ML15139A079

Annual Radiological Environmental Operating Report for January 1 Through December 31, 2014

ML15139A079
Person / Time
Site:	Pilgrim
Issue date:	05/13/2015
From:	Perkins E Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2.15.036
Download: ML15139A079 (169)

Text

Entergy Nuclear Operations, Inc.

SEntergy Pilgrim Nuclear Power Station 600 Rocky Hill Road Plymouth, MA 02360 May 13, 2015 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike Rockville, MD 20852

SUBJECT:

Entergy's Annual Radiological Environmental Operating Report for January 1 through December 31, 2014 Pilgrim Nuclear Power Station Docket No. 50-293 License No. DPR-35 LETTER NUMBER 2.15.036

Dear Sir or Madam:

In accordance with Pilgrim Technical Specification 5.6.2, Entergy Nuclear Operations, Inc.

submits the attached Annual Radiological Environmental Operating Report for January 1 through December 31, 2014.

This letter contains no new regulatory commitments.

Should you have any questions concerning the content of this letter, please contact me at (508) 830-8323.

Sincerely, Everett (Chip) Perkins Jr Manager, Regulatory Assurance/

EP/rmb

Attachment:

Pilgrim's Annual Radiological Environmental Operating Report for January 1 through December 31, 2014

PNPS Letter 2.15.036 Page 2 of 2 cc: Mr. Daniel H. Dorman Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 2100 Renaissance Boulevard, Suite 100 King of Prussia, PA 19406-1415 U. S. Nuclear Regulatory Commission ATTN: Director, Office of Nuclear Reactor Regulation One White Flint North 11555 Rockville Pike Rockville, MD 20852 NRC Senior Resident Inspector Pilgrim Nuclear Power Station Ms. Nadiyah Morgan, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Mail Stop O-8C2A Washington, DC 20555 Mr. John Giarrusso Jr.

Planning, Preparedness & Nuclear Section Chief Mass. Emergency Management Agency 400 Worcester Road Framingham, MA 01702

ATTACHMENT To PNPS Letter 2.15.036 PILGRIM NUCLEAR POWER STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 Annual Radiological Environmental Operating Report January 1 through December 31, 2014

-'Entergy Page 1

MS-Entergy--

PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 01 THROUGH DECEMBER 31, 2014 Prepared by: A~*A~C K.J. kjor "

0,ý -4e -267115

/

Senior HP/Chemistry Specialist Reviewed by: *e* -/*

'GA". rla'-kenbiller Chemistry Superintendent Reviewed by:

A Pe n a Radiation Protection Manager Page 2

Pilgrim Nuclear Power Station Annual Radiological Environmental Operating Report January-December 2014 TABLE OF CONTENTS SECTION SECTION TITLE PAGE EXECUTIVE

SUMMARY

6

1.0 INTRODUCTION

8 1.1 Radiation and Radioactivity 8 1.2 Sources of Radiation 9 1.3 Nuclear Reactor Operations 10 1.4 Radioactive Effluent Control 16 1.5 Radiological Impact on Humans 18 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 23 2.1 Pre-Operational Monitoring Results 23 2.2 Environmental Monitoring Locations 24 2.3 Interpretation of Radioactivity Analyses Results 27 2.4 Ambient Radiation Measurements 28 2.5 Air Particulate Filter Radioactivity Analyses 29 2.6 Charcoal Cartridge Radioactivity Analyses 30 2.7 Milk Radioactivity Analyses 30 2.8 Forage Radioactivity Analyses 31 2.9 Vegetable/Vegetation Radioactivity Analyses 31 2.10 Cranberry Radioactivity Analyses 32 2.11 Soil Radioactivity Analyses 32 2.12 Surface Water Radioactivity Analyses 32 2.13 Sediment Radioactivity Analyses 33 2.14 Irish Moss Radioactivity Analyses 33 2.15 Shellfish Radioactivity Analyses 33 2.16 Lobster Radioactivity Analyses 34 2.17 Fish Radioactivity Analyses 34 3.0

SUMMARY

OF RADIOLOGICAL IMPACT ON HUMANS 68

4.0 REFERENCES

70 APPENDIX A Special Studies 71 APPENDIX B Effluent Release Information 72 APPENDIX C Land Use Census 82 APPENDIX D Environmental Monitoring Program Discrepancies 83 APPENDIX E Environmental Dosimetry Company Annual Quality Assurance Status Report APPENDIX F GEL Laboratories LLC 2014 Annual Quality Assurance Report Page 3

Pilgrim Nuclear Power Station Annual Radiological Environmental Operating Report January-December 2014 LIST OF TABLES TABLE TABLE TITLE PAGE 1.2-1 Radiation Sources and Corresponding Doses 9 1.3-1 PNPS Operating Capacity Factor During 2014 10 2.2-1 Routine Radiological Environmental Sampling Locations 35 2.4-1 Offsite Environmental TLD Results 37 2.4-2 Onsite Environmental TLD Results 39 2.4-3 Average TLD Exposures By Distance Zone During 2014 40 2.5-1 Air Particulate Filter Radioactivity Analyses 41 2.6-1 Charcoal Cartridge Radioactivity Analyses 42 2.7-1 Milk Radioactivity Analyses 43 2.8-1 Forage Radioactivity Analyses 44 2.9-1 Vegetable/Vegetation Radioactivity Analyses 45 2.10-1 Cranberry Radioactivity Analyses 46 2.12-1 Surface Water Radioactivity Analyses 47 2.13-1 Sediment Radioactivity Analyses 48 2.14-1 Irish Moss Radioactivity Analyses 49 2.15-1 Shellfish Radioactivity Analyses 50 2.16-1 Lobster Radioactivity Analyses 51 2.17-1 Fish Radioactivity Analyses 52 3.0-1 Radiation Doses From 2014 Pilgrim Station Operations 69 B.1 Supplemental Information 73 B.2-A Gaseous Effluents Summation of All Releases 74 B.2-B Gaseous Effluents - Elevated Releases 75 B.2-C Gaseous Effluents - Ground Level Releases 77 B.3-A Liquid Effluents Summation of All Releases 79 B.3-B Liquid Effluents: January-December 2014 80 Page 4

Pilgrim Nuclear Power Station Annual Radiological Environmental Operating Report January-December 2014 LIST OF FIGURES FIGURE FIGURE TITLE PAGE 1.3-1 Radioactive Fission Product Formation 12 1.3-2 Radioactive Activation Product Formation 13 1.3-3 Barriers to Confine Radioactive Materials 14 1.5-1 Radiation Exposure Pathways 20 2.2-1 Environmental TLD Locations Within the PNPS Protected Area 53 2.2-2 TLD and Air Sampling Locations: Within 1 Kilometer 55 2.2-3 TLD and Air Sampling Locations: 1 to 5 Kilometers 57 2.2-4 TLD and Air Sampling Locations: 5 to 25 Kilometers 59 2.2-5 Terrestrial and Aquatic Sampling Locations 61 2.2-6 Environmental Sampling and Measurement Control Locations 63 2.5-1 Airborne Gross Beta Radioactivity Levels: Near Station Monitors 65 2.5-2 Airborne Gross Beta Radioactivity Levels: Property Line Monitors 66 2.5-3 Airborne Gross Beta Radioactivity Levels: Offsite Monitors 67 Page 5

EXECUTIVE

SUMMARY

ENTERGY NUCLEAR PILGRIM NUCLEAR POWER STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 01 THROUGH DECEMBER 31, 2014 INTRODUCTION This report summarizes the results of the Entergy Nuclear Radiological Environmental Monitoring Program (REMP) conducted in the vicinity of Pilgrim Nuclear Power Station (PNPS) during the period from January 1 to December 31, 2014. This document has been prepared in accordance with the requirements of PNPS Technical Specifications section 5.6.2.

The REMP has been established to monitor the radiation and radioactivity released to the environment as a result of Pilgrim Station's operation. This program, initiated in August 1968, includes the collection, analysis, and evaluation of radiological data in order to assess the impact of Pilgrim Station on the environment and on the general public.

SAMPLING AND ANALYSIS The environmental sampling media collected in the vicinity of PNPS and at distant locations include air particulate filters, charcoal cartridges, animal forage, vegetation, cranberries, seawater, sediment, Irish moss, shellfish, American lobster, and fishes.

During 2014, there were 1,240 samples collected from the atmospheric, aquatic, and terrestrial environments. In addition, 438 exposure measurements were obtained using environmental thermoluminescent dosimeters (TLDs).

A small number of inadvertent issues were encountered during 2014 in the collection of environmental samples in accordance with the PNPS Offsite Dose Calculation Manual (ODCM).

Two out of 440 TLDs were unaccounted for during the quarterly retrieval process. However, the 438 TLDs that were collected provided the information necessary to assess ambient radiation levels in the vicinity of Pilgrim Station. Equipment failures and power outages resulted in a small number of instances in which lower than normal volumes were collected at the airborne sampling stations. 571 of 572 air particulate and charcoal cartridges were collected and analyzed as required. A full description of any discrepancies encountered with the environmental monitoring program is presented in Appendix D of this report.

There were 1,296 analyses performed on the environmental media samples. Analyses were performed by the GEL Environmental Laboratory in Charleston, SC. Samples were analyzed as required by the PNPS ODCM.

LAND USE CENSUS The annual land use census in the vicinity of Pilgrim Station was conducted as required by the PNPS ODCM between September 09 and September 20, 2014. A total of 28 vegetable gardens having an area of more than 500 square feet were identified within five kilometers (three miles) of PNPS. No new milk or meat animals were located during the census. Of the 28 garden locations identified, samples were collected at or near three of the gardens as part of the environmental monitoring program. Other samples of natural vegetation were also collected in predicted high-deposition areas.

Page 6

RADIOLOGICAL IMPACT TO THE ENVIRONMENT During 2014, samples (except charcoal cartridges) collected as part of the REMP at Pilgrim Station continued to contain detectable amounts of naturally-occurring and man-made radioactive materials.

No samples indicated any detectable radioactivity attributable to Pilgrim Station operations. Offsite ambient radiation measurements using environmental TLDs beyond the site boundary ranged between 43 and 80 milliRoentgens per year. The range of ambient radiation levels observed with the TLDs is consistent with natural background radiation levels for Massachusetts.

RADIOLOGICAL IMPACT TO THE GENERAL PUBLIC During 2014, radiation doses to the general public as a result of Pilgrim Station's operation continued to be well below the federal limits and much less than the collective dose due to other sources of man-made (e.g., X-rays, medical, fallout) and naturally-occurring (e.g., cosmic, radon) radiation.

The calculated total body dose to the maximally exposed member of the general public from radioactive effluents and ambient radiation resulting from PNPS operations for 2014 was about 0.6 mrem for the year. This conservative estimate is well below the EPA's annual dose limit to any member of the general public and is a fraction of a percent of the typical dose received from natural and man-made radiation.

CONCLUSIONS The 2014 Radiological Environmental Monitoring Program for Pilgrim Station resulted in the collection and analysis of hundreds of environmental samples and measurements. The data obtained were used to determine the impact of Pilgrim Station's operation on the environment and on the general public.

An evaluation of direct radiation measurements, environmental sample analyses, and dose calculations showed that all applicable federal criteria were met. Furthermore, radiation levels and resulting doses were a small fraction of those that are normally present due to natural and man-made background radiation.

Based on this information, there is no significant radiological impact on the environment or on the general public due to Pilgrim Station's operation.

Page 7

1.0 INTRODUCTION

The Radiological Environmental Monitoring Program for 2014 performed by Entergy Nuclear Company for Pilgrim Nuclear Power Station (PNPS) is discussed in this report. Since the operation of a nuclear power plant results in the release of small amounts of radioactivity and low levels of radiation, the Nuclear Regulatory Commission (NRC) requires a program to be established to monitor radiation and radioactivity in the environment (Reference 1). This report, which is required to be published annually by Pilgrim Station's Technical Specifications section 5.6.2, summarizes the results of measurements of radiation and radioactivity in the environment in the vicinity of the Pilgrim Station and at distant locations during the period January 1 to December 31, 2014.

The Radiological Environmental Monitoring Program consists of taking radiation measurements and collecting samples from the environment, analyzing them for radioactivity content, and interpreting the results. With emphasis on the critical radiation exposure pathways to humans, samples from the aquatic, atmospheric, and terrestrial environments are collected. These samples include, but are not limited to: air, animal forage, vegetation, cranberries, seawater, sediment, Irish moss, shellfish, American lobster, and fish. Thermoluminescent dosimeters (TLDs) are placed in the environment to measure gamma radiation levels. The TLDs are processed and the environmental samples are analyzed to measure the very low levels of radiation and radioactivity present in the environment as a result of PNPS operation and other natural and man-made sources. These results are reviewed by PNPS's Chemistry staff and have been reported semiannually or annually to the Nuclear Regulatory Commission and others since 1972.

In order to more fully understand how a nuclear power plant impacts humans and the environment, background information on radiation and radioactivity, natural and man-made sources of radiation, reactor operations, radioactive effluent controls, and radiological impact on humans is provided. It is believed that this information will assist the reader in understanding the radiological impact on the environment and humans from the operation of Pilgrim Station.

1.1 Radiation and Radioactivity All matter is made of atoms. An atom is the smallest part into which matter can be broken down and still maintain all its chemical properties. Nuclear radiation is energy, in the form of waves or particles that is given off by unstable, radioactive atoms.

Radioactive material exists naturally and has always been a part of our environment. The earth's crust, for example, contains radioactive uranium, radium, thorium, and potassium. Some radioactivity is a result of nuclear weapons testing. Examples of radioactive fallout that is normally present in environmental samples are cesium-1 37 and strontium-90. Some examples of radioactive materials released from a nuclear power plant are cesium-137, iodine-131, strontium-90, and cobalt-60.

Radiation is measured in units of millirem, much like temperature is measured in degrees. A millirem is a measure of the biological effect of the energy deposited in tissue. The natural and man-made radiation dose received in one year by the average American is about 620 mrem (References 2, 3, 4).

Radioactivity is measured in curies. A curie is that amount of radioactive material needed to produce 37,000,000,000 nuclear disintegrations per second. This is an extremely large amount of radioactivity in comparison to environmental radioactivity. That is why radioactivity in the environment is measured in picocuries. One picocurie is equal to one trillionth of a curie.

Page 8

1.2 Sources of Radiation As mentioned previously, naturally occurring radioactivity has always been a part of our environment. Table 1.2-1 shows the sources and doses of radiation from natural and man-made sources.

Table 1.2-1 Radiation Sources and Corresponding Doses (1)

NATURAL MAN-MADE Radiation Dose Radiation Dose Source (millirem/year) Source (millirem/year)

Internal, inhalation(2) 3 230 Medical' ) 300 External, space 4 30 Consumer ) 12 Internal, ingestion 5 30 Industrial( ) 0.6 External, terrestrial 20 Occupational 0.6 Weapons Fallout < 1 Nuclear Power Plants < 1 Approximate Total 310 Approximate Total 315 Combined Annual Average Dose: Approximately 620 to 625 millirem/year (1)Information from NCRP Reports 160 and 94 (2) Primarily from airborne radon and its radioactive progeny (3) Includes CT (150 millirem), nuclear medicine (74 mrem), interventional fluoroscopy (43 mrem) and conventional radiography and fluoroscopy (30 mrem)

(4) Primarily from cigarette smoking (4.6 mrem), commercial air travel (3.4 mrem), building materials (3.5 mrem), and mining and agriculture (0.8 mrem)

(5) Industrial, security, medical, educational, and research Cosmic radiation from the sun and outer space penetrates the earth's atmosphere and continuously bombards us with rays and charged particles. Some of this cosmic radiation interacts with gases and particles in the atmosphere, making them radioactive in turn. These radioactive byproducts from cosmic ray bombardment are referred to as cosmogenic radionuclides. Isotopes such as beryllium-7 and carbon-14 are formed in this way. Exposure to cosmic and cosmogenic sources of radioactivity results in about 30 mrem of radiation dose per year.

Additionally, natural radioactivity is in our body and in the food we eat (about 30 millirem/yr), the ground we walk on (about 20 millirem/yr) and the air we breathe (about 230 millirem/yr). The majority of a person's annual dose results from exposure to radon and thoron in the air we breathe. These gases and their radioactive decay products arise from the decay of naturally occurring uranium, thorium and radium in the soil and building products such as brick, stone, and concrete. Radon and thoron levels vary greatly with location, primarily due to changes in the concentration of uranium and thorium in the soil. Residents at some locations in Colorado, New York, Pennsylvania, and New Jersey have a higher annual dose as a result of higher levels of radon/thoron gases in these areas.

Page 9

In total, these various sources of naturally-occurring radiation and radioactivity contribute to a total dose of about 310 mrem per year.

In addition to natural radiation, we are normally exposed to radiation from a number of man-made sources. The single largest doses from man-made sources result from therapeutic and diagnostic applications of x-rays and radiopharmaceuticals. The annual dose to an individual in the U.S. from medical and dental exposure is about 300 mrem. Consumer activities, such as smoking, commercial air travel, and building materials contribute about 13 mrem/yr. Much smaller doses result from weapons fallout (less than 1 mrem/yr) and nuclear power plants. Typically, the average person in the United States receives about 314 mrem per year from man-made sources. The collective dose from naturally-occurring and man-made sources results in a total dose of approximately 620 mrem/yr to the average American.

1.3 Nuclear Reactor Operations Pilgrim Station generates about 700 megawatts of electricity at full power, which is enough electricity to supply the entire city of Boston, Massachusetts. Pilgrim Station is a boiling water reactor whose nuclear steam supply system was provided by General Electric Co. The nuclear station is located on a 1600-acre site about eight kilometers (five miles) east-southeast of the downtown area of Plymouth, Massachusetts. Commercial operation began in December 1972.

Pilgrim Station was operational during most of 2014, with the exception of a four day outage in mid-May to repair a feed pump seal, and a six day power reduction in mid-August to repair a feedwater heater. The resulting monthly capacity factors are presented in Table 1.3-1.

TABLE 1.3-1 PNPS OPERATING CAPACITY FACTOR DURING 2014 (Based on rated reactor thermal power of 2028 Megawatts-Thermal)

Month Percent Capacity January 99.9%

February 99.9%

March 98.8%

April 99.8%

May 82.0%

June 99.1%

July 99.9%

August 85.8%

September 99.9%

October 99.0%

November 99.8%

December 98.4%

Annual Average 96.8%

Page 10

Nuclear-generated electricity is produced at Pilgrim Station by many of the same techniques used for conventional oil and coal-generated electricity. Both systems use heat to boil water to produce steam, The steam turns a turbine, which turns a generator, producing electricity. In both cases, the steam passes through a condenser where it changes back into water and recirculates back through the system. The cooling water source for Pilgrim Station is the Cape Cod Bay.

The key difference between Pilgrim's nuclear power and conventional power is the source of heat used to boil the water. Conventional plants bum fossil fuels in a boiler, while nuclear plants make use of uranium in a nuclear reactor.

Inside the reactor, a nuclear reaction called fission takes place. Particles, called neutrons, strike the nucleus of a uranium-235 atom, causing it to split into fragments called radioactive fission products.

The splitting of the atoms releases both heat and more neutrons. The newly-released neutrons then collide with and split other uranium atoms, thus making more heat and releasing even more neutrons, and on and on until the uranium fuel is depleted or spent. This process is called a chain reaction.

The operation of a nuclear reactor results in the release of small amounts of radioactivity and low levels of radiation. The radioactivity originates from two major sources, radioactive fission products and radioactive activation products.

Radioactive fission products, as illustrated in Figure 1.3-1 (Reference 5), originate from the fissioning of the nuclear fuel. These fission products get into the reactor coolant from their release by minute amounts of uranium on the outside surfaces of the fuel cladding, by diffusion through the fuel pellets and cladding and, on occasion, through defects or failures in the fuel cladding. These fission products circulate along with the reactor coolant water and will deposit on the internal surfaces of pipes and equipment. The radioactive fission products on the pipes and equipment emit radiation.

Examples of some fission products are krypton-85 (Kr-85), strontium-90 (Sr-90), iodine-131 (1-131),

xenon-1 33 (Xe-1 33), and cesium-1 37 (Cs-1 37).

Page II

Nuclear Fission Fission is the splitting of the uranium-235 atom by a neutron to release heat and more neutrons, creating a chain reaction.

Radiation and fission products are by-products of the process.

Radiation

-Radition Neutron Uranium Uranium Fission Products Figure 1.3-1 Radioactive Fission Product Formation Page 12

Radioactive activation products (see Figure 1.3-2), on the other hand, originate from two sources.

The first is by neutron bombardment of the hydrogen, oxygen and other gas (helium, argon, nitrogen) molecules in the reactor cooling water. The second is a result of the fact that the internals of any piping system or component are subject to minute yet constant corrosion from the reactor cooling water. These minute metallic particles (for example: nickel, iron, cobalt, or magnesium) are transported through the reactor core into the fuel region, where neutrons may react with the nuclei of these particles, producing radioactive products. So, activation products are nothing more than ordinary naturally-occurring atoms that are made unstable or radioactive by neutron bombardment.

These activation products circulate along with the reactor coolant water and will deposit on the internal surfaces of pipes and equipment. The radioactive activation products on the pipes and equipment emit radiation. Examples of some activation products are manganese-54 (Mn-54), iron-59 (Fe-59), cobalt-60 (Co-60), and zinc-65 (Zn-65).

-- 0 Co-60 Stable Radioactive Neutron Cobalt Nucleus Cobalt Nucleus Figure 1.3-2 Radioactive Activation Product Formation At Pilgrim Nuclear Power Station there are five independent protective barriers that confine these radioactive materials. These five barriers, which are shown in Figure 1.3-3 (Reference 5), are:

• fuel pellets;

• fuel cladding;

• reactor vessel and piping; P primary containment (drywell and torus); and,

• secondary containment (reactor building).

Page 13

SIMPLIFIED DIAGRAM OF A BOILING WATER REACTOR

4. PRIMARY CONTAINMENT

1. FUEL PELLETS 2.

/

REACTOR BUILDING DRYWELL Figure 1.3-3 Barriers To Confine Radioactive Materials Page 14

The ceramic uranium fuel pellets provide the first barrier. Most of the radioactive fission products are either physically trapped or chemically bound between the uranium atoms, where they will remain.

However, a few fission products that are volatile or gaseous may diffuse through the fuel pellets into small gaps between the pellets and the fuel cladding.

The second barrier, the fuel cladding, consists of zirconium alloy tubes that confine the fuel pellets.

The small gaps between the fuel and the cladding contain the noble gases and volatile iodines that are types of radioactive fission products. This radioactivity can diffuse to a small extent through the fuel cladding into the reactor coolant water.

The third barrier consists of the reactor pressure vessel, steel piping and equipment that confine the reactor cooling water. The reactor pressure vessel, which holds the reactor fuel, is a 65-foot high by 19-foot diameter tank with steel walls about nine inches thick. This provides containment for radioactivity in the primary coolant and the reactor core. However, during the course of operations and maintenance, small amounts of radioactive fission and activation products can escape through valve leaks or upon breaching of the primary coolant system for maintenance.

The fourth barrier is the primary containment. This consists of the drywell and the torus. The drywell is a steel lined enclosure that is shaped like an inverted light bulb. An approximately five foot thick concrete wall encloses the drywell's steel pressure vessel. The torus is a donut-shaped pressure suppression chamber. The steel walls of the torus are nine feet in diameter with the donut itself having an outside diameter of about 130 feet. Small amounts of radioactivity may be released from primary containment during maintenance.

The fifth barrier is the secondary containment or reactor building. The reactor building is the concrete building that surrounds the primary containment. This barrier is an additional safety feature to contain radioactivity that may escape from the primary containment. This reactor building is equipped with a filtered ventilation system that is used when needed to reduce the radioactivity that escapes from the primary containment.

The five barriers confine most of the radioactive fission and activation products. However, small amounts of radioactivity do escape via mechanical failures and maintenance on valves, piping, and equipment associated with the reactor cooling water system. The small amounts of radioactive liquids and gases that do escape the various containment systems are further controlled by the liquid purification and ventilation filtration systems. Also, prior to a release to the environment, control systems exist to collect and purify the radioactive effluents in order to reduce releases to the environment to as low as is reasonably achievable. The control of radioactive effluents at Pilgrim Station will be discussed in more detail in the next section.

Page 15

1.4 Radioactive Effluent Control The small amounts of radioactive liquids and gases that might escape the five barriers are purified in the liquid and gaseous waste treatment systems, then monitored for radioactivity, and released only if the radioactivity levels are below the federal release limits.

Radioactivity released from the liquid effluent system to the environment is limited, controlled, and monitored by a variety of systems and procedures which include:

" reactor water cleanup system;

" liquid radwaste treatment system;

" sampling and analysis of the liquid radwaste tanks; and,

• liquid waste effluent discharge header radioactivity monitor.

The purpose of the reactor water cleanup system is to continuously purify the reactor cooling water by removing radioactive atoms and non-radioactive impurities that may become activated by neutron bombardment. A portion of the reactor coolant water is diverted from the primary coolant system and is directed through ion exchange resins where radioactive elements, dissolved and suspended in the water, are removed through chemical processes. The net effect is a substantial reduction of the radioactive material that is present in the primary coolant water and consequently the amount of radioactive material that might escape from the system.

