ML081920283

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Independent Spent Fuel Storage Installation - 2007 Radioactive Effluent Release Report
ML081920283
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 07/10/2008
From:
Calvert Cliffs, Constellation Energy Group, Constellation Generation Group
To:
Office of Nuclear Reactor Regulation
Shared Package
ML081920376 List:
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Download: ML081920283 (20)
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Text

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT Calvert Cliffs Nuclear Power Plant, Inc.

July 10, 2008

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT Facility - Calvert Cliffs Nuclear Power Plant Licensee - Calvert Cliffs Nuclear Power Plant, Inc.

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 [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 2.4 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-rate 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

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT 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, Table II, Column 2 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. 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 radioiodine. 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, Column 2 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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ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT III. TECHNICAL SPECIFICATION REPORTING REQUIREMENTS A. Calvert Cliffs Nuclear Power Plant (CCNPP), Technical Specification 5.6.3

1. 2007 Dose Assessment Summary Actual Percent of ODCM Value ODCM limit Limit Liquid Waste:

Maximum Annual Organ Dose (mRem) 1 0.0031 0.02% 20 Maximum Whole Body Dose (mRem) 0.0012 0.02% 6 Gaseous Waste:

Noble Gases:

Maximum Quarterly Gamma Air Dose (mRad) 0.007 0.07% 10 Maximum Quarterly Beta Air Dose (mRad) 0.004 0.18% 20 Iodines and Particulates:

Maximum Annual Organ Dose (mRem) 2 0.13 0.45% 30 1

The controlling pathway was the fish and shellfish pathway with adult as the controlling age group and the GI-LLI representing the organ with the highest calculated dose during the calendar year of 2007.

2 The controlling pathway was the child-thyroid pathway representing the organ with the highest calculated dose during the calendar year of 2007. There is currently no milk pathway.

2. 40 CFR 190 Total Dose Compliance Based upon the calendar year 2007 and the ODCM calculations, the maximum exposed individual would receive 0.5% of the allowable dose. During the calendar year 2007, 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 may be found in the Annual Radiological Environmental Operating Report.
3. Solid Waste Report Requirements During 2007, the types of radioactive solid waste shipped from Calvert Cliffs were dry compressible waste, spent resins, irradiated components, and cartridge filters which were shipped in either High Integrity Containers (HICs) within NRC approved casks, Sea/Land containers, or steel boxes. Appendix A provides a detailed breakdown of the waste shipments for 2007 per 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 The ODCM was not revised during calendar year 2007. The PCP was not revised in 2007.

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ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT B. Radioactive Effluent Monitoring Instrumentation In 2007, the minimum channels operable requirement for the Unit-1 steam generator blowdown radiation monitor was not satisfied for greater than 30 days. Per ODCM 3.3.3.10, Radioactive Liquid Effluents, Action b:

with less than the minimum number of radioactive liquid effluent monitoring instrumentation channels operable, take the action shown in Table 3.3-13.

Exert best efforts to return the instruments to operable status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the inoperability was not corrected in a timely manner.

There are two radiation monitors on the Unit-1 steam generator blowdown line: 1-RE-4014 and 1-RE-4095. The ODCM requires that one channel remain operable. Contrary to the ODCM requirements, both 1-RE-4014 and 1-RE-4095 were inoperable from 1-Jan-2007 through 10-Aug-2007 at 16:45. The provisions of Action 29 (ODCM Table 3.3-13) were implemented. Those actions required:

with the number of channels operable less than required by the minimum channels operable requirement, effluent releases via this pathway may continue provided grab samples are analyzed for gross radioactivity (beta or gamma) at the lower limit of detection defined in Table 4.11-1 at least every 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> when the specific activity of the secondary coolant is less than or equal to 0.01 microcuries/gram dose equivalent I-131.

Chemistry sampling was discontinued when one steam generator blowdown radiation monitor (1-RI-4095) was returned to service on 10-Aug-2007. 1-RE-4014 remained out of service for all calendar year 2007. The Unit-1 radiation monitors were out of service due to an unavailability of spare parts.

C. Independent Spent Fuel Storage Installation (ISFSI), ISFSI Technical Specification 6.1 Four (4) casks of spent fuel were transferred to the ISFSI during 2007. No quantity of radionuclides was released to the environment during the ISFSI operation in 2007.

