CP-201500443, Transmittal of Year 2014 Radiological Environmental Operating Report

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Transmittal of Year 2014 Radiological Environmental Operating Report
ML15133A101
Person / Time
Site: Comanche Peak  Luminant icon.png
Issue date: 04/30/2015
From: Flores R, Madden F
Luminant Generation Co, Luminant Power
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
CP-201500443, TXX-15053
Download: ML15133A101 (64)


Text

Rafael Flores Luminant Power Senior Vice President P 0 Box 1002 0 & Chief Nuclear Officer 6322 North FM 56 Glen Rose, TX 76043 Lum inant Rafael.flores@Luminant.com T 254 897 5550 C 817 559 0403 F 254 897 6652 CP- 201500443 Ref. # Tech. Spec. 5.6.2 Log # TXX-15053 April 30, 2015 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001

SUBJECT:

COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NOS. 50-445 AND 50-446 TRANSMITTAL OF YEAR 2014 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

Dear Sir or Madam:

Enclosed is the Annual Radiological Environmental Operating Report for the Comanche Peak Radiological Environmental Monitoring Program. This report is submitted pursuant to Section 5.6.2 of the Comanche Peak Units 1 and 2 Technical Specifications (Appendix A to Operating License Nos. NPF-87 and NPF-89). The report covers the period from January 1, 2014 through December 31, 2014 and summarizes the results of measurements and analysis of data obtained from samples collected during this interval.

If there are any questions regarding this report, please contact Steve Dixon at (254) 897-5482 or Deb O'Connor at (254) 897-0151.

Sincerely, Luminant Generation Company LLC Rafael Flores By: __A__ __j

,/Fred W. Madden Director, External Affairs

U.S. Nuclear Regulatory Commission TXX-15053 Page 2 04/30/15 Enclosure - Comanche Peak Annual Radiological Environmental Operating Report For 2014 c- M. L. Dapas, Region IV K. M. Kennedy, Region IV B. Singal, NRR Resident Inspectors, Comanche Peak

Enclosure 1 Comanche Peak Annual Radiological Environmental Operating Report For 2014

LUMINANT COMANCHE PEAK NUCLEAR POWER PLANT ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2014 JANUARY 1, 2014 through DECEMBER 31, 2014 LUMINANT REVIEW and APPROVAL CREATED BY: . 4i9 4 //iw- / 6, Todd Emery Date REVIEWEDBY:

Mac .4 Dat'e

¶adiation Protection Superi r APPROVED BY:Zý* ei < it51( 5 bate' Health Physics Supervisor Documented on RPI-710-2 1

Table of Contents Section Title I. Introduction A. Site and Station Description page 5 B. Objectives and Overview of the CPNPP Radiological Environmental Monitoring Program page 5 II. Program Descriptions and Results A. Sample Locations page 7 Table 1 -- Comanche Peak Nuclear Power Plant Radiological Environmental Monitorin2 Pro2ram for 2014 Table 2 -- Key to Environmental Sampling Locations B. Direct Radiation Program page 11 Methods, Procedures and Result Summaries Exceptions to the Program Table 3 -- 2014 Environmental Direct Radiation Results Table 14 -- TLD Trend Ouarterly Average C. Airborne Program page 16 Methods, Procedures and Result Summaries Exceptions to the Program Table 4 -- 2014 Environmental Airborne Particulate Gross Beta Results Graph 1-- 2014 Environmental Air Sample Gross Beta Results -

Maximum and Minimum Table 5 -- 2014 Environmental Air Sample Iodine-131 Results Table 6 -- 2014 Environmental Air Particulate Composite Gamma Isotopic Results 2

D. Surface Water Program page 23 Methods, Procedures and Result Summaries Exceptions to the Program Table 7 -- 2014 Environmental Surface Water Tritium and Gamma Isotopic Results Graph 2-- 2014 Environmental Surface Water Tritium Results E. Surface Drinking Water Program page 27 Methods, Procedures and Result Summaries Exceptions to the Program Table 8 -- 2014 Environmental Surface Drinking Water Tritium, Gross Beta and Gamma Isotopic Results Graph 3-- Squaw Creek Maximum Tritium Values Graph 4-- 2014 Environmental Surface Drinking Water Tritium Results Graph 5-- 2014 Environmental Surface Drinking Water Gross Beta Results F. Groundwater Program page 33 Methods, Procedures and Result Summaries Exceptions to the Program Table 9 -- 2014 Environmental Groundwater Tritium and Gamma Isotopic Results G. Sediment Program page 35 Methods, Procedures and Result Summaries Exceptions to the Program Table 10 -- 2014 Environmental Sediment Gamma Isotopic Results H. Fish Program page 37 Methods, Procedures and Result Summaries Exceptions to the Program Table 11 -- 2014 Environmental Fish Gamma Isotopic Results 3

I. Food Products Program page 39 Methods, Procedures and Result Summaries Exceptions to the Program Table 12 -- 2014 Environmental Food Products Gamma Isotopic Results J. Broadleaf Program page 41 Methods, Procedures and Result Summaries Exceptions to the Program Table 13 -- 2014 Environmental Broadleaf Iodine-131 and Gamma Isotopic Results K. Conclusions page 43 L. Inter Laboratory Comparison and Cross Check Program page 43 III. Appendix A Comanche Peak Nuclear Power Plant Land Use Census 2014 page 46 4

Introduction Results of the Radiological Environmental Monitoring Program for the Comanche Peak Nuclear Power Plant (CPNPP) for the year 2014 are contained within this report. This report covers the period from January 1, 2014 through December 31, 2014 and summarizes the results of measurements and analysis of data obtained from environmental samples collected during this same timeframe.

A. Site and Station Description CPNPP consists of two pressurized water reactor units, each designed to operate at a power level of about 1250 megawatts (electrical). The Station is located on Squaw Creek reservoir in Somervell and Hood counties, about forty miles southwest of Fort Worth, Texas. Unit 1 received a low power operating license February 8, 1990 and achieved initial criticality on April 3, 1990. A full power license for Unit 1 was issued on April 17, 1990 and commercial operation was declared on August 13, 1990. Unit 2 achieved initial criticality on March 24, 1993 and synchronized to the electrical grid on April 9, 1993.

B. Objectives and Overviews of the CPNPP Radiological Environmental Monitoring Program The United States Nuclear Regulatory Commission (USNRC) regulations require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA). To assure that these criteria are met, each license authorizing reactor operation includes technical specifications governing the release of radioactive effluents.

In-plant monitoring is used to assure that these predetermined release limits are not exceeded. However, as a precaution against unexpected and undefined processes that might allow undue accumulation of radioactivity in any sector of the environment, a program for monitoring the plant environs, is also included.

Sampling locations were selected on the basis of local ecology, meteorology, physical characteristics of the region, and demographic and land use features of the site vicinity. The radiological environmental monitoring program was designed on the basis of the USNRC Branch Technical Position "An Acceptable Radiological Environmental Monitoring Program" on radiological environmental monitoring issued by the Radiological Assessment Branch, Revision 1 (November 1979), the CPNPP Technical Specification "Technical Specifications for Comanche Peak Nuclear Power Plant Units 1 and 2" and the "CPSES Offsite Dose Calculation Manual" (ODCM).

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In 2014, the Radiological Environmental Monitoring Program included the following:

  • The measurement of ambient gamma radiation by Thermal Luminescent dosimetry;
  • The determination of airborne gross beta, gamma emitters, and Iodine- 131;
  • The determination of tritium and gamma emitters in surface water;
  • The determination of gross beta, tritium, Iodine- 131, and gamma emitters in drinking water;
  • The determination of tritium and gamma emitters in ground water;
  • The determination of gamma emitters in sediment and fish;
  • The determination of gamma emitters in food products and;
  • The determination of gamma emitters and Iodine- 131 in broadleaf vegetation.

The regulations governing the quantities of radioactivity in reactor effluents allow nuclear power plants to contribute, at most, only a small percentage increase above normal background radioactivity. Background levels at any one location are not constant but vary with time as they are influenced by external events such as cosmic ray bombardment; weapons test fallout, and seasonal variations. These levels also can vary spatially within relatively short distances reflecting variations in geological composition. To differentiate between background radiation levels and increases resulting from operation of CPNPP, the radiological surveys of the plant environs were divided into pre-operational and operational phases.

The pre-operational phase of the program provided a general characterization of the radiation levels and concentrations prevalent in these areas prior to plant operation along with an indication of the degree of natural variation to be expected. The operational phase of the program obtains data which, when considered along with the data obtained in the pre-operational phase, assists in the evaluation of the radiological impact of plant operation.

Pre-operational measurements were conducted at CPNPP from 1981 to 1989. These pre-operational measurements were performed to:

  • Evaluate procedures, equipment, and techniques;
  • Identify potentially important pathways to be monitored after plant operation;
  • Measure background levels and the variations along potentially important pathways; 0 Provide baseline data for statistical comparisons with future operational analytical results.

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The operational Radiological Environmental Monitoring Program is conducted to:

  • Verify that measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways;
  • Verify the effectiveness of in-plant measures used for controlling the release of radioactive materials;
  • Identify changes in the areas at and beyond the site boundary that may impact the principal pathways of exposure.

This report documents the twenty-fourth year of operational measurements and is submitted in accordance with the requirements of the CPSES Offsite Dose Calculation Manual, Part I, Administrative Control 6.9.1.3.

Program Descriptions and Results A. Sample Locations Within a radius of twenty miles of the CPNPP site there are seventy-two (72) sample locations included in the monitoring program for the year 2014. The number of sample points and the specific locations for the sample points were determined by considering locations where the highest off-site environmental concentrations have been predicted from plant effluent source terms, site hydrology, and site meteorological conditions.

Other factors considered were applicable regulations, population distribution, ease of access to sampling stations, availability of samples at desired locations, security and future program integrity. Additionally an annual land use census is conducted to identify changes in the areas surrounding the plant. If changes are identified that impact the principle pathways of exposure, appropriate changes to the radiological environmental monitoring program are implemented. A copy of the report "Comanche Peak Nuclear Power Plant Land Use Census 2014" is provided in Appendix A to this report.

Table 1 - Comanche Peak Nuclear Power Plant Radiological Environmental Monitoring Program for 2014 contains a brief outline of the current program. This table specifies the sample media type, the number of locations for each media type, the sector and distance identifier for each sample location, the sample frequency, the type of analysis required and the analytical frequency required.

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Table 2 - Key to Environmental Sampling Locations provides a reference that links the sampling point designations used in procedures and forms to the appropriate physical sample location (sector and distance) and to the correct sample type. This cross-reference enhances the ability to review data and tie the data to the correct sample points and to ensure all samples are collected and analyzed as specified.

Currently there are no milk sample locations within ten miles of the CPNPP site and there are no milk sample locations within twenty miles that will participate in the environmental program. CPNPP already samples extra broadleaf locations as required due to no milk locations within the ten-mile radius therefore, no changes to the program are necessary. Milk sampling will be resumed if any future annual land use census determines a dairy has been established within the specified area.

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Table 1 - Comanche Peak Nuclear Power Plant Radiological Environmental Monitoring Program for 2014 Media Number of Identification by Sector and Distance (miles) Sampling Analysis Analtical Locations Frequency (a) Frequency (a)

N-1.45; N-4.4; N-6.5; N-9.4; NNE-1.1; NNE-5.65; NE-1.7; NE-4.8; ENE-2.5; ENE-5.0; E-0.5; E-1.9; E-3.5; E-4.2; ESE-1.4; ESE-4.7; SE-1.3; Gamma SE-3.85; SE-4.6; SSE-1.3; SSE-4.4; SSE-4.5; Thermo Luminescent 43 S-1.5; S-4.2; SSW-1.1; SSW-4.4; SW-0.9; Q, A (TLD)Dosimetry Q, A Exposure SW-4.8; SW-12.3; WSW-1.0; WSW-5.35; WSW-7.0; W-1.0; W-2.0; W-5.5; WNW-1.0; WNW-5.0; WNW-6.7; NW-I.0; NW-5.7; NW-9.9; NNW-1.35; NNW-4.6 Gross Beta Air Particulate 8 N-9.4; E-3.5; SSE-4.5; SW-12.3; NW-1.0; W Gamma Isotopic Filter QC Air Iodine N-1.45; SW/WSW-0.95; S/SSW-1.2 Gamma Isotopic W Charcoal 4 N-19.3; ESE-1.4; N-1.5; NE-7.4 M(b) Gamma Isotopic M Surface Water Tritium QC Gross Beta M Surface 2 NNW-0.1; N-9.9 M(c) Gamma Isotopic M Water/Drinking Iodine-131 M Tritium QC Ground Water 5 SSE-4.6; W-1.2; WSW-0.1; N-9.8; N-1.45 Q Gamma Isotopic Q Tritium Q Sediment 4 N-9.9; NNE-1.0; NE-7.4; SE-5.3 SA Gamma Isotopic SA Fish 2 NNE-8.0; ENE-2.0 SA Gamma Isotopic SA Food Products 1 ENE-9.0, E-4.2 MH Gamma Isotopic MH Iodine-131 MH Broadleaf Vegeat 3 N-1.45; SW-1.0; SW-13.5 M Gamma Isotopic M Vegetation (a) Frequency codes are: W-Weekly; M-Monthly; Q-Quarterly; QC-Quarterly Composite; MH-Monthly at Harvest; SA-Semiannual; A-Annual (b) Surface water samples from Squaw Creek are monthly composites of weekly grab samples. Surface water samples from Lake Granbury are monthly grab samples.

(c) Surface water drinking samples are a monthly composite of weekly grab samples.

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Table 2 Key to Environmental Sampling Locations SAMPLING LOCATION SAMPLE SAMPLING LOCATION SAMPLE POINT (SECTOR-MILE) TYPE* POINT (SECTOR-MILE) TYPE*

Al N-1.45 A R29 SW-12.3 R A2 N-9.4 A R30 WSW-1.O R A3 E-3.5 A R31 WSW-5.35 R A4 SSE-4.5 A R32 WSW-7.0 R A5 S/SSW-1.2 A R33 W-1.0 R A6 SW-12.3 A R34 W-2.0 R A7 SW/WSW-0.95 A R35 W-5.5 R A8 NW-1.0 A R36 WNW-1 .0 R RI N-1.45 R R37 WNW-5.0 R R2 N-4.4 R R38 WNW-6.7 R R3 N-6.5 R R39 NW-1.0 R R4 N-9.4 R R40 NW-5.7 R R5 NNE-1.1 R R41 NW-9.9 R R6 NNE-5.65 R R42 NNW-1.35 R R7 NE-1.7 R R43 NNW-4.6 R R8 NE-4.8 R SWI N-1.5 SW R9 ENE-2.5 R SW2 N-9.9 SW/DW RIO ENE-5.0 R SW3 N-19.9 SW R11 E-0.5 R SW4 NE-7.4 SW R12 E-1.9 R SW5 ESE- 1.4 SW R13 E-3.5 R SW6 NNW-0.1 SW/DW R14 E-4.2 R GWI W- 1.2 GW/DW R15 ESE- 1.4 R GW2 WSW-0.1 GW/DW R16 ESE-4.7 R GW3 SSE-4.6 GW/DW R17 SE-1.3 R GW4 N-9.8 GW/DW R18 SE-3.85 R GW5 N-1.45 GW/DW R19 SE-4.6 R SS1 NNE-1.0 SS R20 SSE-1.3 R SS2 N-9.9 SS R21 SSE-4.4 R SS3 NE-7.4 SS R22 SSE-4.5 R SS4 SE-5.3 SS R23 S-1.5 R F1 ENE-2.0 F R24 S-4.2 R F2 NNE-8.0 F R25 SSW-I.1 R FP1 ENE-9.0 FP R26 SSW-4.4 R FP2 E-4.2 FP R27 SW-0.9 R BLI N-1.45 BL R28 SW-4.8 R BL2 SW-1.0 BL BL3 SW-13.5 BL Sample Type* A - AIR SAMPLE GW - GROUND WATER F - FISH R- DIRECT RADIATION SS - SHORELINE SEDIMENT FP - FOOD PRODUCT SW- SURFACE WATER BL - BROADLEAF VEGETATION DW - DRINKING WATER 10

B. Direct Radiation Starting in 2013 Thermo Luminescent Dosimeters (TLDs) were used to determine the direct (ambient) radiation levels at the designated monitoring locations. The monitoring locations were chosen according to the criteria given in the USNRC Branch Technical Position on Radiation Monitoring (Revision 1, November 1979). The area around the station was divided into 16 radial sectors of 22-1/2 degrees each, corresponding to the cardinal points of the compass. TLDs were placed in each of these sectors.

The TLDs were placed in two rings around the station. An inner ring was located as close as possible to the site boundary and an outer ring was located at a distance of 4 to 6 miles from the station.

Eleven additional TLDs were located at points related to higher population areas and two additional control locations. For routine direct radiation measurements, two sets of the TLDs were used at each of the 43 monitoring locations. One set of TLDs was exchanged on a quarterly basis and a second set of TLDs was exchanged on a yearly basis. Additional sets of in-transit TLDs were used as control TLDs for the quarterly and annual TLDs.

In 2013 CPNPP contracted the services of Mirion Technologies to provide and process Thermo Luminescent Dosimeters (TLDs.) The TLDs are used to determine the direct (ambient) radiation levels in designated monitoring locations. Mirion Technologies is accredited by the National Voluntary Laboratory Accreditation Program (NVLAP.)

From years 2009-2012 CPNPP contracted the: services of Landauer Inc. to provide and process Optically Stimulated Luminescent dosimeters (OSLs) to determine the direct (ambient) radiation levels at the designated monitoring locations. Landauer Inc. is accredited by the National Voluntary Laboratory Accreditation Program (NVLAP.)