Reactor cooling water that might escape the primary cooling system and other radioactive water sources are collected in floor and equipment drains. These drains direct this radioactive liquid waste to large holdup tanks. The liquid waste collected in the tanks is purified again using the liquid radwaste treatment system, which consists of a filter and ion exchange resins.

Processing of liquid radioactive waste results in large reductions of radioactive liquids discharged into Cape Cod Bay. Of all wastes processed through liquid radwaste treatment, 90 to 95 percent of all wastes are purified and the processed liquid is re-used in plant systems.

Prior to release, the radioactivity in the liquid radwaste tank is sampled and analyzed to determine if the level of radioactivity is below the release limits and to quantify the total amount of radioactive liquid effluent that would be released. If the levels are below the federal release limits, the tank is drained to the liquid effluent discharge header.

This liquid waste effluent discharge header is provided with a shielded radioactivity monitor. This detector is connected to a radiation level meter and a strip chart recorder in the Control Room. The radiation alarm is set so that the detector will alarm before radioactivity levels exceed the release limits. The liquid effluent discharge header has an isolation valve. If an alarm is received, the liquid effluent discharge valve will automatically close, thereby terminating the release to the Cape Cod Bay and preventing any liquid radioactivity from being released that may exceed the release limits.

An audible alarm notifies the Control Room operator that this has occurred.

Some liquid waste sources which have a low potential for containing radioactivity, and/or may contain very low levels of contamination, may be discharged directly to the discharge canal without passing through the liquid radwaste discharge header. One such source of liquids is the neutralizing sump. However, prior to discharging such liquid wastes, the tank is thoroughly mixed and a representative sample is collected for analysis of radioactivity content prior to being discharged.

Page 16

Another means for adjusting liquid effluent concentrations to below federal limits is by mixing plant cooling water from the condenser with the liquid effluents in the discharge canal. This larger volume of cooling water further dilutes the radioactivity levels far below the release limits.

The preceding discussion illustrates that many controls exist to reduce the radioactive liquid effluents released to the Cape Cod Bay to as far below the release limits as is reasonably achievable.

Radioactive releases from the radioactive gaseous effluent system to the environment are limited, controlled, and monitored by a variety of systems and procedures which include:

• reactor building ventilation system;

" reactor building vent effluent radioactivity monitor;

• sampling and analysis of reactor building vent effluents;

• standby gas treatment system;

• main stack effluent radioactivity monitor and sampling;

• sampling and analysis of main stack effluents;

• augmented off-gas system;

• steam jet air ejector (SJAE) monitor; and,

• off-gas radiation monitor.

The purpose of the reactor building ventilation system is to collect and exhaust reactor building air.

Air collected from contaminated areas is filtered prior to combining it with air collected from other parts of the building. This combined airflow is then directed to the reactor building ventilation plenum that is located on the side of the reactor building. This plenum, which vents to the atmosphere, is equipped with a radiation detector. The radiation level meter and strip chart recorder for the reactor building vent effluent radioactivity monitor is located in the Control Room. To supplement the information continuously provided by the detector, air samples are taken periodically from the reactor building vent and are analyzed to quantify the total amount of tritium and radioactive gaseous and particulate effluents released.

If air containing elevated amounts of noble gases is routed past the reactor building vent's effluent radioactivity monitor, an alarm will alert the Control Room operators that release limits are being approached. The Control Room operators, according to procedure, will isolate the reactor building ventilation system and initiate the standby gas treatment system to remove airborne particulates and gaseous halogen radioactivity from the reactor building exhaust. This filtration assembly consists of high-efficiency particulate air filters and charcoal adsorber beds. The purified air is then directed to the main stack. The main stack has dilution flow that further reduces concentration levels of gaseous releases to the environment to as far below the release limits as is reasonably achievable.

The approximately 335 foot tall main stack has a special probe inside it that withdraws a portion of the air and passes it through a radioactivity monitoring system. This main stack effluent radioactivity monitoring system continuously samples radioactive particulates, iodines, and noble gases. Grab samples for a tritium analysis are also collected at this location. The system also contains radioactivity detectors that monitor the levels of radioactive noble gases in the stack flow and display the result on radiation level meters and strip chart recorders located in the Control Room. To supplement the information continuously provided by the detectors, the particulate, iodine, tritium, and gas samples are analyzed periodically to quantify the total amount of radioactive gaseous effluent being released.

The purpose of the augmented off-gas system is to reduce the radioactivity from the gases that are removed from the condenser. This purification system consists of two 30-minute holdup lines to Page 17

reduce the radioactive gases with short half-lives, several charcoal adsorbers to remove radioactive iodines and further retard the short half-life gases, and offgas filters to remove radioactive particulates. The recombiner collects free hydrogen and oxygen gas and recombines them into water. This helps reduce the gaseous releases of short-lived isotopes of oxygen that have been made radioactive by neutron activation.

The radioactive off-gas from the condenser is then directed into a ventilation pipe to which the off-gas radiation monitors are attached. The radiation level meters and strip chart recorders for this detector are also located in the Control Room. If a radiation alarm setpoint is exceeded, an audible alarm will sound to alert the Control Room operators. In addition, the off-gas bypass and charcoal adsorber inlet valve will automatically re-direct the off-gas into the charcoal adsorbers if they are temporarily being bypassed. If the radioactivity levels are not returned to below the alarm setpoint within 13 minutes, the off-gas releases will be automatically isolated, thereby preventing any gaseous radioactivity from being released that may exceed the release limits.

Therefore, for both liquid and gaseous releases, radioactive effluent control systems exist to collect and purify the radioactive effluents in order to reduce releases to the environment to as low as is reasonably achievable. The effluents are always monitored, sampled and analyzed prior to release to make sure that radioactivity levels are below the release limits. If the release limits are being approached, isolation valves in some of the waste effluent lines will automatically shut to stop the release, or Control Room operators will implement procedures to ensure that federal regulatory limits are always met.

1.5 Radiological Impact on Humans The final step in the effluent control process is the determination of the radiological dose impact to humans and comparison with the federal dose limits to the public. As mentioned previously, the purpose of continuous radiation monitoring and periodic sampling and analysis is to measure the quantities of radioactivity being released to determine compliance with the radioactivity release limits.

This is the first stage for assessing releases to the environment.

Next, calculations of the dose impact to the general public from Pilgrim Station's radioactive effluents are performed. The purpose of these calculations is to periodically assess the doses to the general public resulting from radioactive effluents to ensure that these doses are being maintained as far below the federal dose limits as is reasonably achievable. This is the second stage for assessing releases to the environment.

The types and quantities of radioactive liquid and gaseous effluents released from Pilgrim Station during each given year are reported to the Nuclear Regulatory Commission annually. The 2014 Radioactive Effluents are provided in Appendix B and will be discussed in more detail in Section 3 of this report. These liquid and gaseous effluents were well below the federal release limits and were a small percentage of the PNPS ODCM effluent control limits.

These measurements of the physical and chemical nature of the effluents are used to determine how the radionuclides will interact with the environment and how they can result in radiation exposure to humans. The environmental interaction mechanisms depend upon factors such as the hydrological (water) and meteorological (atmospheric) characteristics in the area. Information on the water flow, wind speed, wind direction, and atmospheric mixing characteristics are used to estimate how radioactivity will distribute and disperse in the ocean and the atmosphere.

Page 18

The most important type of information that is used to evaluate the radiological impact on humans is data on the use of the environment. Information on fish and shellfish consumption, boating usage, beach usage, locations of cows and goats, locations of residences, locations of gardens, drinking water supplies, and other usage information are utilized to estimate the amount of radiation and radioactivity received by the general public.

The radiation exposure pathway to humans is the path radioactivity takes from its release point at Pilgrim Station to its effect on man. The movement of radioactivity through the environment and its transport to humans is portrayed in Figure 1.5-1.

Page 19

-' )~~ GASEOUS

(. EFFLUENTS LIQUID EFFLUENTS

3. DIRECT RADIATION

4. DIRECT RADIATION (STATION)

/ /

2. AIR INHALATION //

(SOIL DEPOSITION) 1. DIRECT RADIATION (AIR SUBMERSION)

1. SHORELINE DIRECT RADIAl (FISHING, PICNICING)

5. CONSUMPTION (VEGETATION)

ZCL"'--"*,*DEPOSITION

2. DIRECT RADIATION (IMMERSION IN OCEAN, BOATING, SWIMMING)

INGESTION IO flEAT)! 6 DEPOSITION Figure 1.5-1 Radiation Exposure Pathways Page 20

There are three major ways in which liquid effluents affect humans:

• external radiation from liquid effluents that deposit and accumulate on the shoreline;

" external radiation from immersion in ocean water containing radioactive liquids; and,

• internal radiation from consumption of fish and shellfish containing radioactivity absorbed from the liquid effluents.

There are six major ways in which gaseous effluents affect humans:

• external radiation from an airborne plume of radioactivity;

• internal radiation from inhalation of airborne radioactivity;

• external radiation from deposition of radioactive effluents on soil;

• ambient (direct) radiation from contained sources at the power plant;

• internal radiation from consumption of vegetation containing radioactivity deposited on vegetation or absorbed from the soil due to ground deposition of radioactive effluents; and,

• internal radiation from consumption of milk and meat containing radioactivity deposited on forage that is eaten by cattle and other livestock.

In addition, ambient (direct) radiation emitted from contained sources of radioactivity at PNPS contributes to radiation exposure in the vicinity of the plant. Radioactive nitrogen-1 6 contained in the steam flowing through the turbine accounts for the majority of this "sky shine" radiation exposure immediately adjacent to the plant. Smaller amounts of ambient radiation result from low-level radioactive waste stored at the site prior to shipping and disposal.

To the extent possible, the radiological dose impact on humans is based on direct measurements of radiation and radioactivity in the environment. When PNPS-related activity is detected in samples that represent a plausible exposure pathway, the resulting dose from such exposure is assessed (see Appendix A). However, the operation of Pilgrim Nuclear Power Station results in releases of only small amounts of radioactivity, and, as a result of dilution in the atmosphere and ocean, even the most sensitive radioactivity measurement and analysis techniques cannot usually detect these tiny amounts of radioactivity above that which is naturally present in the environment. Therefore, radiation doses are calculated using radioactive effluent release data and computerized dose calculations that are based on very conservative NRC-recommended models that tend to result in over-estimates of resulting dose. These computerized dose calculations are performed by or for Entergy Nuclear personnel. These computer codes use the guidelines and methodology set forth by the NRC in Regulatory Guide 1.109 (Reference 6). The dose calculations are documented and described in detail in the Pilgrim Nuclear Power Station's Offsite Dose Calculation Manual (Reference 7), which has been reviewed by the NRC.

Monthly dose calculations are performed by PNPS personnel. It should be emphasized that because of the very conservative assumptions made in the computer code calculations, the maximum hypothetical dose to an individual is considerably higher than the dose that would actually be received by a real individual.

After dose calculations are performed, the results are compared to the federal dose limits for the public. The two federal agencies that are charged with the responsibility of protecting the public from radiation and radioactivity are the Nuclear Regulatory Commission (NRC) and the Environmental Protection Agency (EPA).

Page 21

The NRC, in 10CFR 20.1301 (Reference 8) limits the levels of radiation to unrestricted areas resulting from the possession or use of radioactive materials such that they limit any individual to a dose of:

• less than or equal to 100 mrem per year to the total body.

In addition to this dose limit, the NRC has established design objectives for nuclear plant licensees.

Conformance to these guidelines ensures that nuclear power reactor effluents are maintained as far below the legal limits as is reasonably achievable.

The NRC, in 10CFR 50 Appendix I (Reference 9) establishes design objectives for the dose to a member of the general public from radioactive material in liquid effluents released to unrestricted areas to be limited to:

• less than or equal to 3 mrem per year to the total body; and,

• less than or equal to 10 mrem per year to any organ.

The air dose due to release of noble gases in gaseous effluents is restricted to:

• less than or equal to 10 mrad per year for gamma radiation; and,

• less than or equal to 20 mrad per year for beta radiation.

The dose to a member of the general public from iodine-1 31, tritium, and all particulate radionuclides with half-lives greater than 8 days in gaseous effluents is limited to:

0 less than or equal to 15 mrem per year to any organ.

The EPA, in 40CFR1 90.10 Subpart B (Reference 10), sets forth the environmental standards for the uranium fuel cycle. During normal operation, the annual dose to any member of the public from the entire uranium fuel cycle shall be limited to:

• less than or equal to 25 mrem per year to the total body;

• less than or equal to 75 mrem per year to the thyroid; and,

• less than or equal to 25 mrem per year to any other organ.

The summary of the 2014 radiological impact for Pilgrim Station and comparison with the EPA dose limits and guidelines, as well as a comparison with natural/man-made radiation levels, is presented in Section 3 of this report.

The third stage of assessing releases to the environment is the Radiological Environmental Monitoring Program (REMP). The description and results of the REMP at Pilgrim Nuclear Power Station during 2014 is discussed in Section 2 of this report.

Page 22

2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2.1 Pre-Operational Monitorinn Results The Radiological Environmental Monitoring Program (REMP) at Pilgrim Nuclear Power Station was first initiated in August 1968, in the form of a pre-operational monitoring program prior to bringing the station on-line. The NRC's intent (Reference 11) with performing a pre-operational environmental monitoring program is to:

• measure background levels and their variations in the environment in the area surrounding the licensee's station; and,

" evaluate procedures, equipment, and techniques for monitoring radiation and radioactivity in the environment.

The pre-operational program (Reference 12) continued for approximately three and a half years, from August 1968 to June 1972. Examples of background radiation and radioactivity levels measured during this time period are as follows:

• Airborne Radioactivity Particulate Concentration (gross beta): 0.02 - 1.11 pCi/m 3;

" Ambient Radiation (TLDs): 4.2 - 22 micro-R/hr (37 - 190 mR/yr);

• Seawater Radioactivity Concentrations (gross beta): 12 - 31 pCi/liter;

• Fish Radioactivity Concentrations (gross beta): 2,200 - 11,300 pCi/kg;

• Milk Radioactive Cesium-1 37 Concentrations: 9.3 - 32 pCi/liter;

• Milk Radioactive Strontium-90 Concentrations: 4.7 - 17.6 pCi/liter;

" Cranberries Radioactive Cesium-1 37 Concentrations: 140 - 450 pCi/kg;

• Forage Radioactive Cesium-1 37 Concentrations: 150 - 290 pCi/kg.

This information from the pre-operational phase is used as a basis for evaluating changes in radiation and radioactivity levels in the vicinity of the plant following plant operation. In April 1972, just prior to initial reactor startup (June 12, 1972), Boston Edison Company implemented a comprehensive operational environmental monitoring program at Pilgrim Nuclear Power Station.

This program (Reference 13) provides information on radioactivity and radiation levels in the environment for the purpose of:

• demonstrating that doses to the general public and levels of radioactivity in the environment are within established limits and legal requirements;

• monitoring the transfer and long-term buildup of specific radionuclides in the environment to revise the monitoring program and environmental models in response to changing conditions;

• checking the condition of the station's operation, the adequacy of operation in relation to the adequacy of containment, and the effectiveness of effluent treatment so as to provide a mechanism of determining unusual or unforeseen conditions and, where appropriate, to trigger special environmental monitoring studies;

• assessing the dose equivalent to the general public and the behavior of radioactivity released during the unlikely event of an accidental release; and, Page 23

• determining whether or not the radiological impact on the environment and humans is significant.

The Nuclear Regulatory Commission requires that Pilgrim Station provide monitoring of the plant environs for radioactivity that will be released as a result of normal operations, including anticipated operational occurrences, and from postulated accidents. The NRC has established guidelines (Reference 14) that specify an acceptable monitoring program. The PNPS Radiological Environmental Monitoring Program was designed to meet and exceed these guidelines. Guidance contained in the NRC's Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 15) has been used to improve the program. In addition, the program has incorporated the provisions of an agreement made with the Massachusetts Wildlife Federation (Reference 16). The program was supplemented by including improved analysis of shellfish and sediment at substantially higher sensitivity levels to verify the adequacy of effluent controls at Pilgrim Station.

2.2 Environmental Monitoring Locations Sampling locations have been established by considering meteorology, population distribution, hydrology, and land use characteristics of the Plymouth area. The sampling locations are divided into two classes, indicator and control. Indicator locations are those that are expected to show effects from PNPS operations, if any exist. These locations were primarily selected on the basis of where the highest predicted environmental concentrations would occur. While the indicator locations are typically within a few kilometers of the plant, the control stations are generally located so as to be outside the influence of Pilgrim Station. They provide a basis on which to evaluate fluctuations at indicator locations relative to natural background radiation and natural radioactivity and fallout from prior nuclear weapons tests.

The environmental sampling media collected in the vicinity of Pilgrim Station during 2014 included air particulate filters, charcoal cartridges, animal forage, vegetation, cranberries, seawater, sediment, Irish moss, shellfish, American lobster, and fishes. The sampling medium, station description, station number, distance, and direction for indicator and control samples are listed in Table 2.2-1.

These sampling locations are also displayed on the maps shown in Figures 2.2-1 through 2.2-6.

The radiation monitoring locations for the environmental TLDs are shown in Figures 2.2-1 through 2.2-4. The frequency of collection and types of radioactivity analysis are described in Pilgrim Station's ODCM, Sections 3/4.5.

The land-based (terrestrial) samples and monitoring devices are collected by Entergy personnel. The aquatic samples are collected by Marine Research, Inc. The radioactivity analysis of samples and the processing of the environmental TLDs are performed by the GEL Environmental Laboratory.

The frequency, types, minimum number of samples, and maximum lower limits of detection (LLD) for the analytical measurements, are specified in the PNPS ODCM. During 2003, a revision was made to the PNPS ODCM to standardize it to the model program described in NUREG-1302 (Reference

14) and the Branch Technical Position of 1979 (Reference 15). In accordance with this standardization, a number of changes occurred regarding the types and frequencies of sample collections.

In regard to terrestrial REMP sampling, routine collection and analysis of soil samples was discontinued in lieu of the extensive network of environmental TLDs around PNPS, and the weekly collection of air samples at 11 locations. Such TLD monitoring and air sampling would provide an early indication of any potential deposition of radioactivity, and follow-up soil sampling could be performed on an as-needed basis. Also, with the loss of the indicator milk sample at the Plymouth County Farm and the lack of a sufficient substitute location that could provide suitable volumes for Page 24

analysis, it was deemed unnecessary to continue to collect and analyze control samples of milk.

Consequently, routine milk sampling was also dropped from the terrestrial sampling program. NRC guidance (Reference 14) contains provisions for collection of vegetation and forage samples in lieu of milk sampling. Such samples have historically been collected near Pilgrim Station as part of the routine REMP program.

In the area of marine sampling, a number of the specialized sampling and analysis requirements implemented as part of the Agreement with the Massachusetts Wildlife Federation (Reference 16) for licensing of a second reactor at PNPS were dropped. This agreement, made in 1977, was predicated on the construction of a second nuclear unit, and was set to expire in 1987. However, since the specialized requirements were incorporated into the PNPS Technical Specifications at the time, the requirements were continued. When the ODCM was revised in 1999 in accordance with NRC Generic Letter 89-01, the sampling program description was relocated to the ODCM. When steps were taken in 2003 to standardize the PNPS ODCM to the NUREG-1302 model, the specialized marine sampling requirements were changed to those of the model program. These changes include the following:

• A sample of the surface layer of sediment is collected, as opposed to specialized depth-incremental sampling to 30 cm and subdividing cores into 2 cm increments.

• Standard LLD levels of about 150 to 180 pCi/kg were established for sediment, as opposed to the specialized LLDs of 50 pCi/kg.

• Specialized analysis of sediment for plutonium isotopes was removed.

• Sampling of Irish moss, shellfish, and fish was rescheduled to a semiannual period, as opposed to a specialized quarterly sampling interval.

• Analysis of only the edible portions of shellfish (mussels and clams), as opposed to specialized additional analysis of the shell portions.

" Standard LLD levels of 130 to 260 pCi/kg were established for edible portions of shellfish, as opposed to specialized LLDs of 5 pCi/kg.

The PNPS ODCM was revised in 2009. In conjunction with this revision, two changes were made to the environmental sampling program. Due to damage from past storms to the rocky areas at Manomet Point, there is no longer a harvestable population of blue mussels at this site. Several attempts have been made over the past years to collect samples from this location, but all efforts were unsuccessful. Because of unavailability of mussels at this location as a viable human foodchain exposure pathway, this location was dropped from the sampling program. The other change involved the twice per year sampling of Group II fishes in the vicinity of the PNPS discharge outfall, represented by species such as cunner and tautog. Because these fish tend to move away from the discharge jetty during colder months, they are not available for sampling at a six-month semi-annual sampling period. The sampling program was modified to reduce the sampling for Group II fishes to once per year, when they are available during warmer summer months.

Upon receipt of the analysis results from the analytical laboratories, the PNPS staff reviews the results. If the radioactivity concentrations are above the reporting levels, the NRC must be notified within 30 days. For radioactivity that is detected that is attributable to Pilgrim Station's operation, calculations are performed to determine the cumulative dose contribution for the current year.

Depending upon the circumstances, a special study may also be completed (see Appendix A for 2014 special studies). Most importantly, if radioactivity levels in the environment become elevated as a result of the station's operation, an investigation is performed and corrective actions are recommended to reduce the amount of radioactivity to as far below the legal limits as is reasonably achievable.

The radiological environmental sampling locations are reviewed annually, and modified if necessary.

A garden and milk animal census is performed every year to identify changes in the use of the environment in the vicinity of the station to permit modification of the monitoring and sampling locations. The results of the 2014 Garden and Milk Animal Census are reported in Appendix C.

Page 25

The accuracy of the data obtained through Pilgrim Station's Radiological Environmental Monitoring Program is ensured through a comprehensive Quality Assurance (QA) programs. PNPS's QA program has been established to ensure confidence in the measurements and results of the radiological monitoring program through:

" Regular surveillances of the sampling and monitoring program;

" An annual audit of the analytical laboratory by the sponsor companies;

• Participation in cross-check programs;

• Use of blind duplicates for comparing separate analyses of the same sample; and,

" Spiked sample analyses by the analytical laboratory.

QA audits and inspections of the Radiological Environmental Monitoring Program are performed by the NRC, American Nuclear Insurers, and by the PNPS Quality Assurance Department.

The GEL Environmental Laboratory conducts extensive quality assurance and quality control programs. The 2014 results of these programs are summarized in Appendix E. These results indicate that the analyses and measurements performed during 2014 exhibited acceptable precision and accuracy.

Page 26

2.3 Interpretation of Radioactivity Analyses Results The following pages summarize the analytical results of the environmental samples collected during 2014. Data for each environmental medium are included in a separate section. A table that summarizes the year's data for each type of medium follows a discussion of the sampling program and results. The unit of measurement for each medium is listed at the top of each table. The left hand column contains the radionuclides being reported, total number of analyses of that radionuclide, and the number of measurements that exceed ten times the yearly average for the control station(s). The latter are classified as "non-routine" measurements. The next column lists the Lower Limit of Detection (LLD) for those radionuclides that have detection capability requirements specified in the PNPS ODCM.

Those sampling stations within the range of influence of Pilgrim Station and which could conceivably be affected by its operation are called "indicator" stations. Distant stations, which are beyond plant influence, are called "control" stations. Ambient radiation monitoring stations are broken down into four separate zones to aid in data analysis.

For each sampling medium, each radionuclide is presented with a set of statistical parameters. This set of statistical parameters includes separate analyses for (1) the indicator stations, (2) the station having the highest annual mean concentration, and (3) the control stations. For each of these three groups of data, the following values are calculated:

• The mean value of detectable concentrations, including only those values above LLD;

" The standard deviation of the detectable measurements;

" The lowest and highest concentrations; and,

• The number of positive measurements (activity which is three times greater than the standard deviation), out of the total number of measurements.

Each single radioactivity measurement datum is based on a single measurement and is reported as a concentration plus or minus one standard deviation. The quoted uncertainty represents only the random uncertainty associated with the measurement of the radioactive decay process (counting statistics), and not the propagation of all possible uncertainties in the sampling and analysis process.

A sample or measurement is considered to contain detectable radioactivity if the measured value (e.g., concentration) exceeds three times its associated standard deviation. For example, a vegetation sample with a cesium-137 concentration of 85 +/- 21 pCi/kilogram would be considered "positive" (detectable Cs-1 37), whereas another sample with a concentration of 60 +/- 32 pCi/kilogram would be considered "negative", indicating no detectable cesium-137. The latter sample may actually contain cesium-137, but the levels counted during its analysis were not significantly different than the background levels.

The analytical laboratory that analyzes the various REMP samples employs a background subtraction correction for each analysis. A blank sample that is known not to contain any plant-related activity is analyzed for radioactivity, and the count rate for that analysis is used as the background correction. That background correction is then subtracted from the results for the analyses in that given set of samples. For example, if the blank/background sample produces 50 counts, and a given sample being analyzes produces 47 counts, then the net count for that sample is reported as -3 counts. That negative value of -3 counts is used to calculate the concentration of radioactivity for that particular analysis. Such a sample result is technically more valid than reporting a qualitative value such as "<LLD" (Lower limit of Detection) or "NDA" (No Detectable Activity".