Additional information regarding the ISFSI radiological environmental 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 detector for the principal gamma emitting noble gas radionuclides. The total activity released is based on the pressure/volume relationship (gas laws). The Plant Vent Stack Radiation Monitor typically monitors containment releases, and the 4

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT values from the radiation monitor may be used to assist in the calculation of activity discharged from containment during venting.

2. Continuous Releases A gas sample is collected at least weekly from the main vents and analyzed by gamma spectroscopy using a germanium 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. The Plant Vent Stack Radiation Monitor continuously measures routine plant vent stack releases, per design, and the values from the radiation monitor may be used to assist in the calculation of activity discharged in routine plant vent stack discharges.

Prior to and after each containment purge, a gas sample is collected and analyzed by gamma spectroscopy using a germanium detector to determine the concentration of principal gamma emitting noble gas radionuclides inside containment. The total activity released is based on containment volume and purge rate. Alternatively, total activity released during a containment purge is based on continuous radiation monitor responses, grab samples, and purge fan flow 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 weekly (or more often) and are analyzed by gamma spectroscopy using a germanium 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. A plate-out correction factor is applied to the results to account for the amount of iodine lost in the sample lines prior to sample collection. The weekly particulate filters are then combined to form monthly and quarterly composites for the gross alpha and strontium-89 and strontium-90 analyses.

Fuel failures in 2007 continued to cause iodine releases to be elevated relative to historical average values. Analyses on main vent filters indicated the presence of gross alpha activity in 2007. Alpha activity was detected in June and July on Unit 1, and was also detected in March and April on Unit 2. Although these values were reported, it is strongly suspected these results are related to naturally occurring radon, thoron, and their progeny. In future years, alpha spectroscopy may be used on 5

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT samples indicating positive gross alpha activity to distinguish naturally occurring radioactive material from plant related radioactive material.

C. Liquid 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 concentration 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, and this is used to prepare monthly tritium and gross alpha, iron-55, nickel-63, strontium-89, and strontium-90 samples for analysis are prepared quarterly for offsite analysis.

Batch discharges of secondary (normally uncontaminated) waste streams are also monitored for radioactivity. No activity is normally detected in these secondary waste streams. In the fourth quarter of 2007, the composite sample indicated the presence of Fe-55 activity at 8.1E-7 uCi/ml. No other activity (tritium, gamma, Ni-63, Sr-89, or Sr-90) was detected in this composite sample. A re-sample of the fourth quarters composite was sent for re-analysis in the first quarter of 2008 and results for Fe-55 were less than detectable activity < 3.1E-7 uCi/ml.

There were no major changes to the liquid radwaste system in calendar year 2007.

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 and gamma isotopic analysis is performed 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. 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 discharged to the circulating water conduits. This water is sampled weekly and composited. The composite sample is analyzed at least monthly for tritium and 6

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT 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:

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.

E. Reporting and Recordkeeping for Decommissioning In accordance with 10 CFR 50.75.g, each licensee shall keep records of information important to the safe and effective decommissioning of the facility in an identified location until the license is terminated by the Commission. If records of relevant information are kept for other purposes, reference to these records and their locations may be used.

Information the Commission considers important to decommissioning consists of records of spills or other unusual occurrences involving the spread of contamination in and around the facility, equipment, or site. These records may be limited to instances when significant contamination remains after any cleanup procedures or when there is reasonable likelihood that contaminants may have spread to inaccessible areas as in the case of possible seepage into porous materials such as concrete. These records must include any known information on identification of involved nuclides, quantities, forms, and concentrations.

To assist in the decommissioning, and to provide early and advance detection of any unmonitored releases of radioactive material from the site, groundwater is routinely sampled.

These groundwater samples are analyzed for gamma and tritium activity. Sample size and/or count times are adjusted to achieve analytical sensitivities better than the environmental lower limit of detections (LLDs) for gamma emitters (listed in ODCM Table 4.12-1), and approximately 350 pCi/l for tritium.

