ML15198A035

From kanterella
Jump to navigation Jump to search
ISFSI - Annual Radioactive Effluent Release Report for 2014
ML15198A035
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 07/14/2015
From: Flaherty M
Exelon Generation Co
To:
Document Control Desk, Office of Nuclear Material Safety and Safeguards, Office of Nuclear Reactor Regulation
References
Download: ML15198A035 (32)
v • d • e


Text

~Exelton Generation Mark D. Flaherty Plant Manager Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657 410 495 5205 Office 410 495 5444 Fax 443 534 5476 Mobile www.exeloncorp.com mark~fiaherty@exeloncorp.com and 72.44(d)(3)

July 14, 2015 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 Renewed Facility Operating License Nos. DPR-53 and DPR-69 NRC Docket Nos. 50-317 and 50-318 Calvert Cliffs Nuclear Power Plant Independent Spent Fuel Storage Installation, License No. SNM-2505 NRC Docket No. 72-8

Subject:

Annual Radioactive Effluent Release Report

References:

1. Calvert Cliffs Unit Nos. 1 and 2 Technical Specification 5.6.3
2. Calvert Cliffs ISFSI Technical Specification 6.3 As required by References 1 and 2, the attached Enclosure is provided. Meteorological data is kept in an onsite file and is available upon request.

There are no regulatory commitments contained in this correspondence.

Should you have questions regarding this matter, please contact Mr. Larry D. Smith at (410) 495-5219.

Respectfully, Mark D. Flaherty Plant Manager MDF/PSF/bjm S__/**

, s

Document Control Desk July 14, 2015 Page 2

Enclosure:

Annual Radioactive Effluent Release Report for Calvert Cliffs Nuclear Power Plant and Independent Spent Fuel Storage Installation-2014 cc: NRC Project Manager, Calvert Cliffs S. Gray, MD-DNR NRC Regional Administrator, Region I Director, NMSS NRC Resident Inspector, Calvert Cliffs J. Folkwein, ANI

ENCLOSURE Annual Radioactive Effluent Release Report for Calvert Cliffs Nuclear Power Plant and Independent Spent Fuel Storage Installation-2014 This report covers the period January 1, 2014 to December 31, 2014 for the Calvert Cliffs Nuclear Power Plant This report covers the period June 1, 2014 to May 31, 2015 for the Independent Spent Fuel Storage Installation Calvert Cliffs Nuclear Power Plant July 14, 2015

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2014 Facility - Calvert Cliffs Nuclear Power Plant and Independent Spent Fuel Storage Installation Licensee - Calvert Cliffs Nuclear Power Plant, LLC This report covers the period January 1, 2014 to December 31, 2014 for Calvert Cliffs Nuclear Power Plant.

This report covers the period June 1, 2014 to May 31, 2015 for the Independent Spent Fuel Storage Installation.

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 mremdyear to the whole body or greater than 3000 mrem/year to the skin (Offsite Dose Calculation Manual (ODCM) Rev. 0802, 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 torero/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).

2

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2014

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 mremlqtr, any organ 30 mrern/year, any organ less than 0.1% of the above limits as a result of burning contaminated oil.

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

C. Liquid Effluents

1. The concentrations of radionuclides in liquid effluents from the plant shall not exceed the values specified in 10 CFR Part 20, Appendix B, Table II, Colunmn 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 mrern/qtr, any organ 6 mrem/year, total body 20 mrein/year, any organ

4. All 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.

3

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2014 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.

