ML003735538

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Radioactive Effluent Release Report and Dose Report, Annual Report for 1999
ML003735538
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 07/21/2000
From:
Constellation Nuclear
To:
NRC/OCIO/IMD/RMB
References
+kBR1SISP20060313, -RFPFR
Download: ML003735538 (20)
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Text

ENCLOSURE (1)

Calvert Cliffs Nuclear Power Plant - Units 1 & 2 Independent Spent Fuel Storage Installation July 21, 2000

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION Facility - Calvert Cliffs Nuclear Power Plant Licensee - Calvert Cliffs Nuclear Power Plant, Inc.

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 [Offsite Dose Calculation Manual (ODCM) 3.11.2.1].
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 (ODCM 3.11.2.4).
3. The air dose at the site boundary due to noble gases released in gaseous effluents shall not exceed (ODCM 3.11.2.2):

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 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 (ODCM 3.11.2.1).
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 (ODCM 3.11.2.4).
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 (ODCM 3.11.2.3):

15 mrem/qtr, any organ 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.

1

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION 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 (ODCM 3.11.1.1).
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 (ODCM 3.11.1.3).
3. The dose to a member of the public in unrestricted areas shall not exceed (ODCM 3.11.1.2):

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 ODCM 3.11.2.1 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 ODCM.

C. Liquid Effluents The maximum permissible concentrations (MPCs) used for radioactive materials released in liquid effluents are in accordance with ODCM 3.11.1.1 and the values from 10 CFR Part 20, Appendix B, Table II including applicable table notes. In all cases, the more restrictive (lower) MPC found for each radionuclide is used regardless of solubility.

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CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION III. TECHNICAL SPECIFICATION REPORTING REQUIREMENTS A. Calvert Cliffs Nuclear Power Plant (CCNPP), Technical Specification 5.6.3

1. 1999 Dose Assessment Summary Actual Percent of ODCM Value ODCM Limit Limit Liquid Waste:

Maximum Annual Organ Dose (mrem) 1 0.70 3.50 20 Maximum Whole Body Dose (mrem)' 0.11 0.18 6 Gaseous Waste:

Noble Gases:

Maximum Quarterly Gamma Air Dose (mrad) 0.004 0.036 10 Maximum Quarterly Beta Air Dose (mrad) 0.016 0.078 20 Iodines and Particulates:

Maximum Annual Organ Dose Rate (mrem) 2 0.020 0.001 1500 Maximum Annual Organ Dose (mrem) 2 0.130 0.434 30 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 calendar year of 1999.

2 The controlling pathway was the child-infant-thyroid pathway representing the organ with the highest calculated dose during the calendar year of 1999.

2. 40 CFR 190 Total Dose Compliance Based upon the calendar year 1999 and the ODCM calculations, the maximum exposed individual would receive less than 1% of the allowable dose. During the calendar year 1999, 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 1999, the types of radioactive solid waste shipped from Calvert Cliffs were dry compressible waste, filters, and dewatered resins 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 1998 per the categories specified in Technical Specification 5.6.3. 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.
4. Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP)

Changes There were no changes to the ODCM. The PCP was revised in 1999, a copy is attached.

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CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION B. Radioactive Gaseous Effluent Monitoring Instrumentation No effluent pathway was unmonitored for more than 30 consecutive days in 1999.

C. Independent Spent Fuel Storage Installation (ISFSI), Technical Specification 6.3 No casks of spent fuel transferred to the ISFSI during 1999 No quantity of radionuclides was released to the environment during the ISFSI operation in 1999. Additional information regarding the ISFSI radiation-monitoring program is 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).

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 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.

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 the sample analysis and the main vent flow.

B. Iodine and Particulates

1. 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 4

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION 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 from each release, this is used in turn to prepare monthly tritium and quarterly gross alpha, iron-55, and strontium-89 and -90 samples for analysis.

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 analysis.

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 weekly 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.

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CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION 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:

1. Liquid
a. Error in volume of liquid released prior to dilution during batch releases.
b. Error in volume of liquid released via steam generator blowdown.
c. Error in amount of dilution water used during the reporting period.
2. Gases
a. Error in main vent release flow.
b. Error in sample flow rate.
c. Error in containment purge release flow.
d. Error in gas decay tank pressure.