Groundwater samples were collected from five piezometer tubes in 2007. A piezometer tube is a shallow monitoring well which allows access to groundwater at a depth of approximately 40 feet beneath the site. Of the five piezometer tubes sampled in 2007 none showed any plant-related activity. The 2007 tritium analysis results are reproduced on the following table.

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ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT Groundwater Monitoring Sample Results Sample location Date Tritium Concentration microcuries/milliliter picocuries/liter 11 Piezometer 2/9/2007 Not Detected, < 3.32E-7 Not Detected,< 332 12 Piezometer 2/9/2007 Not Detected,< 3.32E-7 Not Detected,< 332 13 Piezometer 2/9/2007 Not Detected,< 3.32E-7 Not Detected,< 332 15 Piezometer 2/9/2007 Not Detected,< 3.32E-7 Not Detected,< 332 18 Piezometer 2/9/2007 Not Detected,< 3.32E-7 Not Detected,< 332 11 Piezometer 5/16/2007 Not Detected,< 3.39E-7 Not Detected,< 339 12 Piezometer 5/16/2007 Not Detected,< 3.39E-7 Not Detected,< 339 13 Piezometer 5/16/2007 Not Detected,< 3.39E-7 Not Detected,< 339 15 Piezometer 5/16/2007 Not Detected,< 3.39E-7 Not Detected,< 339 18 Piezometer 5/16/2007 Not Detected,< 3.39E-7 Not Detected,< 339 11 Piezometer 9/13/2007 Not Detected,< 3.58E-7 Not Detected,< 358 12 Piezometer 9/13/2007 Not Detected,< 3.58E-7 Not Detected,< 358 13 Piezometer 9/13/2007 Not Detected,< 3.58E-7 Not Detected,< 358 15 Piezometer 9/13/2007 Not Detected,< 3.58E-7 Not Detected,< 358 18 Piezometer 9/13/2007 Not Detected,< 3.58E-7 Not Detected,< 358 11 Piezometer 12/9/2007 Not Detected,< 3.62E-7 Not Detected,< 362 12 Piezometer 12/9/2007 Not Detected,< 3.62E-7 Not Detected,< 362 13 Piezometer 12/9/2007 Not Detected,< 3.62E-7 Not Detected,< 362 15 Piezometer 12/9/2007 Not Detected,< 3.62E-7 Not Detected,< 362 18 Piezometer 12/9/2007 Not Detected,< 3.62E-7 Not Detected,< 362 8

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT VI. BATCH RELEASES 2007 1ST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER A. Liquid

1. Number of batch releases 1.40E+01 1.20E+01 1.10E+01 7.00E+00
2. Total time period for batch 6.02E+03 5.10E+03 3.61E+03 4.29E+03 releases (min)
3. Maximum time period for a 6.42E+02 6.07E+02 6.00E+02 6.75E+02 batch release (min)
4. Average time period for 4.30E+02 4.25E+02 3.28E+02 6.12E+02 batch releases (min)
5. Minimum time period for a 2.70E+01 2.90E+01 5.00E+00 5.65E+02 batch release (min)
6. Average stream flow during 4.51E+06 4.23E+06 4.20E+06 4.62E+06 periods of effluent into a flowing stream (liters/min of dilution water)

B. Gaseous

1. Number of batch releases 7.00E+00 1.00E+00 1.00E+00 2.00E+00
2. Total time period for batch 4.32E+03 1.59E+03 1.82E+02 2.83E+02 releases (min)
3. Maximum time period for a 2.16E+03 1.59E+03 1.82E+02 1.51E+02 batch release (min)
4. Average time period for 6.18E+02 1.59E+03 1.82E+02 1.42E+02 batch release (min)
5. Minimum time period for a 1.10E+02 1.59E+03 1.82E+02 1.32E+02 batch release (min) 9

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT VII. ABNORMAL RELEASES 2007 1ST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER A. Liquid

