ML11195A066

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Radioactive Effluent Release Report
ML11195A066
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 07/12/2011
From: Lauver D
Calvert Cliffs, Constellation Energy Group
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML11195A066 (25)
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Text

Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, Maryland 20657 CENG a joint venture of Constellation 45:e,*-eDF O EneMg- 3 CALVERT CLIFFS NUCLEAR POWER PLANT July 12, 2011 U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant; Unit Nos. I & 2; Docket Nos. 50-317 & 50-318 Independent Spent Fuel Storage Installation, Docket No. 72-8 2010 Radioactive Effluent Release Report

REFERENCES:

(a) Calvert Cliffs Unit Nos. 1 and 2 Technical Specification 5.6.3 (b) Calvert Cliffs Independent Spent Fuel Storage Installation Technical Specification 6.3 As required by References (a) and (b), Enclosure (1) is provided. Meteorological data is kept in an onsite file and is available upon request.

Should you have questions regarding this matter, please contact Mr. Douglas E. Lauver at (410) 495-5219.

Very truly yours, Douglas E. Lauver Director - Licensing

'DEL/PSF/bjd

Enclosure:

(1) Calvert Cliffs Nuclear Power Plant and Independent Spent Fuel Storage Installation Radioactive Effluent Release Annual Report - 2010

Document Control Desk July 12, 2011 Page 2 cc: D. V. Pickett, NRC S. Gray, DNR V. Ordaz, NRC S. P. Focht, ANI (Without Enclosure)

W. M. Dean, NRC Resident Inspector, NRC

ENCLOSURE (1 CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT -

2010 Calvert Cliffs Nuclear Power Plant, LLC July 12, 2011

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2010 Facility - Calvert Cliffs Nuclear Power Plant and Independent Spent Fuel Storage Installation Licensee - Calvert Cliffs Nuclear Power Plant, LLC 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) Rev. 0800, 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. lodines 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.

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ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2010 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. 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 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 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2010 III. TECHNICAL SPECIFICATION REPORTING REQUIREMENTS A. Calvert Cliffs Nuclear Power Plant (CCNPP), Technical Specification 5.6.3

1. 2010 Offsite Dose Due to Carbon-14 Carbon-14 releases from Calvert Cliffs were estimated using the EPRI Carbon-14 Source Term Calculator using specific reactor core data and reactor coolant chemistry to estimate the products of the activation reactions. The resulting estimate of Carbon-14 released from the Calvert Cliffs Site is 14.18 Curies.

Dose due to Carbon-14 in gaseous effluents was calculated using the following conditions:

a. C-14 released to the atmosphere, 6.79 Curies of C-14 from Unit I and 7.39 curies from Unit 2.
b. Release was consistent throughout the year.
c. 10% of the C-14 was in the chemical form of C02, which is the only dose contributor. The bulk of C-14 was in the chemical form of methane (CH4) which would exhibit high upward velocity due to its low density relative to air.

In addition CH4 does not have an uptake pathway for humans.

d. Meteorological dispersion factor, (X/Q), at the site boundary to the hypothetical maximally exposed member of the public is 2.08E-07 sec/m 3.
e. Dose calculations and dose factors are from Regulatory Guide 1.109 methodology.
f. Pathways considered were inhalation and vegetation ingestion.
g. Critical receptor is child at the site boundary in the SE direction.

Maximum dose values due to C-14 in gaseous effluents in 2010 Organ Age mRem/yr RG- 1.109 Bone Child 8.57E-02 RG-1.109 T.Body/Other Child 2.36E-02 3

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2010

2. 2010 Dose Assessment Summary Actual Percent of ODCM Value ODCM limit Limit Liquid Waste:

Maximum Annual Organ Dose (mRem) 1 0.0137 0.07% 20 Maximum Annual Whole Body Dose (mRem) 0.0029 0.05% 6 Gaseous Waste:

Noble Gases:

Maximum Quarterly Gamma Air Dose (mRad) 0.002 0.02% 10 Maximum Quarterly Beta Air Dose (mRad) 0.0272 0.14% 20 lodines and Particulates:

Maximum Annual Organ Dose (mRem) 2 0.130 0.43% 30 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 2010.