Page 27

As an example of how to interpret data presented in the results tables, refer to the first entry on the table for air particulate filters (page 41). Gross beta (GR-B) analyses were performed on 571 routine samples. None of the samples exceeded ten times the average concentration at the control location. The lower limit of detection (LLD) required by the ODCM is 0.01 pCi/m 3.

For samples collected from the ten indicator stations, 502 out of 519 samples indicated detectable gross beta activity at the three-sigma (standard deviation) level. The mean concentration of gross beta activity in these 519 indicator station samples was 0.011 +/- 0.0058 (1.1E-2 +/- 5.8E-3) pCi/m 3.

Individual values ranged from -0.0055 to 0.034 (-5.5E 3.4E-2) pCi/m 3.

The monitoring station which yielded the highest mean concentration was indicator location PC (Plymouth Center), which yielded a mean concentration of 0.013 +/- 0.0063 pCi/m 3 , based on 50 detectable indications out of 52 samples observations. Individual values ranged from -0.00038 to 0.032 pCi/m 3 . Fifty-two of the fifty-two samples showed detectable activity at the three-sigma level.

At the control location, 51 out of 52 samples yielded detectable gross beta activity, for an average concentration of 0.012 +/- 0.0054 pCi/m 3. Individual samples at the East Weymouth control location ranged from -0.0017 to 0.026 pCi/m 3 .

Referring to the last entry row in the table, analyses for cesium-137 (Cs-137) were performed 44times (quarterly composites for 11 stations

• 4 quarters). No samples exceeded ten times the mean control station concentration. The required LLD value Cs-137 in the PNPS ODCM is 0.06 pCi/m 3.

At the indicator stations, all 40 of the Cs-137 measurements were below the detection level. The same was true for the four measurements made on samples collected from the control location.

2.4 Ambient Radiation Measurements The primary technique for measuring ambient radiation exposure in the vicinity of Pilgrim Station involves posting environmental thermoluminescent dosimeters (TLDs) at given monitoring locations and retrieving the TLDs after a specified time period. The TLDs are then taken to a laboratory and processed to determine the total amount of radiation exposure received over the period. Although TLDs can be used to monitor radiation exposure for short time periods, environmental TLDs are typically posted for periods of one to three months. Such TLD monitoring yields average exposure rate measurements over a relatively long time period. The PNPS environmental TLD monitoring program is based on a quarterly (three month) posting period, and a total of 110 locations are monitored using this technique. In addition, 27 of the 110 TLDs are located onsite, within the PNPS protected/restricted area, where the general public does not have access.

Out of the 440 TLDs (110 locations

• 4 quarters) posted during 2014, 438 were retrieved and processed. Those TLDs missing from their monitoring locations were lost to degradation of TLD holders. In addition, several TLDs that had been posted during the 4 th Quarter of 2014 were left in the field for an additional quarter due to limited access following January storms that interrupted the retrieval and exchange. When these TLDs were ultimately retrieved in Apr-2015, the exposure results for the 6-month period monitored by the TLDs were reported for the 4 th quarter 2014 period.

These discrepancies are discussed in Appendix D. The results for environmental TLDs located offsite, beyond the PNPS protected/restricted area fence, are presented in Table 2.4-1. Results from onsite TLDs posted within the restricted area are presented in Table 2.4-2. In addition to TLD results for individual locations, results from offsite TLDs were grouped according to geographic zone to determine average exposure rates as a function of distance. These results are summarized in Table 2.4-3. All of the listed exposure values represent continuous occupancy (2190 hr/qtr or 8760 hr/yr).

Page 28

Annual exposure rates measured at locations beyond the PNPS protected area boundary ranged from 43 to 173 mR/yr. The average exposure rate at control locations greater than 15 km from Pilgrim Station (i.e., Zone 4) was 60.0 +/- 7.7 mR/yr. When the 3-sigma confidence interval is calculated based on these control measurements, 99% of all measurements of background ambient exposure would be expected to be between 37 and 83 mR/yr. The results for all TLDs within 15 km (excluding those Zone 1 TLDs posted within the site boundary) ranged from 47 to 82 mR/yr, which compares favorably with the preoperational results of 37 - 190 mR/yr.

Inspection of onsite TLD results listed in Table 2.4-2 indicates that all of those TLDs located within the PNPS protected/restricted area yield exposure measurements higher than the average natural background. Such results are expected due to the close proximity of these locations to radiation sources onsite. The radionuclide nitrogen-16 (N-16) contained in steam flowing through the turbine accounts for most of the exposure onsite. Although this radioactivity is contained within the turbine and is not released to the atmosphere, the "sky shine" which occurs from the turbine increases the ambient radiation levels in areas near the turbine building.

A small number of offsite TLD locations in close proximity to the protected/restricted area indicated ambient radiation exposure above expected background levels. All of these locations are on Pilgrim Station controlled property, and experience exposure increases due to turbine sky shine (e.g.,

locations OA, TC, PB, and P01) and/or transit and storage of radwaste onsite (e.g., locations BLE and BLW). Due to heightened security measures following September 11 2001, members for the general public do not have access to such locations within the owner-controlled area.

One TLD, located on the exterior wall of the Plymouth Memorial Hall, indicated an annual exposure of 80 mR in 2014. The higher exposure within the building at this location is due to the close proximity of stone (granite) building material, which contains higher levels of naturally-occurring radioactivity.

It should be noted that several of the TLDs used to calculate the Zone 1 averages presented in Table 2.4-3 are located on Pilgrim Station property. If the Zone 1 value is corrected for the near-site TLDs (those less than 0.6 km from the Reactor Building), the Zone 1 mean falls from a value of 72.6

+/- 23.1 mR/yr to 62.2 +/- 8.1 mR/yr. Additionally, exposure rates measured at areas beyond Entergy's control did not indicate any increase in ambient exposure from Pilgrim Station operation. For example, the annual exposure rate calculated from the two TLDs adjacent to the nearest offsite residence 0.80 kilometers (0.5 miles) southeast of the PNPS Reactor Building was 64.9 +/- 7.5 mR/yr, which compares quite well with the average control location exposure of 62.2 +/- 8.1 mR/yr.

In conclusion, measurements of ambient radiation exposure around Pilgrim Station do not indicate any significant increase in exposure levels. Although some increases in ambient radiation exposure level were apparent on Entergy property very close to Pilgrim Station, there were no measurable increases at areas beyond Entergy's control.

2.5 Air Particulate Filter Radioactivity Analyses Airborne particulate radioactivity is sampled by drawing a stream of air through a glass fiber filter that has a very high efficiency for collecting airborne particulates. These samplers are operated continuously, and the resulting filters are collected weekly for analysis. Weekly filter samples are analyzed for gross beta radioactivity, and the filters are then composited on a quarterly basis for each location for gamma spectroscopy analysis. PNPS uses this technique to monitor 10 locations in the Plymouth area, along with the control location in East Weymouth.

Page 29

Out of 572 filters (11 locations

• 52 weeks), 571 samples were collected and analyzed during 2014.

One set of filters was left on during a two-week period in Feb-2014 when the sampler at Manomet Substation was inaccessible due to ice buildup. Although the sampler was inaccessible, there was no loss of sampling during the period. There were also a few instances where power was lost or pumps failed during the course of the sampling period at some of the air sampling stations, resulting in lower than normal sample volumes. All of these discrepancies are noted in Appendix D.

The results of the analyses performed on these 571 filter samples are summarized in Table 2.5-1.

Trend plots for the gross beta radioactivity levels at the near station, property line, and offsite airborne monitoring locations are shown in Figures 2.5-1, 2.5-2 and 2.5-3, respectively. Gross beta radioactivity was detected in 553 of the filter samples collected, including 51 of the 52 control location samples. This gross beta activity arises from naturally-occurring radionuclides such as radon decay daughter products. Naturally-occurring beryllium-7 was detected in 44 out of 44 of the quarterly composites analyzed with gamma spectroscopy. No airborne radioactivity attributable to Pilgrim Station was detected in any of the samples collected during 2014, and results of any detectable naturally-occurring radioactivity were similar to those observed in the preoperational monitoring program.

2.6 Charcoal Cartridge Radioactivity Analyses Airborne radioactive iodine is sampled by drawing a stream of air through a charcoal cartridge after it has passed through the high efficiency glass fiber filter. As is the case with the air particulate filters, these samplers are operated continuously, and the resulting cartridges are collected weekly for analysis. Weekly cartridge samples are analyzed for radioactive iodine. The same eleven locations monitored for airborne particulate radioactivity are also sampled for airborne radioiodine.

Out of 572 cartridges (11 locations

• 52 weeks), 571 samples were collected and analyzed during 2014. One set of filters was left on during a two-week period in Feb-2014 when the sampler at Manomet Substation was inaccessible due to ice buildup. Although the sampler was inaccessible, there was no loss of sampling during the period. There were also a few instances where power was lost or pumps failed during the course of the sampling period at some of the air sampling stations, resulting in lower than normal sample volumes. All of these discrepancies are noted in Appendix D.

Despite such events during 2014, required LLDs were met on 571 of the 571 cartridges collected during 2014.

The results of the analyses performed on these charcoal cartridges are summarized in Table 2.6-1.

No airborne radioactive iodine attributable to Pilgrim Station was detected in any of the charcoal cartridges collected.

2.7 Milk Radioactivity Analyses In July 2002, the Plymouth County Farm ceased operation of its dairy facility. This was historically the only dairy facility near Pilgrim Station, and had been sampled continuously since Pilgrim Station began operation in 1972. Although attempts were made to obtain samples from an alternate indicator location within 5 miles as specified in NRC guidance (Reference 14), a suitable substitute location could not be found. Thus, milk collection at an indicator location was discontinued in July 2002, but control samples of milk continued to be collected and analyzed in the event an indicator location could be secured. In conjunction with the standardization of the ODCM during 2003, the decision was made to remove milk sampling from the PNPS Radiological Environmental Monitoring Program since no suitable milk sampling location existed in the vicinity of Pilgrim Station.

The nearest milk animals to Pilgrim Station are located at the Plimoth Plantation, approximately 2.5 miles west of PNPS, in a relatively upwind direction. Due to the limited number of milk animals available, this location is not able to provide the necessary volume of 4 gallons of milk every two Page 30

weeks to facilitate the milk sampling program and meet the required detection sensitivities. Although milk sampling is not performed at Plimoth Plantation, effluent dose calculations are performed for this location assuming the presence of a milk ingestion pathway, as part of the annual Effluent and Waste Disposal Report (Reference 17).

As included in a provision in standard ODCM guidance in NUREG-1302 (Reference 13), sampling and analysis of vegetation from the offsite locations calculated to have the highest D/Q deposition factor can be performed in lieu of milk sampling. Such vegetation sampling has been routinely performed at Pilgrim Station as part of the radiological environmental monitoring program, and the results of this sampling are presented in Section 2.9.

2.8 Foraae Radioactivity Analyses Samples of animal forage (hay) had been collected in the past from the Plymouth County Farm, and from control locations in Bridgewater. However, due to the absence of any grazing animals within a five-mile radius of Pilgrim Station that are used for generation of food products (milk or meat), no samples of forage were collected during 2014. A number of wild vegetation samples were collected within a five mile radius of Pilgrim Station as part of the vegetable/vegetation sampling effort, and the results of this sampling would provide an indication of any radioactivity potentially entering the forage-milk or forage-meat pathways. Results of the vegetable/vegetation sampling effort are discussed in the following section.

2.9 VegetableNecietation Radioactivity Analyses Samples of vegetables and naturally-growing vegetation have historically been collected from the Plymouth County Farm and from the control locations in Bridgewater, Sandwich, and Norton.

Results of the land-use census census are discussed in Appendix C. In addition to these garden samples, naturally-growing vegetation is collected from locations yielding the highest D/Q deposition factors. All of the various samples of vegetables/vegetation are collected annually and analyzed by gamma spectroscopy.

Seventeen samples of vegetables/vegetation were collected and analyzed as required during 2014.

Results of the gamma analyses of these samples are summarized in Table 2.9-1. Naturally-occurring beryllium-7, potassium-40, and actinium/thorium-228 were identified in several of the samples collected. Cesium-137 was also detected in four out of 10 samples of vegetation collected from indicator locations, and one of seven control samples collected, with concentrations ranging from non-detectable (<12 pCi/kg) up to 133 pCi/kg. The highest concentration of 133 pCi/kg was detected in a sample of natural vegetation collected from the Pine Hills area of the Pine Hills south of PNPS. This Cs-1 37 result is within of the normal range of average values expected for weapons-testing fallout (75 to 145 pCi/kg as projected from the pre-operational sampling program). It should be noted that natural vegetation samples collected in the 1990s often showed detectable Cs-137 from nuclear weapons tests up into the range of 300 to 400 pCi/kg, whereas soil samples often indicated concentrations in excess of 2000 pCi/kg. Cs-137 has a 30-year half-life, and measureable concentrations still remain in soil and vegetation as a result of atmospheric nuclear weapons testing performed during the 1950s through 1970s. Weekly particulate air filters collected from the Cleft Rock sampling station within 400 meters of where the vegetation was sampled indicated no detectable Cs-1 37. A review of effluent data presented in Appendix B indicates that there were no measurable airborne releases of Cs-1 37 from Pilgrim Station during 2014 that could have attributed to this level. The sample with the highest level of Cs-137 also contained high levels of AcTh-228, indicating appreciable soil content on the vegetation. This sample of natural vegetation was analyzed "as is" without any measure to clean the samples as normally would be performed prior to consuming vegetables, and would have detected any Cs-137 in soil adhering to those leaves collected. Certain species of plants such as sassafras are also known to concentrate chemical Page 31

elements like cesium, and this higher-than-expected level is likely due to a combination of external soil contamination and bioconcentration in the leaves of the plants sampled. These levels are not believed to be indicative of any releases associated with Pilgrm Station. No radioactivity attributable to Pilgrim Station was detected in any of the vegetable/vegetation samples collected during 2014, and results of any detectable naturally-occurring radioactivity were similar to those observed in the preoperational monitoring program.

2.10 Cranberry Radioactivity Analyses Samples of cranberries are normally collected from two bogs in the Plymouth area and from the control location in Kingston. Samples of cranberries are collected annually and analyzed by gamma spectroscopy. In 2012, the bog on Bartlett Road ceased harvesting operations, and a sample was collected from an alternate location along Beaver Dam Road. Samples were also not available from the historical control location in Halifax, and a substitute control sample was collected from a bog in Kingston. These discrepancies are noted in Appendix D.

Two samples of cranberries were collected and analyzed during 2014. One of the bogs normally sampled along Bartlett Road is no longer in production. Results of the gamma analyses of cranberry samples are summarized in Table 2.10-1. Cranberry samples collected during 2014 yielded detectable levels of naturally-occurring beryllium-7, potassium-40, and actinium/thorium-228. No radioactivity attributable to Pilgrim Station was detected in any of the samples collected during 2014, and results of any detectable naturally-occurring radioactivity were similar to those observed in the preoperational monitoring program.

2.11 Soil Radioactivity Analyses In the past, a survey of radioactivity in soil had been conducted once every three years at the 10 air sampling stations in the Plymouth area and the control location in East Weymouth. However, in conjunction with standardization of the ODCM during 2003, the soil survey effort was abandoned in favor of the extensive TLD monitoring effort at Pilgrim Station. Prior to ending the soil survey effort, there had been no apparent trends in radioactivity measurements at these locations.

2.12 Surface Water Radioactivity Analyses Samples of surface water are routinely collected from the discharge canal, Bartlett Pond in Manomet and from the control location at Powder Point Bridge in Duxbury. Grab samples are collected weekly from the Bartlett Pond and Powder Point Bridge locations. Samples of surface water are composited every four weeks and analyzed by gamma spectroscopy and low-level iodine analysis. These monthly composites are further composited on a quarterly basis and tritium analysis is performed on these quarterly samples.

A total of 36 samples (3 locations

• 12 sampling periods) of surface water were collected and analyzed as required during 2014. Results of the analyses of water samples are summarized in Table 2.12-1. Naturally-occurring potassium-40 was detected in several of the samples, especially those composed primarily of seawater. No radioactivity attributable to Pilgrim Station was detected in any of the surface water samples collected during 2014.

In response to the Nuclear Energy Institute Groundwater Protection Initiative, Pilgrim Station installed a number of groundwater monitoring wells within the protected area in late 2007. Because all of these wells are onsite, they are not included in the offsite radiological monitoring program, and are not presented in this report. Details regarding Pilgrim Station's groundwater monitoring effort can be found in the Annual Radioactive Effluent Release Report.

Page 32

2.13 Sediment Radioactivity Analyses Samples of sediment are routinely collected from the outfall area of the discharge canal and from three other locations in the Plymouth area (Manomet Point, Plymouth Harbor and Plymouth Beach),

and from control locations in Duxbury and Marshfield. Samples are collected twice per year and are analyzed by gamma spectroscopy.

Twelve of twelve required samples of sediment were collected during 2014. Gamma analyses were performed on these samples. Results of the gamma analyses of sediment samples are summarized in Table 2.13-1. Naturally-occurring beryllium-7, potassium-40, thallium-208, lead-12, lead-214, radium-226, and actinium/thorium-228 were detected in a number of the samples. No radioactivity attributable to Pilgrim Station was detected in any of the samples collected during 2014, and results of any detectable naturally-occurring radioactivity were similar to those observed in the preoperational monitoring program.

2.14 Irish Moss Radioactivity Analyses Samples of Irish moss are collected from the discharge canal outfall and two other locations in the Plymouth area (Manomet Point, Ellisville), and from a control location in Marshfield (Brant Rock). All samples are collected on a semiannual basis, and processed in the laboratory for gamma spectroscopy analysis.

Eight samples of Irish moss scheduled for collection during 2014 were obtained and analyzed.

Results of the gamma analyses of these samples are summarized in Table 2.14-1. Naturally-occurring potassium-40 was detected in a number of the samples. No radioactivity attributable to Pilgrim Station was detected in any of the samples collected during 2014, and results of any detectable naturally-occurring radioactivity were similar to those observed in the preoperational monitoring program.

2.15 Shellfish Radioactivity Analyses Samples of blue mussels, soft-shell clams and quahogs are collected from the discharge canal outfall and one other location in the Plymouth area (Plymouth Harbor), and from control locations in Duxbury and Marshfield. All samples are collected on a semiannual basis, and edible portions processed in the laboratory for gamma spectroscopy analysis.

Nine of the 10 required samples of shellfish meat scheduled for collection during 2014 were obtained and analyzed. Samples were unavailable during the spring collection season due to scouring action from winter storms. This discrepancy is discussed in Appendix D. Results of the gamma analyses of these samples are summarized in Table 2.15-1. Naturally-occurring potassium-40 was detected in a number of the samples. No radioactivity attributable to Pilgrim Station was detected in any of the samples collected during 2014, and results of any detectable naturally-occurring radioactivity were similar to those observed in the preoperational monitoring program.

Page 33

2.16 Lobster Radioactivity Analyses Samples of lobsters are routinely collected from the outfall area of the discharge canal and from control locations in Cape Cod Bay and Vineyard Sound. Samples are collected monthly from the discharge canal outfall from June through September and once annually from the control locations.

All lobster samples are normally analyzed by gamma spectroscopy.

Nine samples of lobsters were collected as required during 2014. Results of the gamma analyses of these samples are summarized in Table 2.16-1. Naturally-occurring potassium-40 was detected in a number of the samples. No radioactivity attributable to Pilgrim Station was detected in any of the samples collected during 2014, and results of any detectable naturally-occurring radioactivity were similar to those observed in the preoperational monitoring program.

2.17 Fish Radioactivity Analyses Samples of fish are routinely collected from the area at the outfall of the discharge canal and from the control locations in Cape Cod Bay and Buzzard's Bay. Fish species are grouped into four major categories according to their biological requirements and mode of life. These major categories and the representative species are as follows:

• Group I - Bottom-Oriented: Winter Flounder, Yellowtail Flounder

" Group II - Near-Bottom Distribution: Tautog, Cunner, Pollock, Atlantic Cod, Hake

" Group III - Anadromous: Alewife, Smelt, Striped Bass

• Group IV - Coastal Migratory: Bluefish, Herring, Menhaden, Mackerel Group I fishes are sampled on a semiannual basis from the outfall area of the discharge canal, and on an annual basis from a control location. Group II, Ill, and IV fishes are sampled annually from the discharge canal outfall and control location. All samples of fish are analyzed by gamma spectroscopy.

Six samples of fish were collected during 2014. The autumn sample of Group I Fish (flounder) was not available from the Discharge Canal Outfall during the October sampling period due to seasonal unavailability as the fish moved away from the Discharge Outfall to deeper water. The seasonal sample of Group II fish (tautog; cunner) was not available from the Discharge Outfall due to population declines in the species along the outer breakwater. The sample of Group III fish (alewife, smelt, striped bass) from the control location was missed due to seasonal unavailability, fishing restrictions, and low fish numbers during the latter half of the year. These discrepancies are discussed in Appendix D. Results of the gamma analyses of fish samples collected are summarized in Table 2.17-1. The only radionuclide detected in any of the fish samples was naturally-occurring potassium-40. No radioactivity attributable to Pilgrim Station was detected in any of the fish samples collected during 2014, and results of any detectable naturally-occurring radioactivity were similar to those observed in the preoperational monitoring program.

Page 34

Table 2.2-1 Routine Radiological Environmental Sampling Locations Pilgrim Nuclear Power Station, Plymouth, MA Description Code Distance Direction Air Particulate Filters, Charcoal Cartridges Medical Building WS 0.2 km SSE East Rocky Hill Road ER 0.9 km SE West Rocky Hill Road WR 0.8 km WNW Property Line PL 0.5 km NNW Pedestrian Bridge PB 0.2 km N Overlook Area OA 0.1 km W East Breakwater EB 0.5 km ESE Cleft Rock CR 1.3 km SSW Plymouth Center PC 6.7 km W Manomet Substation MS 3.6 km SSE East Weymouth Control EW 40 km NW Forage Plymouth County Farm CF 5.6 km W Hansen Farm Control HN 35 km W Vegetation Plymouth County Farm CF 5.6 km W Hansen Farm Control HN 35 km W Cranberries Bartlett Road Bog BT 4.3 km SSE Beaverdam Road Bog MR 3.4 km S Hollow Farm Bog Control HF 16 km WNW Page 35

Table 2.2-1 (continued)

Routine Radiological Environmental Sampling Locations Pilgrim Nuclear Power Station, Plymouth, MA Description Code Distance Direction Surface Water Discharge Canal DIS 0.2 km N Bartlett Pond BP 2.7 km SE Powder Point Control PP 13 km NNW Sediment Discharge Canal Outfall DIS 0.8 km NE Plymouth Harbor Ply-H 4.1 km W Duxbury Bay Control Dux-Bay 14 km NNW Plymouth Beach PLB 4.0 km WNW Manomet Point MP 3.3 km ESE Green Harbor Control GH 16 km NNW Irish Moss Discharge Canal Outfall DIS 0.7 km NNE Manomet Point MP 4.0 km ESE Ellisville EL 12 km SSE Brant Rock Control BR 18 km NNW Shellfish Discharge Canal Outfall DIS 0.7 km NNE Plymouth Harbor Ply-H 4.1 km W Duxbury Bay Control Dux-Bay 13 km NNW Manomet Point MP 4.0 km ESE Green Harbor Control GH 16 km NNW Lobster Discharge Canal Outfall DIS 0.5 km N Plymouth Harbor Ply-H 6.4 km WNW Duxbury Bay Control Dux-Bay 11 km NNW Fisheg Discharge Canal Outfall DIS 0.5 km N Priest Cove Control PC 48 km SW Jones River Control JR 13 km WNW Vineyard Sound Control MV 64 km SSW Buzzard's Bay Control BB 40 km SSW Cape Cod Bay Control CC-Bay 24 km ESE Page 36

Table 2.4-1 Offsite Environmental TLD Results TLD Station TLD Location* Quarterly Exposure - mR/quarter (Value + Std.Dev.)