III. TECHNICAL SPECIFICATION REPORTING REOUIREMENTS A. Calvert Cliffs Nuclear Power Plant (CCNPP), Technical Specification 5.6.3

1. 2014 Offsite Dose Due to Carbon-14 Dose due to Carbon-14 in gaseous effluents was calculated using the following conditions:
a. C-14 released to the atmosphere: 18.53 Curies of C-14 from Unit 1 and 20.44 curies from Unit 2.
b. Release was consistent throughout the year.
c. Carbon-14 release values were estimated using the methodology included in the Electric Power Research Institute (EPRI) Technical Report 1021106, using the 2014 Calvert Cliffs Nuclear Power Plant assumed parameters of normalized Carbon-14 production rate of 3.822 Ci/GWt-yr, a gaseous release fraction of 0.98, a Carbon-14 carbon dioxide fraction of 0.30, a reactor power rating of 2737 MWt for Unit 1 and 2737 MWt for Unit 2, and equivalent full power operation of 323.18 days for Unit 1 and 356.64 days for Unit 2.
d. Meteorological dispersion factor (X/Q) at the nearest residence and garden location at 1.1 miles in the southwest meteorological sector and to the hypothetical maximally exposed member of the public (child) is 3.38E-7 sec/rn 3.
e. Pathways considered were inhalation and leafy vegetation ingestion.

4

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2014

2. 2014 Dose Assessment Summary Quarter 1 Quarter 2 Quarter 3 Quarter 4 Yearly Liquid Effluent Dose LmtToaBoy3 mrem 3 mrem 3 mrem 3 mrem 6 mrem Total Body Dose 6.61E-04 2.89E-04 4.43E-04 3.74E-04 1.77E-03

% of Limit 2.20E-02 9.63E-03 1.48E-02 1.25E-02 2.94E-02 Liui ffuetDoe 10 mrem 10 mrem 10 mrem 10 mrem 20 mrem Limit, Any Organ Organ Dose 1.02E-03 6.80E-04 7.09E-04 4.18E-04 2.50E-03

% of Limit 1.02E-02 6.80E-03 7.09E-03 4.18E-03 1.25E-02 Gaseous Effluent Dose Limit, Gamma 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad Air Gamma Air Dose 3.29E-04 4.03E-05 3.66E-05 2.41E-05 4.30E-04

% of Limit 3.29E-03 4.03E-04 3.66E-04 2.41E-04 2.15E-03 Gaseous Effluent20ma 20ma 20ma 20rd 40ra Dose Limit, Beta Air 20md 20md 20md 20ra 40md Beta Air Dose 1.09E-03 2.44E-04 1.22E-03 3.99E-05 2.59E-03

% of Limit 5.44E-03 1.22E-03 6.08E-03 2.00E-04 6.47E-03 Gaseous Effluent Dose Limit, Any Organ (Iodine, Tritium, 15 mrem 15 mrem 15 mrem 15 mrem 30 mrem Particulates with >8 day halif-life)

Organ Dose 2.30E-03 4.65E-04 3.22E-04 2.49E-04 3.18E-03

% of Limit 1.54E-02 3.10E-03 2.14E-03 1.66E-03 1.06E-02 Total Body Dose 2.27E-04 3.67E-04 2.26E-04 2.49E-04 1.07E-03 Skin Dose _____2.00E-03 C-14 Total Body/Organ _____ _____ mrem Bone Dose 8.51E-03 1.1OE-02 1.12E-02 ]1.13E-02 4.21E-02 Total Body Dose 1.67E-03 j2.16E-03 J2.20E-03 J2.22E-03 8.24E-03 SThe controlling pathway was the fish and shellfish pathway with adult as the controlling age group and the GI-LLU representing the organ with the highest calculated dose during the calendar year of 2014.

2The controlling pathway was the infant-thyroid pathway representing the organ with the highest calculated dose during the calendar year of 20 14. There is currently no milk pathway.

5

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2014

3. 40 CFR 190 Total Dose Compliance Based upon the calendar year 2014 and the ODCM calculations, the maximum exposed individual would receive 0.18% of the allowable dose. During the calendar year 2014, 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.