From years 2001 to 2008 Thermo Luminescent Dosimeters (TLDs) were processed on-site by CPNPP National Voluntary Laboratory Accreditation Program (NVLAP) certified. Individual dosimeters were calibrated by exposure to an accurately known radiation field from a certified Cs-137 source. The year 2001 was the first year that CPNPP used the Panasonic TLD System to supply all the required direct radiation (ambient) monitoring.

D. C. Oakley's report "National Radiation Exposure in the United States", published in 1972, calculated a background radiation dose rate equivalent of 0.22 mR/day for the area surrounding Fort Worth, Texas. This calculated value varies widely with changes in location but represents an appropriate reference value to compare with actual measured TLD doses.

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Using data from the pre-operational program for the two years prior to the startup of Unit 1, the quarterly TLDs averaged a calculated dose rate of 0.14 mR/day while the yearly TLDs averaged a calculated dose rate of 0.16 mR/day. The range of measured values from this same two-year period varied from a minimum of 0.11 mR/day to a maximum of 0.22 mR/day.

Table 3 - 2014 Environmental Direct Radiation Results contains the measured dose (mR) for each quarterly TLD from each of the 43 monitoring locations. The corresponding quarterly calculated dose rate (mR/day) values are listed as well. The statistical average doses (mR) and dose rate (mR/day) values for each set of quarterly TLDs is also displayed. Additionally, the table includes the total dose (mR) of all four quarters for each specific location. The table also includes the measured dose (mR) for each annual TLD from each of the 43 monitoring locations. The corresponding annual calculated dose rate (mR/day) values are listed as well. The statistical annual average dose (mR) for the entire set of annual TLDs is reported along with the average dose rate (mR/day) for the entire set of annual TLDs.

For the year 2014, the measured dose rates of all the quarterly TLDs ranged from a minimum of 0.075 mR/day to a maximum of 0.177 mR/day with an average dose rate of 0.126 mR/day. This resulted in an average quarterly dose of 11 mR and a total annual dose of 43.00 mR for all of the forty three monitoring stations.

The measured dose rates of all the annual TLD's ranged from a minimum of 0.084 mR/day to a maximum of 0.164 mR/day with an average dose rate of 0.126 mR/day. This resulted in an average quarterly dose of 10.8 mR and a total annual dose of 43.0 mR for all of the forty three monitoring stations.

Comparing the pre-operational data and operational data collected through the year 2014 did not produce any anomalies. The direct radiation dose data for 2014 was consistent with previous years of data during the pre-operational program. Table 14 - TLD Trend Quarterly Average contains the average quarterly OSL/TLD for the five most current years from each of the 43 monitoring locations.

The implementation of the Mirion TLDs and the method to calculate direct radiation results by subtraction of shipping transient dose from the TLDs accounts for the lower/accurate values and account for consistent response from each location's total quarterly TLDs to the Annual TLDs.

[See CR-2013-004934 for additional clarification on the background subtraction method].

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The 2012 CPNPP Annual Direct Radiation results were reported using personnel OSLs packaged as environmental OSL field badges. The difference between the two is the chips under copper filters. The environmental OSLs use the average of two chips and the personnel OSLs use one to calculate the direct radiation results.

Condition Report CR-2012-003122 can be referenced.

In 2013 CPNPP performed a Background TLD Study which improved the reporting accuracy of Direct Radiation Results. In summary, this study incorporated calculating the daily average in mR/Day of the background TLDs stored in the lead storage container during the monitoring period. This Background Study provided the necessary data to determine the transient dose during shipping to and from Mirion in Irvine, California. Details of this study can be found in Condition Report 2013-0004934.

No abnormal quarterly results were obtained by either CPNPP or by the State of Texas, Bureau of Radiation Control.

  • CR-2014-005489 The Quarterly Environmental TLD for location #34 was not exchanged until 4/21/14. All other quarterly Environmental TLDs were exchanged on 3/27/14.

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Table 3 -2014 Environmental Direct Radiation Results (Units of mR dose and mR/day dose rate) 1ST 2ND 3RD 4TH AVG Annual Annual QTR Average QTR Average QTR Average QTR Average QTR TLD Average TLD TLD Location Total mR/Day Total mR/Day Total mR/Day Total mR/Day Total Total mR/day N-1.45 R1 10 0.123 11 0.117 10 0.115 14 0.146 11 47 0.128 N-4.4 R2 12 0.142 13 0.138 12 0.138 15 0.157 13 50 0.136 N-6.5 R3 10 0.120 10 0.106 12 0.138 14 0.146 12 44 0.120 N-9.4 R4 11 0.126 11 0.119 11 0.124 14 0.146 12 48 0.131 NNE-1.1 R5 7 0.084 8 0.085 8 0.092 9 0.095 8 32 0.087 NNE-5.65 R6 11 0.134 12 0.127 12 0.138 14 0.146 12 49 0.134 NE-1.7 R7 7 0.084 8 0.085 7 0.081 10 0.105 8 32 0.087 NE-4.8 R8 12 0.143 13 0.138 12 0.138 15 0.157 13 55 0.150 ENE-2.5 R9 12 0.138 13 0.138 13 0.150 15 0.157 13 53 0.145 ENE-5.0 RIO 13 0.159 15 0.159 15 0.173 17 0.177 15 60 0.164 E-0.5 R11 12 0.137 12 0.130 13 0.146 14 0.146 13 50 0.136 E-1.9 R12 8 0.100 9 0.096 10 0.115 12 0.126 10 42 0.114 E-3.5 R13 10 0.118 10 0.106 10 0.115 13 0.136 11 46 0.125 E-4.2 R14 12 0.138 12 0.127 12 0.138 14 0.146 13 50 0.136 ESE-1.4 R15 10 0.116 11 0.117 14 0.161 13 0.136 12 47 0.128 ESE-4.7 R16 11 0.125 12 0.127 12 0.138 14 0.146 12 50 0.136 SE-1.3 R17 11 0.128 10 0.106 12 0.138 14 0.146 12 50 0.136 SE-3.85 R18 10 0.114 11 0.117 11 0.127 11 0.115 11 45 0.123 SE-4.6 R19 10 0.116 11 0.116 10 0.104 13 0.136 11 44 0.120 SSE-1.3 R20 10 0.116 11 0.1.17 .10 0.115 13 0.136 11 44 0.120 SSE-4.4 R21 11 0.128 11 0.119 11 0.124 13 0.136 12 47 0.128 SSE-4.5 R22 10 0.120 12 0.130 11 0.124 14 0.146 12 47 0.128 S-1.5 R23 9 0.106 10 0.106 10 0.115 12 0.126 10 42 0.114 S-4.2 R24 10 0.122 12 0.130 13 0.146 15 0.157 13 49 0.134 SSW-1.1 R25 11 0.130 12 0.127 11 0.127 14 0.146 12 48 0.131 SSW-4.8 R26 10 0.123 11 0.119 11 0.124 14 0.146 12 46 0.125 SW-0.9 R27 10 0.113 11 0.117 11 0.127 14 0.146 12 44 0.120 SW-4.8 R28 10 0.118 10 0.108 10 0.113 12 0.126 11 43 0.117 SW-12.3 (C) R29 10 0.123 11 0.119 11 0.124 13 0.136 11 47 0.128 WSW-1.0 R30 11 0.130 11 0.117 11 0.127 14 0.146 12 49 0.134 WSW-5.35 R31 11 0.126 11 0.119 11 0.124 14 0.146 12 45 0.123 WSW-7.0 (C)R32 12 0.137 12 0.130 13 0.146 14 0.146 13 51 0.139 W-1.0 R33 9 0.104 9 0.096 10 0.115 11 0.115 10 40 0.109 W-2.0 R34 11 0.102 9 0.133 9 0.102 11 0.115 10 39 0.106 W-5.5 R35 10 0.114 10 0.108 10 0.113 12 0.126 11 42 0.114 WNW-1.0 R36 11 0.135 11 0.119 12 0.135 14 0.146 12 51 0.139 WNW-5.0 R37 11 0.132 11 0.119 11 0.124 14 0.146 12 48 0.131 WNW-6.7 R38 10 0.119 11 0.119 11 0.124 13 0.136 11 46 0.125 NW-1.0 R39 10 0.124 11 0.119 10 0.113 13 0.136 11 46 0.125 NW-5.7 R40 10 0.124 12 0.130 12 0.135 14 0.146 12 48 0.131 NW-9.9 R41 10 0.114 10 0.108 10 0.113 12 0.126 11 42 0.114 NNW-1.35 R42 7 0.079 7 0.075 7 0.081 9 0.095 8 31 0.084 NNW-4.6 R43 12 0.138 12 0.127 12 0.138 15 0.157 13 52 0.142 AVERAGES 10 0.122 11 0.119 11 0.127 13 0.139 11 43 0.126 14

Table 14 - TI Quarterly A erage (Five most current years)

Location 2010 2011 2012 2013 2014 %Diff 2014 2010-2014 %Diff 2014 to 2013 1 mR Ava

_______ - +

to Averaae RI 22 23 26 11 I11 0% 18.60 -51%

R2 23 22 26 13 13 0% 19.40 -40%

R3 22 20 25 11I 12 9% 18.00 -40%

R4 22 22 26 12 12 0% 18.80 -44%

R5 17 17 20 8 8 0% 14.00 -55%

R6 23 23 27 12 12 0% 19.40 -47%

R7 19 17 21 7 8 13% 14.40 -57%

R8 25 24 25 13 13 0% 20.00 -42%

R9 24 23 27 13 13 0% 20.00 -42%

R10 24 26 30 14 15 7% 21.80 -37%

R11 23 21 25 12 13 8% 18.80 -36%

R12 20 21 23 9 10 11% 16.60 -50%

R13 22 21 25 12 11 -9% 18.20 -49%

R14 25 23 27 13 13 0% 20.20 -43%

R15 22 21 24 11 12 9%1 18.00 -40% Legend:

R16 23 23 26 12 12 0% 19.20 -46%

R17 23 24 26 12 12 0% 19.40 -47%

R18 21 22 22 11 I11 0% 17.40 -45%

R19 22 21 24 11I 11 0% 17.80 -47%

R20 23 21 24 12 11 -9% 18.20 -49%

R21 23 21 24 11 12 9% 18.20 -41%

R22 23 21 27 11 12 9% 18.80 -44%

R23 21 19 21 11I 10 -10% 16.40 -48%

R24 20 21 24 11 13 17% 17.80 -31%

R25 21 22 25 12 12 0% 18.40 -42%

R26 22 22 26 12 12 0% 18.80 -44%

R27 20 22 25 11 12 9% 18.00 -40%

R28 22 21 24 11 11 0% 17.80 -47%

R29 23 21 25 11I 11 0% 18.20 -49%

R30 22 20 26 12 12 0% 18.40 -42%

R31 22 22 25 10 12 18% 18.20 -41%

R32 24 21 26 13 13 0% 19.40 -40%

R33 20 19 23 10 10 0% 16.40 -48%

R34 22 18 22 9 10 11% 16.20 -47%

R35 20 19 23 10 11 10% 16.60 -41%

R36 23 24 26 13 12 -8% 19.60 -48%

R37 24 23 25 12 12 0% 19.20 -46%

R38 23 22 25 11I 11 0% 18.40 -50%

R39 23 21 23 11 11 0% 17.80 -47%

R40 23 22 24 11 12 9% 18.40 -42%

R41 21 19 23 11 11 0% 17.00 -43%

R42 18 17 20 7 8 13% 14.00 -55%

R43 24 21 26 13 13 0% 19.40 -40%

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C. Airborne Program Air particulate and air iodine samples were collected each week from the eight monitoring locations described in Table 1 -

Comanche Peak Nuclear Power Plant Radiological Monitoring Program for 2014. Each air particulate sample was collected by drawing air through a 47 millimeter-diameter glass-fiber filter. Air iodine was collected by drawing air through a TEDA impregnated charcoal cartridge which was connected in series behind the air particulate filter. Shipped to an independent laboratory, air particulate filters were analyzed weekly for gross beta activity and were composited quarterly for gamma spectrometry analysis.

Charcoal cartridges were analyzed weekly for Iodine- 131.

For the year 2014, a total of 416 air particulate filters were collected and analyzed for gross beta activity. The reported gross beta activity ranged from a minimum value of 1.8E-02 pCi/ma to a maximum value of 1.79E-01 pCi/mr3 . Table 4 - 2014 Environmental Airborne Particulate Gross Beta Results contains the reported values of all samples. There were no anomalies noted in the data reported for 2014 when compared to pre-operational and previous operational data. Graph 1 - 2014 Environmental Air Sample Gross Beta Results - Maximum and Minimum trends the weekly high and low gross beta values to show the seasonal variation of the results as well as providing indication of consistency between the individual monitoring locations.

A total of 416 charcoal cartridges were analyzed for airborne Iodine- 131. Table 5 -2011 Environmental Air Sample Iodine-131 Results contains the reported values of each Iodine- 131 analysis, all of which are less than the required lower limit of detection (LLD).

All air particulate filters were collected and composited quarterly and then analyzed by gamma spectrometry. The gamma isotopic data is presented in Table 6 - 2014 Environmental Air Particulate Composite Gamma Isotopic Results. Typical of pre-operational and previous operational data results, the only radioactive nuclide identified in all the samples was cosmogenic Beryllium-7, a naturally occurring isotope. Several Air Particulate Composite results were positive for Potassium-40. However, results indicate both were below the reporting levels, A review of all the State of Texas air sample data indicated no anomalies.

16

During the year 2014, there were two exceptions to the Airborne Program.

CR-2014-13683- A-2 Filter Cartridge for the period 12/9/14 to 12/16/14 not sent to GEL Laboratories (on 12/16/14) until 12/23/14.

CR-2014-10743- Environmental Air Sampler A-I at Squaw Creek Park lost power on 10/3/14 at 17:59. An RP technician investigated power loss and found/reset the GFI. No apparent cause for the tripped GFI could be identified. CR generated for tracking potential conditions which could affect Environment Air sampling collection and the subsequent GEL Laboratory analysis results.

This loss of power occurred over a short duration and had no effect on the analysis.

17

Table 4 - 2014 Environmental Airborne Particulate Gross Beta Results (Units of pCi/m3)

A-8 A-7 A-5 A-6 A4 A-3 A-I A-2 Location NW-1.0 SW/WSW-0.95 S/SSW-1.2 SW-12.3 I SSE-4.5 E-3.5 N-1.45 I N-9.4 Date Control Control 4.96E-02 3.82E-02 5.23E-02 5.19E-02 5.09E-02 7.54E-02 3.05E-02 2.77E-02 3.03E-02 3.64E-02 2.94E-02 3.68E-02 3.22E-02 5.54E-02 3.47E-02 2.75E-02 2.73E-02 2.86E-02 3.51E-02 4.51E-02 3.13E-02 4.07E-02 2.75E-02 3.09E-02 3.20E-02 4.31E-02 4.26E-02 5.13E-02 3.73E-02 5.48E-02 3.23E-02 4.49E-02 3.91E-02 4.18E-02 4.38E-02 4.64E-02 5.05E-02 4.85E-02 5.17E-02 3.03E-02 3.62E-02 4.53E-02 4.64E-02 4.51 E-02 4.85E-02 4.96E-02 5.26E-02 3.99E-02 5.33E-02 6.46E-02 6.34E-02 6.09E-02 6.44E-02 6.90E-02 7.28E-02 5.86E-02 3.51E-02 3.99E-02 4.04E-02 3.87E-02 4.18E-02 4.94E-02 5.65E-02 3.23E-02 4.69E-02 4.98E-02 5.71 E-02 5.50E-02 5.03E-02 5.65E-02 5.80E-02 3.96E-02 5.15E-02 5.45E-02 6.38E-02 5.46E-02 6.11E-02 6.42E-02 7.52E-02 4.90E-02 2.52E-02 3.05E-02 2.78E-02 2.82E-02 3.65E-02 3.45E-02 4.16E-02 3.14E-02 3.83E-02 4.25E-02 4.20E-02 4.44E-02 5.99E-02 5.05E-02 4.97E-02 3.27E-02 3.27E-02 2.76E-02 3.40E-02 3.22E-02 4.45E-02 3.44E-02 3.81 E-02 4.07E-02 2.96E-02 3.19E-02 3.52E-02 3.54E-02 5.74E-02 3.62E-02 3.58E-02 4.57E-02 3.26E-02 2.44E-02 2.98E-02 3.32E-02 5.84E-02 3.77E-02 3.45E-02 3.14E-02 4.09E-02 3.69E-02 4.74E-02 5.34E-02 9.92E-02 5.45E-02 5.63E-02 5.42E-02 3.38E-02 4.29E-02 4.38E-02 4.32E-02 9.55E-02 4.73E-02 4.31E-02 4.77E-02 2.55E-02 3.36E-02 3.36E-02 3.65E-02 4.35E-02 3.80E-02 4.05E-02 4.29E-02 2.68E-02 3.90E-02 3.20E-02 6.89E-02 5.01E-02 4.1OE-02 4.08E-02 5.01 E-02 2.61E-02 3.22E-02 3.67E-02 4.15E-02 4.61E-02 3.82E-02 5.31E-02 4.65E-02 3.05E-02 3.43E-02 3.49E-02 3.60E-02 5.65E-02 4.23E-02 4.24E-02 3.66E-02 2.41E-02 3.12E-02 2.11E-02 2.69E-02 3.54E-02 2.72E-02 2.61E-02 2.99E-02 2.03E-02 2.34E-02 2.32E-02 2.35E-02 3.57E-02 1.85E-02 2.46E-02 2.86E-02 3.40E-02 2.72E-02 3.26E-02 3.17E-02 5.14E-02 3.34E-02 3.94E-02 3.93E-02 3.04E-02 3.95E-02 3.15E-02 3.27E-02 4.81 E-02 3.88E-02 4.45E-02 3.43E-02 2.67E-02 3.54E-02 3.61E-02 3.18E-02 5.11E-02 4.12E-02 4.41E-02 3.94E-02 3.72E-02 3.16E-02 3.54E-02 4.38E-02 4.61E-02 3.77E-02 4.34E-02 4.26E-02 3.58E-02 4.57E-02 3.1OE-02 3.29E-02 5.73E-02 4.28E-02 5.24E-02 5.09E-02 2.53E-02 3.30E-02 2.82E-02 2.99E-02 3.83E-02 2.88E-02 4.04E-02 3.62E-02 3.63E-02 4.81E-02 4.05E-02 3.65E-02 6.72E-02 4.46E-02 4.91E-02 5.11E-02 3.65E-02 5.21E-02 5.75E-02 4.56E-02 7.03E-02 4.79E-02 5.63E-02 5.15E-02 4.OOE-02 4.27E-02 3.59E-02 3.73E-02 5.36E-02 3.97E-02 4.63E-02 4.73E-02 3.02E-02 3.92E-02 3.67E-02 4.01 E-02 6.29E-02 4.04E-02 5.51 E-02 4.85E-02 4.11E-02 3.65E-02 4.26E-02 3.79E-02 4.91E-02 3.49E-02 4.21E-02 4.12E-02 3.58E-02 3.86E-02 3.53E-02 3.54E-02 4.54E-02 2.75E-02 4.40E-02 4.35E-02 2.41E-02 2.69E-02 2.83E-02 3.05E-02 3.72E-02 2.29E-02 2.93E-02 3.40E-02 3.OOE-02 3.17E-02 2.84E-02 2.48E-02 3.62E-02 2.17E-02 2.32E-02 2.92E-02 3.73E-02 3.31 E-02 2.96E-02 3.02E-02 3.97E-02 3.88E-02 3.23E-02 2.50E-02 6.10E-02 4.34E-02 4.41E-02 5.56E-02 6.90E-02 5.11E-02 4.82E-02 4.93E-02 3.78E-02 2.67E-02 3.07E-02 5.18E-02 4.74E-02 3.82E-02 4.12E-02 3.29E-02 4.10E-02 3.07E-02 2.01E-02 3.91E-02 4.96E-02 2.75E-02 3.85E-02 3.36E-02 8.92E-02 4.67E-02 3.76E-02 7.44E-02 8.OOE-02 6.82E-02 5.52E-02 5.81E-02 1.34E-01 7.14E-02 6.98E-02 9.69E-02 1.31E-01 8.05E-02 9.57E-02 7.89E-02 9.85E-02 4.88E-02 4.80E-02 7.19E-02 8.08E-02 5.48E-02 5.77E-02 5.24E-02 3.70E-02 3.39E-02 3.01E-02 3.64E-02 6.04E-02 3.58E-02 3.15E-02 2.76E-02 4.59E-02 4.12E-02 3.81E-02 6.07E-02 7.19E-02 4.05E-02 4.87E-02 5.05E-02 4.24E-02 4.24E-02 4.01 E-02 4.71 E-02 6.52E-02 5.54E-02 4.66E-02 4.23E-02 3.90E-02 3.96E-02 4.03E-02 4.72E-02 6.87E-02 3.78E-02 3.91E-02 3.91E-02 5.61E-02 5.1OE-02 4.53E-02 6.67E-02 9.36E-02 5.31E-02 5.04E-02 4.60E-02 6.20E-02 4.82E-02 4.41E-02 7.21E-02 9.09E-02 6.15E-02 5.26E-02 5.96E-02 5.77E-02 4.22E-02 3.74E-02 5.73E-02 7.52E-02 4.54E-02 4.25E-02 3.18E-02 3.79E-02 2.70E-02 2.85E-02 4.21 E-02 6.90E-02 2.97E-02 4.22E-02 3.34E-02 Reqiuired t LLD 1.00E-02 18