2014 Annual-*

ID Description Distance/Direction Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure

_mE/year Zone 1 TLDs: 0-3 km 0-3 km 17.9+/- 5.5 18.0+/- 5.4 19.0 +/- 6.7 17.6 +/- 5.4 72.6 +/-23.1 BLW BOAT LAUNCH WEST 0.11 km E 32.7 +/- 2.5 33.5 +/- 1.8 41.1 +/- 3.1 26.9 +/- 1.1 134.1 +/-23.7 OA OVERLOOK AREA 0.15 kmW 43.7+/-2.1 41.4+/-2.1 44.8+/- 1.7 43.1+/-2.5 173.1 7.0 TC HEALTH CLUB 0.15 km WSW 21.1 +/- 1.3 19.7 +/- 1.1 20.1 +/- 1.1 21.4 +/- 1.4 82.2 +/-4.1 BLE BOAT LAUNCH EAST 0.16 km ESE 25.1 +/- 1.1 30.2 +/- 1.8 40.0 +/- 2.5 22.9 +/- 0.9 118.2 30.6 PB PEDESTRIAN BRIDGE 0.21 km N 27.7 +/- 1.6 27.7 +/- 1.7 27.2 +/- 1.3 29.0 +/- 2.2 111.6 4.6 P01 SHOREFRONT SECURITY 0.22 km NNW 19.0 +/- 1.1 17.6 +/- 1.2 18.6 +/- 0.8 18.6 +/- 1.3 73.9 +/- 3.2 WS MEDICAL BUILDING 0.23 km SSE 21.0 +/- 1.2 20.8 +/- 1.3 21.4 +/- 0.8 22.2 +/- 1.2 85.5 +/- 3.3 CT PARKING LOT 0.31 km SE 18.6 +/- 1.0 18.5 +/- 1.2 21.5 +/- 1.1 19.5 +/- 1.2 78.1 +/-5.9 PA SHOREFRONT PARKING 0.35 km NNW 20.6+/-0.9 20.0+/- 1.0 19.9+/-0.7 22.1 +/- 1.6 82.6+/-4.6 A STATION A 0.37 kmWSW 15.0 +/- 0.7 16.1 t 1.1 16.9 +/- 1.1 13.5 +/- 1.3 61.5 +/- 6.2 F STATION F 0.43 km NW 15.4 +/- 1.2 16.6 +/- 1.6 16.7 +/- 1.2 14.3 +/- 0.7 63.0 +/- 5.0 EB EAST BREAKWATER 0.44 km ESE 18.7 +/- 0.9 18.4 +/- 1.0 19.3 +/- 0.7 20.3 +/- 1.5 76.6 +/- 4.0 B STATION B 0.44 km S 20.2+/- 1.1 21.6+/- 1.1 21.8+/- 1.0 19.0+/-0.7 82.6+/-5.5 PMT PNPS MET TOWER 0.44 km WNW 17.2 +/- 0.8 18.1 +/- 1.1 18.7 +/- 0.7 16.3 +/- 0.6 70.3 +/- 4.4 H STATION H 0.47 kmSW 18.5+/-0.9 19.4+/-1.1 19.2+/-0.8 15.9+/-1.2 73.0+/-6.7 1STATION I 0.48 km WNW 15.4 +/- 1.0 16.9 +/- 1.1 17.2 +/- 0.7 14.6 +/- 0.5 64.1 +/- 5.3 L STATION L 0.50 km ESE 17.5 +/- 0.9 17.1 +/- 0.9 18.6 +/- 0.6 19.6 +/- 1.2 72.9 +/- 5.0 G STATION G 0.53 km W 15.0 +/- 0.7 15.4 +/- 1.3 15.7 +/- 0.9 17.4 +/- 1.2 63.5 +/- 4.8 D STATION D 0.54 km NNW 17.4 +/- 1.3 17.5 +/- 0.9 17.9 +/- 0.6 16.0 +/- 0.6 68.8 +/- 3.6 PL PROPERTY LINE 0.54 km NW 17.0 +/- 1.0 15.6 +/- 0.8 17.0 +/- 0.9 18.0 +/- 1.4 67.7 +/- 4.5 C STATION C 0.57 km ESE 17.3+/-0.9 17.0+/- 1.0 17.8+/-0.7 18.0+/- 1.7 70.1+/-2.9 HB HALL'S BOG 0.63 km SE 18.3 +/- 1.2 16.9 +/- 0.8 18.1 +/- 0.9 19.4 +/- 1.2 72.7 +/- 4.6 GH GREENWOOD HOUSE 0.65 km ESE 18.0 +/- 1.1 17.1 +/- 1.0 17.6 +/- 0.7 18.3 +/- 1.3 71.1 +/- 3.0 WR W ROCKY HILL ROAD 0.83 kmWNW 20.6+/- 1.0 19.8+/- 1.2 19.9+/-0.8 21.2+/- 1.7 81.5+/-3.6 ER E ROCKY HILL ROAD 0.89 kmSE 15.2+/-0.9 13.2+/-0.8 14.4+/-0.5 16.0+/- 1.4 58.8+/-5.2 MT MICROWAVE TOWER 1.03 km SSW 16.7 +/- 1.0 15.9 +/- 0.8 18.3 +/- 0.8 16.9 +/- 1.1 67.7 +/- 4.5 CR CLEFT ROCK 1.27 km SSW 17.3 +/- 0.8 15.2 +/- 0.9 16.7 +/- 0.7 18.4 +/- 1.3 67.6 +/- 5.7 BD BAYSHORE/GATE RD 1.34 km WNW 15.2 +/- 0.8 16.0 +/- 0.9 15.5 +/- 0.6 14.5 +/- 0.6 61.2 +/- 2.8 MR MANOMET ROAD 1.38 km S 17.3 +/- 0.8 17.5 +/- 1.1 18.2 +/- 0.6 15.7 +/- 0.8 68.7 +/- 4.6 DR DIRT ROAD 1.48 kmSW 12.9+/-0.7 14.5+/- 1.0 14.1+/-0.7 12.5+/-0.6 54.0 +/- 4.2 EM EMERSON ROAD 1.53 km SSE 15.2 +/- 0.8 15.8 +/- 1.0 16.4 +/- 1.0 14.8 +/- 1.0 62.3 +/- 3.4 EP EMERSON/PRISCILLA 1.55 kmSE 16.5+/- 1.0 15.6+/- 1.0 16.6+/-0.9 15.1+/-0.9 63.8+/-3.6 AR EDISON ACCESS ROAD 1.59 kmSSE 13.6+/-0.7 14.2+/-0.9 14.3+/-0.6 13.4+/-0.5 55.4+/-2.3 BS BAYSHORE 1.76 km W 17.3 +/- 1.0 18.4 +/- 0.9 18.4 +/- 1.1 16.8 +/- 0.5 70.8 +/- 3.6 E STATION E 1.86 kmS 14.9+/-1.0 15.6+/-1.1 15.8+/-0.8 13.3+/-0.5 59.6+/-4.8 JG JOHN GAULEY 1.99 km W 15.8 +/- 0.7 16.5 +/- 0.9 16.6 +/- 0.9 15.3 +/- 0.7 64.2 +/- 2.8 J STATION J 2.04 km SSE 13.9 +/- 0.7 15.1 +/- 0.9 15.6 +/- 0.9 14.0 +/- 0.4 58.6 +/- 3.7 WH WHITEHORSE ROAD 2.09 km SSE 15.3+/-0.8 14.8+/-0.9 16.5+/-0.6 14.6+/-1.0 61.3+/-3.8 RC PLYMOUTH YMCA 2.09 km WSW 15.1 +/- 0.8 15.8 +/- 0.8 15.8 +/- 0.9 14.4 +/- 0.8 61.1 +/- 3.1 K STATION K 2.17 kmS 14.2+/-1.1 14.9+/-0.8 14.5+/-0.6 13.1+/-0.6 56.8+/-3.5 TT TAYLOR/THOMAS 2.26 km SE 15.0 +/- 0.8 14.7 +/- 0.7 15.4 +/- 0.7 13.2 +/- 0.9 58.2 +/- 4.1 YV YANKEE VILLAGE 2.28 km WSW 15.6 +/- 0.8 16.3 +/- 1.0 16.3 +/- 0.8 14.8 +/- 0.7 63.0 +/- 3.3 GN GOODWIN PROPERTY 2.38 km SW 11.3 +/- 0.6 11.8 +/- 0.8 11.6 +/- 0.7 11.0 +/- 0.5 45.6 +/- 2.0 RW RIGHT OF WAY 2.83 kmS 13.1 +/-0.8 13.1 +/-0.8 13.1 +/- 1.0 11.6+/-0.9 50.9+/-3.4 TP TAYLOR/PEARL 2.98 km SE 14.0+/-0.6 14.0+/-0.8 15.7+/- 1.3 13.7+/-1.0 57.4+/-4.2

• Distance and direction are measured from centerline of Reactor Building to the monitoring location.

Annual value is based on arithmetic mean of the observed quarterly values multiplied by four quarters/year.

Page 37

Table 2.4-1 (continued)

Offsite Environmental TLD Results TLD Station TLD Location* Quarterl Exposure - mR/quarter (Value +/- Std.Dev.)

2014 Annual*

ID Description Distance/Direction Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure Zone 2 TLDs: 3-8 km 3-8 km 14.3 +/- 2.1 14.2 +/- 2.0 15.1 t 2.0 14.4 +/- 2.4 58.1 +8.4 VR VALLEY ROAD 3.26 km SSW Missing 12.5+/-0.7 13.3+/-0.7 12.51+/- 1.2 51.1 2.9 ME MANOMET ELEM 3.29 km SE 14.8 +/- 0.8 15.0 +/- 0.8 15.9 +/- 0.9 15.3 +/- 1.3 61.1 2.7 WC WARREN/CLIFFORD 3.31 kmW 13.5+/-0.8 14.5+/- 1.1 15.5+/-0.9 14.0+/-0.7 57.5+/-3.8 BB RT.3A/BARTLETT RD 3.33 km SSE 14.9 +/- 0.8 15.2 +/- 1.1 15.3 +/- 0.8 18.9 +/- 1.8 64.2 + 7.9 MP MANOMET POINT 3.57 km SE 13.3 +/- 0.7 13.7 +/- 0.7 14.8 +/- 0.7 14.3 +/- 0.9 56.1 3.1 MS MANOMET SUBSTATION 3.60 km SSE 17.6 +/- 0.7 16.6 +/- 1.0 17.9 +/- 0.6 19.2 +/- 1.3 71.3 +/- 4.8 BW BEACHWOOD ROAD 3.93 km SE 13.9 +/- 0.9 14.6 +/- 0.7 15.5 +/- 0.6 14.3 +/- 0.9 58.3 +/- 3.1 PT PINES ESTATE 4.44 km SSW 13.6 +/- 1.0 13.0 +/- 0.9 15.2 +/- 0.8 12.9 +/- 1.0 54.7 +/- 4.6 EA EARL ROAD 4.60 km SSE 12.6 +/- 0.7 13.8 +/- 0.9 13.7 +/- 0.6 12.3 +/- 0.5 52.4 +/- 3.4 SP S PLYMOUTH SUBST 4.62 km W 15.4 +/- 1.1 14.4 +/- 1.0 15.8 +/- 0.7 14.0 +/- 1.1 59.6 +/- 3.9 RP ROUTE 3 OVERPASS 4.81 km SW 15.6 +/- 1.3 14.6 +/- 0.9 15.8 +/- 0.7 15.0 +/- 1.1 61.1 +/- 3.0 RM RUSSELL MILLS RD 4.85 km WSW 14.5 +/- 0.7 14.2 +/- 1.0 15.3 +/- 0.7 13.1 +/- 0.9 57.1 +/- 4.1 HD HILLDALE ROAD 5.18 km W 14.3 +/- 0.8 15.1 +/- 1.1 15.3 +/- 0.7 14.0 +/- 0.6 58.7 +/- 2.9 MB MANOMET BEACH 5.43 km SSE 14.9 +/- 1.1 15.2 +/- 0.9 16.0 +/- 0.9 14.5 +/- 1.1 60.6 +/- 3.3 BR BEAVERDAM ROAD 5.52 km S 15.3 +/- 0.7 14.8 +/- 0.9 16.2 +/- 0.7 14.8 +/- 1.3 61.0 +/- 3.3 PC PLYMOUTH CENTER 6.69 km W 11.0 +/- 0.9 9.2 +/- 0.7 10.4 +/- 0.6 12.4 +/- 0.9 42.9 +/- 5.6 LD LONG POND/DREW RD 6.97 km WSW 13.2+/- 1.0 14.2+/-0.8 Missing 11.4+/- 0.6 51.7+/-6.1 HR HYANNIS ROAD 7.33 km SSE 13.2 +/- 0.6 13.8 +/-0.8 14.7 +/- 0.7 13.1 +/- 0.8 54.9 +/- 3.4 SN SAQUISH NECK 7.58 km NNW 11.1+/-0.7 10.9+/-0.6 11.4+/-0.6 13.2+/- 1.2 46.6+/-4.4 MH MEMORIAL HALL 7.58 km WNW 20.1 +/- 1.0 19.5 +/- 1.1 19.7 +/- 0.9 20.3 +/- 1.2 79.7 +/- 2.6 CP COLLEGE POND 7.59 km SW 13.7 +/- 0.8 13.7 +/-0.8 15.3 +/- 0.6 13.4 +/- 0.9 56.0 +/- 3.7 Zone3 TLDs: 8-15 km 8-15 km 13.9+/- 1.3 13.7+/- 1.9 15.0+/- 1.6 13.6+/- 1.8 56.1 +/-6.7 DW DEEP WATER POND 8.59 kmW 15.5+/-0.8 16.1 +/-1.0 18.0+/- 1.5 15.0+/-1.3 64.7+/-5.8 LP LONG POND ROAD 8.88 km SSW 12.8 +/- 0.8 12.5 +/- 0.9 14.2 +/- 0.8 12.0 +/- 0.9 51.5 +/- 4.1 NP NORTH PLYMOUTH 9.38 km WNW 16.6 +/- 0.8 17.7 +/- 1.2 17.2 +/- 0.6 16.3 +/- 1.5 67.9 +/- 3.4 SS STANDISH SHORES 10.39 km NW 13.7 +/- 0.7 13.9 +/- 1.0 14.1 +/- 0.5 15.3 +/- 1.3 57.1 +/- 3.5 EL ELLISVILLE ROAD 11.52 km SSE 13.6 +/- 0.9 13.3 +/- 1.1 14.8 +/- 0.8 14.6 +/- 1.0 56.4 +/- 3.5 UC UP COLLEGE POND RD 11.78 kmSW 12.8+/-0.7 11.9+/-0.7 13.6+/-0.7 11.0+/- 1.0 49.3+/-4.7 SH SACRED HEART 12.92 km W 13.5 +/- 1.0 13.0 +/- 0.8 15.3 +/- 0.7 12.5 +/- 0.9 54.4 +/- 5.2 KC KING CAESAR ROAD 13.11 km NNW 13.7 +/- 0.9 13.4 +/- 0.8 13.5 +/- 0.8 14.2 +/- 0.9 54.8 +/- 2.2 BE BOURNE ROAD 13.37 kmS 12.8+/-0.8 11.5+/-0.6 13.8+/-0.7 12.1+/-0.8 50.3+/-4.1 SA SHERMAN AIRPORT 13.43 km WSW 13.4+/- 1.0 13.2+/- 1.1 15.2+/-0.9 12.9+/- 1.2 54.7+/-4.7 Zone4TLDs: >15km >15km 14.6+/- 1.6 14.3+/-2.2 16.0+/-2.3 15.2+/- 1.6 60.0+/-7.7 CS CEDARVILLE SUBST 15.93 km S 15.2 +/- 0.7 14.8 +/- 0.9 17.3 +/- 1.7 15.0 +/- 0.8 62.3 +/- 5.2 KS KINGSTON SUBST 16.15 kmWNW 14.9+/- 0.6 14.3+/- 0.8 16.1 +/-0.9 15.0+/- 1.2 60.4+/- 3.5 LR LANDING ROAD 16.46 km NNW 14.6 +/- 0.8 13.7 +/- 0.8 14.1 +/- 0.7 14.9 +/- 1.2 57.3 +/- 2.8 CW CHURCH/WEST 16.56 km NW 11.5+/-0.7 10.2+/-0.8 12.0+/-0.7 13.6+/- 1.1 47.2+/-5.8 MM MAIN/MEADOW 17.02 kmWSW 13.7+/-0.7 14.1 +/- 1.0 16.0+/- 1.0 13.4+/- 1.1 57.3+/-5.1 DMF DIV MARINE FISH 20.97 km SSE 15.8 +/- 1.2 16.2 +/- 1.1 17.7 +/- 1.0 16.9 +/- 1.0 66.6 +/- 4.0 EW E WEYMOUTH SUBST 39.69 km NW 16.3 +/- 0.8 16.7 +/- 1.2 18.5 +/- 0.8 17.2 +/- 1.4 68.8 +/- 4.4 Distance and direction are measured from centerline of Reactor Building to the monitoring location.

• Annual value is based on arithmetic mean of the observed quarterly values multiplied by four quarters/year.

Page 38

Table 2.4-2 Onsite Environmental TLD Results TLD Station TLD Location* Quarterli Exposure - mR/quarter (Value _ Std.Dev.)

2014 Annual*

ID Description Distance/Direction Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure

_______________________________mR/year SOnsite TLDs P21 O&M/RXB. BREEZEWAY 50 m SE 24.7 +/- 1.1 24.1 +/- 1.3 26.9 +/- 1.0 24.2 +/- 1.4 99.9 +/- 5.8 P24 EXEC.BUILDING 57 m W 48.7 +/- 3.8 55.8 +/- 2.3 58.1 +/- 2.3 43.3 +/- 1.7 205.8 +/- 27.6 P04 FENCE-R SCREENHOUSE 66 m N 42.5 +/- 2.8 58.3 +/- 3.0 63.7 +/- 2.3 54.2 +/- 3.2 218.8 +/- 36.5 P20 O&M - 2ND W WALL 67mSE 27.7+/- 1.3 28.4+/- 1.4 31.4+/- 1.5 25.4+/- 1.0 112.9+/- 10.3 P25 EXEC.BUILDING LAWN 76 m WNW 47.9 +/- 2.8 50.2 +/- 2.6 51.9 +/- 2.5 38.1 +/- 2.0 188.1 +/- 25.2 P05 FENCE-WATER TANK 81 m NNE 23.8 +/- 1.1 24.9 +/- 1.1 27.8 +/- 1.1 22.5 +/- 1.3 99.1 +/- 9.3 P06 FENCE-OIL STORAGE 85 m NE 40.8 +/- 1.7 34.4 +/- 1.7 42.3 +/- 1.4 30.3 +/- 1.2 147.8 +/- 22.6 P19 O&M - 2ND SW CORNER 86 m S 21.1 +/- 1.0 21.9 +/- 1.2 24.2 +/- 0.9 20.4+/- 0.7 87.6 +/- 7.0 P18 O&M - 1ST SW CORNER 90 m S 30.7 +/- 2.4 32.3 +/- 1.9 32.9 +/- 1.3 27.5 +/- 2.0 123.3 +/- 10.4 P08 COMPRESSED GAS STOR 92 m E 32.2 +/- 2.8 32.6 +/- 2.6 37.2 +/- 2.7 27.8 +/- 1.9 129.8 +/- 16.2 P03 FENCE-L SCREENHOUSE 100 m NW 35.0 +/- 1.7 35.4 +/- 1.6 38.1 +/- 1.4 32.0 +/- 1.9 140.5 +/- 10.5 P17 FENCE-EXEC.BUILDING 107 m W 52.5 +/- 2.6 52.3 +/- 2.3 57.3 +/- 2.2 76.3 +/- 4.6 238.3 +/- 45.9 P07 FENCE-INTAKE BAY 121 m ENE 29.5 +/- 1.7 27.1 +/- 1.5 31.8 +/- 1.8 24.4 +/- 0.8 112.8 +/- 13.1 P23 O&M- 2ND S WALL 121 mSSE 29.6+/- 1.3 33.0+/- 1.9 33.4+/- 1.7 27.5+/- 1.6 123.6+/- 11.8 P26 FENCE-WAREHOUSE 134 m ESE 27.0 +/- 1.2 30.7 +/- 2.2 38.9 +/- 2.3 24.6 +/- 1.3 121.2 +/- 25.4 P02 FENCE-SHOREFRONT 135 m NW 28.8 +/- 1.7 29.8 +/- 1.5 31.3 +/- 1.3 25.6 +/- 0.9 115.6 +/- 10.1 P09 FENCE-W BOAT RAMP 136 m E 26.0 +/- 1.3 26.8 +/- 1.3 31.0 +/- 1.5 22.5 +/- 1.2 106.3 +/- 14.1 P22 O&M - 2ND N WALL 137 m SE 20.8+/- 1.1 22.5+/- 1.2 26.4+/- 1.6 20.0+/-0.7 89.7+/- 11.8 P16 FENCE-W SWITCHYARD 172 m SW 72.2 +/- 3.9 78.8 +/- 5.7 83.2 +/- 4.4 56.5 +/- 5.3 290.6 +/- 47.8 P11 FENCE-TCF GATE 183 m ESE 29.6 +/- 1.2 39.7 +/- 2.4 72.9 +/- 3.4 32.4 +/- 1.3 174.6 +/-79.9 P27 FENCE-TCF/BOAT RAMP 185 m ESE 20.9 +/- 1.1 22.7 +/- 1.3 27.1 +/- 1.2 19.4 +/- 0.7 90.2 +/- 13.5 P12 FENCE-ACCESS GATE 202 m SE 23.6 +/- 1.3 24.5 +/- 1.3 26.6 +/- 1.6 20.0 +/- 0.8 94.6 +/-11.3 P15 FENCE-E SWITCHYARD 220 m S 24.2 +/- 1.0 25.0 +/- 1.2 26.7 +/- 1.1 20.6 +/- 0.9 96.5 +/- 10.4 P10 FENCE-TCF/INTAKE BAY 223 m E 23.1 +/- 1.1 25.7 +/- 1.5 30.0 +/- 1.0 22.4 +/- 0.9 101.2 +/- 14.0 P13 FENCE-MEDICAL BLDG. 224 m SSE 23.1 +/- 1.0 23.3 +/- 1.5 25.4 +/- 1.8 20.2 +/- 1.2 92.1 +/- 8.9 P14 FENCE-BUTLER BLDG 228 m S 22.0 +/- 1.0 20.5 +/- 1.1 22.2 +/- 1.3 17.0 +/- 0.8 81.8 +/- 9.9 P28 FENCE-TCF/PRKNG LOT 259 m ESE 41.4 +/- 1.8 53.7 +/- 3.2 67.2 +/- 4.9 37.8 +/- 2.2 200.1 +/- 53.6 Distance and direction are measured from centerline of Reactor Building to the monitoring location.

• • Annual value is based on arithmetic mean of the observed quarterly values multiplied by four quarters/year.

Page 39

Table 2.4-3 Average TLD Exposures By Distance Zone During 2014 Average Exposure +/- Standard Deviation: mR/ eriod Exposure Zone 1* 1 Zone 2 Zone 3 Zone 4 Period 0-3 km 3-8 km 8-15 km >15 km Jan-Mar 17.9 +/- 5.5 14.3 +/- 2.1 13.9 +/- 1.3 14.6 +/- 1.6 Apr-Jun 18.0 +/- 5.4 14.2 +/- 2.0 13.7 +/- 1.9 14.3 +/- 2.2 Jul-Sep 19.0 +/- 6.7 15.1 +/- 2.0 15.0 +/- 1.6 16.0 +/- 2.3 Oct-Dec 17.6 +/- 5.4 14.4 +/- 2.4 13.6 +/- 1.8 15.2 +/- 1.6 Jan-Dec 72.6 +/- 23.1** 58.1 +/- 8.4 56.1 +/- 6.7 60.0 +/- 7.7

• Zone 1 extends from the PNPS restricted/protected area boundary outward to 3 kilometers (2 miles), and includes several TLDs located within the site boundary.

• • When corrected for TLDs located within the site boundary, the Zone 1 annual average is calculated to be 62.2 +/- 8.1 mR/yr.

Page 40

Table 2.5-1 Air Particulate Filter Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2014)

MEDIUM: Air Particulates (AP) UNITS: DCVcubic meter Indicator Stations Station with Highest Mean Control Stations Mean +/- Std.Dev. Station: Mean +/- Std.Dev. Mean +/- Std.Dev.

No. Analyses Required Range Range Range Radionuclide Non-routine* LLD Fraction>LLD Fraction>LLD Fraction>LLD Gross Beta 571 0.01 1. 1E-2 +/- 5.8E-3 PCi 1.3E-2 +/- 6.3E-3 1.2E-2 +/- 5.411-3 0 -5.5E 3.4E-2 -3.8E 3.2E-2 -1.7E 2.6E-2 502/519 50/52 51/52 Be-7 44 1.1E-1 +/- 2.1E-2 ER: 1.2E-1 +/- 2.4E-2 1.1E-1 +/- 2.4E-2 0 6.2E 1.4E-1 8.3E 1.4E-1 7.3E 1.3E-1 40/40 4/4 4/4 Cs-134 44 0.05 -2.3E-5 +/- 2.9E-4 PL: 2.5E-4 +/- 3.2E-4 2.2E-4 +/- 2.6E-4 0 -4.9E 6.3E-4 -6.6E 5.1E-4 2.4E 5.4E-4 0/40 0/40 0/4 Cs-137 44 0.06 -8.1E-6 +/- 2.4E-4 PB: 1.7E-4+/-2.2E-4 -7.OE-5 +/- 2.OE-4 0 -4.4E 5.2E-4 -5.1E 3.6E-4 -2.8E 1.3E-4 0/40 0/40 0/4

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.

Page 41

Table 2.6-1 Charcoal Cartridge Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2014)

MEDIUM: Charcoal Cartridoe (CF) UNITS: r)Ci/cubic meter Indicator Stations Station with Highest Mean Control Stations Mean A Std.Dev. Station: Meang Std.Dev. Mean Std.Dev.

g No. Analyses Required Range Range Range Radionuclide Non-routine* LLD Fraction>LLD Fraction>LLD Fraction>LLD 1-131 571 0.07 2.5E-4 +/- 8.8E-3 OA: 2.1E-3 +/- 8.2E-3 1.6E-3 +/- 8.1E-3 0 -4.5E 2.6E-2 -1.6E 2.5E-2 -2.1E 1.9E-2 0/519 0/52 0/52

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.