EPA 40CFR190 Individual in the Unrestricted Area Whole Body Thyroid Any Other Organ Dose Limit 25 mrem 75 mrem 25 mrem Liquid 1.77 E-03 1.15E-03 2.03 E-03 Gas 1.07E-03 3.18E-03 3.20E-04 C-14 8.24E-03 4.21E-02 Dose 1.11E-02 4.33E-03 4.45E-02

%of Limit 4.43E-02 5.77E-03 1.78E-01 Child bone dose was used for Any Other Organ due to C-14

4. Solid Waste Report Requirements During 2014, 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 2014 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.
5. Offsite Dose Calculation Manual (ODCM) and Process Control Program (PCP) Changes The ODCM and PCP were not revised in 2014.

B. Radioactive Effluent Monitoring Instrumentation

1. For 2014, inoperable gaseous effluent monitors were retumned to service within 30 days in accordance with section 3.3.3.9 of the Offsite Dose Calculation Manual.
2. For 2014, inoperable liquid effluent monitors were returned to service within 30 days in accordance with section 3.3.3.10 of the Offsite Dose Calculation Manual.

6

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2014 C. Independent Spent Fuel Storage Installation (ISFSI). ISFSI Technical Specification 6.3 Four casks of spent fuel were transferred to the ISFSI during the reporting period. No quantity of radionuclides was released to the environment during the ISFSI operation in 2014. Additional information regarding the ISFSI radiological environmental monitoring program is included in the Annual Radiological Environmental Operation Report.

lV. 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 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.

7

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2014 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 release methodology discussed in section V.B.2.
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, strontium-89, and strontium-90 analyses. Iron-55 is analyzed twice per year.

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 l.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 2014.

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.

8

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2014 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:

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. Meteorological Data A summary of required meteorological data is retained on site in lieu of submission with the Radioactive Effluent Release Report.

9

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2014 F. 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 (see Tables below). Sample size and/or count times are adjusted to achieve analytical sensitivities lower than the environmental LLDs for gamma emitters (listed in ODCM Table 4.12-1). Established LLD limits for tritium are approximately 350 pCi/1 for tritium.

Groundwater samples were collected from seventeen on-site piezometer tubes throughout 2014. 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 piezometer tubes sampled, only #11 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 this location does not impact any drinking water pathway.

The 2014 analysis result for tritium and gamma are shown in the following tables.

10

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2014 Concentration of Tritium in Groundwater (Results in units of pCi/L)

Sample Piezometer Tube Date 11 12 13 15 18 19 20 21 22 23 24 25 26 27 28 29 30 03/02/14 478 4 4 4 4 4 4 4 # 4 # 4 # 4 4 5/19/14 # # 4 # 4 # 4 ND ND ND ND ND ND ND ND 6/24/14 - ND ND ND ND ND ND ND ND ND # #4 # # #

07/18/14 825 4 4 # # 4 4 # ND ND ND ND ND ND ND ND 8/16/14 ND ND ND ND ND ND ND ND ND 4 4 ND 4 ND ND ND 82/4ND ND ND ND ND ND ND ND ND ND ND # ND ND 4 # #

11/22/14 1570 # # 4 # # # # 4 ND ND ND ND ND ND ND ND 12/13/14 ND ND ND ND ND ND ND ND ND # # # # 4 # 4

  1. Tritium Less than Minimum Detectable Activity (<MDA)

ND No Data - Quarterly sample obtained as required.

11

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2014 Gross Concentration of Gamma Emitters (Results in units of pCi/L)

Sample Date Piezometer Tube 11 12 13 15 18 19 20 21 22 23 24 25 26 27 28 29 30 03/02/14 * * * * * * * * * * * * * * * *

  • 5/19/14 * * * * * * * *
  • ND ND ND ND ND ND ND ND 6/24/14 ND ND ND ND ND ND ND ND ND * * * * * * *
  • 7/18/14 * * * * * * * *
  • ND ND ND ND ND ND ND ND 8/16/14 ND ND ND ND ND ND ND ND ND *
  • ND *
  • ND ND ND 8/29/14 ND ND ND ND ND ND ND ND ND ND ND
  • ND ND * *
  • 11/22/14 * * * * * * * *
  • ND ND ND ND ND ND ND ND 12/13/14 ND ND ND ND ND ND ND ND ND * * * * * * * *
    • AII Non-Natural Gamma Emitters < MDA ND No Data - Quarterly sample obtained as required 12