2 The controlling pathway was the child-thyroid pathway representing the organ with the highest calculated dose during the calendar year of 2010. There is currently no milk pathway.

3. 40 CFR 190 Total Dose Compliance Based upon the calendar year 2010 and the ODCM calculations, the maximum exposed individual would receive 0.02% of the allowable dose. During the calendar year 2010, 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.
4. Solid Waste Report Requirements During 2010, the types of radioactive solid waste shipped from Calvert Cliffs were dry compressible waste, spent resins, 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 2010 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.

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ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2010

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

Changes The ODCM was not revised during calendar year 2010. The PCP was not revised in 2010.

B. Radioactive Effluent Monitoring Instrumentation

1. The Unit 1 and Unit 2 Steam Generator Blowdown Radiation Monitors 1/2-RE-4014 were inoperable during the calendar year 2010 due to unavailability of spare parts.

Replacement projects for these monitors are completed and the monitors are expected to be operable in 2011. In addition to the above radiation monitors there are two redundant radiation monitors on the Unit-i and Unit 2 steam generator blowdown lines: 1-RE-4095 and 2-RE-4095 were declared inoperable for greater than 30 days as the criteria and methodology for testing the monitors did not meet the ODCM requirements. The testing procedures were revised, approved and the required testing was performed to meet ODCM requirements.

During the period the Radiation Monitors were inoperable, compensatory actions were performed in accordance with the ODCM requirements.

2. The Liquid Radwaste Monitor 0-RE-2201 was declared inoperable for greater than 30 days as the criteria and methodology for testing the monitor did not meet the ODCM requirements. The testing procedure was revised, approved and the required testing was performed to meet ODCM requirements.

During the period the Radiation Monitor was inoperable, compensatory actions were performed in accordance with the ODCM requirements.

C. Independent Spent Fuel Storage Installation (ISFSI), ISFSI Technical Specification 6.3 Three (3) casks of spent fuel were transferred to the ISFSI during 2010. No quantity of radionuclides was released to the environment during the ISFSI operation in 2010.

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 values from the radiation monitor may be used to assist in the calculation of activity 5

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2010 discharged from containment during venting. Carbon-14 is estimated per section III.A. 1.

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.

During 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. 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.

Carbon-14 is estimated per section III.A. 1.

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 release methodology discussed in section V.B.2.

2. Continuous Releases Durinig 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, Iron-55 is analyzed twice per year.

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ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2010 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 (excluding tritium).

There were no major changes to the liquid radwaste system in calendar year 2010.

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 once per week.

These results are multiplied by the actual quantity of blowdown to determine the total activity released. The weekly sample is also used to prepare monthly composites for tritium analysis.

During the monitoring for primary-to-secondary leakage low levels of tritium have been detected in the Turbine Building sumps. This water is sampled and analyzed for principal gamma emitting radionuclides weekly and composited. The composite sample is analyzed at least monthly for tritium. 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:

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ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2010

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.

During the reporting period liquid was spilled on the ground from the 15B Feedwater Heater (also see Section VII A). Tritium was the only radionuclide released (1.92E-08 curies). The soil at the spill location was remediated, and the release data was recorded in accordance with 10 CFR 50.75.g.

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 (see Tables below).

Sample size and/or count times are adjusted to achieve analytical sensitivities better than the environmental LLDs for gamma emitters (listed in ODCM Table 4.12-1). Established LLD limits for tritium are approximately 350 pCi/I for tritium.

Groundwater samples were collected from six on-site piezometer tubes in 2010. A piezometer tube is a shallow monitoring well which allows access to groundwater at a depth of approximately 40 feet beneath the site. Number 19 Piezometer Tube was added to the program in 2010, 3 additional wells were installed in December of 2010 and will be included in 2011 monitoring. Of the piezometer tubes sampled, only #I1 Piezometer Tube showed any plant related activity. This activity was previously identified and evaluated in December of 2005. The activity consists of tritium originating from normal radwaste discharges and was previously reported in the Annual Radioactive Effluent Release Reports. The tritium contamination is contained on site. No drinking water has been affected; the groundwater at 8

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2010 this location does not impact any drinking water pathway. The 2010 analysis result for tritium is shown in the following table.