Page 42

Table 2.7-1 Milk Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2014)

No milk sampling was performed during 2014, as no suitable indicator locations for milk production were available for sampling within 5 miles of Pilgrim Station.

Page 43

Table 2.8-1 Forage Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2014)

No forage sampling was performed during 2014, as no grazing animals used for food products were available at any indicator locations within 5 miles of Pilgrim Station.

Page 44

Table 2.9-1 Vegetable/Vegetation Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2014)

I*,11:::1*11I1*/I. \/=n=f==tiP.'* /TI:\ I rKIITQ- -- Uin KAP:n1HKA- W-fti- ITFI WZMA Indicator Stations Station with Highest Mean Control Stations Mean A Std.Dev. Station: Meang Std.Dev. Mean Std.Dev.

g No. Analyses Required Range Range Range Radionuclide Non-routine LLD Fraction>LLD Fraction>LLD Fraction>LLD Be-7 17 2.OE+3 +/- 7.1E+2 DMF: 3.9E+3 +/- 9.7E+1 2.3E+3 +/- 2.2E+3 0 1.OE+3 - 3.OE+3 3.9E+3 - 3.9E+3 7.7E+2 - 3.9E+3 8/10 1/1 2/7 K-40 17 3.OE+3 +/- 7.4E+2 Gmwood: 3.9E+3 +/- 1.6E+2 2.6E+3 +/- 6.5E+2 0 2.OE+3 - 4.4E+3 3.9E+3 - 3.9E+3 1.7E+3 - 3.6E+3 10/10 1/1 7/7 1-131 17 60 -1.6E+0 +/- 1.1E+1 DMF: 1.2E+1 +/- 1.3E+1 2.OE-1 +/- 7.9E+0 0 -2.6E+1 - 1.2E+1 1.2E+1 - 1.2E+1 -9.6E+0 - 1.2E+1 0/10 0/1 0/7 Cs-134 17 60 1.OE+0 +/- 3.8E+0 PineHill: 7.7E+0 +/- 5.OE+0 1.8E+0 +/- 3.OE+0 0 -4.5E+0 - 7.7E+0 7.7E+0 - 7.7E+0 1.0E 7.2E+0 0/10 0/1 0/7 Cs-137 17 80 2.8E+1 +/- 4.3E+1 PineHill: 1.3E+2 +/- 9.5E+0 3.3E+0 +/- 7.5E+0 0 -2.6E+0- 1.3E+2 1.3E+2- 1.3E+2 -3.OE+0- 1.9E+1 4/10 1/1 1/7 AcTh-228 17 9.9E+2 +/- 4.5E+1 Gmwood: 9.9E+2 +/- 4.5E+1 1.3E+2 +/- 2.1E+1 0 9.9E+2 - 9.9E+2 9.9E+2 - 9.9E+2 1.3E+2 - 1.3E+2 1/10 1/1 1/7

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.

Page 45

Table 2.10-1 Cranberry Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2014)

CMIHAA r' k  ; I IKllT(c *PII, 6 ,

IVI--.,JIerVI U*II. esII I*lQ62 Q .IV., 0

,,..:.Rl U rl Indicator Stations Station with Highest Mean Control Stations Mean +/- Std.Dev. Station: Mean +/- Std.Dev. Mean +/- Std.Dev.

No. Analyses Required Range Range Range Radionuclide Non-routine LLD Fraction>LLD Fraction>LLD Fraction>LLD Be-7 2 2.6E+2 +/- 2.8E+1 BvDmBog: 2.6E+2 +/- 2.8E+1 <LLD 0 2.6E+2 - 2.6E+2 2.6E+2 - 2.6E+2 <LLD 1/1 1/1 0/1 K-40 2 5.7E+2 + 4.6E+1 HollowBog: 5.9E+2 +/- 4.3E+1 5.9E+2 +/- 4.3E+1 0 5.7E+2 - 5.7E+2 5.9E+2 - 5.9E+2 5.9E+2 - 5.9E+2 1/1 1/1 1/1 1-131 2 60 1.8E+0 +/- 2.3E+O BvDmBog:1.8E+0 +/- 2.3E+0 -3.9E-1 +/- 3.9E+0 0 1.8E+0 - 1.8E+0 1.8E+0 - 1.8E+0 -3.9E -3.9E-1 0/1 0/1 0/1 Cs-134 2 60 4.9E+0:+/-12.1E+0 BvDmBog: 4.9E+0 +/- 2.1E+0 1.OE+0 +/- 1.8E+0 0 4.9E+0 - 4.9E+0 4.9E+0 - 4.9E+0 1.OE+0 - 1.0E+0 0/1 0/1 0/1 Cs-137 2 80 -2.4E+0 +/- 3.2E+0 HollowBog: 8.3E-1 +/- 1.7E+0 8.3E-1 +/- 1.7E+0 0 -2.4E+0 - -2.4E+0 8.3E 8.3E-1 8.3E 8.3E-1 0/1 0/1 0/1 AcTh-228 2 3.9E+1 +/- 1.1E+1 BvDmBog: 3.9E+1 +/- 1.1E+1 <LLD 0 3.9E+1 - 3.9E+1 3.9E+1 - 3.9E+1 <LLD 1/1 1/1 0/1

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.

Page 46

Table 2.12-1 Surface Water Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2014)

KArflhIHIA' C. ,for MIoto (MAIQZ I IMKITQ r"riJln J J

Radionuclide No. Analyses Required J Indicator Stations Station with Highest Mean Control Stations H-3 12 3000 -2.2E+0 +/- 2.3E+2 BrtPnd: 7.2E+1 +/- 2.7E+2 -3.2E+1 +/- 1.6E+2 0 -2.6E+2 - 2.9E+2 -1.7E+2 - 2.9E+2 -2.1E+2 - 1.2E+2 0/8 0/4 0/4 K-40 36 3.0E+2 +/- 8.6E+1 DIS: 3.2E+2 +/- 2.9E+1 3.0E+2 +/- 2.8E+1 0 3.1E+1 - 3.8E+2 2.6E+2 - 3.8E+2 2.6E+2 - 3.4E+2 13/24 12/12 12/12 Mn-54 36 15 9.2E-2 +/- 1.3E+0 DIS: 9.6E-2 +/- 1.4E+0 -1.1E-1 +/- 7.OE-1 0 -2.3E+0 - 2.2E+0 -2.3E+0 - 2.2E+0 -1.1E+0 - 8.2E-1 0/24 0/12 0/12 Fe-59 36 30 -3.8E-2 +/- 2.3E+0 PdrPnt: 4.1E-1 +/- 3.1E+0 4.1E-1 +/- 3.1E+0 0 -3.6E+0 - 5.OE+0 -4.7E+0 - 7.8E+0 -4.7E+0 - 7.8E+0 0/24 0/12 0/12 Co-58 36 15 -1.6E-1 +/- 9.4E-1 PdrPnt: -2.6E-2 +/- 9.7E-1 -2.6E-2 +/- 9.7E-1 0 -1.8E+0- 1.9E+0 -1.5E+0- 1.7E+0 -1.5E+0- 1.7E+0 0/24 0/12 0/12 Co-60 36 15 1.5E-2 +/- 9.6E-1 PdrPnt: 3.2E-1 +/- 1.4E+0 3.2E-1 +/- 1.4E+0 0 -2.2E+0 - 1.7E+0 -1.5E+0 - 2.6E+0 -1.5E+0 - 2.6E+0 0/24 0/12 0/12 Zn-65 36 30 -4.7E-1 +/- 2.9E+0 BrtPnd: -3.5E-1 +/- 3.3E+0 -1.4E+0 +/- 1.7E+0 0 -4.3E+0 - 8.8E+0 -3.6E+0 - 8.8E+0 -4.7E+0 - 4.6E-1 0/24 0/12 0/12 Zr-95 36 30 1.8E-1 +/- 1.3E+0 BrtPnd: 3.8E-1 +/- 1.1E+0 -4.3E-1 +/- 1.7E+0 0 -2.2E+0 - 2.1E+0 -1.5E+0 - 1.8E+0 -3.0E+0 - 1.2E+0 0/24 0/12 0/12 Nb-95 36 15 5.6E-1 +/- 1.3E+0 DIS: 6.3E-1 +/- 1.4E+0 -1.3E-1 +/- 1.2E+0 0 -1.7E+0 - 3.6E+0 -1.7E+0 - 3.6E+0 -2.4E+0 - 1.2E+0 0/24 0/12 0/12 1-131 36 15 -3.2E-1 +/- 1.7E+0 BrtPnd: 3.5E-1 +/- 1.6E+0 -3.2E-1 +/- 1.6E+0 0 -3.4E+0 - 2.6E+0 -1.9E+0 - 2.6E+0 -3.3E+0 - 1.4E+0 0/24 0/12 0/12 Cs-134 36 15 2.6E-1 +/- 1.7E+0 DIS: 2.8E-1 +/- 2.1E+0 -1.2E-1 +/- 1.4E+0 0 -2.4E+0 - 5.8E+0 -2.4E+0 - 5.8E+0 -2.8E+0 - 1.2E+0 0/24 0/12 0/12 Cs-137 36 18 -4.7E-1 +/- 7.3E-1 PdrPnt: 2.0E-1 +/- 1.3E+0 2.0E-1 +/- 1.3E+0 0 -2.0E+0- 1.OE+0 -2.4E+0- 1.8E+0 -2.4E+0- 1.8E+0 0/24 0/12 0/12 Ba-140 36 60 -1.7E-1 +/- 1.5E+0 PdrPnt: 1.7E-1 +/- 1.3E+0 1.7E-1 +/- 1.3E+0 0 -2.6E+0 - 2.8E+0 -2.0E+0 - 1.6E+0 -2.0E+0 - 1.6E+0 0/24 0/12 0/12 La-140 36 15 -1.7E-1 +/- 1.5E+0 PdrPnt: 1.7E-1 +/- 1.3E+0 1.7E-1 +/- 1.3E+0 0 -2.6E+0 - 2.8E+0 -2.0E+0 - 1.6E+0 -2.OE+0 - 1.6E+0 0/24 0/12 0/12

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.

Page 47

Table 2.13-1 Sediment Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2014)

IvEl-LIlVl. O*JlIllL-t Or-) UINI IC. .; ,1 VlU UIV Indicator Stations Station with Highest Mean Control Stations Mean A Std.Dev. Station: Meang Std.Dev. Mean Std.Dev.

g No. Analyses Required Range Range Range Radionuclide Non-routine* LLD Fraction>LLD Fraction>LLD Fraction>LLD K-40 12 1.0E+4 +/- 1.5E+3 PlyHbr: 1.1E+4 +/- 2.4E+3 9.4E+3 +/- 1.4E+3 0 8.0E+3- 1.3E+4 9.7E+3- 1.3E+4 8.1E+3- 1.1E+4 818 212 414 Cs-134 12 150 1.2E+1 +/- 2.2E+1 DuxBay: 1.7E+1 +/- 1.8E+1 1.4E+1 +/- 1.1E+1 0 -1.2E+1 - 4.3E+1 7.6E+0 - 2.7E+1 7.6E+0 - 2.7E+1 0/8 0/2 0/4 Cs-137 12 180 4.9E+0 +/- 1.7E+1 ManPt: 2.OE+1 +/- 8.1E+0 6.6E+0 +/- 6.7E+0 0 -1.9E+1 - 2.1E+1 2.OE+1 - 2.1E+1 2.6E+0 - 1.1E+1 0/8 0/2 0/4 TI-208 12 1.2E+2 +/- 8.3E+1 PlyHbr: 2.4E+2 +/- 1.1E+2 1.2E+2 +/- 4.9E+1 0 6.4E+1 - 3.1E+2 1.7E+2 - 3.1E+2 7.3E+1 - 1.8E+2 8/8 2/2 4/4 Pb-212 12 3.8E+2 +/- 2.4E+2 PlyHbr: 8.1E+2 +/- 5.5E+1 4.4E+2 +/- 1.gE+2 0 1.4E+2 - 8.1E+2 8.1 E+2 - 8.1E+2 3.OE+2 - 7.2E+2 6/8 1/2 4/4 Pb-214 12 2.OE+2 t 1.4E+2 PlyBch: 3.9E+2 +/- 6.4E+1 3.4E+2 +/- 1.5E+2 0 1.OE 3.9E+2 3.9E+2 - 3.9E+2 2.4E+2 - 5.2E+2 518 1/2 3/4 Ra-226 12 2.6E+2 +/- 1.8E+2 PlyHbr: 4.4E+2 +/- 7.OE+1 3.5E+2 +/- 4.4E+1 0 4.9E+ 1 - 4.7E+2 4.OE+2 - 4.7E+2 3.5E+2 - 3.5E+2 5/8 2/2 1/4 AcTh-228 12 4.3E+2 +/- 1.7E+2 DuxBay: 6.4E+2 +/- 6.8E+1 5.5E+2 +/- 1.3E+2 0 2.8E+2 - 7.OE+2 6.4E+2 - 6.4E+2 4.7E+2 - 6.4E+2 5/8 1/2 2/4

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.

Page 48

Table 2.14-1 Irish Moss Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2014)

R*AM'1lI RA. Irbhk RA* A[ I IkflTO. .~CNIL.,,

IV Ii

--JI*ll 1 O 1VU I /*L I* I* I H* qJ,~%,

we; Indicator Stations Station with Highest Mean Control Stations Mean +/- Std.Dev. Station: Mean +/- Std.Dev. Mean +/- Std.Dev.

No. Analyses Required Range Range Range Radionuclide Non-routine* LLD Fraction>LLD Fraction>LLD Fraction>LLD K-40 8 5.2E+3 +/- 6.7E+2 DIS: 5.7E+3 +/- 1.4E+2 5.4E+3 +/- 2.4E+3 0 4.2E+3 - 5.8E+3 5.7E+3 - 5.7E+3 3.6E+3 - 7.1 E+3 6/6 2/2 2/2 Mn-54 8 130 2.1E-1 +/- 3.5E+0 BntRck: 7.5E+0 +/- 8.2E+0 7.5E+0 +/- 8.2E+0 0 -3.3E+0 - 3.2E+0 2.4E+0 - 1.3E+1 2.4E+0 - 1.3E+1 0/6 0/2 0/2 Fe-59 8 260 -2.4E+0 +/- 8.6E+0 BntRck: 5.6E+0 +/- 9.1E+0 5.6E+0 +/- 9.1E+0 0 -1.5E+1 - 5.6E+0 3.6E+0 - 7.6E+0 3.6E+0 - 7.6E+0 0/6 0/2 0/2 Co-58 8 130 -6.8E-1 +/- 2.6E+0 DIS: 1.2E+0 +/- 3.7E+0 7.OE-1 +/- 4.1E+0 0 -3.5E+0 - 2.3E+0 6.6E 2.3E+0 1.OE 1.4E+0 0/6 0/2 0/2 Co-60 8 130 4.3E+0 +/- 5.8E+0 DIS: 7.4E+0 +/- 1.1E+1 2.8E-1 +/- 6.1E+0 0 1.OE 1.5E+1 1.OE 1.5E+1 -2.3E+0 - 2.9E+0 0/6 0/2 0/2 Zn-65 8 260 -9.1E+0 +/- 8.2E+0 DIS: -4.5E+0 +/- 1.OE+1 -6.2E+0 +/- 2.2E+1 0 -2.OE+1 - 4.6E-1 -9.5E+0 - 4.6E-1 -2.OE+1 - 7.1E+0 0/6 0/2 0/2 Cs-134 8 130 2.4E+0 +/- 5.1E+0 BntRck: 6.8E+0 +/- 7.7E+0 6.8E+0 +/- 7.7E+0 0 -4.5E+0 - 7.4E+0 2.8E+0 - 1.1 E+ 1 2.8E+0 - 1.1 E+ 1 0/6 0/2 0/2 Cs-1 37 8 150 2.4E+0 +/- 3.9E+0 DIS: 4.7E+0 +/- 7.4E+0 -5.7E+0 +/- 7.9E+0 0 -1.OE 9.3E+0 -1.OE 9.3E+0 -1.OE+I - -1.2E+0 0/6 0/2 0/2

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.

Page 49

Table 2.15-1 Shellfish Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2014)

RACMI"RA I &I cc "Kllý  ; 6 I  : *.1KI X--Lis L/ lil..1- I 32

,.. *6E..JL' Q

• • rl*wC Indicator Stations Station with Highest Mean Control Stations Mean +/- Std.Dev. Station: Mean +/- Std.Dev. Mean +/- Std.Dev.

No. Analyses Required Range Range Range Radionuclide Non-routine* LLD Fraction>LLD Fraction>LLD Fraction>LLD K-40 9 1.5E+3 +/- 4.OE+2 DuxBay: 2.OE+3 +/- 2.9E+2 1.9E+3 +/- 2.7E+2 0 1.OE+3 - 2.OE+3 1.8E+3 - 2.2E+3 1.6E+3 - 2.2E+3 5/5 2/2 4/4 Mn-54 9 130 -1.4E+0 + 3.9E+0 DuxBay: 1.6E+0 +/- 2.4E+0 -1.2E+0 +/- 3.8E+0 0 -4.3E+0 - 8.5E-1 6.0E 2.6E+0 -5.OE+O - 2.6E+0 0/5 0/2 0/4 Fe-59 9 260 -3.3E+0 +/- 1.2E+1 GmHbr: 5.4E+0 +/- 9.1E+0 4.5E+0 +/- 5.5E+0 0 -1.8E+1 - 5.3E+0 1.1E+0 - 9.8E+0 1.1E+0 - 9.8E+0 0/5 0/2 0/4 Co-58 9 130 6.3E-1 +/- 4.7E+0 DIS: 4.8E+0 +/- 6.7E+0 1.4E+0 +/- 4.5E+0 0 -3.8E+0 - 4.8E+0 4.8E+0 - 4.8E+0 -4.3E+0 - 5.5E+0 0/5 0/1 0/4 Co-60 9 130 -1.3E+0 +/- 8.3E+0 DIS: 8.9E+0 +/- 5.9E+0 2.4E+0 +/- 3.8E+0 0 -1.3E+1 - 8.9E+0 8.9E+0 - 8.9E+0 -1.5E+0 - 6.4E+0 0/5 0/1 0/4 Zn-65 9 260 -1.1E+0 +/- 8.7E+0 DIS: 3.5E+0 +/- 1.2E+1 -8.6E+0 +/- 9.7E+0 0 -6.7E+0 - 4.1E+0 3.5E+0 - 3.5E+0 -1.9E+1 - 7.8E-1 0/5 0/1 0/4 Cs-134 9 130 7.2E+0 +/- 1.1E+1 PlyHbr: 7.5E+0 +/- 1.3E+1 1.6E+0 +/- 5.5E+0 0 -6.OE 2.6E+1 -6.OE 2.6E+1 -4.OE+0 - 7.4E+0 0/5/ 5 0 0/ 4 0/4 Cs-137 9 150 5.8E-1 +/- 4.7E+0 GmHbr: 7.4E+0 +/- 5.7E+0 3.9E+0 t 5.5E+0 0 -3.OE+0 - 5.3E+0 4.OE+0 - 1.1E+1 -1.5E+0 - 1.1E+1 0/5 0/2 0/4

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.

Page 50

Table 2.16-1 Lobster Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2014)

UA:rlll l"A. A.-., '- I 4 (W LA I W117C r". ILI IVL l I l. Rll~ l, l L IJL-I k1 jt* UI  : W !d,*%l~*

Indicator Stations Station with Highest Mean Control Stations Mean +/- Std.Dev. Station: Mean +/- Std.Dev. Mean +/- Std.Dev.

No. Analyses Required Range Range Range Radionuclide Non-routine LLD Fraction>LLD Fraction>LLD Fraction>LLD K-40 8 2.3E+3 +/- 4.1E+2 CCBay: 2.4E+3 +/- 6.4E+2 2.4E+3 +/- 6.4E+2 0 1.9E+3 - 2.9E+3 1.8E+3 - 3.OE+3 1.8E+3 - 3.OE+3 5/5 3/3 3/3 Mn-54 8 130 -5.1E-1 +/- 3.6E+0 CCBay: 5.9E-1 +/- 2.5E+0 5.9E-1 +/- 2.5E+0 0 -6.2E+0 - 2.6E+0 -1.6E+0 - 2.6E+0 -1.6E+0 - 2.6E+0 0/5 0/3 0/3 Fe-59 8 260 1.7E+0 +/- 4.5E+0 CCBay: 3.4E+0 +/- 5.0E+0 3.4E+0 +/- 5.OE+0 0 -2.OE+0 - 5.3E+O -7.3E 5.4E+0 -7.3E 5.4E+0 0/5 0/3 0/3 Co-58 8 130 -1.6E+O +/- 4.4E+0 CCBay: 1.6E+0 +/- 3.gE+0 1.6E+0 +/- 3.9E+0 0 -9.OE+0 - 1.5E+0 -4.0E 5.6E+0 -4.OE 5.6E+0 0/5 0/3 0/3 Co-60 8 130 2.2E-1 +/- 1.7E+0 DIS: 2.2E-1 +/- 1.7E+0 -2.3E+0 +/- 5.9E+0 0 -1.3E+0 - 1.4E+0 -1.3E+0 - 1.4E+0 -8.8E+0 - 2.1E+0 0/5 0/5 0/3 Zn-65 8 260 2.gE+0 +/- 6.9E+0 DIS: 2.9E+0 +/- 6.gE+0 -4.4E+0 +/- 6.6E+0 0 -2.OE+0 - 1.3E+1 -2.OE+0 - 1.3E+1 -1.OE+1 - 7.6E-1 0/5 0/5 0/3 Cs-134 8 130 -4.8E-1 +/- 1.8E+0 CCBay: 8.1E-2 +/- 5.6E+0 8.1E-2 +/- 5.6E+0 0 -2.4E+0 - 2.5E-1 -4.7E+0 - 5.8E+0 -4.7E+0 - 5.8E+0 0/5 0/3 0/3 Cs-137 8 150 2.5E+0 +/- 4.6E+0 DIS: 2.5E+0 +/- 4.6E+0 -2.2E-1 +/- 5.5E+0 0 -2.4E+0 - 6.9E+0 -2.4E+0 - 6.9E+0 -6.OE+0 - 4.5E+0 0/5 0/5 0/3

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.

Page 51

Table 2.17-1 Fish Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2014)

RAl~r'llIIH I. C~~ I1:-- "K1170 fl; Lý Indicator Stations Station with Highest Mean Control Stations No. Analyses Required Range Range Range Radionuclide Non-routine* LLD Fraction>LLD Fraction>LLD Fraction>LLD K-40 6 3.4E+3 +/- 3.2E+2 CCBay: 4.OE+3 +/- 1.6E+2 3.6E+3 +/- 4.5E+2 0 3.OE+3 - 3.6E+3 4.OE+3 - 4.OE+3 3.1E+3 - 4.OE+3 3/3 1/1 3/3 Mn-54 6 130 1.1E+0 +/- 2.7E+0 BuzBay: 5.1E+O +/- 2.6E+0 3.3E+O +/- 3.3E+O 0 -1.9E 3.5E+0 5.1E+0- 5.1E+0 5.3E 5.1E+0 0/3 0/1 0/3 Fe-59 6 260 4.9E+0 +/- 1.9E+1 NarBay: 9.3E+0 +/- 1.2E+1 8.7E-1 +/- 9.4E+0 0 -7.9E+0 - 1.8E+1 9.3E+0 - 9.3E+0 -6.7E+0 - 9.3E+0 0/3 0/1 0/3 Co-58 6 130 -2.3E+0 +/- 2.4E+0 NarBay: 2.3E+0 +/- 5.7E+0 3.OE-1 +/- 3.OE+0 0 -3.3E+0 - -4.1E-1 2.3E+0 - 2.3E+0 -1.7E+0 - 2.3E+0 0/3 0/1 0/3 Co-60 6 130 7.5E-1 +/- 3.5E+0 CCBay: 8.2E+0 +/- 3.7E+0 2.7E+0 +/- 5.5E+0 0 -2.2E+0 - 3.2E+0 8.2E+0 - 8.2E+0 -1.4E+0 - 8.2E+0 1 0/3 0/1 0/3 Zn-65 6 260 -7.9E+0 +/- 6.5E+0 CCBay: 1.7E+0 +/- 8.4E+0 -5.4E-1 +/- 5.9E+0 0 -1.3E+1 - -4.7E+0 1.7E+0 - 1.7E+0 -3.8E+0 - 1.7E+0 0/3 0/1 0/3 Cs-134 6 130 -3.OE+0 +/- 5.gE+0 NarBay: 2.OE+0 +/- 6.2E+0 -9.OE-1 +/- 4.5E+0 0 -9.3E+0 - 1.4E+0 2.OE+0 - 2.OE+0 -5.2E+0 - 2.OE+0 0/3 0/1 0/3 Cs-137 6 150 2.4E+0 +/- 5.6E+0 CCBay: 9.9E+0 +/- 3.5E+0 6.6E+0 +/- 3.7E+0 0 -4.7E 5.3E+0 9.9E+0 - 9.9E+0 4.7E+0 - 9.9E+0 1 0/3 0/3 0/3

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.