Where errors could be estimated they are usually considered additive.

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CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION VI. BATCH RELEASES 1999 IST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER A. Liquid

1. Number of batch releases 2.30E+01 2.90E+01 2.60E+01 1.70E+01
2. Total time period for batch 6.73E+03 9.50E+03 7.15E+03 7.08E+03 releases (min)
3. Maximum time period for a 6.21E+02 1.84E+03 6.05E+02 6.05E+02 batch release (min)
4. Average time period for batch 2.93E+02 3.28E+02 2.75E+02 4.16E+02 releases (min)
5. Minimum time period for a 1.40E+01 1.10E+01 2.40E+01 1.70E+01 batch release (min)
6. Average stream flow during 8.14E+06 7.20E+06 8.90E+06 8.93E+06 periods of effluent into a flowing stream (liters/min of dilution water)

B. Gaseous

1. Number of batch releases 5. OOE+00 1.60E+O1 0. OOE+00 3.OOE+00
2. Total time period for batch 7.37E+02 4.44E+03 O.OOE+00 2.05E+02 releases (min)
3. Maximum time period for a 3.25E+02 1.71E+03 0.OOE+00 9.50E+01 batch release (min)
4. Average time period for batch 1.47E+02 2.78E+02 0.OOE+00 6.83E+01 release (min)
5. Minimum time period for a 5.OOE+00 4.OOE+00 0.OOE+00 5.50E+01 batch release (min)

VII. ABNORMAL RELEASES 1999 1ST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER A. Liquid

1. Number of releases -0 -0 -0 -0
2. Total activity released (Curies) -0 -0 -0 -0 B. Gaseous
1. Number of releases -0 -0 -0 -0
2. Total activity releases (Curies) 7

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 1A - REGULATORY GUIDE 1.21 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 1ST 2ND EST. TOTAL A. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER ERROR, %

1. Total Release Ci 6.28E+01 5.70E+01 +1.20E+01
2. Average release rate for period uCi/sec 8.08E+00 7.25E+00
3. Percent of Tech. Spec. limit (1)  % 8.79E-04 9.14E-04
4. Percent of Tech. Spec. limit (2)  % 5.366E-04 6.90E-04
5. Percent of Tech. Spec. Limit(3)  % 1.28E-02 1.28E-02
6. Percent of Tech. Spec. limit (4)  % 6.42E-03 6.39E-03
7. Percent of Tech. Spec. limit (5)  % 2.83E-02 3.20E-02
8. Percent of Tech. Spec. limit (6)  % 1.41E-02 1.60E-02 B. IODINES
1. Total Iodine - 131 Ci 4.26E-04 3.38E-03 +6.50E+00
2. Average release rate for period uCi/sec 5.48E-05 4.30E-04
3. Percent of Tech. Spec. limit (7)  % 1.30E-04 1.02E-03
4. Percent of Tech. Spec. limit (8)  % 8.16E-02 6.47E-01
5. Percent of Tech. Spec. limit (9)  % 4.08E-02 3.24E-01 C. PARTICULATES
1. Particulates with half lives greater than 8 days Ci (10) (10) +/-2.80E+01
2. Average release rate for period uCi/sec (10) (10)
3. Percent of Tech. Spec. limit (7)  % (10) (10)
4. Percent of Tech. Spec. limit (8)  % (10) (10)
5. Percent of Tech. Spec. limit (9)  % (10) (10)
6. Gross alpha radioactivity Ci (10) (10) N/A 3RD 4TH EST. TOTAL A. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER ERROR, %
1. Total Release Ci 1.34E+01 2.57E+01 +1.20E+01
2. Average release rate for period uCi/sec 1.68E+00 3.23E+00
3. Percent of Tech. Spec. limit (1)  % 3.22E-04 3.87E-04
4. Percent of Tech. Spec. limit (2)  % 1.23E-04 2.42E-04
5. Percent of Tech. Spec. limit (3)  % 4.65E-03 5.65E-03
6. Percent of Tech. Spec. limit (4)  % 2.33E-03 2.83E-03
7. Percent of Tech. Spec. limit (5)  % 5.50E-03 1.23E-02
8. Percent of Tech. Spec. limit (6)-  % 2.75E-03 6.14E-03 B. IODINES
1. Total Iodine - 131 Ci 3.56E-04 3.65E-04 +6.50E+00
2. Average release rate for period uCi/sec 4.48E-05 4.59E-05
3. Percent of Tech. Spec. limit (7)  % 1.06E-04 1.09E-04
4. Percent of Tech. Spec. limit (8)  % 6.82E-02 6.99E-02
5. Percent of Tech. Spec. limit (9)  % 3.41E-02 3.49E-02 C. PARTICULATES
1. Particulates with half lives greater than 8 days Ci (10) (10) +2.80E+01
2. Average release rate for period uCi/sec (10) (10)
3. Percent of Tech. Spec. limit (7)  % (10) (10)
4. Percent of Tech. Spec. limit (8)  % (10) (10)
5. Percent of Tech. Spec. limit (9)  % (10) (10)
6. Gross alpha radioactivity Ci (10) (10) N/A 8