Concentration of Tritium in Groundwater (Results in units of pCi/L +/- 2a)

Sample Date Piezometer Tube #s 11 12 13 15 18 19 03/06/2010 <202 <203 <203 <203 <202 --

04/09/2010 <203 <220 <220 <220 <220 --

07/30/2010 412+/-67.9 <178 <176 <179 <181 --

10/25/2010 739 +/- 180 <295 <289 <289 <293 <293 Gross Concentration of Gamma Emitters (Results in units of pCi/L +/- 2a)

Sample Date Piezometer Tube #s 11 12 13 15 18 19 03/06/2010 * * * *

  • 04/09/2010 * * * *
  • 07/30/2010 * * * *
  • 10/25/2010 * * * * * *
  • All Non-Natural Gamma Emitters < MDA 9

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2010 VI. BATCH RELEASES 2010 1ST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER A. Liquid

1. Number of batch releases 20 14 15 15
2. Total time period for batch 1.37E+05 1.36E+05 1.37E+05 1.37E+05 releases (min)
3. Maximum time period for a 4.46E+04 4.46E+04 4.46E+04 4.46E+04 batch release (min)
4. Average time period for 6.85E+03 9.68E+03 9.17E+03 9.14E+03 batch releases (min)
5. Minimum time period for a 2.93E+01 2.53E+01 2.13E+01 2.33E+01 batch release (min)
6. Average stream flow during 4.04E+06 4.58E+06 4.59E+06 4.48E+06 periods of effluent into a flowing stream (liters/min of dilution water)

B. Gaseous

1. Number of batch releases 20 20 17 17
2. Total time period for batch 1.57E+04 1.07E+04 6.24E+03 5.OOE+03 releases (min)
3. Maximum time period for a 5.50E+03 1.85E+03 5.40E+02 4.45E+02 batch release (min)
4. Average time period for 7.84E+02 5.37E+02 3.67E+02 2.94E+02 batch release (min)
5. Minimum time period for a 1.38E+02 1.60E+01 1.88E+02 1.38E+02 batch release (min) 10

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2010 VII. ABNORMAL RELEASES 2010 1ST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER A. Liquid

1. Number of releases 1* 2. Total activity released (Curies) 1.92E-8 B. Gaseous
1. Number of releases 2. Total activity releases (Curies) *A permit was generated to account for the liquid spilled on the ground from the 15B Feedwater Heater.

The tritium was the only radionuclide released.

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ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2010 VIII. CORRECTIONS TO THE 2009 RADIOACTIVE EFFLUENT RELEASE REPORT TABLE 1A - REG GUIDE 1.21 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES 1ST 2ND 3RD 4TH EST. TOTAL FISSION AND ACTIVATION GASES UNITS QUARTER QUARTER QUARTER QUARTER ERROR, %

1. Total Release Ci 2.17E+02 6.63E+00 3.54E+01 9.84E+00 +/-1.20E+01
2. Average release rate for period [tCi/sec 2.80E+O1 8.43E-01 4.46E+00 1.24E+00
3. Percent of Tech. Spec. limit (1)  % 8.64E-04 8.64E-04 8.64E-04 2.64E-04
4. Percent of Tech. Spec. limit (2)  % 5.10E-04 5.10E-04 5.1OE-04 5.1OE-04
5. Percent of Tech. Spec. limit (3)  % 4.40E-02 8.75E-04 3.60E-03 3.13E-03
6. Percent of Tech. Spec. limit (4)  % 2.58E-02 2.58E-02 2.58E-02 2.58E-02
7. Percent of Tech. Spec. limit (5)  % 9.45E-02 3.46E-03 9.15E-03 3.95E-03
8. Percent of Tech. Spec. limit (6)  % 5.55E-02 5.55E-02 5.55E-02 5.55E-02 IODINES
1. Total Iodine - 131
2. Average release rate for period
4. Percent of Tech. Spec. limit (7)

ItCi/sec Ci 2.13E-03 2.74E-04 4.13E-01 6.25E-05 7.95E-06 5.77E-04 2.21E-03 2.77E-04 4.25E-01 7.88E-06 9.92E-07 5.76E-04