Page 52

Figure 2.2-1 Environmental TLD Locations Within the PNPS Protected Area TLD Station Location*

Description (Code Distance/Direction TLDs Within Protected Area O&M/RXB. BREEZEWAY P21 50 m SE EXEC.BUILDING P24 57 m W FENCE-R SCREENHOUSE P04 66 m N O&M - 2ND W WALL P20 67 m SE EXEC.BUILDING LAWN P25 76 m WNW FENCE-WATER TANK P05 81 m NNE FENCE-OIL STORAGE P06 85 m NE O&M-2ND SW CORNER P19 86 m S O&M - 1ST SW CORNER P18 90 m S COMPRESSED GAS STOR P08 92 m E FENCE-L SCREENHOUSE P03 100 m NW FENCE-EXEC.BUILDING P17 107 m W O&M- 2ND S WALL P23 121 m ENE FENCE-INTAKE BAY P07 121 m SSE FENCE-WAREHOUSE P26 134 m ESE FENCE-SHOREFRONT P02 135 m NW FENCE-W BOAT RAMP P09 136 m E O&M - 2ND N WALL P22 137 m SE FENCE-W SWITCHYARD P16 172 m SW FENCE-TCF GATE Pll 183 m ESE FENCE-TCF/BOAT RAMP P27 185 m ESE FENCE-ACCESS GATE P12 202 m SE FENCE-E SWITCHYARD P15 220 m S FENCE-TCF/INTAKE BAY P10 223 m E FENCE-MEDICAL BLDG. P13 224 m SSE FENCE-BUTLER BLDG P14 228 m S FENCE-TCF/PRKNG LOT P28 259 m ESE Distance and direction are measured from centerline of Reactor Building to the monitoring location.

Page 53

Figure 2.2-1 (continued)

Environmental TLD Locations Within the PNPS Protected Area Protected Area Fence Page 54

Figure 2.2-2 TLD and Air Sampling Locations: Within 1 Kilometer TLD Station Location* Air Sampling Station Location*

Description Code Distance/Direction Description Code Distance/Direction Zone 1 TLDs: 0-3 km BOAT LAUNCH WEST BLW 0.11 km E OVERLOOK AREA OA 0.15 km W OVERLOOK AREA OA 0.15 km W PEDESTRIAN BRIDGE PB 0.21 km N HEALTH CLUB TC 0.15 km WSW MEDICAL BUILDING WS 0.23 km SSE BOAT LAUNCH EAST BLE 0.16 km ESE EAST BREAKWATER EB 0.44 km ESE PEDESTRIAN BRIDGE PB 0.21 km N PROPERTY LINE PL 0.54 Ikn NNW SHOREFRONT SECURITY P01 0.22 km NNW W ROCKY HILL ROAD WR 0.83 km WNW MEDICAL BUILDING WS 0.23 km SSE E ROCKY HILL ROAD ER 0.89 krn SE PARKING LOT CT 0.31 km SE SHOREFRONT PARKING PA 0.35 km NNW STATION A A 0.37 km WSW STATION F F 0.43 km NW STATION B B 0.44 km S EAST BREAKWATER EB 0.44 km ESE PNPS MET TOWER PMT 0.44 km WNW STATION H H 0.47 km SW STATION I I 0.48 km WNW STATION L L 0.50 km ESE STATION G G 0.53 km W STATION D D 0.54 km NW PROPERTY LINE PL 0.54 km NNW STATION C C 0.57 km ESE HALL'S BOG HB 0.63 km SE GREENWOOD HOUSE GH 0.65 km ESE W ROCKY HILL ROAD WR 0.83 km WNW E ROCKY HILL ROAD ER 0.89 km SE Page 55

Figure 2.2-2 (continued)

TLD and Air Sampling Locations: Within 1 Kilometer BLE Page 56

Figure 2.2-3 TLD and Air Sampling Locations: 1 to 5 Kilometers TLD Station Location* Air Sampling Station Location*

Description Code Distance/Direction Description Code Distance/Direction Zone 1 TLDs: 0-3 km MICROWAVE TOWER MT 1.03 km SSW CLEFT ROCK CR 1.27 km SSW CLEFT ROCK CR 1.27 km SSW MANOMET SUBSTATION MS 3.60 km SSE BAYSHORE/GATE RD BD 1.34 km WNW MANOMET ROAD MR 1.38 km S DIRT ROAD DR 1.48 km SW EMERSON ROAD EM 1.53 km SSE EMERSON/PRISCILLA EP 1.55 km SE EDISON ACCESS ROAD AR 1.59 km SSE BAYSHORE BS 1.76 km W STATION E E 1.86 km S JOHN GAULEY JG 1.99 km W STATION J J 2.04 km SSE WHITEHORSE ROAD WH 2.09 km SSE PLYMOUTH YMCA RC 2.09 km WSW STATION K K 2.17 km S TAYLOR/THOMAS TT 2.26 km SE YANKEE VILLAGE YV 2.28 km WSW GOODWIN PROPERTY GN 2.38 km SW RIGHT OF WAY RW 2.83 km S TAYLOR/PEARL TP 2.98 km SE Zone 2 TLDs: 3-8 km VALLEY ROAD VR 3.26 km SSW MANOMET ELEM ME 3.29 km SE WARREN/CLIFFORD WC 3.31 km W RT.3AJBARTLETT RD BB 3.33 km SSE MANOMET POINT MP 3.57 km SE MANOMET SUBSTATION MS 3.60 km SSE BEACHWOOD ROAD BW 3.93 km SE PINES ESTATE PT 4.44 km SSW EARL ROAD EA 4.60 km SSE S PLYMOUTH SUBST SP 4.62 km W ROUTE 3 OVERPASS RP 4.81 km SW RUSSELL MILLS RD RM 4.85 km WSW Distance and direction are measured from centerline of Reactor Building to the monitoring location.

Page 57

Figure 2.2-3 (continued)

TLD and Air Sampling Locations: 1 to 5 Kilometers Page 58

Figure 2.2-4 TLD and Air Sampling Locations: 5 to 25 Kilometers TLD Station Location* Air Sampling Station Location*

Description Code Distance/Direction Description Code Distance/Direction Zone 2 TLDs: 3-8 km HILLDALE ROAD HD 5.18 km W PLYMOUTH CENTER PC 6.69 km W MANOMET BEACH MB 5.43 km SSE BEAVER DAM ROAD BR 5.52 km S PLYMOUTH CENTER PC 6.69 km W LONG POND/DREW RD LD 6.97 km WSW HYANNIS ROAD HR 7.33 km SSE MEMORIAL HALL MH 7.58 km WNW SAQUISH NECK SN 7.58 km NNW COLLEGE POND CP 7.59 km SW Zone 3 TLDs: 8-15 km DEEP WATER POND DW 8.59 km W LONG POND ROAD LP 8.88 km SSW NORTH PLYMOUTH NP 9.38 km WNW STANDISH SHORES SS 10.39 km NW ELLISVILLE ROAD EL 11.52 km SSE UP COLLEGE POND RD UC 11.78 km SW SACRED HEART SH 12.92 km W KING CAESAR ROAD KC 13.11 km NNW BOURNE ROAD BE 13.37 km S SHERMAN AIRPORT SA 13.43 km WSW Zone 4TLDs: >15km CEDARVILLE SUBST CS 15.93 km S KINGSTON SUBST KS 16.15 km WNW LANDING ROAD LR 16.46 km NNW CHURCH/WEST CW 16.56 km NW MAIN/MEADOW MM 17.02 km WSW DIV MARINE FISH DMF 20.97 km SSE Distance and direction are measured from centerline of Reactor Building to the monitoring location.

Page 59

Figure 2.2-4 (continued)

TLD and Air Sampling Locations: 5 to 25 Kilometers

,*:**.**=**.*:,*:

.,*-.:***i! .

Page 60

Figure 2.2-5 Terrestrial and Aquatic Sampling Locations Description Code Distance/Direction. Description Code Distance/Direction*

FORAGE SURFACE WATER Plymouth County Farm CF 5.6 km W Discharge Canal DIS 0.2 km N Bridgewater Control BF 31 km W Bartlett Pond BP 2.7 km SE Hanson Farm Control HN 34 km W Powder Point Control PP 13 km NNW SEDIMENT Discharge Canal Outfall DIS 0.8 km NE Plymouth Beach PLB 4.0 km W Manomet Point MP 3.3 km ESE VEGETABLESIVEGETAT ION Plymouth Harbor PLY-H 4.1 km W Site Boundary C BC 0.5 km SW Duxbury Bay Control DUX-BAY 14 km NNW Site Boundary B BB 0.5 km ESE Green Harbor Control GH 16 km NNW Rocky Hill Road RH 0.9 km SE Site Boundary D Bd 1.1 km S IRISH MOSS Site Boundary A BA 1.5 km SSW Discharge Canal Outfall DIS 0.7 km NNE Clay Hill Road CH 1.6 km W Manomet Point MP 4.0 km ESE Brook Road BK 2.9 km SSE Ellisville EL 12 km SSE Beaver Dam Road BD 3.4 km S Brant Rock Control BK 18 km NNW Plymouth County Farm CF 5.6 km W Hanson Farm Control HN 34 km W SHELLFISH Norton Control NC 50 km W Discharge Canal Outfall DIS 0.7 In NNE Plymouth Harbor PLY-H 4.1 km W CRANBERRIES Manomet Point MP 4.0 km ESE Bartlett Road Bog BT 4.3 km SSE Duxbury Bay Control DUX-BAY 13 km NNW Beaverdam Road Bog MR 3.4 km S Powder Point Control PP 13 km NNW Hollow Farm Bog Control HF 16 km WNW Green Harbor Control GH 16 km NNW LOBSTER Discharge Canal Outfall DIS 0.5 km N Plymouth Beach PLB 4.0 km W Plymouth Harbor PLY-H 6.4 km WNW Duxbury Bay Control DUX-BAY 11 km NNW FISHES Discharge Canal Outfall DIS 0.5 km N Plymouth Beach PLB 4.0 km W Jones River Control JR 13 km WNW Cape Cod Bay Control CC-BAY 24 km ESE N River-Hanover Control NR 24 km NNW Cataumet Control CA 32 km SSW Provincetown Control PT 32 km NE Buzzards Bay Control BB 40 km SSW Priest Cove Control PC 48 km SW Nantucket Sound Control NS 48 km SSE Atlantic Ocean Control AO 48 km E Vineyard Sound Control MV 64 km SSW

• Distance and direction are measured from the centerline of the reactor to the sampling/monitoring location.

Page 61

Figure 2.2-5 (continued)

Terrestrial and Aquatic Sampling Locations SYMBOL KEY SHELLFISH (M BLUE MUSSEL)

(S SOFT-SHELL)

(H HARD-SHELL) 0 IRISH MOSS

[Z LOBSTER (D FISHES SURFACE WATER D SEDIMENT

< CRANBERRY A VEGETATION 0 MImES 2 SCALE 31 KILOMETERS WEST 34 KILOMETERS WEST 32 KILOMETEF.S NORTHEAST I0K:ILOMETERS WEST EAST WHITEHORSE BEACH M241T-IOMETERS EAST-SOUTHEAST 48 IKILCMETERS

-# - SITHWEST r,

4o mILOMETERS SOUTH-SOUTHWEST 64 KIL SOUTI 48 KILOMETERS SOUTH-SOUTHEAST Page 62

Figure 2.2-6 Environmental Sampling And Measurement Control Locations Description Code Distance/Direction* Description Code DistancelDirection*

TLD SURFACE WATER Cedarville Substation CS 16 km S Powder Point Control PP 13 km NNW Kingston Substation KS 16 km WNW Landing Road LR 16 km NNW SEDIMENT Church & West Street CW 17 km NW Duxbury Bay Control DUIX-BAY 14 km NNW Main & Meadow Street MM 17 km WSW Green Harbor Control GH 16 km NNW Div. Marine Fisheries DMF 21 km SSE East Weymouth Substation EW 40 km NW IRISH MOSS Brant Rock Control BK 18 km NNW AIR SAMPLER East Weymouth Substation EW 40 km NW SHELLFISH Duxbury Bay Control DUX-BAY 13 km NNW FORAGE Powder Point Control PP 13 km NNW Bridgewater Control BF 31 km W Green Harbor Control GH 16 km NNW Hanson Farm Control HN 34 km W LOBSTER VEGETABLESNEGETATION Duxbury Bay Control DUX-BAY 11 km NNW Hanson Farm Control HN 34 km W Norton Control NC 50 km W FISHES Jones River Control JR 13 km WNW Cape Cod Bay Control CC-BAY 24 km ESE CRANBERRIES N River-Hanover Control NR 24 km NNW Hollow Farm Bog Control HF 16 km WNW Cataumet Control CA 32 km SSW Provincetown Control PT 32 km NE Buzzards Bay Control BB 40 km SSW Priest Cove Control PC 48 km SW Nantucket Sound Control NS 48 km SSE Atlantic Ocean Control AO 48 km E Vineyard Sound Control MV 64 km SSW

• Distance and direction are measured from the centerline of the reactor to the sampling/monitoring location.

Page 63

Figure 2.2-6 (continued)

Environmental Sampling And Measurement Control Locations SYMB113OL KEY CZi SHELLFISH (M BLUE MUSSEL)

(S SOFT-SHELL CLAM)

(H HARD-SHELL CLAM)

C)IRISH MOSS EX LOBSTER MASSACHUSETTSBAY CX FISHES BOSTONHARBOB D---

VjSURFACE WATER C:3 CRANBERRY HABORVEGETATION/I*ORAGE gR-STO

[ AM SAMPLER

-~ QTLD 0 MILES 10 SCALE CAPECODBAY

<ZBAY Page 64

Airborne Gross-Beta Radioactivity Levels Near-Station Monitors

-1.OE-02 I Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month - 2014

-- AP-00 Warehouse = AP-07 Pedestrian Bridge

- - AP-08 Overlook Area u AP-09 East Breakwater

-in- AP-21 East Weymouth Control Figure 2.5-1 Airborne Gross-Beta Radioactivity Levels: Near Station Monitors Page 65

Airborne Gross-Beta Radioactivity Levels Property Line Monitors E

0) 0 CL

-1.OE-024 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month - 2014

-- AP-01 E. Rocky Hill Road = AP-03 W. Rocky Hill Road

- - AP-06 Property Line --n AP-21 East Weymouth Control Figure 2.5-2 Airborne Gross-Beta Radioactivity Levels: Property Line Monitors Page 66

Airborne Gross-Beta Radioactivity Levels Offsite Monitors 5.OE-02

~2)

E 0

n U

G)

U 0

C-)

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month - 2014 AP-10 Cleft Rock -i-a AP-1 5 Plymouth Center

- - AP-1 7 Manomet Substation -w- AP-21 East Weymouth Control Figure 2.5-3 Airborne Gross-Beta Radioactivity Levels: Offsite Monitors Page 67

3.0

SUMMARY

OF RADIOLOGICAL IMPACT ON HUMANS The radiological impact to humans from the Pilgrim Station's radioactive liquid and gaseous releases has been estimated using two methods:

• calculations based on measurements of plant effluents; and

" calculations based on measurements of environmental samples.

The first method utilizes data from the radioactive effluents (measured at the point of release) together with conservative models that calculate the dispersion and transport of radioactivity through the environment to humans (Reference 7). The second method is based on actual measurements of radioactivity in the environmental samples and on dose conversion factors recommended by the Nuclear Regulatory Commission. The measured types and quantities of radioactive liquid and gaseous effluents released from Pilgrim Station during 2014 were reported to the Nuclear Regulatory Commission, copies of which are provided in Appendix B. The measured levels of radioactivity in the environmental samples that required dose calculations are listed in Appendix A.

The maximum individual dose from liquid effluents was calculated using the following radiation exposure pathways:

• shoreline external radiation during fishing and recreation at the Pilgrim Station Shorefront;

• external radiation from the ocean during boating and swimming; and

• ingestion of fish and shellfish.

For gaseous effluents, the maximum individual dose was calculated using the following radiation exposure pathways:

" external radiation from cloud shine and submersion in gaseous effluents;

• inhalation of airborne radioactivity;

" external radiation from soil deposition;

• consumption of vegetables; and

• consumption of milk and meat.

The results from the dose calculations based on PNPS operations are presented in Table 3.0-1.

The dose assessment data presented were taken from the "Radioactive Effluent Release Report" for the period of January 1 through December 31, 2014 (Reference 17).

Page 68

Table 3.0-1 Radiation Doses from 2014 Pilgrim Station Operations Maximum Individual Dose From Exposure Pathway - mrem/yr Gaseous Liquid Ambient Receptor Effluents* Effluents Radiation** Total Total Body 0.045 0.00000029 0.52 0.57 Thyroid 0.047 0.00000020 0.52 0.57 Max. Organ 0.088 0.00000087 0.52 0.61

• Gaseous effluent exposure pathway includes combined dose from particulates, iodines and tritium in addition to noble gases, calculated at the nearest residence.

• • Ambient radiation dose for the hypothetical maximum-exposed individual at a location on PNPS property yielding highest ambient radiation exposure value as measured with TLDs.

Two federal agencies establish dose limits to protect the public from radiation and radioactivity. The Nuclear Regulatory Commission (NRC) specifies a whole body dose limit of 100 mrem/yr to be received by the maximum exposed member of the general public. This limit is set forth in Section 1301, Part 20, Title 10, of the U.S. Code of Federal Regulations (10CFR20). By comparison, the Environmental Protection Agency (EPA) limits the annual whole body dose to 25 mrem/yr, which is specified in Section 10, Part 190, Title 40, of the Code of Federal Regulations (40CFR1 90).

Another useful "gauge" of radiation exposure is provided by the amount of dose a typical individual receives each year from natural and man-made sources of radiation. Such radiation doses are summarized in Table 1.2-1. The typical American receives about 620 mrem/yr from such sources.

As can be seen from the doses resulting from Pilgrim Station Operations during 2014, all values are well within the federal limits specified by the NRC and EPA. In addition, the calculated doses from PNPS operation represent only a fraction of a percent of doses from natural and man-made radiation.

In conclusion, the radiological impact of Pilgrim Station operations, whether based on actual environmental measurements or calculations made from effluent releases, would yield doses well within any federal dose limits set by the NRC or EPA. Such doses represent only a small percentage of the typical annual dose received from natural and man-made sources of radiation.

Page 69

4.0 REFERENCES

1) United States of America, Code of Federal Regulations, Title 10, Part 50, Appendix A Criteria 64.

2) Donald T. Oakley, "Natural Radiation Exposure in the United States." U. S. Environmental Protection Agency, ORP/SID 72-1, June 1972.

3) National Council on Radiation Protection and Measurements, Report No. 93, "Ionizing Radiation Exposures of the Population of the United States," September 1987.

4) United States Nuclear Regulatory Commission, Regulatory Guide 8.29, "Instructions Concerning Risks from Occupational Radiation Exposure," Revision 0, July 1981.

5) Boston Edison Company, "Pilgrim Station" Public Information Brochure 100M, WNTHP, September 1989.

6) United States Nuclear Regulatory Commission, Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I," Revision 1, October 1977.

7) Pilgrim Nuclear Power Station Offsite Dose Calculation Manual, Revision 9, June 2003.

8) United States of America, Code of Federal Regulations, Title 10, Part 20.1301.

9) United States of America, Code of Federal Regulations, Title 10, Part 50, Appendix I.

10) United States of America, Code of Federal Regulations, Title 40, Part 190.

11) United States Nuclear Regulatory Commission, Regulatory Guide 4.1, "Program for Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975.

12) ICN/Tracerlab, "Pilgrim Nuclear Power Station Pre-operational Environmental Radiation Survey Program, Quarterly Reports," August 1968 to June 1972.

13) International Commission of Radiological Protection, Publication No. 43, "Principles of Monitoring for the Radiation Protection of the Population," May 1984.

14) United States Nuclear Regulatory Commission, NUREG-1 302, "Offsite Dose Calculation Manual Guidance: Standard Radiological Effluent Controls for Boiling Water Reactors," April 1991.

15) United States Nuclear Regulatory Commission, Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.

16) Settlement Agreement Between Massachusetts Wildlife Federation and Boston Edison Company Relating to Offsite Radiological Monitoring - June 9, 1977.

17) Pilgrim Nuclear Power Station, "Annual Radioactive Effluent Release Report", May 2014.

Page 70

APPENDIX A SPECIAL STUDIES There were no environmental samples collected during 2014 that contained plant-related radioactivity.

Therefore, no special studies were required to estimate dose from plant-related radioactivity.

Page 71

APPENDIX B Effluent Release Information TABLE TITLE PAGE B.1 Supplemental Information 73 B.2-A Gaseous Effluents Summation of All Releases 74 B.2-B Gaseous Effluents - Elevated Releases 75 B.2-C Gaseous Effluents - Ground Level Releases 77 B.3-A Liquid Effluents Summation of All Releases 79 B.3-B Liquid Effluents 80 Page 72

Table B.1 Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Supplemental Information January-December 2014 FACILITY: PILGRIM NUCLEAR POWER STATION LICENSE: DPR-35

1. REGULATORY LIMITS

a. Fission and activation gases: 500 mrem/yr total body and 3000 mrem/yr for skin at site boundary b,c. lodines, particulates with half-life: 1500 mrem/yr to any organ at site boundary

>8 days, tritium

d. Liquid effluents: 0.06 mrem/month for whole body and 0.2 mrem/month for any organ I (without radwaste treatment)

2. EFFLUENT CONCENTRATION LIMITS

a. Fission and activation gases: 10CFR20 Appendix B Table II

b. lodines: 10CFR20 Appendix B Table II

c. Particulates with half-life > 8 days: 10CFR20 Appendix B Table II

d. Liquid effluents: 2E-04 j.Ci/mL for entrained noble gases; 10CFR20 Appendix B Table II values for all other radionuclides

3. AVERAGE ENERGY Not Applicable

4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY

a. Fission and activation gases: High purity germanium gamma spectroscopy for all

b. lodines: gamma emitters; radiochemistry analysis for H-3,

c. Particulates: Fe-55 (liquid effluents), Sr-89, and Sr-90

d. Liquid effluents:

5. BATCH RELEASES Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec 2014 2014 2014 2014

_ 2014

a. Liquid Effluents

1. Total number of releases: N/A 1 N/A N/A 1

2. Total time period (minutes): N/A 1.44E+03 N/A N/A 1.44E+03

3. Maximum time period N/A 1.44E+03 N/A N/A 1.44E+03 (minutes):

4. Average time period (minutes): N/A 1.44E+03 N/A N/A 1.44E+03

5. Minimum time period (minutes): N/A 1.44E+03 N/A N/A 1.44E+03

6. Average stream flow during periods duigprosoof release ees offN/A 1.17E+06 N/A N/A 1.17E+06 effluents into a flowing stream (Liters/min): I

b. Gaseous Effluents None None None None None

6. ABNORMAL RELEASES

a. Liquid Effluents None None None None None

b. Gaseous Effluents None None None None None Page 73

Table B.2-A Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Summation of All Releases January-December 2014 Est.

RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Total 2014 2014 2014 2014 2014 Error A. FISSION AND ACTIVATION GASES Total Release: Ci NDA NDA NDA 1.68E+00 1.68E+00 Average Release Rate: pjCi/sec N/A N/A N/A 2.13E-01 5.32E-02 +/-22%

Percent of Effluent Control Limit*. ....

B. IODINE-131 Total lodine-131 Release: Ci 3.91E-05 7.04E-05 9.16E-05 5.25E-05 2.54E-04 Average Release Rate: pjCi/sec 4.96E-06 8.93E-06 1.16E-05 6.66E-06 8.04E-06 +/-20%

Percent of Effluent Control Limit*...

C. PARTICULATES WITH HALF-LIVES > 8 DAYS Total Release: Ci 2.41 E-05 5.27E-05 2.11E-04 1.79E-05 3.05E-04 Average Release Rate: p.Ci/sec 3.05E-06 6.68E-06 2.67E-05 2.26E-06 9.68E-06 Percent of Effluent Control Limit* * +/-21%

Gross Alpha Radioactivity: Ci NDA NDA NDA NDA NDA D. TRITIUM Total Release: Ci 2.32E+01 2.38E+01 2.07E+01 2.23E+01 9.01E+01 Average Release Rate: pCi/sec 2.95E+00 3.02E+00 2.62E+00 2.83E+00 2.86E+00 +/-20%

Percent of Effluent Control Limit*. ....

E. CARBON-14 Total Release: Ci 2.14E+00 2.01E+00 2.04E+00 2.15E+00 8.33E+00 Average Release Rate: pCi/sec 2.71 E-01 2.55E-01 2.59E-01 2.73E-01 2.64E-01 N/A Percent of Effluent Control Limit*. ....

Notes for Table 2.2-A:

• Percent of Effluent Control Limit values based on dose assessments are provided in Section 6 of this report.