Graph 1 -- 2014 Environmental Air Sample Gross Beta Results - Maximum and Minumumi 1.40E-01 1.20E-01 1.OOE-O1 E

c38.OOE-02 [iiimumj iMiiumI S600OE-02 2.OOE.02 O.OOE+00 1 5 9 13 17 21 25 29 33 37 41 45 49 Weekly Data Points 19

Table 5 -- 2014 Environmental Air Sample Iodine-131 Results (Units of pCi/m3)

A-8 A-7 A-5 A-6 A-4 A-3 A-1 A-2 NW-1.0 1 ~0.95 S SSW-5.2 SW-12.3 SSE-4.5 E-3.5 N-1.45 1 N-9.4 Control Control

<1.43E-02 <1.21E-02 <1.58E-02 <2.78E-02 <1.39E-02 <1.32E-02 <1.60E-02 <1.51 E-02

<1.81E-02 <2.01E-02 <1.62E-02 <1.81E-02 <1.50E-02 <1.42E-02 <1.80E-02 <1.22E-02

<3.93E-02 <3.59E-02 <1.57E-02 <2.96E-02 <2.64E-02 <2.45E-02 <3.07E-02 <3.65E-02

<2.39E-02 <3.51 E-02 <2.46E-02 <4.49E-02 <3.38E-02 <3.29E-02 <1.96E-02 <4.07E-02

<1.88E-02 <2.50E-02 <2.71 E-02 <6.63E-02 <2.21 E-02 <2.99E-02 <2.77E-02 <4.94E-02

<2.44E-02 <3.31 E-02 <3.59E-02 <3.57E-02 <3.30E-02 <2.29E-02 <2.75E-02 <2.70E-02

<1.34E-02 <1.63E-02 <1.45E-02 <1.77E-02 <1.36E-02 <1.03E-02 <1.01 E-02 <1.12E-02

<4.25E-02 <3.28E-02 <2.68E-02 <3.81E-02 <4.33E-02 <4.14E-02 <5.48E-02 <3.11E-02

<1.77E-02 <4.58E-02 <5.52E-02 <3.66E-02 <3.18E-02 <2.63E-02 <2.48E-02 <2.60E-02

<1.39E-02 <1.96E-02 <2.44E-02 <3.73E-02 <1.17E-02 <3.79E-02 <2.99E-02 <2.83E-02

<5.71E-02 <3.90E-02 <2.13E-02 <1.71E-02 <2.67E-02 <2.36E-02 <3.32E-02 <2.74E-02

<3.41 E-02 <6.48E-02 <3.23E-02 <2.85E-02 <2.78E-02 <4.63E-02 <2.30E-02 <3.93E-02

<3.65E-02 <2.60E-02 <2.02E-02 <2.52E-02 <1.49E-02 <3.34E-02 <3.30E-02 <2.09E-02

<1.79E-02 <1.54E-02 <1.40E-02 <1.26E-02 <1.42E-02 <1.49E-02 <1.59E-02 <1.83E-02

<4.32E-02 <4.11E-02 <3.00E-02 <2.58E-02 <2.69E-02 <3.13E-02 <4.21E-02 <2.86E-02

<4.03E-02 <2.83E-02 <2.74E-02 <3.48E-02 <1.77E-02 <1.86E-02 <2.04E-02 <5.28E-02

<2.27E-02 <3.15E-02 <2.76E-02 <3.28E-02 <3.71E-02 <2.82E-02 <4.01E-02 <2.06E-02

<2.41E-02 <4.66E-02 <1.58E-02 <3.70E-02 <3.22E-02 <3.01E-02 <2.09E-02 <1.99E-02

<1.58E-02 <1.33E-02 <1.23E-02 <1.52E-02 <1.60E-02 <1.53E-02 <1.39E-02 <2.35E-02

<5.47E-02 <3.OOE-02 <2.83E-02 <3.38E-02 <4.19E-02 <3.67E-02 <3.63E-02 <3.98E-02

<1.08E-02 <1.76E-02 <1.76E-02 <1.46E-02 <1.40E-02 <3.18E-02 <2.33E-02 <3.29E-02

<5.89E-02 <4.98E-02 <3.65E-02 <3.50E-02 <3.84E-02 <3.71 E-02 <4.62E-02 <3.78E-02

<3.42E-02 <1.86E-02 <4.36E-02 <2.83E-02 <3.48E-02 <3.49E-02 <2.53E-02 <2.20E-02

<1.29E-02 <4.03E-02 <3.40E-02 <2.96E-02 <2.67E-02 <3.27E-02 <4.42E-02 <2.44E-02

<1.97E-02 <1.80E-02 <3.59E-02 <2.32E-02 <2.01 E-02 <2.51 E-02 <2.07E-02 <2.01 E-02

<2.97E-02 <1.07E-02 <2.49E-02 <1.91E-02 <1.65E-02 <2.16E-02 <1.99E-02 <1.66E-02

<3.08E-02 <2.94E-02 <3.50E-02 <1.32E-02 <3.26E-02 <3.45E-02 <3.84E-02 <4.09E-02

<2.1 OE-02 <2.90E-02 <2.03E-02 <2.19E-02 <2.15E-02 <1.86E-02 <1.82E-02 <2.01 E-02

<5.31E-02 <2.24E-02 <2.66E-02 <3.53E-02 <1.93E-02 <3.12E-02 <2.72E-02 <1.71E-02

<5.06E-02 <4.57E-02 <4.47E-02 <3.64E-02 <3.21E-02 <3.28E-02 <4.40E-02 <3.44E-02

<3.43E-02 <2.17E-02 <2.76E-02 <2.90E-02 <2.94E-02 <5.94E-02 <2.47E-02 <4.52E-02

<1.95E-02 <2.60E-02 <3.84E-02 <2.89E-02 <4.82E-02 <2.10E-02 <2.63E-02 <3.43E-02

<2.37E-02 <2.69E-02 <2.54E-02 <2.69E-02 <2.79E-02 <3.16E-02 <1.94E-02 <2.84E-02

<2.55E-02 <2.88E-02 <4.03E-02 <4.19E-02 <4.OOE-02 <4.88E-02 <3.64E-02 <3.35E-02

<2.88E-02 <2.63E-02 <3.73E-02 <3.63E-02 <2.43E-02 <2.37E-02 <1.38E-02 <1.86E-02

<3.33E-02 <2.28E-02 <3.32E-02 <2.65E-02 <2.54E-02 <3.13E-02 <3.13E-02 <2.70E-02

<2.50E-02 <2.41E-02 <3.35E-02 <1.65E-02 <2.24E-02 <3.12E-02 <2.06E-02 <4.30E-02

<1.36E-02 <1.60E-02 <1.96E-02 <1.40E-02 <1.26E-02 <9.03E-03 <1.46E-02 <1.27E-02

<1.88E-02 <2.46E-02 <1.79E-02 <3.99E-02 <1.59E-02 <4.26E-02 <4.04E-02 <6.59E-02

<1.74E-02 <1.20E-02 <2.27E-02 <1.72E-02 <1.53E-02 <1.60E-02 <2.01 E-02 <1.16E-02

<2.68E-02 <1.81E-02 <2.32E-02 <2.1OE-02 <2.18E-02 <1.89E-02 <2.74E-02 <1.99E-02

<2.34E-02 <3.37E-02 <3.47E-02 <2.43E-02 <3.32E-02 <3.49E-02 <2.03E-02 <3.51 E-02

<4.63E-02 <4.56E-02 <3.97E-02 <4.38E-02 <4.53E-02 <4.04E-02 <4.57E-02 <3.65E-02

<2.33E-02 <3.77E-02 <4.80E-02 <3.04E-02 <3.02E-02 <2.82E-02 <3.29E-02 <3.36E-02

<2.81 E-02 <3.52E-02 <5.14E-02 <2.38E-02 <4.47E-02 <2.75E-02 <4.30E-02 <4.61 E-02

<3.62E-02 <1.96E-02 <1.80E-02 <2.92E-02 <3.17E-02 <2.86E-02 <2.68E-02 <2.14E-02

<3.87E-02 <4.66E-02 <2.56E-02 <4.69E-02 <2.34E-02 <5.58E-02 <4.60E-02 <4.04E-02

<2.63E-02 <3.47E-02 <2.70E-02 <1.48E-02 <2.63E-02 <1.93E-02 <4.06E-02 <2.47E-02

<5.59E-02 <3.64E-02 <5.21E-02 <3.39E-02 <4.82E-02 <4.09E-02 <3.76E-02 <4.22E-02

<5.06E-02 <3.73E-02 <3.63E-02 <3.14E-02 <5.12E-02 <5.OOE-02 <5.55E-02 <2.52E-02

<2.40E-02 <3.18E-02 <3.34E-02 <1.88E-02 <5.96E-02 <3.67E-02 <2.81E-02 <2.85E-02

<4.02E-02 <3.15E-02 <4.96E-02 <3.62E-02 <3.57E-02 <8.91E-03 <6.07E-02 <4.43E-02 20

Table 6 - 2014 Environmental Air Particulate Composite Gamma Isotopic Results (Units of pCi/m3)

A-8 A-7 A-5 A-6 A-4 A-3 A-i A-2 Location NW-1.0 SWIwSW-O.95 SSW-1.2 SW-12.3 SSE-4.5 E-3.5 N-1.45 N-9.4 Nuclides Control Control Ba-140 <1.01E-01 <1.26E-01 <1.35E-01 <7.94E-02 <2.02E-01 <1.11E-01 <1.12E-01 <1.37E-01 Be-7 1.27E-01 1.83E-01 1.84E-01 .1.64E-01 1.82E-01 1.95E-01 1.55E-01 1.41E-01 Co-57 <4.65E-04 <4.03E-04 <3.74E-04 <4.38E-04 <6.18E-04 <6.56E-04 <3.90E-04 <5.86E-04 Co-58 <1.65E-03 <1.41E-03 <1.59E-03 <1.28E-03 <1.71E-03 <2.73E-03 <1.34E-03 <1.61E-03 Composite Dates Co-60 <6.60E-04 <8.OOE-04 <1.01 E-03 <1.02E-03 <1.75E-03 <1.42E-03 <1.20E-03 <6.48E-04 1ST QTR Cs-1 34 <8.80E-04 <8.74E-04 <8.50E-04 <8.02E-04 <1.63E-03 <1.27E-03 <9.95E-04 <9.47E-04 Required LLD 5.OE-2 12/31113 - 3125/14 Cs-137 <8.54E-04 <7.30E-04 <7.82E-04 <5.31E-04 <1.42E-03 <1.17E-03 <7.57E-04 <1.03E-03 Required LLD 6.OE-2 Fe-59 <5.55E-03 <4.95E-03 <4.88E-03 <5.46E-03 <1.39E-02 <6.31E-03 <7.03E-03 <5.67E-03 K-40 <8.11 E-03 <4.98E-03 <7.25E-03 <4.73E-03 <2.59E-02 <9.79E-03 <1.69E-02 <1.89E-02 La-140 <1.01E-01 <1.26E-01 <1.35E-01 <7.94E-02 <2.02E-01 <1.11E-01 <1.12E-01 <1.37E-01 Mn-54 <8.79E-04 <9.52E-04 <1.10E-03 <1.08E-03 <1.45E-03 <1.37E-03 <9.46E-04 <8.84E-04 Nb-95 <1.29E-03 <1.94E-03 <1.27E-03 <1.88E-03 <4.14E-03 <2.47E-03 <2.OOE-03 <1.88E-03 Zn-65 <2.11E-03 <2.35E-03 <1.78E-03 <2.10E-03 <4.19E-03 <4.22E-03 <2.43E-03 <1.44E-03 Zr-95 <3.78E-03 <2.81 E-03 <2.OOE-03 <3.20E-03 <4.70E-03 <6.67E-03 <3.28E-03 <2.95E-03 Ba-140 <1.55E-01 <2.88E-01 <1.99E-01 <1.96E-01 <1.74E-01 <2.57E-01 <2.49E-01 <2.55E-01 Be-7 1.28E-01 1.66E-01 7.64E-02 1.64E-01 2.86E-01 1.46E-01 1.02E-01 1.70E-01 Co-57 <4.92E-04 <8.07E-04 <6.81 E-04 <6.31E-04 <5.14E-04 <8.08E-04 <6.57E-04 <5.50E-04 Co-58 <1.67E-03 <2,85E-03 <3.04E-03 <1.70E-03 <1.65E-03 <3.54E-03 <2.49E-03 <2.63E-03 Composite Dates Co-60 <1.02E-03 <1.91 E-03 <1.24E-03 <4.78E-04 <1.01 E-03 <1.82E-03 <1.36E-03 <1.30E-03 2ND QTR CS-134 <9.11E-04 <1.60E-03 <1.72E-03 <1.28E-03 <8.25E-04 <1.58E-03 <1.32E-03 <1.06E-03 Required LLD 5.OE-2 3126/14 - 6/24/14 Cs-137 <7.45E-04 <1.23E-03 <1.24E-03 <7.31E-04 <6,92E-04 <1.48E-03 <1.17E-03 <9.76E-04 Required LLD 6.OE-2 Fe-59 <8.69E-03 <1.46E-02 <7.51E-03 <4.20E-03 <6.07E-03 <1.32E-02 <1.15E-02 <6.68E-03 K-40 <1.70E-02 <1.72E-02 <2.32E-02 <1.33E-02 <9.48E-03 <9.93E-03 <2.11 E-02 <9.42E-03 La-140 <1.55E-01 <2.88E-01 <1.99E-01 <1.96E-01 <1.74E-01 <2.57E-01 <2.49E-01 <2.55E-01 Mn-54 <9.01E-04 <1.98E-03 <1.75E-03 <9.21E-04 <7.80E-04 <1.89E-03 <1.15E-03 <8.02E-04 Nb-95 <2.01E-03 <4.14E-03 <2.37E-03 <2.41E-03 <1.25E-03 <2.87E-03 <3.64E-03 <2.47E-03 Zn-65 <2.97E-03 <4.05E-03 <3.51 E-03 <3.06E-03 <2.42E-03 <3.24E-03 <2.90E-03 <2.43E-03 Zr-95 <2.11E-03 <5.25E-03 <3.83E-03 <3.28E-03 <3.31E-03 <5.80E-03 <7.16E-03 <3.92E-03 21

Table 6 - 2014 Environmental Air Particulate Composite Gamma Isotopic Results (continued)

(Units of pCi/m3)