1. Number of releases 2. Total activity released (Curies) - 6.63E - 1.68E B. Gaseous
1. Number of releases 2. Total activity releases (Curies) On 1-May-2007 at 14:00, a leak was discovered on a waste neutralizing tank (WNT). The leak rate was estimated to be 2.3 gallons per minute and it continued for approximately 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> until the leak was contained. The liquid spilled to a gravel area where it contacted the soil. The liquid flowed across the surface of the ground and entered a concrete culvert which emptied to the Chesapeake Bay. At the time of the leak, the WNT contained tritium at a concentration of 2.50E-6 uCi/ml (2,500 pCi/l). After the event, a liquid radioactive waste release permit (Permit #70050) was prepared. The total activity discharged from the WNT was estimated to be 0.00000663 Ci. A majority of this material drained into the concrete culvert and was discharged to the Chesapeake Bay. The soil and gravel that was wetted was remediated by excavating soil and gravel from the area. After remediation, a soil sample was collected from the hole (i.e., the excavated area). A tritium analysis was conducted on this soil sample. No tritium was detected in the soil sample. The Chesapeake Bay is not a drinking water pathway. This spill totaled 0.00000663 Ci of tritium. By comparison, 827 curies of tritium were discharged in liquid radwaste to the Chesapeake Bay in 2007. The dose resulting from the WNT leak was less than 0.1 mR.

On 1-Aug-2007 at 06:05, water was discovered dripping from the corner of a Sea Land Container. Total leakage was estimated to be 50 gallons. The liquid spilled to the soil. Water from the Sea Land Container was sampled and analyzed for tritium and gamma activity. At the time of the leak, the Sea Land Container contained tritium at a concentration of 8.84E-6 uCi/ml (8,840 pCi/l), Cs-137 at a concentration of 1.42E-8 uCi/ml (14.2 pCi/l), and Co-60 at 3.04E-8 uCi/ml (30.4 pCi/l). After the fact, a liquid radioactive waste release permit (Permit #70049) was prepared. The total activity discharged from the Sea Land Container was estimated to be 5.75 E-6 Ci Co-60, 2.69E-2.69E-8 Ci Cs-137, and 1.67E-6 Ci of H-3. The soil was remediated by excavating soil from the area. After remediation, a soil sample was collected from the hole (i.e., the excavated area). A tritium analysis was conducted on this soil sample.

No tritium was detected in the soil sample. None of the radioactive material left the owner controlled area. The contamination was remediated and as a result, there was no dose to the public.

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APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT TABLE 1A - REG GUIDE 1.21 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 1ST 2ND 3RD 4TH EST. TOTAL A. FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER QUARTER QUARTER ERROR, %

1. Total Release Ci 3.69E+02 5.96E+01 9.02E+01 1.11E+02 +/-1.20E+01
2. Average release rate for period Ci/sec 4.75E+01 7.58E+00 1.13E+01 1.40E+01
3. Percent of Tech. Spec. limit (1)  % 5.10E-03 1.41E-03 1.77E-03 2.08E-03
4. Percent of Tech. Spec. limit (2)  % 3.43E-03 5.50E-04 7.91E-04 1.03E-03
5. Percent of Tech. Spec. limit (3)  % 7.37E-02 2.02E-02 2.59E-02 3.03E-02
6. Percent of Tech. Spec. limit (4)  % 3.69E-02 1.01E-02 1.30E-02 1.51E-02
7. Percent of Tech. Spec. limit (5)  % 1.76E-01 2.46E-02 3.84E-02 5.00E-02
8. Percent of Tech. Spec. limit (6)  % 8.81E-02 1.23E-02 1.92E-02 2.50E-02 B. IODINES
1. Total Iodine - 131 Ci 3.67E-03 5.09E-04 3.99E-04 1.80E-04 +/-6.50E+00
2. Average release rate for period Ci/sec 4.72E-04 6.47E-05 5.02E-05 2.26E-05
3. Percent of Tech. Spec. limit (7)  % 1.12E-03 1.54E-04 1.19E-04 5.38E-05
4. Percent of Tech. Spec. limit (8)  % 2.76E-02 3.83E-03 3.00E-03 1.35E-03
5. Percent of Tech. Spec. limit (9)  % 1.38E-02 1.92E-03 1.50E-03 6.77E-04 C. PARTICULATES
1. Particulates with half lives greater than 8 days Ci 4.71E-06 4.03E-07 (10) (10) +/-1.20E+01
2. Average release rate for period Ci/sec 6.05E-07 5.12E-08 (10) (10)
3. Percent of Tech. Spec. limit (7)  % 1.03E-05 1.03E-05 (10) (10)
4. Percent of Tech. Spec. limit (8)  % 2.36E-04 2.02E-05 (10) (10)
5. Percent of Tech. Spec. limit (9)  % 1.18E-04 1.01E-05 (10) (10)
6. Gross alpha radioactivity Ci 1.55E-07 1.28E-06 7.67E-07 (10) +/-2.50E+01 D. TRITIUM
1. Total Release Ci 3.12E-01 5.74E-01 4.47E+00 5.98E-01 +/-1.32E+01
2. Average release rate for period Ci/sec 4.02E-02 7.30E-02 5.63E-01 7.52E-02 A-1