1. NDA stands for No Detectable Activity.

2. LLD for airborne gross alpha activity listed as NDA is 1 E-1 1 pCi/cc.

3. N/A stands for not applicable.

Page 74

Table B.2-B Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Elevated Release January-December 2014 CONTINUOUS MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released I Jan-Mar 2014 Apr-Jun 2014 Jul-Sep 2014 Oct-Dec 2014 Jan-Dec 2014

1. FISSION AND ACTIVATION GASES: Ci Ar-41 0.OOE+00 0.OOE+00 0.GOE+00 0.OOE+00 O.OOE+00 Kr-85 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Kr-85m 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 0.00E+00 Kr-87 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Kr-88 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Xe-131m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-133 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-1 33m 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-135 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-135m 0.OOE+00 O.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Xe-137 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Xe-1 38 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Total for Period 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00

2. IODINES: Ci 1-131 2.92E-07 2.69E-06 0.OOE+00 0.OOE+00 2.98E-06 1-133 0.00E+00 6.83E-06 1.97E-06 0.0OE+00 8.80E-06 Total for Period 2.92E-07 9.52E-06 1.97E-06 0.00E+00 1.18E-05

3. PARTICULATES WITH HALF-LIVES > 8 DAYS: Ci Cr-51 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Mn-54 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Fe-59 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.00E+00 Co-58 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Co-60 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Zn-65 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 Sr-89 0.00E+00 0.00E+00 0.00E+00 0.OOE+00 0.OOE+00 Sr-90 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.00E+00 Ru-1 03 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 Cs-1 34 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 Cs-1 37 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Ba/La-140 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Total for Period 0.OOE+00 0.OOE+00 0.OOE+00 3.31 E-02 1.08E-01

4. TRITIUM: Ci H-3 I1.23E-02 2.87E-02 3.40E-02 3.31 E-02 I1.08E-01

5. CARBON-14: Ci C-14 2.07E+00 I1.95E+00 I1.98E+00 2.09E+00 8.08E+00 Notes for Table 2.2-B:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

3. LLDs for airborne radionuclides listed as NDA are as follows:

Fission Gases: 1E-04 pCi/cc lodines: 1E-12 pCi/cc Particulates: 1E-11 pCi/cc Page 75

Table B.2-B (continued)

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Elevated Release January-December 2014 BATCH MODE RELEASES FROM ELEVATED RELEASE POINT Nuclide Released Jan-Mar2014 Apr-Jun2014 Jul-Sep2014 I Oct-Dec2014 Jan-Dec2014

1. FISSION AND ACTIVATION GASES: Ci Ar-41 N/A N/A N/A N/A N/A Kr-85 N/A N/A N/A N/A N/A Kr-85m N/A N/A N/A N/A N/A Kr-87 N/A N/A N/A N/A N/A Kr-88 N/A N/A N/A N/A N/A Xe-131 m N/A N/A N/A N/A N/A Xe- 133 N/A N/A N/A N/A N/A Xe-133m N/A N/A N/A N/A N/A Xe- 135 N/A N/A N/A N/A N/A Xe-135m N/A N/A N/A N/A N/A Xe- 137 N/A N/A N/A N/A N/A Xe- 138 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A

2. IODINES: Ci 1-131 N/A N/A N/A N/A N/A 1-133 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A

3. PARTICULATES WITH HALF-LIVES > 8 DAYS: Ci Cr-51 N/A N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A N/A Co-58 N/A N/A N/A N/A N/A Co-60 N/A N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A N/A Ru-103 N/A N/A N/A N/A N/A Cs-134 N/A N/A N/A N/A N/A Cs- 137 N/A N/A N/A N/A N/A Ba/La-140 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A

4. TRITIUM: Ci H-3 N/A N/A N/A N/A N/A

5. CARBON-14: Ci C-14 N/A N/A N/A N/A N/A Notes for Table 2.2-B:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

3. LLDs for airborne radionuclides listed as NDA are as follows:

Fission Gases: 1E-04 pCi/cc lodines: 1E-12 pCi/cc Particulates: 1E-1 1 jiCi/cc Page 76

Table B.2-C Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Ground-Level Release January-December 2014 CONTINUOUS MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released I Jan-Mar 2014 Apr-Jun 2014 Jul-Sep 2014 Oct-Dec 2014 Jan-Dec 2014

1. FISSION AND ACTIVATION GASES: Ci Ar-41 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Kr-85 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 Kr-85m 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Kr-87 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00 Kr-88 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Xe-131m 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Xe-133 0.OOE+00 0.OOE+00 0.OOE+00 8.31E-01 8.31E-01 Xe-133m 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Xe-135 0.OOE+00 0.OOE+00 0.OOE+00 8.48E-01 8.48E-01 Xe-135m 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 Xe-137 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Xe-138 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 Total for period 0.OOE+00 0.OOE+00 0.00E+00 1.68E+00 1.68E+00

2. IODINES: Ci 1-131 3.88E-05 6.78E-05 9.16E-05 5.25E-05 2.51 E-04 1-133 1.34E-04 2.16E-04 3.23E-04 2.51 E-04 9.24E-04 Total for period 1.73E-04 2.84E-04 4.15E-04 3.03E-04 1.17E-03

3. PARTICULATES WITH HALF-LIVES > 8 DAYS: Ci Cr-51 0.OOE+00 9.87E-06 0.OOE+00 9.96E-06 1.98E-05 Mn-54 0.OOE+00 3.26E-05 5.29E-06 0.OOE+00 3.79E-05 Fe-59 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.00E+00 Co-58 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Co-60 4.25E-06 9.34E-06 0.OOE+00 0.00E+00 1.36E-05 Zn-65 0.OOE+00 O.00E+00 0.OOE+00 0.00E+00 0.OOE+00 Sr-89 0.OOE+00 8.70E-07 1.32E-05 2.72E-06 1.68E-05 Sr-90 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 Ru-103 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Cs-134 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Cs-137 0.00E+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00 Ba/La-140 1.98E-05 0.OOE+00 1.92E-04 5.17E-06 2.17E-04 Total for period 2.41 E-05 5.27E-05 2.11 E-04 1.79E-05 3.05E-04

4. TRITIUM: Ci H-3 2.32E+01 2.38E+01 2.06E+01 2.23E+01i 9.OOE+01

5. CARBON-14: Ci C-14 6.41E-02 6.02E-02 6.12E-02 6.52E-02 2.51E-01 Notes for Table 2.2-C:

1. NIA stands for not applicable.

2. NDA stands for No Detectable Activity.

3. LLDs for airborne radionuclides listed as NDA are as follows:

Fission Gases: 1E-04 pCi/cc lodines: 1E-12 pCi/cc Particulates: 1E-1 1 pCi/cc Page 77

Table B.2-C (continued)

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Gaseous Effluents - Ground-Level Release January-December 2014 BATCH MODE RELEASES FROM GROUND-LEVEL RELEASE POINT Nuclide Released Jan-Mar 2014 Apr-Jun 2014 Jul-Sep 2014 Oct-Dec 2014 Jan-Dec 2014

1. FISSION AND ACTIVATION GASES: Ci Ar-41 N/A N/A N/A N/A N/A Kr-85 N/A N/A N/A N/A N/A Kr-85m N/A N/A N/A N/A N/A Kr-87 N/A N/A N/A N/A N/A Kr-88 N/A N/A N/A N/A N/A Xe-131m N/A N/A N/A N/A N/A Xe-133 N/A N/A N/A N/A N/A Xe-133m N/A N/A N/A N/A N/A Xe-135 N/A N/A N/A N/A N/A Xe-135m N/A N/A N/A N/A N/A Xe-137 N/A N/A N/A N/A N/A Xe-138 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A

2. IODINES: Ci 1-131 N/A N/A N/A N/A N/A 1-133 N/A N/A N/A N/A N/A Total for period .N/A N/A N/A N/A N/A

3. PARTICULATES WITH HALF-LIVES > 8 DAYS: Ci Cr-51 N/A N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A N/A Co-58 N/A N/A N/A N/A N/A Co-60 N/A N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A N/A Ru-1 03 N/A N/A N/A N/A N/A Cs-1 34 N/A N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A N/A Ba/La-140 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A

4. TRITIUM: Ci H-3 N/A N/A N/A N/A N/A

5. CARBON-14: Ci C-14 N/A N/A N/A N/A N/A Notes for Table 2.2-C:

1, N/A stands for not applicable.

2, NDA stands for No Detectable Activity.

3, LLDs for airborne radionuclides listed as NDA are as follows:

Fission Gases: 1 E-04 pCi/cc lodines: 1 E-12 pCi/cc Particulates: 1E-11 pCi/cc Page 78

Table B.3-A Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents - Summation of All Releases January-December 2014 I Es.

RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec I Total 2014 2014 2014 2014 2014 Error A. FISSION AND ACTIVATION PRODUCTS Total Release (not including N/A 7.50E-06 N/A N/A 7.50E-06 tritium, gases, alpha): Ci Average Diluted Concentration N/A 4.89E-14 N/A N/A 1.22E-14 +/-12%

During Period: piCi/mL Percent of Effluent N/A 1.47E-06% N/A N/A 3.68E-07%

Concentration Limit*

B. TRITIUM Total Release: Ci N/A 3.87E-03 N/A N/A 3.87E-03 Average Diluted Concentration N/A 2.52E-1 1 N/A NIA 6.30E-12 During Period: pCi/mL +/-9.41 Percent of Effluent N/A 2.52E-06% N/A N/A 6.30E-07%

Concentration Limit*

C. DISSOLVED AND ENTRAINED GASES Total Release: Ci N/A NDA N/A N/A NDA Average Diluted Concentration N/A NDA N/A N/A NDA During Period: pCi/mL +/-16%

Percent of Effluent N/A

_._0E+00% N/A N/A

_.__E+00%

Concentration Limit* N I N N I D. GROSS ALPHA RADIOACTIVITY Total Release: Ci I N/A NDA N/A N/A NDA +/-34%

E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION Waste Volume: Liters I N/A 2.28E+04 N/A N/A 2.28E+04 +/-5.7%

F. VOLUME OF DILUTION WATER USED DURING PERIOD Dilution Volume: Liters 1.52E+11 I1.53E+11 I 1.55E+11 1.55E+11 6.14E+11 +/-10%

Notes for Table 2.3-A:

• Additional percent of Effluent Control Limit values based on dose assessments are provided in Section 6 of this report.

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

3. LLD for dissolved and entrained gases listed as NDA is 1E-05 pCi/mL.

4. LLD for liquid gross alpha activity listed as NDA is 1E-07 pCi/mL.

Page 79

Table B.3-B Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2014 CONTINUOUS MODE RELEASES Nuclide Released Jan-Mar 2014 Apr-Jun 2014 Jul-Sep 2014 Oct-Dec 2014 Jan-Dec 2014

1. FISSION AND ACTIVATION PRODUCTS: Ci Cr-51 N/A N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A N/A Fe-55 N/A N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A N/A Co-58 N/A N/A N/A N/A N/A Co-60 N/A N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A N/A Zn-69m N/A N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A N/A Zr/Nb-95 N/A N/A N/A N/A N/A Mo/Tc-99 N/A N/A N/A N/A N/A Ag-110m N/A N/A N/A N/A N/A Sb-124 N/A N/A N/A N/A N/A 1-131 N/A N/A N/A N/A N/A 1-133 N/A N/A N/A N/A N/A Cs-1 34 N/A N/A N/A N/A N/A Cs-1 37 N/A N/A N/A N/A N/A Ba/La-140 N/A N/A N/A N/A N/A Ce-141 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A

2. DISSOLVED AND ENTRAINED GASES: Ci Xe-1 33 N/A N/A N/A N/A N/A Xe-1 35 N/A N/A N/A N/A N/A Total for period N/A N/A N/A N/A N/A Notes for Table 2.3-B:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

3. LLDs for liquid radionuclides listed as NDA are as follows:

Strontium: 5E-08 ptCi/mL lodines: 1E-06 pjCi/m L Noble Gases: 1E-05 atCi/mL All Others: 5E-07 atCi/mL Page 80

Table B.3-B (continued)

Pilgrim Nuclear Power Station Annual Radioactive Effluent Release Report Liquid Effluents January-December 2014 BATCH MODE RELEASES Nuclide Released Jan-Mar 2014 Apr-Jun 2014 Jul-Sep 2014 Oct-Dec 2014 Jan-Dec 2014

1. FISSION AND ACTIVATION PRODUCTS: Ci Na-24 N/A 0.OOE+00 N/A N/A 0.OOE+00 Cr-51 N/A O.OOE+00 N/A N/A 0.O0E+00 Mn-54 N/A 2.21 E-06 N/A N/A 2.21 E-06 Fe-55 N/A 0.OOE+00 N/A N/A O.00E+00 Fe-59 N/A 0.OOE+00 N/A N/A 0.00E+00 Co-58 N/A 0.OOE+00 N/A N/A 0.OOE+00 Co-60 N/A 4.64E-06 N/A N/A 4.64E-06 Zn-65 N/A 0.00E+00 N/A N/A 0.OOE+00 Zn-69m N/A 0.00E+00 N/A N/A 0.OOE+00 Sr-89 N/A 0.OOE+00 N/A N/A 0.00E+00 Sr-90 N/A 0.00E+00 N/A N/A 0.00E+00 Zr/Nb-95 N/A 0.OOE+00 N/A N/A 0.00E+00 Mo/Tc-99 N/A 0.OOE+00 N/A N/A 0.00E+00 Ag-11Om N/A 0.OOE+00 N/A N/A 0.OOE+00 Sb-124 N/A 0.OOE+00 N/A N/A 0.OOE+00 1-131 N/A 0.00E+00 N/A N/A 0.00E+00 1-133 N/A 0.00E+00 N/A N/A 0.00E+00 Cs-1 34 N/A 0.00E+00 N/A N/A 0.OOE+00 Cs-1 37 N/A 6.39E-07 N/A N/A 6.39E-07 Ba/La-140 N/A 0.OOE+00 N/A N/A 0.OOE+00 Ce-141 N/A 0.OOE+00 N/A N/A 0.OOE+00 Ce-144 N/A 0.00E+00 N/A N/A 0.00E+00 Total for period N/A 7.50E-06 N/A N/A 7.50E-06

2. DISSOLVED AND ENTRAINED GASES: Ci Xe-1 33 N/A NDA N/A N/A NDA Xe-1 35 N/A NDA N/A N/A NDA Total for period N/A NDA N/A N/A NDA Notes for Table 2.3-B:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

3. LLDs for liquid radionuclides listed as NDA are as follows:

Strontium: 5E-08 pCi/mL lodines: 1E-06 pCi/mL Noble Gases: IE-05 1iCi/mL All Others: 5E-07 pCi/mL Page 81

APPENDIX C LAND USE CENSUS RESULTS The annual land use census for gardens and milk and meat animals in the vicinity of Pilgrim Station was performed between September 13 and September 19, 2014. The census was conducted by driving along each improved road/street in the Plymouth area within 5 kilometers (3 miles) of Pilgrim Station to survey for visible gardens with an area of greater than 500 square feet. In compass sectors where no gardens were identified within 5 km (SSW, WNW, NW, and NNW sectors), the survey was extended to 8 km (5 mi). A total of 28 gardens were identified in the vicinity of Pilgrim Station. In addition, the Town of Plymouth Animal Inspector was contacted for information regarding milk and meat animals.

Atmospheric deposition (D/Q) values at the locations of the identified gardens were compared to those for the existing sampling program locations. These comparisons enabled PNPS personnel to ascertain the best locations for monitoring for releases of airborne radionuclides. Samples of naturally-growing vegetation were collected at the site boundary in the ESE and SE sectors to monitor for atmospheric deposition in the vicinity of the nearest resident in the SE sector.

In addition to these special sampling locations identified and sampled in conjunction with the 2014 land use census, samples were also collected at or near the Plymouth County Farm (5.6 km W), and from control locations in Bridgewater (31 km W), Sandwich (21 km SSE), and Norton (49 km W).

Samples of naturally-growing vegetation were also collected in the vicinity of the site boundary locations yielding the highest deposition (D/Q) factors for each of the two release points. These locations, and their distance and direction relative to the PNPS Reactor Building, are as follows:

Highest Main Stack D/Q: 1.2 km SSW Highest Reactor Building Vent D/Q: 0.6 km SE 2 nhighest D/Q, both release points: 1.1 km S No new milk or meat animals were identified during the land use census. In addition, the Town of Plymouth Animal Inspector stated that their office is not aware of any animals at locations other than the Plimoth Plantation. Although milk sampling is not performed at Plimoth Plantation, effluent dose calculations are performed for this location assuming the presence of a milk ingestion pathway, as part of the Annual Radioactive Effluent Release Report (Reference 17).

Page 82

APPENDIX D ENVIRONMENTAL MONITORING PROGRAM DISCREPANCIES There were a number of instances during 2014 in which inadvertent issues were encountered in the collection of environmental samples. All of these issues were minor in nature and did not have an adverse effect on the results or integrity of the monitoring program. Details of these various problems are given below.

During 2014, two offsite thermoluminescent dosimeters (TLD) were not recovered from their assigned locations during the quarterly retrieval process. Degradation of the plastic cages housing the TLDs resulted in the loss of the following TLDs: Valley Road - VR (Qtr 2); and Long Pond &

Drew Road - LD (Qtr 3). In each of these cases, the plastic cage holding the TLD were replaced and a new TLD posted. Despite these losses, the 438 TLDs that were collected (99.5%) allowed for adequate assessment of the ambient radiation levels in the vicinity of Pilgrim Station.

Of the 110 TLDs that had been posted during the 4 th Quarter of 2014, 51 were left in the field for an additional quarter due to limited access following January storms that interrupted the retrieval and exchange process. When these TLDs were ultimately retrieved in Apr-2015, the exposure results for the 6-month period monitored by the TLDs were reported for both the 4 th quarter 2014 and 1st quarter 2015 periods. Although all of the TLDs were retrieved and none were missing, this is reported as a discrepancy due to the departure from the normal quarterly posting period.

Within the air sampling program, there were a few instances in which continuous sampling was interrupted at the eleven airborne sampling locations during 2014. Most of these interruptions were due to short-term power losses and were sporadic and of limited duration (less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> out of the weekly sampling period). Such events did not have any significant impact on the scope and purpose of the sampling program, and lower limits of detection (LLDs) were met for both airborne particulates and iodine-131 on 571 of the 571 filters/cartridges collected.

Out of 572 filters (11 locations

• 52 weeks), 571 samples were collected and analyzed during 2014.

During the week between 03-Feb-2014 and 11-Feb-2014, frozen snow and ice prevented access to the sampling station at Manomet Substation (MS). The area did not become accessible until 21-Feb-2014. Although the station was inaccessible, the sampler never lost power and continued to run during the 428-hour period since the previous collection. Instead of collecting two filters during the period, one filter was in-service during the entire period, which reduced the total complement of filters collected from this location from the normal number of 52 down to 51. Again, it must be emphasized that the station continued to sample during the duration and no monitoring time was lost.

The configuration of air samplers that had been in use at Pilgrim Station since the early 1980s, was replaced between June and August of 2012. Both the pumps and dry gas meters were replaced, and operating experience since changing over to the new configuration has been favorable.

Although the occurrence of pump failures and gas meter problems have been largely eliminated, the new configuration is still subject to trips of the ground fault interrupt circuit (GFCI). Such problems can be encountered at air samplers located at the East Breakwater and Pedestrian Bridge. Both of these locations are immediately adjacent to the shoreline and are subject to significant wind-blown salt water, and are prone to tripping of the GFCI. The following table contains a listing of larger problems encountered with air sampling stations during 2014, many of which resulted in loss of more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> during the sampling period.

Page 83

Location Sampling Period Sampling Problem Description/Resolution Hours Lost MS 02/03 to 02/21 None Filter left on for 2-week period due to inaccessibility at 0.0 of 428.0 location of sampler; filters collected once accessible PB 02/11 to 02/20 40.4 of 216.1 Trip of GFCl outlet; reset GFCl CR 03/25 to 04/01 144.0 of 168.0 Trip of GFCI outlet; reset GFCI CR 04/01 to 04/08 None Flow meter seized; estimated flow from run time and 0.0 of 169.5 previous flow rate CR 07/01 to 07/08 79.5 of 167.4 Pump seized and blew fuse; replaced pump PB 11/18 to 11/25 105.4 of 168.2 Trip of GFCl outlet; reset GFCI and replaced pump Despite the lower-than-normal sampling volumes in the various instances involving power interruptions and equipment failures, required LLDs were met on 571 of the 571 particulate filters, and 571 of the 571 of the iodine cartridges collected during 2014. When viewed collectively during the entire year of 2014, the following sampling recoveries were achieved in the airborne sampling program:

Location Recovery Location Recovery Location Recovery WS 100.0% PB 98.2% PC 100.0%

ER 99.9% OA 99.9% IVMS 100.0%

WR 100.0% EB 99.9% EW 99.9%

PL 100.0% CR 97.4%

An alternate location had to be found for sampling control vegetable samples in the Bridgewater area. In past years, samples had been collected at the Bridgewater County Farm, associated with the Bridgewater Correctional Facility. Due to loss of state funding for garden projects during 2006, no garden was grown. An alternate location was found at the Hanson Farm in Bridgewater, located in the same compass sector, and at approximately the same distance as the Bridgewater County Farm. Additional samples of naturally-occurring vegetation were collected from distant control locations in Sandwich and Norton. As expected for control samples, vegetables and vegetation collected at these locations only contained naturally-occurring radioactivity (Be-7, K-40, and Ac/Th-228).

Some problems were encountered in collection of crop samples during 2014. Crops which had normally been sampled in the past (lettuce, tomatoes, potatoes, and onions) were not grown at the Plymouth County Farm (CF) during 2014. Leafy material from pumpkin plants and com plants were substituted for the lettuce to analyze for surface deposition of radioactivity on edible plants.

Samples of squash, tomatoes, cucumbers, zucchini, and grape leaves were also collected from two other locations in the immediate vicinity of Pilgrim Station. No radionuclides attributed to PNPS operations were detected in any of the edible crop samples collected during 2014.

Naturally-growing leafy vegetation (grass, leaves from trees and bushes, etc.) was collected near some gardens identified during the annual land use census. Due to the unavailability of crops grown in several of these gardens, these substitute samples were collected as near as practicable to the gardens of interest. No radionuclides attributed to PNPS operations were detected in any of the samples. Additional details regarding the land use census can be found in Appendix C of this report.

As presented in Table 2.9-1, several samples of naturally-occurring vegetation (leaves from trees, bushes, and herbaceous plants) were collected at a number of locations where the highest atmospheric deposition would be predicted to occur. Some of these samples indicated Cs-137 at concentrations ranging from non-detectable up to 133 pCi/kg. The highest concentration of 133 pCi/kg was detected in a sample of natural vegetation collected from the Pine Hills area of the Pine Hills south of PNPS. This Cs-1 37 result is within of the normal range of average values expected for Page 84

weapons-testing fallout (75 to 145 pCi/kg as projected from the pre-operational sampling program).

It should be noted that natural vegetation samples collected in the 1990s often showed detectable Cs-1 37 from nuclear weapons tests up into the range of 300 to 400 pCi/kg, whereas soil samples often indicated concentrations in excess of 2000 pCi/kg. Cs-137 has a 30-year half-life, and measureable concentrations still remain in soil and vegetation as a result of atmospheric nuclear weapons testing performed during the 1950s through 1970s. A review of effluent data presented in Appendix B indicates that there were no measurable airborne releases of Cs-137 from Pilgrim Station during 2014 that could have attributed to these detectable levels. The sample with the highest level of Cs-137 also contained high levels of AcTh-228, indicating appreciable soil content on the natural vegetation. This sample of natural vegetation was analyzed "as is" without any measure to clean the samples as normally would be performed prior to consuming vegetables, and would have detected any Cs-1 37 in soil adhering to those leaves collected. Certain species of plants such as sassafras are also known to concentrate chemical elements like cesium, and this higher-than-expected level is likely due to a combination of external soil contamination and bioconcentration in the leaves of the plants sampled. These levels are not believed to be indicative of any releases associated with Pilgrim Station. No radioactivity attributable to Pilgrim Station was detected in any of the vegetable samples collected during 2014, and results of any detectable naturally-occurring radioactivity were similar to those observed in the preoperational monitoring program.

The cranberry bog at the control location Pine Street Bog in Halifax was not in production during 2014, so a sample could not be obtained from this location. A substitute control sample was collected from a bog (Hollow Bog) in Kingston, beyond the influence of Pilgrim Station. In addition, the cranberry bog along Bartlett Road suspended operation during 2014, and was not producing cranberries. Samples were collected from a single indicator location located along Beaverdam Road.

Additional problems were encountered with composite water samples collected from the Discharge Canal. During the weeks of 14-Jan to 21-Jan-2014, and 20-Feb-2014 to 26-Feb-2014, cold weather caused an ice blockage in the hose feeding water from the submersible pump in the Discharge Canal up to the sampling lab at the Pedestrian Bridge. Therefore, water flow to the sampler was interrupted for an unknown portion during each of these weekly sampling periods. No radioactive liquid discharges were occurring during either of these two periods.

Samples of blue mussels are normally collected twice each year in the spring and in the autumn from the vicinity of the Discharge Canal Outfall. Due to water scouring action from winter storms, no mussel samples were available for collection in the area during the April to June sampling period.