+/-6.50E+00

5. Percent of Tech. Spec. limit (8)  % 4.27E-02 2.63E-03 4.27E-01 4.27E-01 PARTICULATES
1. Particulates with half lives greater than 8 days Ci 9.75E-09 (9) (9) (9) +/-1.20E+01
2. Average release rate for period ýtCi/sec 1.25E-09 (9) (9) (9)
3. Percent of Tech. Spec. limit (7)  % 4.13E-01 (9) (9) (9)
4. Percent of Tech. Spec. limit (8)  % 4.27E-02 (9) (9) (9)
5. Gross alpha radioactivity Ci (9) (9) (9) (9) +/-2.50E+01 TRITIUM
1. Total Release Ci 5.19E-0 I 1.15E+00 1.99E+00 1.O0E+00 -1+/-32E+°1
2. Average release rate for period I jiCi/sec I6.67E-02 I 1.46E-01 I 2.51E-01 I 1.26E-01 NOTES TO TABLE 1A (1) Percent of I.A.1 whole body dose rate limit (500 mRem/year)

(2) Percent of I.A. I skin dose rate limit (3000 mRem/year)

(3) Percent of I.A.3 quarterly gamma-air dose limit (10 mRad) 12

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2010 (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.3 quarterly organ dose limit (15 mRem)

(8) Percent of I.B.3 yearly organ dose limit (30 mRem)

(9) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of ODCM Surveillance Requirement 4.11.2.1.2.

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APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2010 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 1.50E+02 3.41E+01 9.42E+00 9.92E+00 +/-1.20E+01
2. Average release rate for period ýiCi/sec 1.90E+01 4.33E+00 1.20E+00 1.26E+00
3. Percent of Tech. Spec. limit (1)  % 8.07E-04 8.07E-04 8.07E-04 8.07E-04
4. Percent of Tech. Spec. limit (2)  % 2.01E-02 7.52E-04 1.13E-03 3.88E-03
5. Percent of Tech. Spec. limit (3)  % 1.29E-02 1.29E-02 1.29E-02 1.29E-02
6. Percent of Tech. Spec. limit (4)  % 1.36E-01 2.30E-02 6.25E-03 6.05E-03
7. Percent of Tech. Spec. limit (5)  % 8.55E-02 8.55E-02 8.55E-02 8.55E-02
8. Percent of Tech. Spec. limit (6)  % 4.44E-04 4.44E-04 4.44E-04 4.44E-04 B. IODINES
1. Total Iodine - 131 Ci 4.38E-03 6.14E-05 4.67E-05 4.07E-06 +/-6.50E+00
2. Average release rate for period ýtCi!sec 5.55E-04 7.78E-06 5.93E-06 5.16E-07
3. Percent of Tech. Spec. limit (7)  % 8.40E-01 1.55E-02 1.12E-02 2.33E-03
4. Percent of Tech. Spec. limit (8)  % 4.33E-01 4.33E-01 4.33E-01 4.33E-01 C. PARTICULATES
1. Particulates with half lives greater than 8 days Ci 6.64E-06 4.98E-06 (9) (9) +/-1.20E+01
2. Average release rate for period ýtCi/sec 8.42E-07 6.32E-07 (9) (9)
3. Percent of Tech. Spec. limit (7)  % 8.40E-01 1.55E-02 0.OOE+00 0.OOE+00
4. Percent of Tech. Spec. limit (8)  % 4.33E-01 4.33E-01 0.OOE+00 0.OOE+00
5. Gross alpha radioactivity Ci (9) (9) 1.30E-06 3.18E-07 +/-2.50E+01 D. TRITIUM
1. TotalRelease Ci 1.62E+00 2.11E+00 2.11E+00 9.41E-01 +/-1.32E+01
2. Average release rate for period I P~Ci/sec I 2.05E-01 I 2.67E-01 I 2.67E-01 1 1.19E-01I A-1

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2010 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.3 quarterly organ dose limit (15 mRem)

(8) Percent of I.B.3 yearly organ dose limit (30 mRem)

(9) Less than minimum detectable activity which meets the lower limit of detection (LLD) requirements of ODCM Surveillance Requirement 4.11.2.1.2.