CAL VERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 1A - REGULATORY GUIDE 1.21 (Continued)

GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 1ST 2ND EST. TOTAL D. TRITIUM UNITS QUARTER QUARTER ERROR, %

1. Total Rellease Ci 7.68E-01 1.26E+00 +1.32E+01
2. Average release rate for period uCi/sec 9.88E-02 1.60E-01

__m 4

3RD 4TH EST. TOTAL D. TRITIUM UNITS QUARTER QUARTER ERROR, %

r1 II- -I- I 1. Total Release Ci 2.75E+00 1.85E+00 +1.32E+01 L1 2. Average release rate for period uCi/sec 3.46E-01 2.33E-01 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 lowest limit of detection (LLD) requirements of ODCM Surveillance Requirement 4.11.2.1.2.

9

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE IC - REGULATORY GUIDE 1.21 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE

1. FISSION AND ACTIVATION 1ST 2ND IST 2ND GASES UNITS QUARTER QUARTER QUARTER QUARTER Argon -41 Ci (2) (2) 1.36E-05 6.40E-03 Krypton -85 Ci 8.13E+00 9.85E+00 6.98E+00 1.84E+01 Krypton -85m Ci (2) (2) 4.98E-05 3.OOE-02 Krypton -87 Ci (2) (2) (2) 1.47E-02 Krypton -88 Ci (2) (2) (2) 4.07E-02 Xenon -131m Ci 5.63E-01 1.33E-01 1.25E-03 1.26E-01 Xenon -133 Ci 4.58E+O1 1.90E+01 1.40E-01 4.90E+00 Xenon -133m Ci 3.20E-01 3.91E-02 1.78E-03 8.96E-02 Xenon -135 Ci 9.10E-01 3.86E+00 2.53E-03 4.45E-01 Xenon -135m Ci (2) (2) (2) 3.59E-02 Xenon -138 Ci (2) (2) (2) 1.29E-02 Total for Period Ci 5.57E+01 3.29E+01 7.13E+00 2.41E+01
2. HALOGENS Iodine -131 Ci 4.26E-04 3.38E-03 (1) (1)

Iodine -133 Ci 1.54E-03 2.21E-03 (1) (1)

Bromine - 82 Ci (2) (2) (1) (1)

Total For Period Ci Ci 1.97E-03 5.59E-03 (1) (1)

CONTINUOUS MODE BATCH MODE

1. FISSION AND ACTIVATION 3RD 4TH 3RD 4TH GASES UNITS QUARTER QUARTER QUARTER QUARTER Argon -41 Ci (2) (2) (2) (2)

Krypton -85 Ci (2) (2) (2) 7.57E+00 Krypton -85m Ci (2) 1.63E-01 (2) (2)

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

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

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

Xenon -133 Ci 1.21E+01 1.70E+01 (2) (2)

Xenon -133m Ci (2) (2) (2) (2)

Xenon -135 Ci 1.25E+00 9.24E-01 (2) (2)

