ist 2nd D. GROSS ALPHA RADIOACTIVITY UNITS QUARTER QUARTER ERROR, %1. Total Release Ci L(6) (6) N/A E. VOLUME OF WASTE RELEASED (prior to dilution) liters 2.46E+07 1.02E+07 +1.30E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 7.87E+ 11 1 .00E+12 +1 .64E+0 1 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.

14 TABLE 2B -REG GUIDE 1.21'Nolo CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF -1994 LIQUID EFFLUENTS.__ CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd NUCLIDES RELEASED UNITS QUARTER QUARTER QUARTER QUARTER Sodium -24 Ci (1) (1) 9.89E-05 (1)Chromium -51 Ci (1) (1) 1.75E-02 6.26E-02 Manganese

-54 Ci (1) (1) 5.79E-04 2.26E-03 Iron -55 Ci (2) (2) 5.29E-02 4.85E-02 Cobalt -57 Ci (1) (1) 2.09E-06 4.47E-05 Cobalt -58 Ci (1) (1) 6.46E-02 1.02E-01 Iron -59 Ci (1) (1) 8.64E-04 6.15E-03 Cobalt -60 Ci (1) (1) 2.86E-03 1.22E-02 Zinc -65 Ci (1) (1) (1) (1)Strontium

-89 Ci _ (1) (1) 1.13E-04 (1)Strontium

-90 Ci (1) (1) 4.64E-05 1.09E-04 Strontium

-92 Ci _ (1) (1) (1) (1)Niobium -95 Ci (1) (1) 5.40E-03 4.3 1E-02 Zirconium

-95 Ci (1) (1) 3.38E-03 2.33E-02 Niobium -97 Ci (1) (1A (1) (li Zirconium

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

-99 Ci _ (1) ( (1) (1)Technetium

-99M Ci (1) (1) (1) (1)Ruthenium

-103 Ci _ (1) (1) 1.06E-03 1.40E-02 Ruthenium

-106 Ci _ (1) (1) 2.46E-02 Silver -11om Ci__ (1) (1) 1.75E-02 1.1 IE-02 Tin -113 Ci _ (1) (1) 9.91E-04 6.05E-03 15 TABLE 2B -REG GUIDE 1.21 (Continued)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF -1994 LIQUID EFFLUENTS_ CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd NUCLIDES RELEASED UNITS _ QUARTER QUARTER QUARTER QUARTER Antimony -122 Ci (1L 1)L A1L !L)Antimony -124 Ci (1) (1) 7.18E-03 3.87E-03 Antimony -125 Ci (1) (1) 1.62E-02 2.40E-02 Tellurium

-127 Ci(1) (1) (1) (1)Tellurium

-129 Ci _ (1) (1) (1) (1)Iodine -131 Ci _ (1) (1) 2.12E-03 1.99E-04 Iodine -133 Ci (1) (1) 3.80E-04 1.53E-04 Iodine -135 Ci__ (1) (1) (1) (1A Cesium -134 Ci 5.89E-04 (1) 1.62E-02 2.26E-03 Cesium -136 Ci _l _( 1) (1) (1)Cesium -137 Ci 8.32E-04 (1) 2.83E-02 7.43E-03 Barium -139 Ci__ (1) (1) (1) (1)Barium -140 Ci__ (1) (1) (1) (1)Cerium -139 Ci (1) (1) (1) (1)Lanthanum

-140 Ci (1) (1) (1) (1)Cerium -141 Ci (1) (1) (1) 2.86E-04 Cerium -144 Ci _ (1) i 3.18E-03 Tungsten -187 Ci _ (1) 1) (1) (1)Total For Period Ci T 1.42E-03 (I 2.38E-01 3.97E-01 16 TABLE 2B -REG GUIDE 1.21 (Continued)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF -1994 LIOUID EFFLUENTS_ CONTINUOUS MODE BATCH MODE 1st 2nd 1st 2nd NUCLIDES RELEASED UNITS _ QUARTER QUARTER QUARTER QUARTER Krypton -85 Ci _ (1) (1) (1) (1)Xenon -131m Ci _ (1) (1) (1) (_1 Xenon -133 Ci (1) (1) 3.64E-02 5.67E-02 Xenon -133m Ci (1) (1) (1) (1)Xenon -135 Ci__ (1) (1) 2.63E-04 3.91E-05 Xenon -135m Ci )(1) (1) (1)Total For Period Ci _ (1)_(1) 3.67E-02 5.67E-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-55.17 TABLE 3A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DI'SPOSAL SEMI-ANNUAL REPORT FIRST HALF -1994 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 T 6.82E+00 Ci 1.26E+01 +2.OOE+01 b. Dry Compressible Waste (Shipped) m3 7.09E+02 Contaminated Equipment, etc. Ci 5.75E+00 +5.OOE+01 c. Irradiated Components, m O.OOE+00 Control Rods, etc. Ci O.OOE+00 N/A d. Other (Cartridge Filters) m 3.41E+00 Ci 1.93E+00 +2.OOE+01 (b.) Volume represents waste generated prior to offsite volume reduction.