A-8 A-7 A-5 A-6 A-4 A-3 A-1 A-2 Location NW-1.0 sw/wsw-0.95 SSW-1.2 SW-12.3 SSE-4.5 E-3.5 N-1.45 N-9.4 Nuclides Control Control Ba-140 <1.58E-01 <1.68E-01 <1.01E-01 <1.74E-01 <2.08E-01 <1.22E-01 <1.12E-01 <1.51E-01 Be-7 1.62E-01 1.53E-01 1.13E-01 1.14E-01 1.94E-01 1.37E-01 1.46E-01 1.54E-01 Co-57 <4.60E-04 <4.34E-04 <3.27E-04 <3.66E-04 <3.62E-04 <3.71E-04 <3.1OE-04 <3.74E-04 Co-58 <1.78E-03 <1.70E-03 <1.28E-03 <9.38E-04 <1.39E-03 <1.26E-03 <1.22E-03 <1.27E-03 Composite Dates Co-60 <5.99E-04 <7.19E-04 <5.67E-04 <6.21 E-04 <6.48E-04 <6.42E-04 <5.92E-04 <5.45E-04 3RD QTR Cs-1 34 <6.03E-04 <7.52E-04 <5.31 E-04 <5.60E-04 <6.90E-04 <5.43E-04 <4.96E-04 <7.07E-04 Required LLD 5.OE-2 6125114-9/30114 Cs-137 <5.71E-04 <7.40E-04 <5.33E-04 <4.47E-04 <5.71E-04 <4.90E-04 <5.89E-04 <6.20E-04 Required LLD 6.OE-2 Fe-59 <4.52E-03 <4.63E-03 <5.85E-03 <4.06E-03 <4.44E-03 <3.14E-03 <3.91E-03 <4.12E-03 K-40 <4.42E-03 <7.64E-03 1.07E-02 <6.49E-03 9.94E-03 <5.21 E-03 8.69E-03 9.39E-03 La-140 <1.58E-01 <1.68E-01 <1.01E-01 <1.74E-01 <2.08E-01 <1.22E-01 <1.12E-01 <1.51E-01 Mn-54 <7.73E-04 <9.55E-04 <4.97E-04 <6.55E-04 <5.40E-04 <5.79E-04 <5.56E-04 <4.95E-04 Nb-95 <1.92E-03 <1.86E-03 <1.47E-03 <1.46E-03 <167E-03 <1.41E-03 <1.61E-03 <1.56E-03 Zn-65 <2.OOE-03 <1.43E-03 <1.02E-03 <1.47E-03 <1.49E-03 <1.38E-03 <6.09E-04 <1.49E-03 Zr-95 <2.80E-03 <2,79E-03 <1.93E-03 <2.17E-03 <3.08E-03 <2.64E-03 <2.01E-03 <2.51E-03 Ba-140 <1.93E-01 <1.30E-01 <1.26E-01 <1.23E-01 <1.04E-01 <1.52E-01 <2.02E-01 <1.29E-01 Be-7 1.62E-01 1.15E-01 1.08E-01 1.45E-01 1.91E-01 1.25E-01 1.12E-01 1.20E-01 Co-57 <5.48E-04 <4.17E-04 <4.72E-04 <4.39E-04 <4.92E-04 <5.91E-04 <4.46E-04 <4.44E-04 Co-58 <1.14E-03 <1.43E-03 <1.36E-03 <1.34E-03 <1.42E-03 <1.66E-03 <1.97E-03 <1.27E-03 Composite Dates Co-60 <6.77E-04 <7.30E-04 <8.35E-04 <8.98E-04 <8.43E-04 <8.09E-04 <7.75E-04 <7.81E-04 4TH QTR Cs-134 <9.55E-04 <7.44E-04 <9.66E-04 <8.67E-04 ,<5.82E-04 <1.12E-03 <1.34E-03 <9.61E-04 Required LLD 5.OE-2 10101114-12/30114 Cs-1 37 <8.98E-04 <8.09E-04 <7.36E-04 <6.76E-04 <6.32E-04 <8.63E-04 <1.12E-03 <7.11E-04 Required LLD 6.OE-2 Fe-59 <5.27E-03 <2.48E-03 <3.12E-03 <4.93E-03 <4.74E-03 <5.13E-03 <6.38E-03 <4.24E-03 K-40 <1.57E-02 <O.OOE+00 <4.46E-03 <1.72E-02 <1.26E-02 <1.70E-02 <1.81E-02 <1.39E-02 La-140 <6.52E-02 <6.51E-02 <O.OOE+00 <5.12E-02 <2.50E-02 <6.55E-02 <9.34E-02 <4.63E-02 Mn-54 <8.24E-04 <6.79E-04 <6.84E-04 <7.11E-04 <6.93E-04 <1.15E-03 <1.24E-03 <8.72E-04 Nb-95 <1.79E-03 <1.76E-03 <1.42E-03 <1.18E-03 <1.45E-03 <1.40E-03 <1.89E-03 <1.37E-03 Zn-65 <2.76E-03 <2.04E-03 <1.53E-03 <1.56E-03 <1.67E-03 <1.84E-03 <2.19E-03 <2.03E-03 Zr-95 <2.72E-03 <3.35E-03 <2.42E-03 <2.44E-03 <2.03E-03 <2.80E-03 <3.52E-03 <2.40E-03 22

D. Surface Water Program Surface water monitoring stations are found at four locations as detailed in Table 1 - Comanche Peak Nuclear Power Plant Radiological Environmental Monitoring Program. Location N- 1.5 provides samples representative of Squaw Creek reservoir surface water at a location beyond significant influence of the plant discharge.

Location ESE-1.4 provides samples representative of discharges from Squaw Creek reservoir downstream to Squaw Creek and to Lake Granbury via an installed return line. [NOTE: The installedreturnline to Lake Granbury has never been used to send water back to Lake Granbury.]

Location NE-7.4 provides samples of Lake Granbury surface water downstream of the discharge from the return line from Squaw Creek reservoir. A control sample is obtained from the Brazos River, upstream of Lake Granbury at location N-19.3. Surface water samples from Squaw Creek reservoir locations were collected weekly and composited for monthly gamma isotopic analysis. Samples from Lake Granbury locations were collected monthly and analyzed by gamma spectrometry. All surface water samples were also composited quarterly by location for tritium analysis.

For the year 2014 all surface water samples were collected as required. Table 7 -- 2014 Environmental Surface Water Tritium and Gamma Isotopic Results contains the reported values. Forty-eight samples were analyzed by gamma spectrometry. All results for the required radionuclides were reported as less than the required LLDs. Sixteen quarterly composited samples were analyzed for tritium.

The results of the reported tritium values for Squaw Creek reservoir were in line with expected concentrations. The tritium values ranged from a high of 2.02E+04 pCi/l to a low of 1.63E+04 pCi/l. The results from Lake Granbury were all less than the required LLDs as expected. The tritium concentration reported in Squaw Creek is well below the action level of 3.OE+4 pCi/l and is following the expected concentration variations based on fuel cycles, power histories and reservoir makeup due to rain and pump transfers from Lake Granbury. Graph 2 - 2014 Environmental Surface Water Tritium Results indicates the current results and the short-term trend of the tritium concentration in Squaw Creek reservoir. Graph 3 - Squaw Creek Maximum Tritium Values trends the reservoir tritium concentration since it was first detected in 1990 after Unit 1 startup and is located on page 29. This long-term graph also indicates that a slow steady increase in the 23

concentration of Tritium. Squaw Creek reservoir tritium is a direct product of the operation of CPNPP and is the only consistent indicator detectable in the environment surrounding Comanche Peak.

There should not be any significant changes in the tritium concentrations in the near future and no action levels are anticipated. A review of pre-operational and operational data indicated the 2014 results were both expected and consistent with previous data and that no anomalies had occurred.

During the year 2014, there were no exceptions to the Surface Water Program.

24

Table 7 - 2014 Environmental Surface Water Tritium and Gamma Isotopic Results (Units of pCi/I) 25

Graph 2-- 2014 Environmental Surface Water Tritium Results 25000 20000 -

15000 --r -

  • 10000 -

5000 0

Mar-14 Jun-14 Sep-14 Dec-14 Monthly/Composite Sample Dates 26

E. Surface Drinking Water Program Surface drinking water was collected at two monitoring locations.

Table 1 -- Comanche Peak Nuclear Power Plant Radiological Environmental Monitoring Program for 2014 details the location and types of analysis required. Samples of water from Squaw Creek reservoir were collected at the monitoring location NNW-0.1 and analyzed at detection levels required for drinking water standards even though the water is not allowed to be used as potable water. There is not a surface water drinking source within a mile of CPNPP. Monitoring location N-9.9 was used as a surface drinking water location based on the proximity of the City of Granbury intake to the Granbury potable water system. All surface drinking water samples were collected weekly and then composited for Iodine- 131 analysis, gamma isotopic analysis, and gross beta analysis on a monthly basis. Tritium analysis was performed on a quarterly basis.

For the year 2014, all samples were analyzed for gamma emitting radionuclides. The results are reported in Table 8 - Environmental Surface Drinking Water Tritium, Gross Beta and Gamma Isotopic Results. There were no gamma emitting radionuclides identified in any of the twenty-four composite samples. Tritium reported in Squaw Creek reservoir ranged from 2.OOE+04 pCi/I to 1.43E+04 pCi/I and averaged 1.67E+04 pCi/I. Tritium reported from all Lake Granbury water samples indicated less than the required LLD as expected. Graph 4 - 2014 Environmental Surface Drinking Water Tritium Results trends the results reported for the *year2014.

Gross Beta results at the indicator location NNW-0. 1 ranged from

<2.48+01 pCi/I to 1.23E+01 pCi/I with an average of 1.85+01 pCi/I. Gross Beta results at the control location N-9.9 ranged from

<3.69E+00 pCi/I to 1.04E+01 pCi/I with an average of 8.63E+00 pCi/I. Graph 5 - 2014 Environmental Surface Drinking Water Gross Beta Results trends the gross beta results for the two monitor locations and indicates no influence from Comanche Peak in the levels detected in the two different bodies of water. The gross beta results received are within values previously reported and there is no reportable level for gross beta so no action is required at this time.

During the year 2014, there was one exception to the Surface Drinking Water Program.

27

CR-2014-013378- Quarterly Squaw Creek Lake water Tritium results from Gel Laboratories indicated an observable decrease from the 2 nd quarter to the 3 rd and 4 th quarters of 2014. Contacted Gel Laboratories to re-analysis the 2 n quarter SW-6, H-3 on 09-30-14. The new results are posted below. Results also attached to CR. The SW-6, H-3 results will continue to be monitored for any changes by the normal routine station procedure process.

28

Table 8 - 2014 Environmental Surface Drinking Water Tritium, Gross Beta and Gamma Isotopic Results (Units of pCiIl)

____ SW-6 _____ Gross Nuclides ____

Date location H-3 Beta 1-131 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 La-140 Mn-54 Nb-95 Zn-65 Zr-95 NNW-0.1 _____<1.41E+01 <1.05E+01 <1.10E+01 <4.90E+00 <3.86E+00 <5.24E+00 <5.06E+00 <7.82E+00 <1.10E+01 <5.05E+00 <5.08E+00 <9.18E+00 <9.94E+00 NNW-0.1 _____ 2.15E+01 <1.22E+01 <7.54E+00 <2.98E+00 <3.20E+00 <3.73E+00 <3.26E+00 <7.29E+00 <7.54E+00 <3.19E+00 <3.49E+00 <6.14E+00 <7.16E+00 NNW-O.1 1.67E+04 <2.08E+01 <1.30E+01 <1.24E+01 <4.20E+00 <3.49E+00 <3.81 E+00 <3.35E+00 <6.98E+OO <1.24E+01 <3.73E+00 <3.88E+00 <7.27E+00 <5.34E+00 NNW-O.1 _____ 2.48E+01 <9.02E-01 <5.18E+00 <1.93E+00 <1.87E+00 <1.85E+00 <1.67E+00 <4.49E+00 <5.18E+00 <1.63E+00 <1.95E+00 <3.25E+00 <3.38E+OO-NNW-0.1 _____ 1.69E+01 <7.46E+00 <4.93E+00 <1.62E+00 <1.49E+00 <c1.55E+00 <1.56E+00 <3.62E+00 <4.93E+00 <1.47E+00 <1.67E+00 <3.24E+00 <3.OOE+00 NNW-0.1 2.OOE+04 2.21E+01 <9.08E-01 <4.06E+00 <1.50E+00 <1.48E+00 <1.56E+00 <1.59E+00 <3.35E+00 <4.06E+00 <1.39E+00 <c1.69E+00 <2.95E+00 <2.63E+00 NNW-0.1 _____<1.89E+01 <1.29E+00 <6.35E+00 <1.65E+00 <1.54E+00 <1.51E+00 <1.52E+00 <3.86E+00 <6.35E+00 <1.43E+00 <1.83E+00 <3.09E+00 <2.88E+00 NNW-O.1 <2.09E+01 <8.29E-01 <5.40E+00 <1.71E+00 <1.50E+00 <1.54E+00 <1.60E+00 <3.67E+00 <5.40E+00 <1.48E+00 <1.69E+00 <3.09E+00 <3.07E+00 NNW-O.1 1.43E+04 1.23E+0i <9.03E-01 <4.61 E+00 <1.58E+00 <1.52E+00 <1.62E+00 <1.44E+00 <3.53E+00 <4.61 E+00 <1.48E+00 <1.66E+00 <3.01 E+00 <2.75E+00 NNW-0.1 <1.77E+01 <c8.70E-01 <6.22E+00 <1.76E+00 <1.68E+00 <1.61E+00 <1l.76E+00 <3.64E+00 <6.22E+00 <1.58E+00 <1.77E+00 <3.22E+00 <3.25E+00 NNW-O .1 1.58E+01 <8.57E-01 <7.82E+00 <2.50E+00 <2.31E+00 <2.39E+00 <2.22E+00 <5.19E+00 <7.82E+00 <2.04E+00 <c2.29E+00 <4.16E+00 <4.13E+00 NNW-O .1 1.57E+04 <1.32E+01 <8.63E-01 <6.65E+00 <2.16E+00 <1.86E+00 <1.99E'-00 <1.83E+00 <5.23E+OO <6.65E+00 <1.74E+00 <2.15E+00 <3.76E+00 <3.89E+00 SW-2 N-9.9 <3.69E+00 <1.24E+01 <9.82E+00 <4.85E+00 <5.48E+00 <5.29E+00 <5.92E+00 <9.27E+00 <9.82E+00 <4.94E+00 <5.08E+00 <1.10E+01 <7.40E+GO N-9.9 <4.94E+00 <1.89E+01 <7.68E+00 <4.94E+00 <4.21 E+00 <5.05E+00 <4.02E+OO <7.95E+00 <7.68E+00 <3.76E+00 <4.20E+00 <8.48E+00 <7.27E+O0 N-9.9 <3.88E+02 <7.03E+00 <1.30E+01 <7.98E+00 <2.95E+00 <3.75E+00 <3.03E+00 <3.48E+00 <8.56E+00 <7.98E+00 <2.98E+00 <3.38E+00 <6.17E+00 <6.65E+00 N-9.9 4.53E+00 <8.41E-01 <3.77E+00 <1.44E+00 <1.52E+00 <1.56E+00 <1.31E+00 <3.01 E+00 <3.77E+00 <1.39E+00 <1.61E+00 <2.77E+:O7OZ2.51 E+0O N-9.9 6.29E-400 <1.05E+01 <6.53E+00 <2.27E+00 <2.04E+00 <2.42E+00 <2.1 1E+00 <5.22E+00 <6.53E+00 <2.1 1E+00 <2.51E+00 <4.21E+00 <4.48E+00 N-9.9 <4.24E+02 8.84E+00O <9.15E-01 <4.47E+00 <1.55E+00 <1.43E+OO <1.61E+00 <1.62E+00O <3.47E+00 <4.47E+00 <1.50E+00 <1.69E+00O <3.07E+00 <3.01 E+00 N-9.9 4.33E+00 <1.IOE+OO <7.27E+00 <1.88E+00 <1 .58E+00 <1 .74E+00 <1 .69E+00 <4.40E+00 <7'.27E+00 <1 .57E+00 <1 .88E+00 <3.39E+00 <3.22E+00 N-9.9 <5.43E+00 <7.89E-01 <4.81 E+00 <147E+OO <1.56E+00 <1.62E+00 <1 .51 E+00 <3.50E+00 <4.81E+00O <1.39E+00 <1.84E+00 <3.17E+00 <3.07E+OO-N-9.9 <5.64E+02 1.04E+01 <8.56E-01 <4.32E+00 <1.50E+00 <1.43E+00- <1.47E+00 <1.52E+00 <3.18E+00 <4.32E+00 <1.32_E+00 <1.58E+00 <2.68E+00 <2.65E+00 N-9.9 <5.86E+00 <8.38E-01 <4.91 E+00 <1 .60E+00 <1 .54E+00 <1.77E+00 <1 .52E+00 <4.03E+00 <4.91 E+00 <1 .53E+00 <1 .69E+00 <3.27E+00 <3.25E+00 N-9.9 <5.18E+00 <8.57E-01 <6.52E+00 <1 .81 E+00 <1.91 E+00 <1.78E+00 <1.64E+00 <4.15E+00 <6.52E+00 <1.56E+00 <1.85E+00 <3.47E+00 <3.31 E+00 N-9.9 <3.99E+02 1.02E+01 <8.50E-01 <6.1 1E+00 <1.92E+00 <1.74E+00 <2.03E+00 <1.86E+00 <4.23E+00 <6.1 1E+00 <1.66E+00 <2.12E+00 <3.45E+00 <3.62E+00 Reqird LLD's 2.OOE+03 4.00E4OO 1.OOE+00 1.50E+01 1.50E+01 1.50E+01 1.5015+01 1.8012+01 3.OOE+O1 1.50E+01 1.50E+01 1.50E+O1 3.OOE+O1 1.50E+01 RpraIs Level 2.OOE+04 None 2.OOEeOO 2.OOE+02 1.0OE+03 3.OOE4+O2 3.OOE+01 5.00E+01 4.OOE+02 2.00E402 1.OOE+03 4.OOE+02 3.OOE+02 4.OOE+02 29

Graph 3 -- Squaw Creek Maximum Tritium Values 30000 25000 o 20000 CL

'* 15000 I --*---Maximum tritium

  • ~10000 5000 0

S , Z , % . .P . r. ..