Xenon -135m Ci (2) (2) (2) (2)

Xenon -138 Ci (2) (2) (2) (2)

Total for Period Ci 1.34E+01 1.81E+01 0.00E+00 7.57E+00

2. HALOGENS Iodine -131 Ci 3.56E-04 3.65E-04 (1) (1)

Iodine -133 Ci 2.41E-03 1.72E-03 (1) (1)

Bromine - 82 Ci 1.13E-05 2.65E-05(1) (1)

Total For Period Ci Ci 2.78E-03 2.11E-03 (1) (1) 10

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE IC - REGULATORY GUIDE 1.21 (Continued)

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) (1)

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

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

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

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

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

Strontium -90 Ci (2) (2) (1) (1)

Molybdenum -99 Ci (2) (2) (1) (1)

Cesium -134 Ci (2) (2) (1) (1)

Cesium -137 Ci (2) (2) (1) (1)

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

Cerium -144 Ci (2) (2) (1) (1)

Gross Alpha Radioactivity Ci (2) (2) (1) (1)

Total For Period Ci Ci (2) (2) (1) (1)

CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH

3. PARTICULATES UNITS QUARTER QUARTER QUARTER QUARTER Manganese -54 Ci (2) (2) (1) (1)

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

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

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

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

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

Strontium -90 Ci (2) (2) (1) (1)

Molybdenum -99 Ci (2) (2) (1) (1)

Cesium -134 Ci (2) (2) (1) (1)

Cesium -137 Ci (2) (2) (1) (1)

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

Cerium -144 Ci (2) (2) (1) (1)

Gross Alpha Radioactivity Ci (2) (2) (1) (1)

Total For Period Ci Ci (2) (2) (1) (1)

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 ODCM Surveillance Requirement 4.11.2.1.2.

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CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 2A - REGULATORY GUIDE 1.21 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 1ST 2ND EST. TOTAL A. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER ERROR, %

1. Total Release (not including tritium, Ci 1.22E-01 3.82E-01 +1.03E+01 gases, alpha)
2. Average diluted concentration during uCi/ml 1.15E-10 4.05E-10 period
3. Percent of Tech. Spec. limit (1)  % 7.50E-01 3.93E+00
4. Percent of Tech. Spec. limit (2)  % 3.75E-01 1.97E+00
5. Percent of Tech. Spec. limit (3)  % 7.97E-02 2.14E-01
6. Percent of Tech. Spec. limit (4)  % 3.99E-02 1.07E-01 B. TRITIUM
1. Total Release Ci 2.74E+02 1.78E+02
2. Average diluted concentration during uCi/ml 2.59E-07 1.89E-07 period
3. Percent of applicable limit (5)  % 8.62E-03 6.29E-03 C. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci 1.29E-02 2.41E-02
2. Average diluted concentration during uCi/ml 1.22E- 11 2.55E-1 1 period _7 I 3RD 4TH EST. TOTAL A. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER ERROR, %
1. Total Release (not including tritium, gases, alpha) Ci 9.47E-02 7.75E-02 +l.03E+01
2. Average diluted concentration during period uCi/ml 8.03E-11 6.57E-11
3. Percent of Tech. Spec. limit (1)  % 1.22E+00 1.09E+00
4. Percent of Tech. Spec. limit (2)  % 6.11 E-01 5.45E-01
5. Percent of Tech. Spec. limit (3)  % 3.86E-02 2.32E-02
6. Percent of Tech. Spec. limit (4)  % 1.93E-02 1.16E-02 B. TRITIUM
1. Total Release Ci 2.05E+02 2.79E+02
2. Average diluted concentration during period uCi/ml 1.74E-07 2.37E-07
3. Percent of applicable limit (5)  % 5.79E-03 7.88E-03 C. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci 8.46E-03 5.62E-02
2. Average diluted concentration during period uCi/ml 7.17E-12 4.76E-11 12

CAL VERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 2A - REGULATORY GUIDE 1.21 (Continued)

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 1ST 2ND EST. TOTAL D. GROSS ALPHA RADIOACTIVITY UNITS QUARTER QUARTER ERROR, %