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2014 VI. BATCH RELEASES 201...44 1ST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER A.Liid

1. Number of batch releases 15. 11 10 I1
2. Total time period for batch 1.91E+04 4.80E+04 1.37E+05 1.37E+05 releases (min)
3. Maximum time period for a 9.93E+03 4.32E+04 4.46E+04 4.46E+04 batch release (min)
4. Average time period for 1.27E+03 4.37E+03 1.37E+04 1.25E+04 batch releases (min)
5. Minimum time period for a 2.21 E+02 6.00E+01 5.25E+02 5.48E+02 batch release (min)
6. Average stream flow during 4.33E+06 4.61E+06 4.59E+06 4.60E+06 periods of effluent into a flowing stream (liters/mmn of dilution water) 13

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2014 B. Gaseous IST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER

1. Number of batch releases 25 25 22 14
2. Total time period for batch 1.50E+04 1.23E+04 8.63E+03 4.71E+03 releases (min)
3. Maximum time period for a 4.44E+03 3.00E+03 7.04E+02 5.25E+02 batch release (min)
4. Average time period for 6 .OOE+02 4.92E+02 3.92E+02 3.36E+02 batch release (min)
5. Minimum time period for a 6.30E+01 1.42E+02 8.50E+0O1 2.16E+02 batch release (min) 14

ENCLOSURE (1)

CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION RADIOACTIVE EFFLUENT RELEASE ANNUAL REPORT - 2014 VII. ABNORMAL RELEASES 201._.4 1ST 2ND 3RD 4TH QUARTER QUARTER QUARTER QUARTER A. Lqi

1. Number of releases 2. Total activity released (Curies) B. Gaseous
1. Number of releases 2. Total activity releases (Curies) 15

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2014 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 1.18E+01 1.86E+00 9.06E+00 3.07E-01 +1.20E+01
2. Average release rate for period *tCi/sec 1.50E+00 2.36E-01 1.15E+00 3.89E-02
5. Percent of ODCM limit (1)  % 3.29E-03 4.03E-04 3.66E-04 2.4 1E-04
6. Percent of ODCM limit (2)  % 5.44E-03 1.22E-03 6.08E-03 2.00E-04 B. IODINES
1. Total Iodine - 131 Ci 7.57E-05 1.19E-05 8.65E-06 0.00E+00 +6.50E+00
2. Average release rate for period *iCi/sec 9.61E-06 1.51E-06 1.10E-06 0.00E+00
3. Percent of ODCM limit  %(3) (3) (3) (3)

C. PARTICULATES

1. Particulates with half lives greater than11 8 days Ci <LLD <LLD <LLD <LLD +1.20E+0O1
2. Average release rate for period BCi/sec <LLD <LLD <LLD <LLD
3. Percent of ODCM limit J  % (3) (3) ( (3) ( 3)______

A-I

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2014 ANNUAL REPORT D. TRITIUM

1. Total Release Ci 7.87E+00 1.02E+01 1.04E+01 T 1.05E+I N/
2. Average release rate for period gtCi/sec 1.01E+00 1.30E+00 1.3 IE+00 1.32E+00 NOTES TO TABLE 1A (1) Percent of quarterly gamma-air dose limit (10 mRad)

(2) Percent of quarterly beta-air dose limit (20 mRad)

(3) Iodine, Tritium, Carbon-14, and Particulates are treated as a group. % limit can be found in Section III.A.2 A-2

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2014 ANNUAL REPORT TABLE 1C - REG GUIDE 1.21 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE T