Yearly Maximum 30

Graph 4 -- 2014 Environmental Surface Drinking Water Tritium Results 2.50E+04 2.OOE+04

() 1.50E+04 C. s N-9.9 --- NNW-0.1 I,- O 1.00E+04 5.OOE+03 O.0OE+00 Mar-14 Jun-14 Sep-14 Dec-14 Composite Sample Dates 31

2014 Environmental Surface Drinking Graph 5-- 2014 Environmental Surface Drinking Water Gross Beta Results 3.OOE+01 2.50E+01 C.)

2.00E+01 4.-

0 1.50E+01 -

m- NNW-0.1 1.OOE+01 m 5.OOE+00 O.OOE+00 Monthly Data Points 32

F. Groundwater Program Table 1 - Comanche Peak Nuclear Power Plant Radiological Environmental Monitoring Program for 2014 specifies the five groundwater monitoring locations. Groundwater supplies in the site area are not affected by plant effluents and are sampled only to provide confirmation that groundwater is not affected by plant discharges. Groundwater samples were collected quarterly and analyzed for gamma isotopes and tritium at each location.

For the year 2014 a total of twenty groundwater samples were collected from the five different monitoring locations. There were no radionuclides identified in any of the samples. All required LLDs were met for each required gamma emitting radionuclide.

Tritium analysis was performed on twenty samples, all indicated less than the required LLD. Results for all the groundwater analyses are reported in Table 9 - 2014 Environmental Groundwater Tritium and Gamma Isotopic Results. These results confirm that plant discharges are having no effect on groundwater in the area surrounding Comanche Peak.

For 2014 seventeen (17) sample locations of perched groundwater were taken quarterly in accordance with STA-654, "Groundwater Protection Program". Results from these samples are included in the Annual Radioactive Effluent Release Report.

During the year 2014, there were no exceptions to the Groundwater Program.

33

Table 9 -- 2014 Environmental Groundwater Tritium and Gamma Isotopic Results (Units of pCill)

Nuclides I Location I H-3 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1 1-131 La-140 Mn-54 Nb-95 I Zn-65 Zr-95 toe GW-3 IIIIIIIIII SSE-4.6 <4.17E+02 <5.25E+00 <3.55E+00 <3.25E+00 <3.78E+00 <3.60E+00 <6.54E+00 <4.97E+00 <5.25E+00 <3.60E+00 <3.49E+00 <7.17E+00 <6.04E+00 SSE-4.6 <4.30E+02 <5.01E+00 <2.63E+00 <2.94E+00 <3.05E+00 <3.48E+00 <6.31 E+00 <6.12E+00 <5.OIE+OO <2.77E+00 <2.89E+O0 <c6.24E+0O <5.14E+O0 SSE-4.6 <5.61E+02 <3.20E+00 <1.83E+00 <2.03E+00 <2.04E+00 <1.98E+00 <3.82E+00 <3.23E+00 <3.20E+00 <1.81E+O0 <2.01 E+00 <3.69E+00 <3.18E+00 SSE-4.6 <5.54E+02 <1.08E+01 <4.69E+00 <&.63E+00 <5.25E+00 <5.11E+00 <1.03E+01 <8.29E+00 <1.08E+01 <5.47E+00 <5.70E+00 <1.08E+01 <9.06E+00 GW-5 N-1.45 <4.12E+02 <5.34E+00 <2.77E+00 <3.OOE+OO <2.85E+00 <2.89E+00 <5.71 E+00 <5.23E+00 <5.34E+00 <2.62E+00 <3.04E+O0 <3.92E+00 <4.61 E+00 N-1.45 <4.24E+02 <4.95E+00 <2.70E+00 <2.89E+00 <2.82E+00 <2.91 E+00 <5.52E+00 <5.29E+00 <4.95E-'00 <2.53E+00 <2.71 E+00 <5.31 E+00 <4.89E+00 N-1.45 <5.61E+02 <2.51 E+00 <1.60E+00 <1.59E+00 <1.79E+00 <1.69E+00 <122E+00 <2.86E+00 <2.51 E+00 <1 .40E+00 <1.67E+00 <3.14E+00 <3.05E+00O N-1.45 <5.58E+02 <6.53E+00 <5.07E+00 <5.38E+00 <4.88E+00 <5.95E+00 <1.17E+01 <1.05E+01 <6.53E+00 <3.56E+00 <5.29E+00 <1.02E+01 <8.39E+00 GW-4___ _

N-9.8 <4.14E+02 <4.50E+00 <2.66E+00 <3.49E+00 -<3.-43E+00 <2.79E+00 <5.51 E+00 <5.26E+00 <4.50E+00 <2.65E+00 <3.17E+00 <5.59E+00 <5.05E+00 N-9.8 <4.15E+02 <4.96E+00 <2.44E+00 <2.58E+00 <2.77E+00 <3.02E+00 <5.96E+00 <6.13E+00 <4.96E+00 <2.59E+00 <3.13E+00 <5.86E+00 <4,90E+00 N-9.8 <5.67E+02 <2.63E+00 <1.48E+00 <1.62E+00 <1.68E+00 <1.62E+00 <3.04E+00 <3.12E+00 <2.63E+00 <1.54E+00 <1.82E+00 <3.36E+00 <2.82E+00 N-9.8 <5.73E+02 <8.51 E+00 <5.59E+00 <4.61E+00 <5.14E+00 <5.02E+00 <1.17E+01 <7.67E+00 <8.51 E+00 <4.36E+00 <6.16E+00_ <7.02E+00 <9.02E+00 GW-1 ___________ _

W-1.2 <4.17E+02 <4.86E+00 <3.1 1E+00 <3.76E+00 <3.54E+00 <3.32E+00 <7.02E+00 <5.51 E+00 <4.86E+00 <3.08E+00 <3.42E+00 <7.37E+00 <5.40E+00 W-1.2 <4.30E+02 <4.45E+00 <2.39E+00 <2.52E+00 <2.55E+00 <2.93E+00 <4.22E+00 <5.10E+00 <4.45E+00 <2.27E+00 <2.66E+00 <5.31 E+00 <4.38E+00 W-1 .2 <5.66E+02 <2.56E+00 <1 .55E+00 <1 .68E+00 <1 .60E+00 <1 .62E+00 <3.OOE+OO <2.98E+00 <2.56E+00 <1.45E+00 <1 .45E+00 <3.30E+00 <2.58E+00 W-1.2 <5.87E+02 <8.03E+00 <3.60E+00 <4.62E+00 <4.66E+00 <4.21E+00 <9.37E+00 <6.93E+00 <8.03E+00 <3.41 E+00 <4.46E+00 c9.28E+OO <6.54E+00 GW-2___ _

-WSW-0.1 <4.07E+02 <4.10E+00 <2.77+00 <3.33E+00 <2.71 E+00 <3.26E+00 <4.81 E+00 <4.75E+00 <4. 1OE+OO <2.58E+00 <2.68E+00 <5.05E+00 <5.23E'-O0 WSW-0.1 <4.26E-+02 <5.54E+00 <3.16E+00 <3.37E+00 <3.45E+00 <3.76E+00 <5.93E+00 <4.90E+00 <5.54E+00 <3.1 5E+00 <3.18E+00 <5.68E+00 <5.53E+00

-WSW-O.1 <5.74E+02 <2.39E+00 <1.38E+00 <1.67E+00 <1.63E+00 <1.48E+00 <2.78E+00 <2.65E+00 <2.39E+00 <1.59E+00 <1.52E+00 <2.13Ei-O0 <2.69E+00

-WSW-O.1 <5.69E+02 <1.19E+01 <6.OOE+OO <5.61E+00 <5.98E+00 <6.02E+00 <1.23E+01 <1.02E+01 <1.19E+01 <5.65E+00 <6.53E+00 <1.31E+01 <1.31E+01 Required LLD's 1 3.OOE+03 1.50E+01 1.50E+01 1.50E+01 1.50E+01 1.80E+01 3.OOE+01 1.50E+01 J1.50E+01 1.50E+01 [ 1.50E+01 1 3.00E+01 1.50E+O1 Reportable Levels I 2.OOE+04 I 2.OOE+02 I 1.OOE+03 I 3.OOE+02 I3.OOE+O1 I 5.OOE+O1 I 4.OOE+02 I2.OOE+01 I 2.OOE+02 I 1.OOE+03 I 4.00E402 I 3.OOE+02 I 4.OOE+02 34

G. Sediment Program Shoreline sediments were collected at four different monitoring locations. One sample location is along the shore of Squaw Creek Reservoir, one sample location is on Squaw Creek downstream of the dam discharge and two locations are along Lake Granbury's shores. Each sample is collected on a six-month frequency and sent to the contract laboratory for analysis by gamma spectrometry.

The process of shoreline sedimentation is a complex evolution whereby potential radionuclides and stable elements may concentrate in the bottom sediment of particular bodies of water.

The concentrations are effected by such things as colloidal particles combining with chelating agents and biological action of bacteria and other benthic organisms. Monitoring of the area shorelines provides one of the first and best indicators of radionuclide deposition.

For the year 2014 results from the gamma isotopic analysis of shoreline sediments is reported in Table 10 - 2014 Environmental Sediment Gamma Isotopic Results. As expected and in agreement with previous results from both the pre-operational and operational programs, naturally occurring Potassium-40 was detected in all eight samples and Beryillum-7 was detected in one sample. All required radionuclide results were reported as less than the required LLDs. During previous years, both pre-operational and operational, positive indications occasionally had been noted for Cesium-137 and during 2014 there was one positive Cesium-137 result reported. There is not a reportable level for Cesium- 137 for Sediment. As expected, there were no results in any sediment sample that indicated any direct influence from CPNPP discharges to the local environment.

During the year 2014, there were no exceptions to the Sediment Program.

35

Table 10 - 2014 Environmental Sediment Gamma Isotopic Results (Units of pCi/kg)

___________Nucldes Ba-140 Be-7 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Zn-65 Zr-95 Date Location 01-14-14 SE-5.3 <1.63E+02 <2.37E+02 <1.91E+01 <2.38E+01 <3.97E+01 <3.62E+01 <6.59E+01 <4.39E+01 3.98E+03 <3.78E÷01 <3.07E+01 <3.64E+01 <6.62E+01 <5.42E+01 01-14-14 NNE-1.0 <2.26E+02 <4.53E+02 <4.48E+01 <5.28E+01 <5.46E+01 <6.OOE+01 <1.03E+02 <7.63E+01 3.11E+03 <7.12E+01 <4.39E+01 <5.88E+01 <1.04E+02 <9.24E+01 01-14-14 NE-7A <1.53E+02 <2.49E+02 <3.06E+01 <3.84E+01 <3.93E+01 <3.30E+01 <6.95E+01 '5.07E+01 4.04E+03 <3.76E+01 <3.59E+01 <3.95E+01 <6.59E+01 <6.04E+01 01-14-14 N-9.9 <1.53E+02 <2.77E+02 <2.55E+01 <3.34E+01 <3.94E+01 <3.38E+01 <6.24E+01 <4.96E+01 9.75E+03 <4.08E+01 <3.26E+01 <3.66E+01 <7.15E+01 <5.90E+01 07-08-14 SE-5.3 <1.18E+02 <7.64E+02 <7.07E+01 <7.66E+01 <8.94E+01 <8.43E+01 <1.75E+02 <1.25E+02 2.80E+03 <1.18E+02 <7.73E+01 <8.82E+01 <1.75E+02 <1.58E+02 07-08-14 NNE-1.0 <7.99E+01 4.18E+02 <3.26E+01 <3.73E+01 <4.49E+01 5.26E+01 <9.15E+01 <5.46E+01 3.94E+03 <7.99E+01 <3.25E+01 <3.76E+01 <6.66E+01 <6.79E+01 07-08-14 NE-7A <7.59E+01 <3.68E+02 <4.16E+01 <4.67E+01 <5.23E+01 <4.63E+01 <9.79E&01 <7.60E+01 7.59E+03 <7.59E+01 <4.30E+01 <5.40E01 01.17E+02 <7.54E+01 07-08-14 N-9.9 <7.89E+01 <4.04E+02 <5.19E+01 <4.26E+01 <5.70E+01 <5-20E+01 <1.02E+02 <9.17E+01 1.88E+03 <7.89E+01 <4.67E+01 <5.27E+01 01.07E+02 9.22E+01 Required LLD's 1.50E+02 1.80E+02 Reportable Levels None None NOTE: During previous years, both pre-operational and operational, positive indications occasionally had been noted for Cesium-137 and during 2014 there was one positive Cesium- 137 results reported.

36

H. Fish Program Fish samples were collected at two locations during the year 2014. One monitoring location is an area approximately two miles east-northeast of the site on Squaw Creek Reservoir. The second location is on Lake Granbury approximately eight miles north-northeast of the site. Fish sampling is scheduled for the months of April and October. The collected fish are frozen and shipped to the independent laboratory where the edible portions are analyzed for gamma emitting radio-nuclides.

For the year 2014, the results of the analysis performed on the collected fish samples are reported in Table 11 -- 2014 Environmental Fish Gamma Isotopic Results. Catfish and Bass samples were analyzed as indicated in the table. There were no positive results reported except for the expected Potassium-40, which is naturally occurring in all living organisms. All required radionuclide results were reported as less than the required LLDs.

As a result of the fish-sampling program, there were no anomalies noted and no indication of any influence on the surrounding environment from Comanche Peak plant discharges.

No abnormal results were reported by CPNPP or by the State of Texas.

As expected, Potassium-40 was the only positive isotope found.

CR-2014-13335 Fish are currently analyzed for gamma in accordance with the ODCM for Radiological Environmental Monitoring. An evaluation of the 2/26/2010 cooked fish sample tritium results was performed and the following was the conclusion:

According to the Regulatory Guide 1.109, "a pathway is considered significant if a conservative evaluation yields an additional dose increment equal to or more than 10 percent of the total from all pathways considered in this guide. Based on the 2013 CPNPP Annual Effluent Report, our total dose contribution to the public from liquid and gaseous effluents was 0.235 mRem and the limit for a member of the public from radioactive releases is 25 mrem. Based on the effluent data, the data from "cooked fish" and conservative assumptions made in the calculations, tritium in fish are not considered a significant dose pathway. The 10% criteria can only be exceeded when the fish is eaten raw and still does not exceed 10%

of the public exposure monitoring limit. However, due to the current public sensitivity toward tritium ingestion, Tritium in fish consumption will be included in the analyzed results reported starting in the 2015 Annual Environmental Report. Future results will be compared and trended in future REMP reports.

During the year 2014 there was one exception to the Fish Program.

CR-2014-10928- This condition report was generated when no Catfish Environmental Samples were available for collection at location NNE-8.0, F-2, Lake Granbury. Personnel at Squaw Creek Lake were able to collect the environmental monitoring catfish samples 3 weeks later for analysis by GEL Laboratory and included within this report.

37

Table 11 -2014 Environmental Fish Gamma Isotopic Results (Units of pCi/kg wet)

Nuclides Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Zn-65 Zr-95 Fish Type Date Location 04-15-14 Squaw Creek <5.13E-03 <5.74E-03 <6.80E-03 <6.73E-03 <6.47E-03 <1.40E-02 <9.45E-03 3.53E+00 <5.13E-03 <5.55E-03 <5.97E-03 <1.54E-02 <1.07E-02 Catfish 04-15-14 Squaw Creek <8.20E-03 <9.39E-03 <1.12E-02 <8.26E-03 <9.3 1E-03 <2.19E-02 <1.30E-02 3.29E+00 <8.20E-03 <8.76E-03 <8.59E-03 <2.46E-02 <1.87E-02 Bass 10-07-14 Squaw Creek <4.27E-03 <3.83E-03 <4.59E-03 <4.57E-03 <3.66E-03 <8,49E-03 <4.30E-03 2.32E+00 <4.27E-03 <3.68E-03 <4.OOE-03 <1.02E-02 <6.85E-03 Catfish 10-07-14 Squaw Creek <5.27E-03 <4.49E-03 <5.09E-03 <4.90E-03 <4.72E-03 <1.07E-02 <5.27E-03 2.81E+O0 <5.27E-03 <4,44E-03 <4.87E-03 <1.13E-02 <7.66E-03 Bass 04-15-14 Lake Granbury <8.45E-03 <5.57E-03 <5.48E-03 <6.56E-03 <6.36E-03 <1.42E-02 <9.82E-03 3.08E+00 <8.45E-03 <5.81E-03 <6.11E-03 <1.49E-02 <1.05E-02 Catfish 04-29-14 Lake Granbury <8.13E-03 <4.84E-03 <6.58E-03 <6.68E-03 <6.01E-03 <1.47E-02 <7.13E-03 2.56E+00 <8.13E-03 <6.52E-03 <6.31E-03 <1.51E-02 <1.08E-02 Bass 10-28-14 Lake Granbury <6.72E-03 <4.48E-03 <4.82E-03 <5.01E-03 <4.66E-03 <I.IOE-02 <8.66E-03 3.27E+00 <6.72E-03 <4.1 IE-03 <4.57E-03 <1.15E-02 <8.22E-03 Catfish 10-07-14 Lake Granbury <5.78E-03 <3.93E-03 <4.70E-03 <4.58E-03 <4.27E-03 <9.05E-03 <5.24E-03 1.56E+00 <5.78E-03 <3.90E-03 <3.92E-03 <8.4 1E-03 <7.05E-03 Bass Required LLD's 1.30E+02 1.30E+02 1.30E+02 1.50E+02 2.60E+02 1.30E+02 2.60E+02 Reportable Levels 3.OOE+04 I.OOE+04 I 1.00E+03 2.OOE+03 1.00E+04 I _ _ I 3.E+04 2O0E+04 38

I. Food Products Program Food products (pecans) were collected at the time of harvest. The samples are obtained at monitoring location ENE-9.0 at the time of harvest and are shipped to the contract laboratory for gamma isotopic analysis. There were no food products produced that required monitoring for location E-4.2 in 2014.