A-2

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2010 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

1. FISSION AND ACTIVATION GASESUNITS QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER Argon -41 Ci (2) (2) (2) (2) 2.73E-02 2.69E-02 2.57E-02 1.91E-02 Krypton -85 Ci 1.58E-01 (2) (2) (2) 7.91E+01 3.34E+01 8.08E+00 7.19E+00 Krypton -85m Ci (2) (2) (2) (2) (2) (2) (2) (2)

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

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

Xenon -131m Ci (2) (2) (2) (2) 2.36E-01 (2) 9.OOE-04 (2)

Xenon -133 Ci 6.19E+01 5.76E-01 7.57E-01 1.07E+00 8.41E+00 7.29E-02 5.59E-02 5.95E-02 Xenon -133m Ci (2) (2) (2) (2) 7.97E-02 1.45E-04 4.50E-04 2.1OE-04 Xenon -135 Ci 1.65E-01 1.35E-02 4.99E-01 4.16E-01 5.62E-02 2.97E-04 3.47E-04 1.78E-04 Xenon -135m Ci (2) (2) (2) 1.16E+00 (2) (2) (2) (2)

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

Total for Period Ci 6.22e+01 5.89e-01 1.26e+00 2.65e+00 8.79e+O1 3.35e+01 8.17e+00 7.27e+00

2. IODINES Iodine -131 Ci 4.38E-03 6.14E-05 4.67E-05 4.07E-06 (1) (2) (2) (2)

Iodine -132 c3 4.67E-05 3.29E-04 4.36E-04 2.11E-04 (1) (1) (1) (1)

Iodine -133 Ci (2) (2) (2) (2) (1) (1) (1) (1)

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

Total for Period Ci 4.42e-03 3.90e-04 4.83e-04 2.15e-04 (1) (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 6.64E-06 4.98E-06 (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 (2) (2) (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)

A-3

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2010 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 -141 Ci (2) (2) (2) (2) (1) (1) (1) (1)

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

Gross Alpha Ci (2) (2) 1.30E-06 3.18E-07 (1) (1) (1) (1)

Total For Period Ci 6.64e-06 4.98e-06 1.30e-06 3.18e-07 (1) (1) (1) (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 ODCM Surveillance Requirement 4.11.2.1.2.

A-4

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2010 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 1.05E-01 2.60E-02 6.87E-03 5.41E-03 +/-l.03E+01
2. Average diluted concentration during period ýtCi/ml 5.24E-11 1.07E-1 1 3.58E-12 2.52E-12
3. Percent of Tech. Spec. limit (1)  % 1.10E-01 2.12E-02 6.16E-03 7.82E-03
4. Percent of Tech. Spec. limit (2)  % 6.85E-02 6.85E-02 6.85E-02 6.85E-02
5. Percent of Tech. Spec. limit (3)  % 5.17E-02 2.OOE-02 1.36E-02 1.1OE-02
6. Percent of Tech. Spec. limit (4)  % 4.80E-02 4.80E-02 4.80E-02 4.80E-02 B. TRITIUM
1. Total Release Ci 3.72E+02 2.65E+02 3.28E+02 2.05E+02 +/-1.03E+01
2. Average diluted concentration during period gCi/ml 1.85E-07 1.09E-07 1.71E-07 9.57E-08
3. Percent of applicable limit (5)  % 6.17E-03 3.63E-03 5.70E-03 3.19E-03 C. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci 1.30E-01 1.26E-04 6.14E-04 1.84E-03 +/-1.03E+01
2. Average diluted concentration during period itCi/ml 6.49E-1 1 5.20E-14 3.20E-13 8.59E-13 D. GROSS ALPHA RADIOACTIVITY
1. Total Release Ci (6) (6) (6) 2.89E-05 N/A E. VOLUME OF WASTE RELEASED (prior to dilution)
1. Volume processed through radwaste system liters 9.40E+07 1.05E+08 1.01E+08 8.37E+07 +/-l.30E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD (7) liters 2.01E+12 2.42E+12 1.92E+12 2.14E+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 ýCi/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 CAL VERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2010 ANNUAL REPORT TABLE 2B - REG GUIDE 1.21 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE IST 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) 1.62E-03 (1) (1) (1)

Manganese - 54 Ci (1) (1) (1) (1) 1.82E-04 8.99E-06 3.58E-06 2.54E-06 Iron - 55 Ci (2) (2) (2) (2) 1.58E-02 5.69E-03 1.47E-03 3.26E-03 Cobalt - 57 Ci (1) (1) (1) (1) 4.23E-04 1.45E-04 (1) (1)