____ UNITS 1ST QUARTER 2ND QUARTER 3RD 4TH jQUARTER jQUARTER 1ST QUARTER JQUARTER 2ND 3RD QUARTER 4TH QUARTER

1. FISSION AND ACTIVATION GASES Argon -41 Ci <LLD <LLD <LLD <LLD 2.34E-02 2.77E-02 2.76E-02 2.17E-02 Krypton -85 Ci 2.1 I E-01 <LLD <LLD <LLD 2.08E+00 ].47E+00 8.72E+00 1.36E-01 Krypton -85m Ci 2.70E-01 <LLD <LLD <LLD 1.81E-05 1.53E-05 <LLD <LLD Krypton -87 Ci 3.86E-04 <LLD <LLD <LLD <LLD <LLD 1.93E-05 <LLD Krypton -88 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xenon - 131 m Ci 1.31E-02 <LLD <LLD <LLD 4.95E-02 2.69E-04 9.12E-04 <LLD Xenon -133 Ci 6.85E+00 1.82E-01 <LLD <LLD 1.75E+00 7.43E-02 3.09E-01 9.25E-02 Xenon -133m Ci 4.33E-03 <LLD <LLD <LLD 1.37E-02 6.88E-04 4.21E-03 9.66E-04 Xenon -135 Ci 5.58E-01 1.06E-01 <LLD 5.47E-02 2.53E-03 7.20E-04 3.31E-03 1.37E-03 Xenon -I 35m Ci <LLD <LLD <LLD <LLD <LLD <LLD 2.74E-04 <LLD Xenon - 138 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total for Period Ci 7.90E+00 2.87E-01 O.00E+00 5.47E-02 3.93E+00 1.58E+00 9.06E+00 2.52E-01
2. IODINES A-3

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2014 ANNUAL REPORT TABLE iC REG GUIDE 1.21 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 1ST 2ND 3RD 4TH 1 ST 2ND 3RD 4TH UNITS QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER Iodine -131 Ci 7.57E-05 1.19E-05 8.65E-06 <LLD (1) (1) (1) (1)

Iodine -132 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Iodine -133 Ci 4.47E-04 2.50E-04 1.44E-04 1.81E-04 (1) (1) (1) (1)

Iodine -135 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Total for Period Ci 5.22E-04 2.62E-04 1.53E-04 1.81E-04 (1) (1) (i) (1)

3. PARTICULATES (half life > 8 days)

Manganese -54 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Iron -55 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Iron -59 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Cobalt -58 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Cobalt -60 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Zinc -65 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Strontium -89 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Strontium -90 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

A-4

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2014 ANNUAL REPORT TABLE 1C - REG GUIDE 1.21 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MODE 1ST 2ND 3RD 4TH 1 ST 2ND 3RD 4TH UNITS QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER Molybdenum -99 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Cesium -1 34 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Cesium -1 37 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Cerium -141 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Cerium - 144 Ci <LLD <LLD <LLD <LLD (1) (1) (1) (1)

Total for period Ci <LLD <LLD <LLD <LLD (1) (1!) (1) (1)

4. GROSS ALPHA RADIOACTIVITY Gross Alpha Ci <LLD 9.80E-08 6.2 IE-07 <LLD <LLD <LLD <LLD <LLD
5. TRITIUM Tritium Ci 5.57E-01 3.47E+O0 2.40E+00 2.74E+00 <LLD 4.12E-01 <LLD <LLD 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.

A-5

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2014 ANNUAL REPORT TABLE 2A - REG GUIDE 1.21 LIOUID EFFLUENTS - SUMMATION OF ALL RELEASES 11ST 2ND ] 3RD [ 4TH1 EST. TOTAL UNITS QUARTER QUARTER] QUARTER QUARTER JERROR,  %