For the year 2014, results of the gamma isotopic analyses are reported in Table 12 -- 2014 Environmental Food Products Gamma Isotopic Results. Naturally occurring Potassium 40 was detected in the samples as expected.

During the year 2014, there were no exceptions to the Food Products Program.

39

Table 12 -- 2014 Environmental Food Products Gamma Isotopic Results (Units of pCi/kg wet)

_______ ________ ________ _______ Food Type -Pecans/Fruit & getablea ____ _____- _____ _____ ____ ____

____ ____ Nuclides C-8 C-O I C- 4 C-3 e5 -3 Ia7 -0L-4 n6 b9 n5Z4

____ ____ Ba-140 ______ _______ _______ ______ 34 ___ ________ _______

1-131__ K _0________ b-5 n65Zr Date Location ___________ ______ ______

U. ENE-9.0 <1.13E+01 <8.13E+01 <9.47E+00 <1.25E+01 <1.23E+01 '1O01E.C1 <2.18E+01 <1.24E+01 -- 3.13E+03 '1.13E+O1 <9V6EOO0 <1.22E+01 <2.33E+01 <2.OOE+O1

_____ Location______

-4.2 E____ _______________________ _____ ______

W/A _ _- N/A N/A N/A N/A N/A N/A N/A N/A N/A N/A N/ A N/A N/A I/

ReuiedLLauired__ ______LLD's___ _______ .0E41 .080101_____I______.

________ .08I1 -- ___.______E___ _____E_ ___01__

Reportable Levels I-_____ _____ _____ _____ 1.00E+03 I 2.008403 I_____ 1.00E402 I____ _____- _____ ______ _____

40

J. Broadleaf Program Broadleaf sample collection is conducted in accordance with the requirements of the Radiological Environmental Monitoring Program. The program specifies the sampling based on the absence of milk monitoring locations. One broadleaf control location is located at SW- 13.5 in the vicinity of the previous control milk location. The two indicator locations, N-1.45 and SW-1.0, are located near the site boundaries. The broadleaf samples consist of mainly native grasses and cedar leaves and are analyzed for Iodine- 131 and gamma emitting isotopes.

For the year 2014, all radionuclide analysis met their required LLDs. The naturally occurring radionuclide of Potassium-40 was found in 36 of 36 samples taken. The radionuclide Beryllium-7 was present in 35 of 36 samples. No positive results for Cesium-137 were present.

No abnormal results were reported by CPNPP or by the State of Texas.

During the year 2014, there were no exceptions to the Broadleaf Program.

41

Table 13 - 2014 Environmental Broadleaf Iodine-131 and Gamma Isotopic Results I T T T I 7 1 (Units of pCi/kQ wet) 7 1 T 1 7 1 1 T Nuclides BL-1 1-131 Ba-140 Be-7 Co-S8 Co-60 Cs-134 Cs-137 Fe-59 K-40 La-140 Mn-54 Nb-95 Zn-O5 Zr,05 Location I___I__I I N-1.45 <5.33E+01 <5.45E+01 3.42E+03 <4.1 SE+01 <5.17E+01 <4.79E+01 <4.37E+01 <7.48E+01 2.33E+03 <5.45E+01 <4.14E+01 <4.93E+01 <8.55E+01 <7.74E+01 N-1.45 <2.43E+01 <2.67E+01 2.98E+03 <1.65E+01 <1.88E+01 <2.29E+01 <2.01 E+01 <3.15E+01 7.47E+02 <2.67E+01 <1.81E+01 <1.94E+01 <4.07E+01 <3.48E+01 I N-4.45 <5.69E+01 <5.21E+01 8.32E+03 <4.38E+O1 <3.88E+01 <5.05E+01 -- <4.70E.-O1 <7.08E+01 1.94E+03 <5.21E+01 <4.49E+01 <4.32E+01 <7.90E+01 <7.71E+01 N-1.45 <4.11 E+01 <3.47E+01 9.14E+03 <3.07E+01 <2.96E+01 <3.22E+01 <2.86E+01 <4.57E+01 1.23E+03 <3.47E+01 <2.98E+01 <2.96E+01 <5.36E+01 <4.97E+01 N-1.45 <3.66E+01 '3.79E.O1 1.90E+03 <3.25E+01 <3.01E401 <3.65E+01 <3.41 E+01 <6.05E+01 4.28E+03 '3.79E.O1 <3.07E+01 <3.06E+01 <6.90E+01 <4.55E+01 I -14 <.5EO <.6+O 4.9+0 <1. +O <88EO <.3+O < +5EO <2.3+0 3.4+0 .6EO <83EO < 11EO <1.8+1 <.4i N-11.45 <2.38E+01 <2.49E+01 1.80E+03 <1.98E+01 <2.44E+01 <2.26E+01 <2.16E+01 <4.47E+01 8.01E+03 <2.49E+01 <2.OIE.O1 <1.91E+01 <5.10E+01 <3.49E+01 I N-1.45 <5.20E+01 <4.78E+01 1.40E+03 <2.47E+01 <2.73E4101 <2.83E+01 <2.52E+01 <5.26E+01 7.92E+03 <4.78E401 <2.39E+01 <2.52E+01 -6.19E+01 <4.49E+01 N-1.45 <3.53E+01 <3.1 1E+01 1.06E+03 <1.73E+01 <1.88E+0l <1.98E+01 <1.83E+01 <3.69E+01 4.72E+03 <3.11E+01 <1.76E.C1- 01.74E+01 <4.14E+o1 <2.90E+01 I N-1.45 <5.92E.<01 <5.43E+01 3.73E+03 <3.30E+01 <3.64E+01 <3.86E+01 <3.62E+01 <7.13E+01 3.86E+03 <5A3E4O1 <3.72E+01 <3.61E+01 <6.41E+01 <5.52E+01 N-l.45 <5.24E+01 <3.26E+01 4.24E+03 <2.69E2+O1 <2.76E+01 <2.93E+01 <2.90E+O1 <4.67E+O1 2.25E+03 <3.26E+01 <2.70E+01 <2.62E+01 <4.75E.O1 <5.05E+01 BL-3 1-131 8a-14C Be-7 Co-SB Co-B0 Cs-134 Cs-137 Fe-SO K-40 LO-1 40 Mn-54 Nb-OS Zn-6S Zr-OS Control ______

I SW-13.5 <5.52E+01 <6.56E+01 3.84E+03 <4.90E+01 <6.20E+01 <5.03E+01 <5.53E+01 <9.66E+01 1.32E+03 <6.56E+01 <5.52E+01 <4.86E+01 <1.13E+02 <8.39E+01 I SW-13.5 <2.05E+01 <2.50E+01 2.29E+03 <1.50E+01 <1.74E+01 <1.73E+01 <1.62E+01 <2.91E+01 7.25E+02 <2.50E+01 <1.64E+01 <1.49E+01 <3.65E+01 <2.71E+01 S SW-13.S <4.71 E+01 <5.48E+01 6.43E+03 <3.80E+01 <4.30E+01 <4.20E+01 <4.07E+01 <7.02E+01 1.04E+03 <5.48E+01 <3.OOE+O1 <3.91E+01 <6.75E+01 <6.12E+01 SW-13.S <4.45E+01 <3.18E+01 7.86E+03 <2.34E+01 <2.18E+01 <2.64E+01 <2.32E+01 <4.05E+01 1.32E+03 <3.18E+01 <2.38E+01 <2.32E+01 <3.93E+01 <3.99E+01 I SW-1 3.5 <2.96E+01 <4.17E+01 1.50E.03 <2.17E+01 <2.35E+01 <2.71E+01 <2.40E+01 <5.16E+01 4.13E+03 <4.17E2+01 <2.56E+01 <2.05E+01 <5.28E+01 <4.32E+01 F SW-13.5 <5.97E+01 <5.38E+01 1.36E+03 <3.01 E+01 <3.55E+01 <3.36E+01 <3.06E+01 <6.45E+01 4.41E+03 <5.38E+01 <2.96E+01 <3.47E+01 <7.29E+01 '5.92E.O1 jSW-13.5j <5.89E+01 <4.02E+01 2.97E+02 <1.05E.O1 <1.06E+01 <9.48E+00 <9.07E+00 <2.73E+01 5.37E+03 04.02E+01 <9.07E+00 <1.14E+01 <2.19E+01 <2.05E+01 I SW-1 3.5 <3.17E-.01 <3.32E+01 1.21 E+03 <2.48E+01 <3.02E+01 <2.69E+01 <2.72E+01 <5.29E+01 7.05E+03 <3.32E+01 <2.50E+01 <2.76E+01 <5.86E+01 <4.84E+01 L SW-13.5 04.01E+01 <2.81IE+01 1.35E+03 <1.95E+01 <1.86E+01 <2.04E+01 <1.90E+01 <3.56E+O1 6.86E+03 <2.81E+01 <1.92E+01 <1.99E+01 <4.02E+01 <3.20E+012 SW-13.5 <2.71E+01 '2.04E.O1 1.08E+03 '1.43E<O1 '1.37E.O1 <1.37E+01 <1.17E+01 <3.29E+01 4.49E+03 <2.04E+01 <1.22E+01 <1.38E+01 <3.03E.O01 <2.25E+01 SW-13.5 <4.95E+01 <5.21 E+01 4.07E+03 <2,47E+01 <3,19E+01 <2.87E+O1 <3.12E+01 '5.47E+01 5.35E+03 <5.21E+01 <2.89E+01 <2.81 E+01 <7.07E+01 -4.58E+01]

I SW-13.5 <2.22E+01 <2.52E+01 1.22E+03 <1.24E.O1 <1.82E+01 <1.46E+01 <1.47E<O14 13.02E+O1 5.10E+03 <2.52E+01 <1.19E+01 <1.44E+01 <3.12E+01 <2.74E+01

_____ BL-2 1-131 8a-140 8e-7 Co-SB Co-60 Cs-134 Cs-137 Fe-SO - K La,140 Mn-54 Nb-05 Zn-OS Zr-05 SW-tO8 <5.49E+01 <5.39E+01 3.92E+03 <4.38E+01 <4.80E+0i <5.35E+01 <4.17E+01 <7.51E+O1 2.14E+03 <5.39E+01 <4.59E+01 <4.57E+01 <9.14E+01 <7.06E+01 SW-I.0 <1.71E*-01 <1.69E+01 2.04E+03 <1.22E+01 <1.56E+01 <1.56E+01 <1.73E+01 <2.12E+01 7.83E+02 <1.69E+01 <1.30E+01 <1.32E+01 <2.89E'-01 <2.38E+O1 SW-l.O <4.82E+01 <6.58E+01 4.54E+03 <3.66E+01 <5.17E+01 <4.98E+01 <3.99E+01 <7.68E+01 1.02E+03 <6.58E+01 <4.09E+01 <4.18E+01 -7.22E+01 <6.76E+O1 SW-1.O <3.98E+01 '4.09E+O1 9.30E+03 <2.86E+01 <3.45E+01 <3.27E+01 <3.15E+01 <5.51E+01 1.16E+03 <4.09E+01 <2.34E+01 <3.17E+01 <5.82E+01 <5.11E.O1 SW-l.0 <2.81E+01 <2.82E+01 1.36E+03 <1.69E+01 <2.37E+01 <1.79E+01 <2.55E+01 <4.OOEO01 2.05E+03 <2.82E+01 <2-.14E+01 <2.36E+01 <4.57E+01 <3.80E+01 SW-l.a <5.71 E+01 <3.87E+01 2.22E+03 <3.03E+01 '3.20E+O1 <3.31E+01 <3.22E+01 <5.72E9'01 3.57E+03 <3.87E+01 <3.47E+01 <3.01E+01 <5.84E+01 <5.93E+01 SW-l.0 <5.29E+01 <7.36E+01 1.16E+03 <1.57E+01 <1.45E+01 <1.39E+01 <1.62E+01 <4.09E+01 2.89E+03 <7.36E+01 <1.35E+01 <1.59E+01 <3.1OE+O1 <2.88E+01 SW-l.0 <2.04E+01 <2.28E+01 3.10E+03 <1.77E+01 <1.94E+01 <2.05E+01 <2.01E+01 <189E+01 3.84E+03 <2.28E+01 <1.93E+01 <1.73E+01 <4.37E+O1 <3.39E.01 SW-l.a <2.37E+01 <2.06E+01 1.06E+03 <1.21 E+01 <1.35E+01 <1.32E+01 <1.29E+01 <2.81E+01 5.16E+03 <2.06E+01 <1.20E+01 <1.24E+01 <2.85E+01 <2.18E+01 sw-l.a <2.77E+01 <2.52E+01 1.62E+03 <1.30E+01 <1.45E+01 <1.40E+01 <1.74E+01 <2.91E+01 4.31E+03 <2.52E+01 <1.44E+01 <1.39E+01 <2.95E+01 <2.37E+01 sw-1.o <5.91 E+01 <5.86E+01 3.76E+03 <2.55E+01 <3.33E+01 <3.37Es.01 <4.OOEO01 <5.45E+01 2.20E+03 <5.86E+01 <3.10E+01 <2.59E+O1 <4.97E+01 <5.47E+01 sw-l.a <5.46E+01 <459E+O1 3.93E+03 <2.74E+01 <3.22E+01 <3.34E+01 <3.18E+01 <6.21E+O1 1.71E+03 <4.59E+01 <2.82E+01 <3.01 E+01 <6.20E+01 <5170E.-01 Required LLD's 6.OOE+0l 6.OOE+01 B.COE+Ol Reportable Levels 1.0OE+02 1.OOE+03 2.00E+03 42

K. Conclusions For the year 2014, based on the results presented in this report and from comparisons with the pre-operational and operational program results from previous years, it can be concluded that the impact of Comanche Peak on the environment is very small. The only indication directly attributable to Comanche Peak is the tritium detected in Squaw Creek reservoir.

Gross beta trend indications concerning Squaw Creek Reservoir are consistent with previous values and do not indicate any increase due to influence from Comanche Peak. Future data will be evaluated as it is received and changes will be addressed as necessary.

The tritium in Squaw Creek reservoir has been increasing slowly over the last twenty years and is expected to remain well below the reportable level.

There were no values reported during the year 2014 that exceeded any NRC reportable limit.

L. Inter Laboratory Comparison and Cross Check Program GEL Laboratories LLC GEL Laboratories LLC is the independent contract laboratory that processes the radiological environmental monitoring samples collected by CPNPP.

The contract laboratory is required to participate in an Interlaboratory Comparison Program in accordance with the ODCM Control 3.12.3. GEL participates in multiple programs to ensure all environmental media sent to them are analyzed to the proper standards.

GEL Laboratories, LLC (GEL) is a privately owned environmental laboratory. GEL was established as an analytical testing laboratory in 1981.

Now a full service lab, their analytical divisions use state of the art equipment and methods to provide a comprehensive array of organic, inorganic, and radiochemical analyses.

GEL administers the QA program in accordance with the Quality Assurance Plan, GL-QSB-001. Their Quality Systems include all quality assurance (QA) policies and quality control (QC) procedures necessary to plan, implement, and assess the work they perform. GEL's QA Program establishes a quality management system (QMS) that governs all of the activities of their organization.

43

In May 2014 there wasn't a NUPIC Audit on GEL performed by Cooper Station.

Summary of 2014 Data Results During 2014, forty-four radioisotopes associated with seven matrix types were analyzed under GEL's Performance Evaluation program in participation with ERA, MAPEP, and Eckert & Ziegler Analytics. Matrix types were representative of client analyses performed during 2014. Of the four hundred forty-five (445) total results reported, 98.6% (439 of 445) were found to be acceptable. The list below contains the type of matrix evaluated by GEL.

  • Air Filter

" Cartridge

" Water

" Milk

" Soil

  • Liquid

" Vegetation Summary of Participation in the Eckert & Ziegler Analytics Environmental Cross-Check Program Eckert & Ziegler Analytics provided samples for seventy (70) individual environmental analyses. The accuracy of each result reported to Eckert &

Ziegler Analytics, Inc. is measured by the ratio of GEL's result to the known value. All results fell within GEL's acceptance criteria (100%).

Corrective Action Request and Report (CARR)

There are two categories of corrective action at GEL. One is corrective action implemented at the analytical and data review level in accordance with the analytical SOP. The other is formal corrective action documented by the Quality Systems Team in accordance with GL-QS-E-002. A formal corrective action is initiated when a nonconformance reoccurs or is so significant that permanent elimination or prevention of the problem is required. Formal corrective action investigations include root cause analysis.

GEL includes quality requirements in most analytical standard operating procedures to ensure that data are reported only if the quality control criteria are met or the quality control measures that did not meet the acceptance criteria are documented. A formal corrective action is implemented according to GL-QS-E-002 for Conducting Corrective/Preventive Action and Identifying Opportunities for Improvement. Recording and documentation is performed following guidelines stated in GL-QS-E-012 for Client NCR Database Operation.

44

Any employee at GEL can identify and report a nonconformance and request that corrective action be taken. Any GEL employee can participate on a corrective action team as requested by the QS team or Group Leaders. The steps for conducting corrective action are detailed in GL-QS-E-002. In the event that correctness or validity of the laboratory's test results in doubt, the laboratory will take corrective action. If investigations show that the results have been impacted, affected clients will be informed of the issue in writing within five (5) calendar days of the discovery Quality Assurance Program for Internal and External Audits During each annual reporting period, at least one internal assessment of each area of the laboratory is conducted in accordance with the pre-established schedule from Standard Operating Procedure for the Conduct of Quality Audits, GL-QS-E-001. The annual internal audit plan is reviewed for adequacy and includes the scheduled frequency and scope of quality control actions necessary to GEL's QA program. Internal audits are conducted at least annually in accordance with a schedule approved by the Quality Systems Director. Supplier audits are contingent upon the categorization of the supplier, and may or may not be conducted prior to the use of a supplier or subcontractor. Type I suppliers and subcontractors, regardless of how they were initially qualified, are re-evaluated at least once every three years.