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT TABLE 1A - REG GUIDE 1.21 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 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 quarterly gamma-air dose limit (10 mRad)

(4) Percent of I.A.3 yearly gamma-air dose limit (20 mRad)

(5) Percent of I.A.3 quarterly beta-air dose limit (20 mRad)

(6) Percent of I.A.3 yearly beta-air 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 ODCM Surveillance Requirement 4.11.2.1.2.

A-2

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT TABLE 1C - REG GUIDE 1.21 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 1ST 2ND 3RD 4TH 1ST 2ND 3RD 4TH UNITS QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER

1. FISSION AND ACTIVATION GASES Argon -41 Ci (2) (2) (2) (2) 3.85E-04 1.13E-03 (2) (2)

Krypton -85 Ci 4.94E+01 6.96E-01 (2) (2) 6.53E+01 (2) 8.77E+00 1.90E+01 Krypton -85m Ci 7.11E-03 1.80E-04 (2) (2) 6.91E-04 (2) (2) (2)

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

Krypton -88 Ci 4.85E-03 (2) (2) (2) (2) (2) (2) (2)

Xenon -131m Ci 3.84E+00 (2) (2) (2) 2.71E-01 (2) (2) (2)

Xenon -133 Ci 2.38E+02 5.37E+01 7.61E+01 8.57E+01 1.85E+00 1.50E-04 (2) 1.69E-03 Xenon -133m Ci 1.33E+00 2.34E-03 (2) (2) 1.90E-02 (2) (2) (2)

Xenon -135 Ci 9.28E+00 5.23E+00 5.27E+00 6.68E+00 3.13E-02 (2) (2) (2)

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

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

Total for Period Ci 3.02E+02 5.96E+01 8.14E+01 9.24E+01 6.75E+01 1.28E-03 8.77E+00 1.90E+01

2. HALOGENS Iodine -131 Ci 3.67E-03 5.09E-04 3.99E-04 1.80E-04 3.15E-07 (1) (1) (1)

Iodine -132 Ci (2) (2) (2) (2) (1) (1) (1) (1)

Iodine -133 Ci 1.32E-04 8.11E-05 9.65E-04 5.39E-04 (1) (1) (1) (1)

Iodine -135 Ci (2) (2) (2) (2) (1) (1) (1) (1)

Total for Period Ci 3.80E-03 5.90E-04 1.36E-03 7.19E-04 3.15E-07 (1) (1) (1)

3. PARTICULATES (half life > 8 days)

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

Iron -55 Ci (2) (2) (2) (2) (1) (1) (1) (1)

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

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

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

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

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

Strontium -90 Ci 4.71E-06 4.03E-07 (2) (2) (1) (1) (1) (1)

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

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

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

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

A-3

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT TABLE 1C - REG GUIDE 1.21 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 1ST 2ND 3RD 4TH 1ST 2ND 3RD 4TH UNITS QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER Cerium -144 Ci (2) (2) (2) (2) (1) (1) (1) (1)

Gross Alpha Ci 1.55E-07 1.28E-06 7.67E-07 (2) (1) (1) (1) (1)

Total For Period Ci 4.71E-06 4.03E-07 (2) (2) (1) (1) (1) (1)

NOTES TO TABLE 1C (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.