A. FISSION AND ACTIVATION PRODUCTS

1. Total Release (not including tritium, gases, alpha) Ci 1.39E-02 6.I0E-03 5.46E-03 4.35E-03 +l.03E+01
2. Average diluted concentration during period gCi/ml 6.03E-12 2.49E-12 1.49E-12 1.18E-12
3. Percent of ODCM limit (1)  % 1.02E-02 6.80E-03 7.09E-03 4.18E-03
5. Percent of ODCM limit (2)  % 2.20E-02 9.63E-03 1.48E-02 1.25E-02 B. TRITIUM
1. Total Release Ci 3.31IE+02 1.66E+02 3.05E+02 T 2.85E+02 +l.03E+01
2. Average diluted concentration during period j*tCi/ml 1.43E-07 6.78E-08 8.31lE-08 7.73E-08
3. Percent of applicable limit (3)  % 4.77E-03 2.26E-03 2.77E-03 2.5 8E-03 C. DISSOLVED AND ENTRAINED GASES
1. Total Release Ci 1.58E-02 3.I1E-04 1.01E-02 3.09E-04 +l.03E+01
2. Average diluted concentration during period itCi/ml 6.84E-12 l.27E-13 2.76E-12 8.40E-14 D. GROSS ALPHA RADIOACTIVITY
1. Total Release Ci <LLD <LLD <LLD <LLD N/A A-6

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2014 ANNUAL REPORT E. VOLUME OF WASTE RELEASED (prior to dilution)

1. Volume processed through radwaste system liters 1.12E+08 1.07E+08 - 1.07E+08 1.16E+08 +l.30E+00 F. VOLUME OF DILUTION WATER USED DURING PERIOD (4) liters 2.3 1E+12 2.45E+12 3.67E+12 3.68E+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 ofl1.C.3 Quarterly Whole Body Dose Limit (3 mrem)

(3) Limit used is 3 x 10-3 *tCi/ml (4) Includes dilution water used during continuous discharges.

(5) Liquid releases are higher than normal during refueling outages due to noble gases released from failed fuel A-7

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2014 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 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Sodium - 24 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Chromium - 51 Ci <LLD <LLD <LLD <LLD <LLD 1.791E-04 <LLD <LLD Manganese - 54 Ci <LLD <LLD <LLD <LLD 4.311E-05 <LLD <LLD 2.53E-05 Iron - 55 Ci (2) (2) (2) (2) 2.75E3-03 <LLD 2.4513-03 <LLD Cobalt -57 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cobalt- 58 Ci <LLD <LLD <LLD <LLD 7.77E-04 1.18E3-03 2.61E-04 3.56E3-05 Iron - 59 Ci <LLD <LLD <LLD <LLD 1.7413-05 <LLD <LLD <LLD Cobalt -60 Ci <LLD <LLD <LLD <LLD 1.84E3-03 6.00E-04 5.6513-04 2.24E-04 Nickel-63 Ci <LLD <LLD <LLD <LLD <LLD 9.82E3-04 8.84E-04 1.58E-03

Zinc -65 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Strontium - 89 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Strontium - 90 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Strontium - 91 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD A-8

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2014 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 Strontium - 92 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Niobium - 95 Ci <LLD <LLD <LLD <LLD <LLD 6.82E-05 <LLD <LLD Zirconium - 95 Ci <LLD <LLD <LLD <LLD <LLD 6.34E-05 <LLD <LLD Niobium - 97 Ci <LLD <LLD <LLD <LLD <LLD <LLDJ <LLD <LLD Zirconium - 97 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Molybdenum - 99 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Technetium - 99m Ci' <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ruthenium - 103 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Rhodium - 105 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Ruthenium - 105 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Silver - 110mi Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tin - 113 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tin - 117m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Antimony - 122 Ci <LLD <LLD <LLD <LLD 6.81IE-05 <LLD <LLD <LLD A-9