In addition, prospective customers audit GEL during pre-contract audits.

GEL hosts several external audits each year for both our clients and other programs. These programs include environmental monitoring, waste characterization, and radiobioassay. The following list of programs may audit GEL at least annually or up to every three years depending on the program.

  • NELAC, National Environmental Laboratory Accreditation Program
  • DOECAP, U.S. Department of Energy Consolidated Audit Program
  • DOELAP, U.S. Department of Energy Laboratory Accreditation Program
  • DOE QSAS, U.S. Department of Energy, Quality Systems for Analytical Services

" ISO/IEC 17025:2005

  • A2LA, American Association for Laboratory Accreditation
  • DOD ELAP, US Department of Defense Environmental Accreditation Program
  • NUPIC, Nuclear Procurement Issues Committee

" South Carolina Department of Heath and Environmental Control (SC DHEC)

The annual radiochemistry laboratory internal audit (13-RAD-001) was conducted in July, 2014. One (1) finding, four (4) observations, and eight (8) recommendations resulted from this assessment. By September, 2014, the finding was closed and appropriate laboratory staff addressed each observation and recommendation. The one finding addressed improper labeling of a reagent container and did not affect any of the analytical data.

This finding was documented in CR-2015-003136.

45

LAND USE CENSUS VERIFICATION SHEET Date Completed: 08-20-14 Performed By: Todd Emery' Bonnie Vaughan/

V Print / Signature New locations identified that require the recalculation of D/O or X/O: (E/NO The locations with, "Nearest population" changed from 2013 to 2014 are as follows (Listed as the sector/2013/2014 change in miles): NNE 2.2 to 2.5 miles, NE 2.2 to 2.5 miles, WSW 0.8 to 0.5 miles and WNW 2.8 to 2.5 miles. CR-2014-009862 was generated to document calculation errors and recalculated D/O and X/O values on the 2013 Land Use Census Report. These corrections are reflected within the 2014 Land Use Census report. See attached spreadsheet with corrections in BYW 1OoIt-cW-tPe(ASe Spreocksieet').

Receptors with calculated doses increasing by 20%: YES Specific Locations: The primary "from" wind direction used to calculate the annual average X/0 dose calculation, tritium X/O and D/O is based on SSE,S, and SSW winds. There has been no change in the predominant wind direction that would affect the calculated dose receptors.

Potential Sources of Hazardous Chemicals and/or Toxic Gases: /NO (If YES, Supply copy to Design Engineering Analysis Group)

Specific Locations, Types, and Quantities: Land Use Census map indicates all locations of oil, gas raw LPG and refined products. Design Engineering Analysis is supplied maps for review.

Radiological Environmental Monitoring Program Changes Implemented: YES (N NA Comments:

Approved By: .. L_

Health ýR Supervisor

  • Date:

I/Ml2O11 REFERENCE USE RPI-714-1 Rev. 5 Page 1 of I

2013 Recalculated X/Q and D/Q values BASE0ISTANCE IN MILEW/ILOMEMRS Average Annual Relative Concentration (X/Q) Tables AVIDSECTDEIGNOWS 0.5 1 1.5 2 2.5 3.5 4 4.5 6 7.5 10 15 25 35 45 50 Actual Distance sa Ma a4. Ma Ma - ýM M 4W W 4 40,O "M Oa4 8" NNE 0 1.30£-05 3.10E-06 1.20E-06 6.SE-£07 4.20E-07 230E-07 1.80E-07 LSOE.-07 9.60.-08 7.00*-08 4.60E-08 2.70E-08 1.40E-08 9.SOE-09 7.00*E09 6.20E-09 2.2 5.SSE-07 NE 0 9.20E-06 2.20E-06 8.50.-07 4,K6-07 2.90E-07 1.60E-07 1.30E-07 1.10E-07 6.80A-08 5.00£.08 3.30E-08 2.00E-08 L1-E-08 6.90E-09 5.10E-09 4.50E-09 2.2 3.92E-07 ENE 0 7.50E-06 1.80.-06 G6.01-07 3.70E-07 2.30E107 130M,07 1.006-07 8.40E-08 5.50E-08 4.10£-06 2.70E-08 1.606-08 8.506-09 5.76O-09 4.20E-09 3.70E-09 2.6 2.20E-07 E 0 8.90E-06 2.10E-06 8.00E-07 4.30E-07 2.70E-07 1.50E-07 1.20E-07 9.90--08 6.50-.08 4.80E-08 3.10£-08 L.90E-08 3.OOE-08 6.806-09 5.00E-09 4.40E-09 2.S 2.70E-07 ESE 0 9.70E-06 2.301-06 8.80£-07 4.70E-07 3.00E-07 1.60E-07 33E-07 1.10-E07 7.10.-08 5.20E-08 3.50E-08 2-1E-08 1.10E-08 7.40E-09 5.50K-09 4.90E-09 2.2 4.02E-07 3.10M-08 SE 0 1.40E-05 3.40E-06 1.30E-06 7.104E07 4.50E-07 2.SOE-07 2.-0E-07 1.60E-07 1.10E-07 7.80.-08 5.106-08 1.601-08 .101.-08 8.006-09 7,106-09 2.0 7.101E-07 SSE 0 1.10E-05 2.706-06 £10146 5.80.-07 3.70E-07 2.001E-7 1.60E-07 3.30E-07 8.406-6 6.10£-08 4.00E-08 2.301-08 1.20K-08 8.101-09 6.00.-09 5.306-09 1.5 1.10E-06 S 0 8.60E-06 2.20E-06 8L506-07 4.70E-07 3M()E-07 360E-07 1.30E-07 .10-07 6.70E-06 4.90E-08 3.20E-08 L.90£-08 9.70E-09 6.40-09 4.70E-09 4.106-09 L3 8.50E-07 SSW 0 7.101-06 1.806-06 6.9E-07 3.80147 2.401-07 1.301-07 1.0OE-07 6I606-06 5.50.-08 4.00-06 2.606-08 L3.OE-06 7.80£-09 5.106-09 3.806-09 3.30E-09 1.8 5.04E-07 0 6.50E-06 1.606-06 6.406-06 3.50E-07 2.306-07 1.20E-07 9.70E-08 8.006-08 5.106-08 3.70E-08 2.40E-08 1.40E-08 7.3M£-09 4.80E-09 3.50E-09 3.10E-09 0.8 3.56E-06 WSW 0 7.10E-06 1A0-06 6.90E-06 3.80E-07 2.50E-07 2.306-07 1.10E-07 &.70E-08 5.06-08 4.00E-08 2.60£-08 3.50£-08 8.106-09 5.30E-09 3.90E-09 3.50E-09 0.8 3.92E-06 Ww W 4.90£-06 0 8.60-E06 2.20E-06 8.40E-07 4.60E-07 2.-01-07 1.60£-07 1.30E-07 1.00E.07 6.70E-08 3.20E-08 1.90E-08 9.70E-09 6.40E-09 4.70E-09 4.20E6-* 1.6 7.64E-07 0 1.401E-05 3.40E-06 1.30E-06 7.30E-07 4.70E-07 2.868-07 200E-07 1.70E-07 1.106-07 7.90E-06 5.101-08 3.O0.-09 1.60£-08 1.10£.-43 7.801-09 6&90£-09 2.8 4.07E-07 WNW NW 0 2 30E-05 .701-06 2.206-06 L206-06 7.70E-07 4.10E-07 3.30E-07 2.70F407 1.80E-7 L.30£-07 8.50£-08 5.O0£-08 2.70E-08 3.80.-08 1.30£-08 L20E-08 4.8 2.52E-07 NNW 0 2-501-05 6.101-06 2.406-06 130E-06 8.40E-07 4.506-07 3.60E-07 3.006-07 1.90E-07 1.406-07 9.20E-08 5.40E-08 2.90E-08 1.90E-08 1.40E-08 1.20E-08 2.2 1.12E-06 N 0 2.00.-05 4.90E-06 1.90-06 1.106-06 6.70E-07 3.60E-07 2.90E-07 2.40E-07 1.50E-07 .10-07 7.306-08 4.30E-08 2.30E-08 1.50£-08 1.106-08 9.70E-09 2.6 6.39E-07 BASEDISTANCE IN MILESKIVLOMETERS Average Annual Relative Deposition Rate (D/Q) Tables AFTDSECT0o NDisT 0.5 1 1.5 2 2.5 3.5 4 4.5 6 7.5 10 15 25 35 45 50 Ml 0.8 1.61 2A1 3.22 4.02 5.63 6.44 7.24 9.65 12.07 16.09 24.13 40.22 56.31 72.4 80.45 NNE 0 1.00E-07 2.20E-08 7.20E-09 3.50E- 2.009I -09 9.40E-10 7.40E-10 5.50E-10 3.10E-10 2.00E-10 .10E-10 5.50E-11 2.120-11 3.1OE-11 6.406-12 5.10E-32 2.2 2.90E-09 NE 0 5.00E-08 3.10E-08 3.60E-09 1.706-09 .00E-09 4.60E-10 3.401-10 2.706-10 1.506-10 9.90E-11 S.606-11 2.70E-11 1.00-11 5.30E-32 3.106-12 2.50E-12 2.2 142E-09 ENE 0 3.006-08 6.50E-09 2.20E-09 3.0l-09 6.10E-10 2.80M-10 2.106-10 3.60E-10 9.20E-11 6.10E-n 3.40E-11 .606-11 6.306-12 3.20E-12 1.90E-12 L50E-12 2.6 5.77E-10 E 0 2.9E6-08 6.0E.-0 2.10E-09 9.90E-10sa.8E-10 2.70£-10 2.006-10 3.60E-10 8.70E-11 5.70E-11 3.20E-11 .I60E-11 5.906-12 3.10E-12 1.80E-12 L.50E-12 2.5 5.80E-10 ESE 0 3.506-08 7.506-09 2.S06-09 201E-09 7A00-10 3.20E-10 2.40E-10 3.90E-10 1.106-10 7.00E-11 3.80E-11 L90£-11 7.206-12 3.70E-12 2.20E-12 180£-12 2.2 2.061E-10 SE 0 8.00E-08 3.706-08 5.706-09 284 1.601-09 7.40E-10 5.506-10 4.30E-10 2.40E-10 1.60£-10 9.006-11 4.30E-11 1.70E-11 .SOE-12 5.106-12 4.006-12 2.0 2.80E-09 SSE 0 9.10M-08 3906-0 6.60E-O 3.201-09 1.0E-09 6.501-10 6.306-10 4.90E-10 2.80E-10 3.806-10 1.00E-10 4.90E-11 1.906-11 9.706-12 5.80E-12 4.60E-12 1.5 6.60E-09 8:-106-! 1- "1901-11 -1.506-11 "-770C-12. 4.60£-1-2 3.70E-12 "5.20E-09 S 0 .72,0608O- 1-56E4 8ý411E-. - 06I-09 1401E-09-6.706-10 5O0E-0 190W 2.206 1.406-10 3

SSW o 4.80E-08 .06-08 3.5014E9*1.70E-09 9.836-10 4.50E-10 3.40E-10 2.60E-10 1.501-10 9.70£-11 5.50E-11 2.60E-11 1.006-11 5.20E-32 3.10E-12 2.50E-12 1.8 2.42E-09 SW 0 350E-0 7.-0-09 2.53M-09 3.206-09 7.10£-10 3.30E-10 2.406-10 3.90E-10 3.106-10 7.006-11 4.006-11 3.90E-11 7.306-12 3.706-12 2.20E-12 L.B0O-12 0.8 1.85E-08 WSW 0 3.101646F 6.6SOE-09 2.206-09 .106-09 6.10E-10 ZWO0-10 2.30E-10 3.701-10 9.306-11 6. 10-11 3.40E-11 37OE-11 6.30E-12 3.301-32 1.90M-12 1M*E-22 0.8 1.63E-08 W 0 3.806-0 6.206-09 2.8014- L30E-09 7.706E-10 3,606-10 2.70E-10 2.10E-10 1.206-10 7.70E-11 4.30E-11 2.106-11 8.006-12 4.106-12 2.40E-12 1.906-12 1.6 2.50E-09 WNW 0 7.20E-08 .506-08 5.10-09 2.50E-09 140E-09 6.70E-10 5.006-10 3.9*1-10 2.20E-10 L40E-10 8.10E-11 3.906-11 1.506-11 7.606-12 4.501-12 3.60E-12 2.8 1.18E-09 NW 0 1.20E-07 2.70E-08 9.00E-09 4.30E-09 2.50E.09 3.206-09 8.70E-10 6.801-10 3.801E-10 2.50E-10 1.40E-10 6.806-11 2.60E-11 L30E-U 7.906-12 6.30E-12 4.8 6.201E-10 NNW 0 1.80I-07 3.80E-08 1.30E-08 6.20E-09 3.60-09 3.706-09 1.206-09 9.60E-10 5.40E-10 3.50E-10 2.00E-10 9.606-11 3.706-11 1.90E-11 1.10E-11 9.00F-12 2.2 5.164-09 N 0 1.830E-07 3.90E-08 1.30E-08 6.40E-09 3.70E-09 1.70E-09 1.30E-09 .0OE-09 5.60E-10 3.70E-10 2.10E-10 9.90E-11 3.80E-11 2.00E-11 1.20E-11 9.30E-12 2.6 3.50E-09 NOTE: X/Q and 0/Q In RED are corrected values from the 2013 Land Use Census Reort.

c~/6

RASE DISTANCEIN MILES/IGLOMETERS Average Ajnual Relative Conemtration (X/Q) Tables AF-iD DESIGN Actual SECT DIST 0.5 1 -5 2 2.5 3.5 4 4-5 6 7.5 10 15 25 35 45 50 Distance 0* ~ ~ & .. UM AM - 4 A"* 4