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

A-4

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT TABLE 2A - REG GUIDE 1.21 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES 1ST 2ND 3RD 4TH EST. TOTAL UNITS QUARTER QUARTER QUARTER QUARTER ERROR, %

A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not including tritium, gases, alpha) Ci 9.14E-03 1.68E-02 1.34E-03 2.41E-03 +/-1.03E+01
2. Average diluted concentration during period Ci/ml 3.39E-10 7.57E-10 8.34E-11 1.22E-10
3. Percent of Tech. Spec. limit (1)  % 7.41E-03 1.37E-02 5.73E-03 5.18E-03
4. Percent of Tech. Spec. limit (2)  % 3.71E-03 6.85E-03 2.87E-03 2.59E-03
5. Percent of Tech. Spec. limit (3)  % 1.43E-02 5.57E-03 7.97E-03 1.06E-02
6. Percent of Tech. Spec. limit (4)  % 7.15E-03 2.79E-03 3.99E-03 5.30E-03 B. TRITIUM
1. Total Release Ci 2.94E+02 9.31E+01 1.91E+02 2.50E+02 +/-1.03E+01
2. Average diluted concentration during period Ci/ml 1.26E-06 3.30E-07 2.32E-07 3.02E-07
3. Percent of applicable limit (5)  % 4.21E-02 1.10E-02 7.72E-03 1.01E-02 C. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci 3.60E-01 1.24E-02 4.14E-03 3.81E-02 +/-1.03E+01
2. Average diluted concentration during period Ci/ml 1.34E-08 5.62E-10 2.58E-10 1.92E-09 D. GROSS ALPHA RADIOACTIVITY
1. Total Release Ci (6) (6) (6) (6) N/A E. VOLUME OF WASTE RELEASED (prior to dilution)
1. Volume processed through radwaste system liters 2.50E+06 1.97E+06 1.58E+06 1.68E+06 +/-1.30E+00
2. Volume low activity from secondary system liters 1.58E+07 1.72E+07 5.01E+07 4.43E+07 +/-1.30E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD (7) liters 9.54E+11 1.18E+12 1.20E+12 1.20E+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 Ci/ml (6) Less than minimum detectable activity which meets the LLD requirements of ODCM Surveillance Requirement 4.11.1.1.1.

(7) Includes dilution water used during continuous discharges.

A-5

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT TABLE 2B - REG GUIDE 1.21 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 1ST 2ND 3RD 4TH 1ST 2ND 3RD 4TH NUCLIDES RELEASED Units QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER Beryllium - 7 Ci (1) (1) (1) (1) (1) (1) (1) (1)

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

Chromium - 51 Ci (1) (1) (1) (1) (1) 3.06E-04 (1) (1)

Manganese - 54 Ci (1) (1) (1) (1) 3.52E-05 2.53E-05 2.95E-05 (1)

Iron - 55 Ci (2) (2) (2) (2) 2.98E-03 1.67E-03 5.90E-04 2.06E-03 Cobalt - 57 Ci (1) (1) (1) (1) (1) 2.24E-06 (1) (1)

Cobalt - 58 Ci (1) (1) (1) (1) 5.96E-04 6.83E-04 3.27E-04 2.74E-04 Iron - 59 Ci (1) (1) (1) (1) (1) 1.54E-05 (1) (1)

Cobalt - 60 Ci (1) (1) (1) (1) 2.58E-04 1.12E-04 1.63E-04 6.96E-05 Nickel-63 Ci (1) (1) (1) (1) (1) (1) (1) (1)

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

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

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

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

Niobium - 95 Ci (1) (1) (1) (1) 1.43E-05 1.31E-04 3.99E-05 (1)

Zirconium - 95 Ci (1) (1) (1) (1) 4.61E-06 8.84E-05 1.86E-05 (1)

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

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

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

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

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

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

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

Silver - 110m Ci (1) (1) (1) (1) (1) 1.13E-04 (1) (1)

Tin - 113 Ci (1) (1) (1) (1) (1) (1) (1) (1)

Tin - 117m Ci (1) (1) (1) (1) (1) 8.09E-05 (1) (1)

Antimony - 122 Ci (1) (1) (1) (1) (1) (1) (1) (1)

Antimony - 124 Ci (1) (1) (1) (1) (1) (1) (1) (1)

Antimony - 125 Ci (1) (1) (1) (1) (1) (1) (1) (1)

Tellurium - 125m Ci (1) (1) (1) (1) 4.31E-03 1.35E-02 (1) (1)