Burial volume for this time period was 57.17 cubic meters with approximately 57 cubic meters remaining to be volume reduced.2. Estimate of Major Nuclides (By Type of Waste -Only nuclides >1 % are reported)a.Fe-55 1.60E+00%Co-58 6.20E;+00%

Co-60 1.60E:+00%

Ni-63 4.70E;+O1%

Cs-134 3.56E:+00%

Cs-137 4.94E:+O1%

b.C-14 1.53E:+00%

Cr-51 8.78E+00%Fe-55 2.28E.+01%

Co-58 1.41E+00%Co-60 2.30E+00%Ni-63 1.58E+01%Nb-95 1.71E+00%Zr-95 1.34E+00%Cs-134 1.32E+01%Cs-137 2.97E+01%Ce-144 1. 16E+00%d.C-14 2.66E+00%Fe-55 3.76E+01%Co-58 2.17E+00%Co-60 1.54E+01%Ni-63 1.96E+01%Nb-95 2.93E+00%Zr-95 1.23E+00%Ru-106 7.15E+00%18 TABLE 3A (Continued)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF -1994 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)d. (Continued)

Ag-l10in Sb-125 Cs-137 Ce-144 2.06E.+00%

2.8 1EI+00%1.55E,+00%

2.22E+00%3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 3 14 Motor Surface Transit Motor Surface Transit Chem Nuclear Systems, Inc.Barnwell, SC Scientific Ecology Group Oak Ridge, TN 19 APPENDIX A SOLID RADWASTE SHIPMENT DATA FOR CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF -1994 TYPE WASTE: DAW 10 CFR PART 61 WASTE CLASS: A SOURCE OF WASTE: Radiologically Controlled Areas SHIPPING CONTAINER:

40' Sealand Containers and 90 cubic foot Steel Boxes TOTAL CURIE QUANTITY:

5.75 Ci HOW DETERMINED:

Dose to curie content, conversion by volume based on generic distribution and scaling factors TOTAL SHIPPED WASTE VOLUME: 2.5,038 ft 3 TOTAL BURIAL WASTE VOLUME: 2019 ft 3 HOW DETERMINED:

Container volume and number of containers shipped SOLIDIFICATION AGENT OR ABSORBENT:

None TYPE WASTE: Dewatered Resin 10 CFR PART 61 WASTE CLASS: B SOURCE OF WASTE: Liquid Radwaste Processing Bead Resin SHIPPING CONTAINER:

High Integrity L-8-120 liner (120.3 ft 3)TOTAL CURIE QUANTITY:

12.61 Ci HOW DETERMINED:

Gamma scan using sample of resin. Conversion by weight based on radionuclide distribution and scaling factors.TOTAL SHIPPED WASTE VOLUME: 240.6 ft 3 HOW DETERMINED:

Container volume and number of containers shipped* SOLIDIFICATION AGENT OR ABSORBENT:

No A-1 APPENDIX A SOLID RADWASTE SHIPMENT DATA FOR CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT FIRST HALF -1994 TYPE WASTE: Spent Fuel Pool Filters 10 CFR PART 61 WASTE CLASS: A SOURCE OF WASTE: Spent Fuel Pool Vacuum Filters SHIPPING CONTAINER:

High Integrity Carbon Steel Liner TOTAL CURIE QUANTITY:

1.93 Ci HOW DETERMINED:

Dose to curie content, conversion by weight based on generic distribution and scaling factors.TOTAL SHIPPED WASTE VOLUME: 120.3 ft 3 HOW DETERMINED:

Container volume and number of containers shipped SOLIDIFICATION AGENT OR ABSORBENT:

None A-2