-UM A 48 a*4 M 4 O M NNE 0 IME0-05 3.10E-016 1.20E-06 6.50E-07 4.20E-07 2.30E-07 1.8OE-07 1.SDE-07 9.60E-08 7.001.08 4.601-08 2.70E-08 1.40E-08 9-0E-09 7.00E-09 6,20E-09 2.5 4.20E-07 5.00E-08 NE 0 9.20E-06 2.2015-06 8501E-07 4.60E-07 2.90E-07 1.60E-07 1.30E-07 1.10E-07 6.80E-08 4,!0E-09 3.301-08 2.001-08 1.00E-08 6.90E-09 5.10E-09 4E50-09 2-5 2-90E-07 ENE 0 7.501E-06 LISD-06 1.80F-07 3.701-07 2.30"-07 L30E-07 1.001-07 MOE0-08 5-50E-08 4.10E-.0 2.70E-08 1.G01-08 850E-09 5.70.-09 420E-09 3.70E-09 2.6 7-20"-7 E 0 8301-06 2.10E-06 SME0-07 430E-07 2.70E-07 150E-07 1.20E-07 9.90E-09 6.50E,-08 4ME0-08 3.10E-08 1-90&-08 1.00E-08 6.80S-09 5.00E,09 44AOE-09 2,5 2.70E-07 ESE 0 9.70E-08 2-30r-06 8.80E-07 4.701-07 3.OOE-07 1.60E-07 1-30E-07 1.10E-07 710-08 5.20F-08 3501E-0 2J01-08 1.109I-08 7.0E-09 5.SOE-09 4,0E09 2.2 4.02E-07 SE 0 1.4 3.40E-06 1230E-06 7.10E-07 453E-07 2-S0E-07 2.001-07 I-GOE-07 1.10E-07 7.01E-08 5.101-08 310E-08 1.60E-08 1.10E-08 .001E-09 7.10E-09 2.0 7.10E-07 SSE 0 1.10E-05 2-70E-06 1.10E-06 5S1-E,07 3.70Z-07 2.OOE-07 2.601-07 1.30E-07 8.40E-08 1.I0E-09 4.001-08 7-30E-08 1.20E-08 8.0E-09 6.00E-09 5.30&-09 1.5 1.10E-06 S 0 3.801-06 2-20E-06 8-SOE-07 4.70E-07 B.0OE-07 J-G0E-07 £9E01-C 1-IOE-07 6.70E-08 4.90E-08 320E-08 IME0-09 9.70E-09 6.40E-09 4,70E-08 410E-03 8301-07 2.40E-0-7 5-509-OR 4.00E-03 3.0-09M 1.8 5.04E-07 SSW 0 7.10E-06 LBOE-06 6.90E-07 3.80E-07 2.20E-07 £60E01- 8.60E-08 2.G01-08 £9E014 7.80E-09 S.101-09 3.808-09 230E-07 Sw 0 6-SCE-06 1.60E-06 6.40E-06 3.50E-07 1201-07 9.70E-08 8.001-08 5.10E-08 3.706-08 2.40E-08 1.40E-08 730E-09 4.806-09 3.301-0 3=E1-09 0.8 3-S6E-06 0 7.OE-06 1.30E-06 130E-06 3.80E-07 LWE0-07 IAOE-07 3.70E-08 5.60E-08 4.001-08 2-S0E-08 1.50E-09 810E-09 5.30E-09 330-096E 3-50E-08 3.92E-05 WKW 0 8.60E-06 2.301-06 8.40E-07 4.60E-07 2-90E-07 1.601-07 1-30&W0 2.00E-07 6.70E-08 4-.0E-08 3120E-08 1.90E-08 9.70E-09 6.401-09 4,70E-09 4.20E-09 1.6 7.64E-07 NW 0 1.40E-05 3.401-06 1.301-os 7.30E-07 4,70E-07 2.605-07 2.OOE-07 1.70E-07 3-10E-07 7.90E-08 5-0E408 3.001-08 1.60E-08 1.101-08 7505-0 6.90E-09 2.5 4.70E-07 NNW 0 2-306-05 5.70E-06 2-20E-06 1.20E-06 7.701-07 4.10E-07 3.301-07 2.70E-07 1.80E-07 12oE-o7 8501-08 5.601-08 2.709-08 £SOE-08 130E-08 1.20E-08 4.8 2-SZE-07 NW 0 2.501-05 6-10IF-06 2AD01-06 130E-06 8.40E-07 4,S01-07 3.101-07 3.005-07 1.90E-07 ..40E-07 9.20E-08 5.401-08 2.90E-08 1.90E-08 1.-40-08 1.20808 2.2 142E-08 N 0 2.009-05 4ME0-06 1.901-06 .10E-06 6.70E-07 3.6012-07 2.90E-07 2.40E-07 I-50E-07 1.10E-07 7.30E-08 4.30E-09 2.30E-08 I.901-08 1.10"-s8 9.70E-09 2.5 6-39E-07 BASEDISTANCE INMILES/KILOMETEMR Average Annal Relative Deposition Rate (DIQ) Tables AFD SECTDESIGNDI0! 0.5 1 is 2 2.5 3.5 4 4.5 6 7.5 10 15 25 35 45 50 MI 0.8 1.61 2.41 3.22 4.02 s.63 6.44 7124 9.65 12.07 11.09 24.13 40.22 5631 72.4 80.45 NNE 0 1.0015-07 2.20E-08 7.20E-09 3ME0-09 2-00E-09 9.40F-10 7.40E-10 5.50E-10 3.10-10 2.9OE-10 550-11 2.10E-11 1.I0E-31 .A0E-12 5-10E-12 25 2.O0E-09 1GO1-11 NE 0 S.001-08 3-IOE--08 3.80E-09 3.701-09 1"OE-09 4.60E-10 3140E-10 2.70E-10 1-501-10 2.70E1-f "1.001-li 5.30E-12 3.20E12f 2-WE-12 2.5 LOE-O9 ENE 0 6-50E-9 1.I0E-09 6.10E-10 2-80E-10 210E-10 1.60E-10 9.20E-11 6.101-11 3.40E-11 1.60E-11 630E-12 3.20E-12 3.809-12 LSOE12I 2.6 5.77E-I0 310013-08 2201-09 E 5.80E-10 2.70E-10 2.00E-10 .L60E-10 8.70D-11 6.70-li '1,6G.E11 5-90E-12 3.10E-U2 LB0E-22 1509E-12 25 5.80E-10 0 2.901-08 6.10E-09 2.101-09 9301-10 ESE 0 350E-08 7.506-09 2-50E-09 1201-09 7.00E-10 3.20E-10 2.40E-10 I.30-10 1108E-10 7.00E-11 1.90E-11 720E-12 3.70E-12 2.20E1-2 1.8E012f 22. LOGE-09 1.801-09 9.200-11 SE 0 taboosM 1.70E-09 5.70E-0S 7-SCE-09 7.401-10 5.SOE-10 4.30E-10 12.40E-10 1.60E-10 4.30E-11 1.70E-11 8.51E-12 SME0-12 4,00-12f 2.0 2.80E-09 1.80E-09 1001-10 SSE 0 9.10E-08 1.908-08 6.60!EmO9 3.20E-09 8.50E-10 6.30E-10 4.90E-10 1.80E-10 1.8OE-10 4-90E-11 1.90E-11 9.70E-12 &Mt-1.2 4.60E--12 1.5 6.G0E-0S S 0 7201-O8 1.50E-08 5.20E-09 2.501-09 1-40E-09 6.70E-10 5.00E-10 3.90E-10 2.20-E10 1.4OE-10 8!0E-11 3.90E-11 1.50E-11 7.70E1-Z 4.60E-12 3.7(W12U 2.5 5.20E-09 3A0F:10 1IME-11 2.42E-09 SSW 0 4.801-08 1.00E-08 3.50E-09 L7OE-OS 9.80E-10 4.SOE-10 2.60E-10 1,0E-10 9.70E-11 2.60E-11 5.20E-12 3.10E1-U 2.5015-12 1.8 4.00E-1n SW 0 tSO0E-08 7.50E-09 LWE0-09 120E-09 7.10E-10 3.3DE-10 2.40E-10 1.90E-10 1.101-10 7.00E-11 IM9E-11 7-0E-12 3.70E-12 2-20F-12 1.80E12U 0.8 L85E-O8 WSW 0 3.10E-08 6.50E-09 22CE-09 1.10E-09 610E-10 2.80E-10 2.10E-10 1.701-10 9.30E-11 6.10E-fl L70E-11 630E-12 3.30E-12 1-909-12 1.10E-12 03 L63E-08 4.0OE-11 2-I0E,-12 1.6 W 0 3.80E-08 8.20E09 2.80E-09 1.30E-09 7.70E-10 3.60E-10 2.70E-10 2.10E-10 1.20E-10 7.70E-11 3.401-n 8.00E-12 4.10E-32 2AOE1-12139015-12 2.50E-09 WNW 0 7.20E-08 1-50E-08 5.10E-09 2.501-09 1.40E-09 6.701-10 5.001-10 3.901-10 Z.Z0E-10 1.40E-10 3.1Dg'-nL 3,90E-11 1.50E-11 7.GOE-124301-12 3.60E-12 2.5 IAOE-09 NW 0 1.20E-0Y7 2.70E-08 9.OOE-09 4.30E-09 250E-09 1.20E-09 8,70E-10 6.80E-10 3.801-10 2-0E-10 1.40E-10 6.801-11 2.60E-11 1.30E-11 730E-12 6.30E1-f 43 6.20E-10 NNW 0 1.11-0Y7 3.80E-08 3,-36E-08 6.20E-09 3.60E-09 1.70E-09 L201E-09 9.680-10 5.40A-10 3-501-1r 2..00-10 9.601-11 3.70E-11 1.9IE-11 1.10r11i 9.001-12 2.2 5.16E-09 N 0 1.801-07 3.0-08 1.30E-03 6.40E-09 3.70E-09 1.70E-09 1.30E.'9 LO0E-09 5.60E-10 3.70E-10 2.101-10 93E9-11 3S-11 2.00E 120E-i1 930E-12 2.6 3.50E-09

Appendix A Comanche Peak Nuclear Power Plant Land Use Census 2014 COPY COMANCHE PEAK NUCLEAR POWER PLANT LAND USE CENSUS 2014 I

The Land Use Census identified receptors within a five (5) mile radius of the plant in each of the sixteen (16) meteorological sectors. The Land Use Census 'as conducted August 18-20, 2014 and includes the following items: -.

1. Evaluation of the 2014 Land Use Census
2. Nearest Resident by Sector, Distance, X/Q and D/Q
3. Nearest Garden by Sector, Distance and D/Q
4. Nearest Milk Animal by Sector, Distance and DIQ
5. Population by Sector and Distance
6. Environmental Sample Locations Table
7. Environmental Monitoring Locations Map - 2 Mile Radius
8. 5 Mile Sector and Road Map with Field Data*
9. Environmental Monitoring Locations Map - all sample locations*
  • These maps are vaulted along with this census. Copies of this census will not contain a copy of these maps unless specifically requested.

2

Evaluation of the 2014 Land Use Census The results of the 2014 Land Use Census were reviewed for impact on the Radiological Environmental Monitoring Program (REMP). The specific areas reviewed, that could be affected by changes found in the land use census, were the sampling.requirements for milk, broadleaf vegetation and food products.

Reviewing the milk sampling requirements from the ODCM Table 3.12-1 requires that samples are to be obtained from milking animals in three locations within a 5 km distance having the highest potential dose. If none are available, samples are.. acceptable from milking animals in locations 5 to 8 km distance where doses are calculated to be greater than 1 mRem per year. A sample is also required at a control location. There are currently no identified milking animals (cow or goat) within the specified distances therefore; there are no current milk samples during the year 2014. NOTE: A Control milk location was identified at 12.3 Miles SW, Deridder Dairy, but opetator did not wish to participate. (CR-2011-0013802)

If no milk samples are available, the broadleaf vegetation sampling specified in ODCM Table 3.12-1 will be performed. Broadleaf sample requirements are such that samples of broadleaf vegetation are to be collected from each of two offsite locations of the highest predicted annual average D/Q if milk sampling is not performed at,.all the required locations. Currently, broadleaf vegetation samples are collected.. at two indicator locations (N - 1.45 and WSW - 1.0) and one control location (SW_ - 13.5). These indicator locations are near the site boundary in sectors where broadleaf vegetation is available and D/Q are the highest. Therefore, no change to the broadleaf sampling program is required.

Food product sample requirements of ODCM Table 3.12-1 requires that one sample of each principal class of food product be collected from any area that is ir igated with water in which liquid plant waste has been discharged. No gardens were identified in the land use census and no gardens are located in any area that irrigates with water in which liquid plant wastes are discharged. Currently, food products are sampled ft.Om one indicator location (ENE - 9.0) when in season. The indicator location for ENJ3-9.0 for pecans at time of harvest will be continued since it is a major source of food products sold to the public.

The 2013 Land Use Census identified one location within 5 miles with a garden of greater than 500 ft2 producing broadleaf vegetation as outlined in CPNPP procedures and Comanche Peak Steam Electric Station Offsite Dose Calculation Manual. This garden was not in operation for the year 2014.

3

Calculated values for the associated X/Q and D/Q values for each controlling receptor location and pathway are included along with the receptor distances in-the data tables of this land use census. The values used to determine potential dose -due to radioactive effluent discharges are the highest calculated values based on annual average values. The annual average X/Q used for dose calculations is 3.30E-6, tritium X/Q:i&4.36E-6, and the D/Q value is 3.34 E-8. All these values are conservative based on thie 2014 Land Use Census data and therefore no changes are required in the dose calculation parameters as verified by the field data.

  • XIQ units are Sec/cubic meter
  • DIQ units are inverse square meters 4

Nearest Resident by Sector, Distance, X/Q and D/Q Sector Distance (Miles) X/Q D/Q N 2.6 6.39E-07 3.50E-09 NNE 2.5 4.20E-07 2.OOE-09 NE 2.5 2.90E-07 1.OOE-09 ENE 2.6 2.20E-07 5.77E-10 E 2.5 2.70E-07 5.80E-10 ESE 2.2 4.02E-07 1.OOE-09 SE 2.0 7.1E-07 2.80E-09 SSE 1.5 1.1OE-06 6.60E-09 S 1.5 8.50E-07 5.20E-09 SSW 1.8 5.04 E-7 2.42 E-9 SW 0.8 3.56E-06 1.85E-08 WSW 0.8 3.92E-06 1.63E-08 W 1.6 7.64E-07 2.50E-09 WNW 2.5 4.70E-07 1.40E-09 NW 4.8 2.52E-07 6.20E-10 NNW 2.2 1.12E-06 5.16E-09 Note: The Annual Average X/Q used for dose calculations is 3.30E-06 see/cubic meter.

The Tritium value X/Q used for dose calculations is 4.36E-06 sec/cubic meter.

The Annual Average D/Q used for dose calculations is 3.34E-08 inverse square meters.

5

Nearest Garden by Sector, Distance and D/Q Sector Distance (Miles)* D/Q.,,

N None None.

NE None None NE None None--

ENE None None E None None ESE None None SE None None SSE None None S None None SSW None None SW None None WSW None None W None None WNW None None NW None None NNW None None 6

Nearest Milk Animal by Sector, Distance and D/Q Sector Distance (Miles)* D/Q N None None NNE None None NE None None ENE None None E None None ESE None None SE None None SSE None None S None None SSW None None SW None None WSW None None W None None WNW None None NW None None NNW None None

  • No Milk samples are currently being collected.

7

Population by Sector and Distance Sector 0-1 1-2 2-3 3-4 4-5 Total N - - 5 59 80 1.4.4 NNE - - 5 59 31 95 NE - - 167 169 272 608 ENE - - 79 24 16 119 E - 154 182 22 358 ESE - 66 66 96 228 SE - - 159 340 66 565 SSE - 85 91 82 2489 2747 S 19 118 36 159 332 SSW - 6 3 6 60 75 SW 9 110 6 63., 47 235 WSW 38 69 9 6 - 122 W - 84 6 18 13 121 WNW - - 8 49. 116 173 NW - - - 5 5 NNW - -,, 6 44 -46 96 TOTAL 47 373. 882 1203 .-:3518 6023 Fhe average number of residentý per house was obtained from North Central Texas Council of Governments for Hood and Somervell Counties. The number-of residents per house is 2.57 and 2.74, respectively.

Note: 2011 thru 2014 Land Use Cenisps was performed with the use of maps and information provided by Somervell County/Hood County 9-1-14 addressi ng/ geographic information system. Changes were noted during the 2011 Land Use Cetisus in sector population which attributed to use of 911 (Hood and Somervell counties) dispatchers maps. A 9-1-1 map is vaulted under RPI-714-1.

8

Environmental Sample Locations Table Sampling Point Location Sample Type*

Al N-1.45 (Squaw Creek Park) A A2 N-9.4 (Granbury) A A3 E-3.5 (Children's Home) A A4 SSE-4.5 (Glen Rose) A A5 S/SSW-1.2 A A6 SW-12.3 (CONTROL) A A7 SW/WSW-0.95 A A8 NW-1.0 A Ri N-1.45 (Squaw Creek Park) R R2 N-4.4 R R3 N-6.5 R R4 N-9.4 (Granbury) R R5 NNE-I.1 R R6 NNE-5.65 R R7 NE-1.7 R R8 NE-4.8 R R9 ENE-2.5 R RIO ENE-5.0 R RI E-0.5 R RIZ E-1.9. R R13 E-3.5 (Children's Home) R R14 E-4.2 R R15 ESE-l.4 R R16 ESE-4.7 R R17 SE-1.3 R R18 SE-3.85 R 9

Environmental Sample Locations Table (cont.)

Sampling Point Location Sample Type*

R19 SE-4.6 R R20 SSE-1.3 R R21 SSE-4.4 (Glen Rose) R R22 SSE-4.5 (Glen Rose) R R23 S-1.5 R R24 S-4.2 R R25 SSW-l.i R R26 SSW-4.4 (State Park) R R27 SW-0.9 R R28 SW-4.8 (Girl Scout Camp) R R29 SW-12.3 (CONTROL) R R30 WSW-1.0 R R31 WSW-5.35 R R32 WSW-7.0 (CONTROL) R R33 W-1.0 R R34 W-2.0 R R35 W-5.5 R R36 WNW-1,0 R R37 WNW-5.0 R R38 WNW-6.7 R R39 NW-1.0 R R40 NW-5.7 R R41 NW-9.9 (Tolar) R R42 NNW-1,35 R R43 NNW-4.6 R 10

Environmental Sample Locations Table (cont.)

Sampling Point Location Sample Type*

SWi N-1.5 (Squaw Creek Reservoir Marina) SW SW2 N-9.9 (Lake Granbury) SW/DW' SW3 N-19.3 (CONTROL-Brazos River) SW SW4 NE-7,4 (Lake Granbury) SW SW5 ESE-1.4 (Squaw Creek Reservoir) SW 2 SW6 NNW-0. 1 (Squaw Creek Reservoir) SW/DWZ 3 GW1 W-1.2 (Security Rifle Range) GW 7 GW2 WSW-0. 1 (Somerville Water district) GW 3,4,6 GW3 SSE-4.6 (Glen Rose - Somerville Water District) GW 4 GW4 N-9.8 (Granbury) GW', 4,6 GW5 N-1.45 (Squaw Creek Park) GW4 SS1 NNE-1.0 (Squaw Creek Reservoir) SS SS2 N-9.9 (Lake Granbury) SS SS3 NE-7.4 (Lake Granbury) SS SS4 SE-5.3 (Squaw Creek) SS Fl ENE-2.0 (Squaw Creek Reservoir) F F2 NNE-8.0 (Lake Granbury) F FPI ENE-9.0 (Leonard Bros. Pecan Farm) FP 11

Environmental Sample Locations Table (cont.)

Sampling Point Location Sample Type*

BLU N-1.45 BL BL2 SW-1.0 BLO BL3 SW-13.5 (CONTROL) BRO

  • Sample Type: A - Air Sample; R - Direct Radiation; SW - Surface Water; DW - Drinking Water GW - Ground Water; SS - Shoreline Sediments; M - Milk; F - Fish; FP - Food Products; BL - Broadleaf Vegetation NOTES:
1. The municipal water system for the City of Granbury is supplied by surface water from Lake Granbury (location SW2) and ground water (location GW4). Each of these supplies is sampled. These samples are not required for compliance with Radiological Effluent Control 3/4.12.1, Table 3.12-1, because they are not affected by plant discharges.
2. This sample (location SW6) is representative of discharges from Squaw Creek Reservoir both down Squaw Creek and to Lake Granbury via the return line to Lake Granbury if used.
3. Plant potable water could be supplied by surface water from Squaw Creek Reservoir (location SW6) or ground water from onsite wells (location GW2) but is currently supplied by the Somervell County Water District from the Wheeler Branch Reservoir.

Each of these possible sources of water were sampled.

4. Ground water supplies in the plant site area are not affected by plant liquid effluents as discussed in CPSES FSAR Section 2.4.13 and are therefore not required to be monitored for radioactivity to meet the requirements of the Radiological Effluent Control 3/4.12.1, Table 3.12-1.
5. Broadleaf sampling will be performed at the specified locations if milk samples are unavailable from any location.
6. Plant Potable Water (GW2) and Glen Rose (GW3) are supplied from surface water by the Somervell Water District from the Wheeler Branch Reservoir.
7. CPNPP Security Rifle Range (GWl) is supplied by a local Well.

12

Environmenr.al Sampe .fLocations Map - 2 Mile Radius 13