1. Total Release Ci 2.40E-04 (6)

E. VOLUME OF WASTE RELEASED (prior to dilution) liters 1.45E+07 3.04E+07 +1.30E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 1.06E+12 9.44E+1 1 +1.64E+01 3RD 4TH EST. TOTAL D. GROSS ALPHA RADIOACTIVITY UNITS QUARTER QUARTER ERROR, %

1. Total Release Ci (6) (6)

E. VOLUME OF WASTE RELEASED (prior to dilution) Liters 2.98E+07 2.62E+07 +1.30E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD liters 1.18E+12 1.18E+12 +1.64E+01 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 ODCM Surveillance Requirement 4.11.1.1.1.

13

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 2B - REGULATORY GUIDE 1.21 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 1ST 2ND 1ST 2ND NUCLIDES RELEASED Units QUARTER QUARTER QUARTER QUARTER Beryllium - 7 Ci (1) (1) (1) (1)

Sodium - 22 Ci (1) (1) (1) (1)

Sodium - 24 Ci (1) (1) (1) (1)

Chromium - 51 Ci (1) (1) 3.43E-04 6.95E-02 Manganese - 54 Ci (1) (1) 3.53E-03 2.97E-03 Iron - 55 Ci (2) (2) 5.08E-02 8.10E-02 Cobalt - 57 Ci (1) (1) 1.51E-05 2.531E-04 Cobalt- 58 Ci (1) (1) 9.22E-03 8.39E-02 Iron - 59 Ci (1) (1) 1.72E-05 1.01E-02 Cobalt- 60 Ci (1) (1) 1.86E-02 9.41E-03 Zinc - 65 Ci (1) (1) (1) (1)

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

Strontium - 90 Ci (1) (1) (1) (1)

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

Niobium - 95 Ci (1) (1) 9.68E-03 6.11E-02 Zirconium - 95 Ci (1) (1) 5.21E-03 3.80E-02 Niobium - 97 Ci (1) (1) (1) (1)

Zirconium - 97 Ci (1) (1) (1) 1.77E-04 Molybdenum - 99 Ci (1) (1) (1) (1)

Technetium - 99m Ci (1) (1) (1) (1)

Ruthenium - 103 Ci (1) (1) (1) 8.93E-04 Rhodium- 105 Ci (1) (1) (1) (1)

Ruthenium - 105 Ci (1) (1) (1) (1)

Ruthenium - 106 Ci (1) (1) 3.46E-04 8.84E-04 Silver - Irnm Ci (1) (1) 6.50E-03 1.05E-02 Tin - 113 Ci (1) (1) 8.77E-04 3.79E-03 Tin - 117m Ci (1) (1) 1.32E-05 4.69E-04 Antimony- 122 Ci (1) (1) (1) (1)

Antimony- 124 Ci (1) (1) (1) 1.35E-03 Antimony - 125 Ci (1) (1) 3.38E-03 6.88E-03 Tellurium - 125m Ci (1) (1) 4.61E-03 (1)

Tellurium - 132 Ci (1) (1) (1) (1)

Iodine- 131 Ci (1) (1) 1.79E-04 1.98E-05 Iodine - 133 Ci (1) (1) 4.94E-05 6.01E-06 Iodine- 135 Ci (1) (1) (1) (1)

Cesium- 134 Ci (1) (1) 7.31E-05 3.01E-04 Cesium- 136 Ci (1) (1) (1) (1)

Cesium - 137 Ci (1) (1) 6.41E-04 4.82E-04 Barium- 140 Ci (1) (1) (1) (1)

Lanthanum- 140 Ci (1) (1) (1) 1.59E-04 Cerium- 144 Ci (1) (1) 2.75E-03 (1)

Europium - 154 Ci (1) (1) 3.41E-03 (1)

Europium- 155 Ci (1) (1) 1.40E-03 (1)

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

Total For Period Ci (1) (1) 1.22E-01 3.82E-01 14

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 2B - REGULATORY GUIDE 1.21 (Continued)

LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED Units QUARTER QUARTER QUARTER QUARTER Beryllium - 7 Ci (1) (1) (1) (1)