Cobalt - 58 Ci (1) (1) (1) (1) 6.03E-02 1.24E-02 2.16E-03 5.30E-04 Iron - 59 Ci (1) (1) (1) (1) 1.64E-06 (1) (1) (1)

Cobalt- 60 Ci (1) (1) (1) (1) 3.41E-03 9.84E-04 4.10E-04 1.85E-04 Nickel-63 Ci (1) (1) (1) (1) 1.1OE-02 5.57E-03 1.94E-03 9.56E-04 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 - 91 Ci (1) (1) (1) (1) 3.60E-05 (1) (1) (1)

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

Niobium- 95 Ci (1) (1) (1) (1) 6.23E-04 (1) (1) (1)

Zirconium- 95 Ci (1) (1) (1) (1) 2.19E-04 (1) (1) (1)

Niobium- 97 Ci (1) (1) (1) (1) 7.92e-06 (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) 2.84E-05 (1) 9.68E-05 Tin- 113 Ci (1) (1) (1) (1) (1) (1) (1) (1)

Tin- 117m Ci (1) (1) (1) (1) (1) (1) (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) 5.91E-03 7.26E-05 8.03E-06 2.36E-05 Tellurium- 125m Ci (1) (1) (1) (1) (1) (1) (1) (1)

A-6

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2010 ANNUAL REPORT TABLE 2B - REG GUIDE 1.21 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE 1ST 2ND 3RD 4TH IST 2ND 3RD 4TH NUCLIDES RELEASED Units QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER Tellurium- 132 Ci (1) (1) (1) (1) (1) (1) (1) (1)

Iodine- 131 Ci (1) (1) (1) (1) 2.59E-04 (1) (1) (1)

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

Iodine- 133 Ci (1) (1) (1) (1) (1) (1) (1) (1)

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

Cesium- 134 Ci (1) (1) (1) (1) 2.04E-03 3.78E-04 3.75E-04 1.51E-04 Cesium- 136 Ci (1) (1) (1) (1) (1) (1) (1) (1)

Cesium - 137 Ci (1) (1) (1) (1) 3.43E-03 6.48E-04 4.98E-04 2.11E-04 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) 1.05E-01 2.60e-02 6.87e-03 5.41E-03 Krypton - 85 Ci (1) (1) (1) (1) 5.11E-03 (1) (1) (1)

Xenon- 131m Ci (1) (1) (1) (1) (1) (1) (1) (1)

Xenon- 133 Ci (1) (1) (1) (1) 1.25E-01 1.26E-04 6.14E-04 1.84E-03 Xenon- 133m Ci (1) (1) (1) (1) (1) (1) (1) (1)

Xenon- 135 Ci (1) (1) (1) (1) (1) (1) (1) (1)

Total For Period Ci (1) (1) (1) (1) 1.30E-01 1.26E-04 6.14E-04 1.84E-03 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 AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2010 ANNUAL REPORT TABLE 3A 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 1.22e+01 25%

Ci 5.18e+02 b) Dry compressible m3 7.43E+01 25%

waste, contaminated Ci 8.16E-02 equipment, etc.

c) Irradiated components, m3 0.OOE-00 N/A control rods, etc. Ci 0.OOE+00 d) Other (cartridge filters, m3 5.79E+00 25%

misc. dry Ci 1.25E-01 compressible, Oil)

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) Mn-54 1.10 Fe-55 9.96%

Co-58 2.71%

Co-60 3.40%

Ni-63 25.08%

Cs-134 23.42%

Cs-137 33.55%

b) Fe-55 34.61%

Co-58 32.31%

Co-60 6.64%

Ni-63 20.07%

Cs-137 1.01%

c) N/A d) Fe-55 35.50%

Co-58 29.23%

Co-60 6.85%

Ni-63 21.29%

Cs-137 1.29%

A-8

I.

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2010 ANNUAL REPORT

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 4 Motor Surface Transit Studsvik Processing Facility Memphis, TN 5 Motor Surface Transit Studsvik Processing Facility Erwin, TN B. IRRADIATED FUEL SHIPMENTS (DISPOSITION) N/A A-9
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