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

Iodine - 131 Ci (1) (1) (1) (1) 4.66E-04 8.28E-06 3.20E-05 (1)

A-6

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT TABLE 2B - REG GUIDE 1.21 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 1ST 2ND 3RD 4TH 1ST 2ND 3RD 4TH NUCLIDES RELEASED Units QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER Iodine - 132 Ci (1) (1) (1) (1) 1.61E-05 (1) (1) (1)

Iodine - 133 Ci (1) (1) (1) (1) (1) (1) 3.52E-06 (1)

Iodine - 135 Ci (1) (1) (1) (1) (1) (1) (1) (1)

Cesium - 134 Ci (1) (1) (1) (1) 2.29E-04 2.35E-05 5.32E-05 (1)

Cesium - 136 Ci (1) (1) (1) (1) (1) (1) (1) (1)

Cesium - 137 Ci (1) (1) (1) (1) 2.40E-04 3.67E-05 8.06E-05 (1)

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

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

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

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

Europium - 155 Ci (1) (1) (1) (1) (1) (1) (1) (1)

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

Total For Period Ci (1) (1) (1) (1) 9.15E-03 1.68E-02 1.34E-03 2.41E-03 Krypton - 85 Ci (1) (1) (1) (1) 2.08E-02 5.13E-03 2.47E-03 Xenon - 131m Ci (1) (1) (1) (1) 7.93E-03 4.58E-04 8.69E-04 Xenon - 133 Ci (1) (1) (1) (1) 3.30E-01 6.86E-03 4.14E-03 3.47E-02 Xenon - 133m Ci (1) (1) (1) (1) 7.62E-04 Xenon - 135 Ci (1) (1) (1) (1) 2.04E-05 Total For Period Ci (1) (1) (1) (1) 3.60E-01 1.24E-02 4.14E-03 3.81E-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.

A-7

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT TABLE 3A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT 2007 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (NOT IRRADIATED FUEL)

1. Type of Waste Units 12-Month Period Est. Total Error %

a) Spent resins, Filters m3 1.87E+01 25%

Ci 7.37E+02 b) Dry compressible waste, m3 1.28E+03 25%

contaminated equipment, etc. Ci 2.43E+00 c) Irradiated components, control m3 4.54E-04 25%

rods, etc. Ci 2.46E+04 d) Other (cartridge filters, misc. m3 4.36E+01 25%

dry compressible, Oil) Ci 2.23E+01 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 8.16E+00%

Co-58 1.94E+00%

Co-60 3.36E+00%

Ni-63 3.44E+01%

Cs-134 2.06E+01%

Cs-137 2.92E+01%

b) H-3 2.70E+00%

Cr-51 7.05E+00%

Mn-54 1.68E+00%

Fe-55 2.25E+01%

Co-58 2.01E+01%

Co-60 4.87E+00%

Ni-63 1.78E+01%

Zr-95 2.65E+00%

Nb-95 4.37E+00%

I-131 6.28E+00%

Cs-134 3.08E+00%

Cs-137 3.98E+00%

c) Co-58 1.27E+00%

Co-60 3.50E+01%

Fe-55 5.14E+01%

Mn-54 4.23E+00%

Ni-63 3.64E+00%

Sn-119m 2.03E+00%

Zr-95 1.86E+00%

A-8

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT EFFLUENT AND WASTE DISPOSAL 2007 ANNUAL REPORT d) Cr-51 9.36E+00%

Mn-54 2.85E+00%

Fe-55 1.07E+01%

Co-58 3.21E+01%

Co-60 1.16E+01%

Ni-63 1.31E+01%

Zr-95 5.50E+00%

Nb-95 1.14E+01%

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 1 Water Vessel Studsvik/ RACE, Inc Memphis, TN 2 Motor Surface Transit Energy Solutions Oak Ridge, TN 2 Motor Surface Transit Energy Solutions Barnwell, SC 9 Motor Surface Transit Studsvik, Inc Erwin, TN 39 Motor Surface Transit Studsvik/ RACE, Inc Memphis, TN B. IRRADIATED FUEL SHIPMENTS (DISPOSITION) N/A A-9
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