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2014 ANNUAL REPORT TABLE 2B - REG GUIDE 1.21 LIOUID EFFLUENTS CONTINUOUS MODE BATCH MODE 1 ST 2ND 3RD 4TH 1 ST 2ND 3RD 4TH NUCLIDES RELEASED Units QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER QUARTER Antimony - 124 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Antimony - 125 Ci <LLD <LLD <LLD <LLD 2.72E-03 <LLD 2.92E-04 7.51lE-05 Tellurium - 125m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tellurium - 132 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Iodine - 131 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Iodine - 132 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Iodine - 133 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Iodine - 135 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cesium- 134 Ci <LLD <LLD <LLD <LLD 6.11E-04 3.04E-04 6.90E-05 1.68E-04 Cesium - 136 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cesium - 137 Ci <LLD <LLD <LLD <LLD 5.09E-03 2.72E-03 9.38SE-04 2.23E-03 Barium - 140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Lanthanum - 140 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Cerium - 144 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD A-IO

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2014 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 Europium - 154 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Europium - 155 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Tungsten - 187 Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Total For Period Ci <LLD <LLD <LLD <LLD I .39E-02 6.10E-03 5.46E-03 4.35E-03 Krypton - 85 Ci <LLD <LLD <LLD <LLD <LLD <LLD 1.01 E-02 <LLD Xenon - 131 m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xenon - 133 Ci <LLD <LLD <LLD <LLD 1.55E-02 3.11E-04 6.90E-05 3.09E-04 Xenon - 133m Ci <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD Xenon - 135 Ci <LLD <LLD <LLD <LLD 3.17E-04 <LLD <LLD <LLD Total For Period Ci <LLD <LLD <LLD <LLD 1.58E-02 3.1 IE-04 1.0 1E-02 3.09E-04 Tritium Ci 5.75E-02 1.32E-01 9.78E-02 1.53E-01 3.31E+02 1.66E+-02 3.05E+02 2.85E+02 Total For Period Ci 5.75E-02 1.32E-01 9.78E-02 1.53E-01 3.3 1E+02 1.66E+02 3.05E+02 2.85E+02 A-11

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2014 ANNUAL REPORT 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-12

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2014 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 1.69+01 25%

Ci 2.56E+02 b) Dry compressible m3 4.14E+02 25%

waste, contaminated equipment, etc.Ci27+0 c) Irradiated components, m3 0.00E+00 N/A control rods, etc.

Ci 0.00E+00 d) Other (cartridge filters, m3 5.80E+02 25%

misc. dry compressible, Oil)Ci37E-1 e) Solidification agent or m3 N/A N/A absorbent Volume shipped represents waste generated prior to offsite volume reduction.

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

Spent Resins, Filters Nuclide Abundance (%)

Mn-54 2.63 Fe-55 14.44 Co-5 8 7.74 Co-60 21.56 Ni-63 18.54 Cs-134 6.95 Cs-137 25.92 A-13

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2014 ANNUAL REPORT

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

Dry Active Waste Nuclide Abundance (%)

H-3 1.33 C-14 13.57 Fe-55 15.12 Co-58 12.83 Co-60 17.81 Ni-63 16.38 Zr-95 5.68 Nb-95 10.58 Cs-137 2.81 Pu-241 1.30 Irradiated Components Nuclide ]Abundance (%)

N/A Other Waste Nuclide Abundance (%)

H-3 1.33 C-14 13.62 Fe-55 15.14 Co-58 12.79 Co-60 17.85 Ni-63 16.42 Zr-95 5.66 Nb-95 10.50 Cs-137 2.80 Pu-241 1.30 A-14

APPENDIX A CALVERT CLIFFS NUCLEAR POWER PLANT AND INDEPENDENT SPENT FUEL STORAGE INSTALLATION EFFLUENT AND WASTE DISPOSAL 2014 ANNUAL REPORT

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 17 Motor Surface Transit Energy Solutions (Duratek)

(Hifman)Oak Ridge, TN 9Motor Surface Transit Waste Control Specialists LLC (Hitman)Andrews, TX 3Motor Surface Transit Energy Solutions (Duratek)

(Landtar)Oak Ridge, TN 2 Motor Surface Transit Studsvik Processing Facility Memphis, TN B. IRRADIATED FUEL SHIPMENTS (DISPOSITION) N/A A-15

Retrieved from "https://kanterella.com/w/index.php?title=ML15198A035&oldid=2447797"