Sodium - 22 Ci (1) (1) (1) (1)

Sodium- 24 Ci (1) (1) (1) (1)

Chromium - 51 Ci (1) (1) 6.87E-03 1.39E-03 Manganese - 54 Ci (1) (1) 1.35E-03 1.66E-03 Iron - 55 Ci (2) (2) 9.89E-03 1.19E-02 Cobalt - 57 Ci (1) (1) 3.27E-05 8.40E-05 Cobalt - 58 Ci (1) (1) 2.50E-02 1.93E-02 Iron - 59 Ci (1) (1) 8.09E-04 2.43E-04 Cobalt - 60 Ci (1) (1) 3.64E-03 5.99E-03 Zinc - 65 Ci (1) (1) (1) (1)

Strontium - 89 Ci (1) (1) 1.49E-04 (1)

Strontium - 90 Ci (1) (1) 8.51E-06 (1)

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

Niobium - 95 Ci (1) (1) 1.85E-02 1.47E-02 Zirconium - 95 Ci (1) (1) 1.03E-02 7.32E-03 Niobium - 97 Ci (1) (1) 6.21E-06 (1)

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

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

Technetium - 99m Ci (1) (1) (1) (1)

Ruthenium - 103 Ci (1) (1) (1) (1)

Rhodium- 105 Ci (1) (1) (1) (1)

Ruthenium- 105 Ci (1) (1) (1) (1)

Silver - Irnm Ci (1) (1) 1.23E-02 1.25E-02 Tin - 113 Ci (1) (1) 1.42E-03 7.96E-04 Tin - 117m Ci (1) (1) (1) (1)

Antimony - 122 Ci (1) (1) 1.63E-06 (1)

Antimony - 124 Ci (1) (1) 2.24E-04 (1)

Antimony - 125 Ci (1) (1) 3.77E-03 1.34E-03 Tellurium - 132 Ci (1) (1) (1) (1)

Iodine- 131 Ci (1) (1) 1.23E-05 7.13E-06 Iodine - 133 Ci (1) (1) 7.95E-06 5.66E-06 Iodine- 135 Ci (1) (1) (1) (1)

Cesium - 134 Ci (1) (1) 1.86E-04 4.21E-05 Cesium- 136 Ci (1) (1) (1) (1)

Cesium - 137 Ci (1) (1) 2.40E-04 1.80E-04 Barium- 140 Ci (1) (1) (1) (1)

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

Cerium- 144 Ci (1) (1) (1) (1)

Europium- 154 Ci (1) (1) (1) (1)

Europium - 155 Ci (1) (1) (1) 5.86E-05 Tungsten - 187 Ci (1) (1) (1) (1)

Total For Period Ci (1) (1) 9.47E-02 7.75E-02 15

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 2B - REGULATORY GUIDE 1.21 (Continued)

LIQUID 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)

Xenon-133 Ci (1) (1) 1.28E-02 2.41E-02 Xenon- 135 Ci (1) (1) 8.58E-05 (1)

Total For Period Ci (1) (1) 1.29E-02 2.41E-02 CONTINUOUS MODE BATCH MODE 3RD 4TH 3RD 4TH NUCLIDES RELEASED Units QUARTER QUARTER QUARTER QUARTER Krypton - 85 Ci (1) (1) (1) (1)

Xenon-13 1m Ci (1) (1) 3.68E-05 (1)

Xenon- 133 Ci (1) (1) 8.42E-03 5.61E-02 Xenon - 135 Ci (1) (1) 6.OOE-06 6.58E-05 Total For Period Ci (1) (1) 8.46E-03 5.62E-02 NOTES TO TABLE 2B (1) Less than minimum detectable activity which meets the LLD requirements of ODCM Surveillance Requirement 4.11.1.1.1.

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

16

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 3A SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL) 12-MONTH EST. TOTAL

1. Type of Waste UNITS PERIOD ERROR %
a. Dewatered spent resin MV 1.70E+01 Ci 3.61E+02 +2.OOE+01
b. Dry Compressible Waste (Shipped) mJ 8.11E+02 Contaminated Equipment, etc. Ci 1.57E+00 +5.OOE+O1
b.
  • Dry Compressible Waste (Buried) mJ 9.63E+01 Contaminated Equipment, etc. Ci 1.76E+00 +5.OOE+01 C. Irradiated Components, m3 O.OOE+00 Control Rods, etc. Ci O.OOE+00 N/A
d. Other (Cartridge Filters) mi 3.40E+00 Ci 3.95E+00 N/A (b.) Volume shipped represents waste generated prior to offsite volume reduction.

(b. *) Represents waste buried after volume reduction at offsite processor.

2. Estimate of Major Nuclides (By Type of Waste - Only nuclides >1 % are reported)
a. Mn-54 1.50E+00%

Fe-55 1.17E+01%

Co-58 1.90E+00%

Co-60 4.90E+00%

Ni-63 2.88E+O 1%

Cs-134 2.04E+O 1%

Cs-137 2.99E+01%

b. H-3 5.70E+00%

C- 14 1.67E+00%

Cr-51 7.80E+00%

Fe-55 2.72E+O 1%

Co-58 1.97E+O1%

Co-60 5.70E+00%

Ni-63 9.40E+00%

Nb-95 4.80E+00%

Zr-95 3.30E+00%

Cs-134 3.50E+00%

Cs-137 7.70E+00%

c. N/A 17

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 1999 ANNUAL REPORT SUPPLEMENTAL INFORMATION TABLE 3A (Continued)

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS

d. C-14 5.20E+00%

Cr-51 3.OOE+00%

Mn-54 1.50E+00%

Fe-55 4.33E+01%

Co-58 9.20E+00%

Co-60 9.20E+00%

Ni-63 1.35E+01%

Nb-95 6.80E+00%

Zr-95 2.60E+00%

Cs-134 1.10E+00%

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 6 Motor Surface Transit Chem. Nuclear Systems, Inc.

Barnwell, SC 4 Motor Surface Transit GTS Duratek Oak Ridge, TN 1 Motor Surface Transit Diversified Scientific Services Inc.

Kingston, TN 3 Motor Surface Transit Allied Technology Group Richland, WA 15 Motor Surface Transit US Ecology, Inc.

Oak Ridge, TN 18

APPENDIX (A)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT 1999 TYPE WASTE: DAW 10 CFR PART 61 WASTE CLASS: A SOURCE OF WASTE: Radiologically Controlled Areas SHIPPING CONTAINER: 20' or 40' Sealand Containers, B-25 Metal Boxes, and 55-Gallon Drums TOTAL CURIE QUANTITY: 3.33 Ci HOW DETERMINED: Dose to curie content, conversion by volume based on generic distribution and scaling factors TOTAL SHIPPED WASTE VOLUME: 29,000 ft3 TOTAL BURIAL WASTE VOLUME: 3400 ft3 HOW DETERMINED: Container volume and number of containers shipped, Burial volume is determined from information provided by volume reduction processor.

SOLIDIFICATION AGENT OR ABSORBENT: None 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: 361 Ci HOW DETERMINED: Gamma scan analysis using resin sample, conversion by weight based on radionuclide distribution and scaling factors TOTAL SHIPPED WASTE VOLUME: 601.5 ft3 TOTAL BURIAL WASTE VOLUME: 601.5 ft3 HOW DETERMINED: Waste volume determined by mass and assumed density of dewatered resin SOLIDIFICATION AGENT OR ABSORBENT: None TYPE WASTE: Filters 10 CFR PART 61 WASTE CLASS: C SOURCE OF WASTE: Misc. Waste Processing Systems SHIPPING CONTAINER: High Integrity L-8-120 Liner (120.3)

TOTAL CURIE QUANTITY: 3.95 Ci HOW DETERMINED: Dose to Curie, based on generic filter radionuclide distribution TOTAL SHIPPED WASTE VOLUME: 120.3 ft3 TOTAL BURIAL WASTE VOLUME: 120.3 ft3 HOW DETERMINED: Known filter volume and quantity SOLIDIFICATION AGENT OR ABSORBENT: None A-1

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