Repeated and concerted efforts were made to collect these species, but failed to produce any samples.

Group I fishes, consisting of winter flounder or yellow-tail flounder are normally collected twice each year in the spring and in the autumn from the vicinity of the Discharge Canal Outfall. When fish sampling occurred in the September to November collection period, no samples of Group I fish could be collected, as the species had already moved to deeper water for the upcoming winter. Repeated and concerted efforts were made to collect these species, but failed to produce any samples.

Group II fishes, consisting of tautog, cunner, cod, pollock, or hake are normally collected once each year in the summer from the vicinity of the Discharge Canal Outfall. Recent declines in populations of these species in the rock breakwater outboard of Pilgrim Station resulted in no sample being collected during 2014. Repeated and concerted efforts were made to collect these species, but failed to produce any samples.

Although a sample of Group III fishes (striped bass) was collected from the Discharge Canal Outfall during the summer sampling season, no sample of Group III fishes was collected from a control location during the year. This was due to fishing restrictions, low numbers of target species, and Page 85

seasonal unavailability. Repeated and concerted efforts to catch the desired species failed to produce any samples for the control location.

In summary, the various problems encountered in collecting and analyzing environmental samples during 2014 were relatively minor when viewed in the context of the entire monitoring program.

These discrepancies were promptly corrected when issue was identified. None of the discrepancies resulted in an adverse impact on the overall monitoring program.

Page 86

APPENDIX E ENVIRONMENTAL DOSIMETRY COMPANY Annual Quality Assurance Status Report January - December 2014

ENVIRONMENTAL DOSIMETRY COMPANY ANNUAL QUALITY ASSURANCE STATUS REPORT January - December 2014 Prepared By: Date: d k Z (-j K 1' Approved By:

IC--- Date: s-Environmental Dosimetry Company 10 Ashton Lane Sterling, MA 01564

TABLE OF CONTENTS Paqe LIS T O F TA B LE S ....................................................................................................................... iii EXECUTIVE

SUMMARY

............................................................................................................ iv I. INTRODUCTION .................................................................................................... 1 A. QC Program ................................................................................................... 1 B. Q A P ro g ra m ........................................................................................................ 1 Ii. PERFORMANCE EVALUATION CRITERIA ............................................................... 1 A. Acceptance Criteria for Internal Evaluations ..................................................... 1 B. QC Investigation Criteria and Result Reporting .............................................. 3 C. Reporting of Environmental Dosimetry Results to EDC Customers ................. 3 Ill. DATA

SUMMARY

FOR ISSUANCE PERIOD JANUARY-DECEMBER 2014 ............. 3 A. General Discussion ......................................................................................... 3 B. Result Trending .............................................................................................. 4 IV. STATUS OF EDC CONDITION REPORTS (CR) ...................................................... 4 V. STATUS OF AUDITS/ASSESSMENTS ..................................................................... 4 A. In te rn a l................................................................................................................ 4 B. External ...................................................................................................... 4 VI. PROCEDURES AND MANUALS REVISED DURING JANUARY - DECEMBER 2014... 4 VII. CONCLUSION AND RECOMMENDATIONS ............................................................ 4 V III. R E F E R E NC E S ............................................................................................................... 4 APPENDIX A DOSIMETRY QUALITY CONTROL TRENDING GRAPHS

-ii-

LIST OF TABLES Pawe

1. Percentage of Individual Analyses Which Passed EDC Internal Criteria, January - December 2014 5

2. Mean Dosimeter Analyses (n=6), January - December 2014 5

3. Summary of Independent QC Results for 2014 5

-iii-

EXECUTIVE

SUMMARY

Routine quality control (QC) testing was performed for dosimeters issued by the Environmental Dosimetry Company (EDC).

During this annual period, 100% (72/72) of the individual dosimeters, evaluated against the EDC internal performance acceptance criteria (high-energy photons only), met the criterion for accuracy and 100% (72/72) met the criterion for precision (Table 1). In addition, 100% (12/12) of the dosimeter sets evaluated against the internal tolerance limits met EDC acceptance criteria (Table 2) and 100% (6/6) of independent testing passed the performance criteria (Table 3). Trending graphs, which evaluate performance statistic for high-energy photon irradiations and co-located stations are given in Appendix A.

Two assessments were performed in 2014, one internal and one external. There were no findings.

-iv-

I. INTRODUCTION The TLD systems at the Environmental Dosimetry Company (EDC) are calibrated and operated to ensure consistent and accurate evaluation of TLDs. The quality of the dosimetric results reported to EDC clients is ensured by in-house performance testing and independent performance testing by EDC clients, and both internal and client directed program assessments.

The purpose of the dosimetry quality assurance program is to provide performance documentation of the routine processing of EDC dosimeters. Performance testing provides a statistical measure of the bias and precision of dosimetry processing against a reliable standard, which in turn points out any trends or performance changes. Two programs are used:

A. QC Program Dosimetry quality control tests are performed on EDC Panasonic 814 Environmental dosimeters. These tests include: (1) the in-house testing program coordinated by the EDC QA Officer and (2) independent test perform by EDC clients. In-house test are performed using six pairs of 814 dosimeters, a pair is reported as an individual result and six pairs are reported as the mean result.

Results of these tests are described in this report.

Excluded from this report are instrumentation checks. Although instrumentation checks represent an important aspect of the quality assurance program, they are not included as process checks in this report. Instrumentation checks represent between 5-10% of the TLDs processed.

B. QA Program An internal assessment of dosimetry activities is conducted annually by the Quality Assurance Officer (Reference 1). The purpose of the assessment is to review procedures, results, materials or components to identify opportunities to improve or enhance processes and/or services.

II. PERFORMANCE EVALUATION CRITERIA A. Acceptance Criteria for Internal Evaluations

1. Bias For each dosimeter tested, the measure of bias is the percent deviation of the reported result relative to the delivered exposure. The percent deviation relative to the delivered exposure is calculated as follows:

i 100 Hi where:

H' = the corresponding reported exposure for the ith

-dosimeter (i.e., the reported exposure)

H= the exposure delivered to the ith irradiated dosimeter (i.e., the delivered exposure) 1 of 6

2. Mean Bias For each group of test dosimeters, the mean bias is the average percent deviation of the reported result relative to the delivered exposure. The mean percent deviation relative to the delivered exposure is calculated as follows:

where:

H' = the corresponding reported exposure for the ith dosimeter (i.e., the reported exposure)

Hi = the exposure delivered to the ith irradiated test dosimeter (i.e., the delivered exposure) n = the number of dosimeters in the test group

3. Precision For a group of test dosimeters irradiated to a given exposure, the measure of precision is the percent deviation of individual results relative to the mean reported exposure. At least two values are required for the determination of precision. The measure of precision for the ith dosimeter is:

where:

Hi = the reported exposure for the ith dosimeter (i.e., the reported exposure)

H the mean reported exposure; i.e., H=- I n = the number of dosimeters in the test group

4. EDC Internal Tolerance Limits All evaluation criteria are taken from the "EDC Quality System Manual,"

(Reference 2). These criteria are only applied to individual test dosimeters irradiated with high-energy photons (Cs-137) and are as follows for Panasonic Environmental dosimeters: +/- 15% for bias and +/-

12.8% for precision.

2 of 6

B. QC Investigation Criteria and Result Reporting EDC Quality System Manual (Reference 2) specifies when an investigation is required due to a QC analysis that has failed the EDC bias criteria. The criteria are as follows:

1. No investigation is necessary when an individual QC result falls outside the QC performance criteria for accuracy.

2. Investigations are initiated when the mean of a QC processing batch is outside the performance criterion for bias.

C. Reporting of Environmental Dosimetry Results to EDC Customers

1. All results are to be reported in a timely fashion.

2. If the QA Officer determines that an investigation is required for a process, the results shall be issued as normal. If the QC results, prompting the investigation, have a mean bias from the known of greater than +/-20%, the results shall be issued with a note indicating that they may be updated in the future, pending resolution of a QA issue.

3. Environmental dosimetry results do not require updating if the investigation has shown that the mean bias between the original results and the corrected results, based on applicable correction factors from the investigation, does not exceed +/-20%.

Ill. DATA

SUMMARY

FOR ISSUANCE PERIOD JANUARY-DECEMBER 2014 A. General Discussion Results of performance tests conducted are summarized and discussed in the following sections. Summaries of the performance tests for the reporting period are given in Tables 1 through 3 and Figures 1 through 4.

Table 1 provides a summary of individual dosimeter results evaluated against the EDC internal acceptance criteria for high-energy photons only. During this period, 100% (72/72) of the individual dosimeters, evaluated against these criteria met the tolerance limits for accuracy and 100% (72/72) met the criterion for precision.

A graphical interpretation is provided in Figures 1 and 2.

Table 2 provides the Bias + Standard deviation results for each group (N=6) of dosimeters evaluated against the internal tolerance criteria. Overall,100%

(12/12) of the dosimeter sets evaluated against the internal tolerance performance criteria met these criteria. A graphical interpretation is provided in Figures 3 Table 3 presents the independent blind spike results for dosimeters processed during this annual period. All results passed the performance acceptance criterion. Figure 4 is a graphical interpretation of Seabrook Station blind co-located station results.

3 of 6

B. Result Trending One of the main benefits of performing quality control tests on a routine basis is to identify trends or performance changes. The results of the Panasonic environmental dosimeter performance tests are presented in Appendix A. The results are evaluated against each of the performance criteria listed in Section II, namely: individual dosimeter accuracy, individual dosimeter precision, and mean bias.

All of the results presented in Appendix A are plotted sequentially by processing date.

IV. STATUS OF EDC CONDITION REPORTS (CR)

No condition reports were issued during this annual period.

V. STATUS OF AUDITS/ASSESSMENTS A. Internal EDC Internal Quality Assurance Assessment was conducted during the fourth quarter 2014. There were no findings identified.

B. External The FPL/NextEra Energy Nuclear Oversight Audit SBK-14-019 was conducted on September 24, 2014. There were no findings identified.

VI. PROCEDURES AND MANUALS REVISED DURING JANUARY - DECEMBER 2014 No procedures or manuals were revised in 2014.

VII. CONCLUSION AND RECOMMENDATIONS The quality control evaluations continue to indicate the dosimetry processing programs at the EDC satisfy the criteria specified in the Quality System Manual. The EDC demonstrated the ability to meet all applicable acceptance criteria.

VIII. REFERENCES

1. EDC Quality Control and Audit Assessment Schedule, 2014.

2. EDC Manual 1, Quality System Manual, Rev. 3, August 1, 2012.

4 of 6

TABLE I PERCENTAGE OF INDIVIDUAL DOSIMETERS THAT PASSED EDC INTERNAL CRITERIA JANUARY - DECEMBER 2014(1)' (2)

(1)This table summarizes results of tests conducted by EDC.

(2)Environmental dosimeter results are free in air.

TABLE 2 MEAN DOSIMETER ANALYSES (N=6)

JANUARY - DECEMBER 2014(1)' (2) 4 2.7 1.6 Pass Pass 4/22/2014 4/22/2014 4

-0.1

-0.1

4. 0.9 0.9 1

Pass 4/30/2014 4 0.1 4.

1.9 I Pass 7/22/2014 1.7 1.5 Pass 7/25/2014 2.8 1.2 Pass 8/04/2014 -3.6 1.0 Pass 9/24/2014 2.5 0.6 Pass 10/21/2014 0.7 0.5 Pass 10/28/2014 3.9 1.5 Pass 1/25/2015 4.1 1 1.1 Pass 1/28/2015 2.1 1.6 Pass 3/11/2015 -8.2 1.0 Pass (1)This table summarizes results of tests conducted by EDC for TLDs issued in 2014.

(2)Environmental dosimeter results are free in air.

TABLE 3

SUMMARY

OF INDEPENDENT DOSIMETER TESTING JANUARY - DECEMBER 2014(1)' (2) 1"- Qtr. 4 Millstone 2.8 3.2 Pass 2 nd Qtr. Millstone -6.0 4.5 Pass

4. Sea brook Millstone 4 -6.0 4 4.5 4. Pass 2nd Qtr. 44 Seabrook 0.3 1.6 Pass 3V Qtr. 2014 Millstone -10.2 3.6 Pass 4th Qtr.2014 Millstone -6.5 2.9 Pass 4 th Qtr.2014 Seabrook 5.5 1.7 Pass

( 1)Performance criteria are +/- 30%.

(2)Blind spike irradiations using Cs-137 5 of 6

APPENDIX A DOSIMETRY QUALITY CONTROL TRENDING GRAPHS ISSUE PERIOD JANAURY - DECEMBER 2014 6 of 6

INDIVIDUAL ACCURACY ENVIRONMENTAL FIGURE 1 16-12-10-8.

6-4-0 42 00 000

• 0**6 0- T16 00 0 2 S .0 0

00 0

0 0

-6 S

se S

-10 S

-12.

-14jl

-16 - T T- - -- - T ---

QOSI DATE "N N 4 ev IN PROCESSING DATE

INDIVIDUAL PRECISION ENVIRONMENTAL FIGURE 2 16-14-12-10-8-

6-4-

o 0 z 2- *o 0 0 tamnjt = fl-a

o. a 0es ~

• 9 0 '9 0

0 O0*

-- - p - -- a -

- 0 -* *0 0, *-- OO a- & 0 wA 0 0* 0*

Lu 0 0 1

x --41I C-LCL - 800

.r,r NF /-,

N N 4'ý IN -- U-- N Nv N

'V 'V NN (Ný 4'V PROCESSING DATE

MEAN ACCURACY ENVIRONMENTAL FIGURE 3 if-144JV-- - - -------------------------------------------------

12-10-8-

6-4- 0 a 0 0 2- 0 a Co flIT;npt = 0

- - 0 40 lo, Vl \ N N N N

-[ .;  ;  :¸ * .. ...

• V. V "IV A' PROCESSING DATE

SEABROOK CO-LOCATE ACCURACY FIGURE 4 22-20-18-16-0 14- 0 12-10-0

8. 0 0 0a 1 0 6-

4.

• 0 a 0 0

2 Tarelet = 0 0 0

-2. 0 a 0 C', S a

-4.

0 0 0 0

-6 0 0

-8 0 0

-16].. .

-18] . . . . ..

-22. --------------------------------------

1\ Cb 0 10 A~ C N0N Itl "b NZ NW NW Nw N11 NýW N11 N01 NIV AVI EXPECTED FIELD EXPOSURE (mR/STD. QUARTER)

APPENDIX F GEL Laboratories LLC 2014 ANNUAL QUALITY ASSURANCE REPORT FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

LLaboratories LLC 2014 ANNUAL QUALITY ASSURANCE REPORT FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

GEL LABORATORIES, LLC P.O. Box 30712, Charleston, SC 29417 843.556.8171

M I Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 2 of 64 2014 ANNUAL QUALITY ASSURANCE REPORT FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

ADDroved BV: February 15, 2015 Rev. 1 Robert L. Pullano Date Director, Quality Systems

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 3 of 64 TABLE OF CONTENTS

1. INT R O DUC T ION ..................................................................................................................... 5

2. QUALITY ASSURANCE PROGRAMS FOR INTER-LABORATORY, INTRA-LABORATORY AND THIRD PARTY CROSS-CHECK ....................................................................................... 6

3. QUALITY ASSURANCE PROGRAM FOR INTERNAL AND EXTERNAL AUDITS ........ 7

4. PERFORMANCE EVALUATION ACCEPTANCE CRITERIA FOR ENVIRONMENTAL SAMPLE A NA LYS IS ............................................................................................................................... 8

5. PERFORMANCE EVALUATION SAMPLES ...................................................................... 8

6. QUALITY CONTROL PROGRAM FOR ENVIRONMENTAL SAMPLE ANALYSIS ........ 8

7. SUM MARY OF DATA RESULTS ...................................................................................... 9

8.

SUMMARY

OF PARTICIPATION IN THE ECKERT & ZIEGLER ANALYTICS ENVIRONMENTAL C RO SS-CHECK PRO G RAM ............................................................................................... 9

9.

SUMMARY

OF PARTICIPATION IN THE MAPEP MONITORING PROGRAM ............... 10

10.

SUMMARY

OF PARTICIPATION IN THE ERA MRAD PT PROGRAM ......................... 10

11.

SUMMARY

OF PARTICIPATION IN THE ERA PT PROGRAM ..................................... 10

12. CORRECTIVE ACTION REQUEST AND REPORT (CARR) .......................................... 10 13 . R EF ER ENC ES .................................................................................................................... 12

MLaboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 4 of 64 TABLE OF CONTENTS (CONTINUED)

TABLES Table 1 2014 Radiological Proficiency Testing Results and Acceptance Criteria ................. 13 Table 2 2014 Eckert & Ziegler Analytics Performance Evaluation Results .......................... 29 Table 3 2014 Department of Energy Mixed Analyte Performance Evaluation Program (MAPEP)

R e su lts ........................................................................................................ . . 31 Table 4 2014 ERA Program Performance Evaluation Results ............................................ 36 Table 5 2014 ERA Program (MRAD) Performance Evaluation Results .............................. 38 Table 6 REMP Intra-Laboratory Data Summary: Bias and Precision By Matrix ................. 53 Table 7 All Radiological Intra-Laboratory Data Summary: Bias and Precision By Matrix ................................................................................................ . . . 5 5 Table 8 2014 Corrective Action Report Summary ...................................................... 62 FIGURES Figure 1 Cobalt-60 Performance Evaluation Results and % Bias ....................................... 44 Figure 2 Cesium-1 37 Performance Evaluation Results and % Bias .................................... 45 Figure 3 Tritium Performance Evaluation Results and % Bias ............................................ 46 Figure 4 Strontium-90 Performance Evaluation Results and % Bias .................................. 47 Figure 5 Gross Alpha Performance Evaluation Results and % Bias .................................... 48 Figure 6 Gross Beta Performance Evaluation Results and % Bias ..................................... 49 Figure 7 Iodine-131 Performance Evaluation Results and % Bias ....................................... 50 Figure 8 Americium-241 Performance Evaluation Results and % Bias ................................ 51 Figure 9 Plutonium-238 Performance Evaluation Results and % Bias ................................ 52

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 5 of 64 2014 ANNUAL QUALITY ASSURANCE REPORT FOR THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM (REMP)

1. Introduction GEL Laboratories, LLC (GEL) is a privately owned environmental laboratory dedicated to providing personalized client services of the highest quality. GEL was established as an analytical testing laboratory in 1981. Now a full service lab, our analytical divisions use state of the art equipment and methods to provide a comprehensive array of organic, inorganic, and radiochemical analyses to meet the needs of our clients.

At GEL, quality is emphasized at every level of personnel throughout the company. Management's ongoing commitment to good professional practice and to the quality of our testing services to our customers is demonstrated by their dedication of personnel and resources to develop, implement, assess, and improve our technical and management operations.

The purpose of GEL's quality assurance program is to establish policies, procedures, and processes to meet or exceed the expectations of our clients. To achieve this, all personnel that support these services to our clients are introduced to the program and policies during their initial orientation, and annually thereafter during company-wide training sessions.

GEL's primary goals are to ensure that all measurement data generated are scientifically and legally defensible, of known and acceptable quality per the data quality objectives (DQOs), and thoroughly documented to provide sound support for environmental decisions. In addition, GEL continues to ensure compliance with all contractual requirements, environmental standards, and regulations established by local, state and federal authorities.

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

This report entails the quality assurance program for the proficiency testing and environmental monitoring aspects of GEL for 2014. GEL's QA Program is designed to monitor the quality of analytical processing associated with environmental, radiobioassay, effluent (10 CFR Part 50), and waste (10 CFR Part 61) sample analysis.

This report covers the category of Radiological Environmental Monitoring Program (REMP) and includes:

" Intra-laboratory QC results analyzed during 2014.

• Inter-laboratory QC results analyzed during 2014 where known values were available.

ILaboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 6 of 64

2. Quality Assurance Programs for Inter-laboratory, Intra-laboratory and Third Party Cross-Check In addition to internal and client audits, our laboratory participates in annual performance evaluation studies conducted by independent providers. We routinely participate in the following types of performance audits:

• Proficiency testing and other inter-laboratory comparisons

" Performance requirements necessary to retain Certifications

• Evaluation of recoveries of certified reference and in-house secondary reference materials using statistical process control data.

" Evaluation of relative percent difference between measurements through SPC data.

We also participate in a number of proficiency testing programs for federal and state agencies and as required by contracts. It is our policy that no proficiency evaluation samples be analyzed in any special manner. Our annual performance evaluation participation generally includes a combination of studies that support the following:

• US Environmental Protection Agency Discharge Monitoring Report, Quality Assurance Program (DMR-QA). Annual national program sponsored by EPA for laboratories engaged in the analysis of samples associated with the NPDES monitoring program. Participation is mandatory for all holders of NPDES permits. The permit holder must analyze for all of the parameters listed on the discharge permit. Parameters include general chemistry, metals, BOD/COD, oil and grease, ammonia, nitrates, etc.

" Department of Energy Mixed Analyte Performance Evaluation Program (MAPEP). A semiannual program developed by DOE in support of DOE contractors performing waste analyses.

Participation is required for all laboratories that perform environmental analytical measurements in support of environmental management activities. This program includes radioactive isotopes in water, soil, vegetation and air filters.

• ERA's MRAD-Multimedia Radiochemistry Proficiency test program. This program is for labs seeking certification for radionuclides in wastewater and solid waste. The program is conducted in strict compliance with USEPA National Standards for Water Proficiency study.

• ERA's InterLaB RadCheM Proficiency Testing Program for radiological analyses. This program completes the process of replacing the USEPA EMSL-LV Nuclear Radiation Assessment Division program discontinued in 1998. Laboratories seeking certification for radionuclide analysis in drinking water also use the study. This program is conducted in strict compliance with the USEPA National Standards for Water Proficiency Testing Studies. This program encompasses Uranium by EPA method 200.8 (for drinking water certification in Utah/Primary NELAP), gamma emitters, Gross Alpha/Beta, Iodine-131, naturally occurring radioactive isotopes, Strontium-89/90, and Tritium.

" ERA's Water Pollution (WP) biannual program for waste methodologies includes parameters for both organic and inorganic analytes.

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 7 of 64

• ERA's Water Supply (WS) biannual program for drinking water methodologies includes parameters for organic and inorganic analytes.

• Environmental Cross-Check Program administered by Eckert & Ziegler Analytics, Inc. This program encompasses radionuclides in water, soil, milk, naturally occurring radioactive isotopes in soil and air filters.

GEL procures single-blind performance evaluation samples from Eckert & Ziegler Analytics to verify the analysis of sample matrices processed at GEL. Samples are received on a quarterly basis. GEL's Third-Party Cross-Check Program provides environmental matrices encountered in a typical nuclear utility REMP. The Third-Party Cross-Check Program is intended to meet or exceed the inter-laboratory comparison program requirements discussed in NRC Regulatory Guide 4.15. Once performance evaluation samples have been prepared in accordance with the instructions provided by the PT provider, samples are managed and analyzed in the same manner as environmental samples from GEL's clients.

3. 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.

ILaboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 8 of 64

4. Performance Evaluation Acceptance Criteria for Environmental Sample Analysis GEL utilized an acceptance protocol based upon two performance models. For those inter-laboratory programs that already have established performance criteria for bias (i.e., MAPEP, and ERA/ELAP),

GEL will utilize the criteria for the specific program. For intra-laboratory or third party quality control programs that do not have a specific acceptance criteria (i.e. the Eckert-Ziegler Analytics Environmental Cross-check Program), results will be evaluated in accordance with GEL's internal acceptance criteria.

5. Performance Evaluation Samples Performance Evaluation (PE) results and internal quality control sample results are evaluated in accordance with GEL acceptance criteria. The first criterion concerns bias, which is defined as the deviation of any one result from the known value. The second criterion concerns precision, which deals with the ability of the measurement to be replicated by comparison of an individual result with the mean of all results for a given sample set.

At GEL, we also evaluate our analytical performance on a regular basis through statistical process control (SPC) acceptance criteria. Where feasible, this criterion is applied to both measures of precision and accuracy and is specific to sample matrix. We establish environmental process control limits at least annually.

For Radiochemistry analysis, quality control evaluation is based on static limits rather than those that are statistically derived. Our current process control limits are maintained in GEL's AlphaLIMS. We also measure precision with matrix duplicates and/or matrix spike duplicates. The upper and lower control limits (UCL and LCL respectively) for precision are plus or minus three times the standard deviation from the mean of a series of relative percent differences. The static precision criteria for radiochemical analyses are 0 - 20%, for activity levels exceeding the contract required detection limit (CRDL).

6. Quality Control Program for Environmental Sample Analysis GEL's internal QA Program is designed to include QC functions such as instrumentation calibration checks (to insure proper instrument response), blank samples, instrumentation backgrounds, duplicates, as well as overall staff qualification analyses and statistical process controls. Both quality control and qualification analyses samples are used to be as similar as the matrix type of those samples submitted for analysis by the various laboratory clients. These performance test samples (or performance evaluation samples) are either actual sample submitted in duplicate in order to evaluate the precision of laboratory measurements, or fortified blank samples, which have been given a known quantity of a radioisotope that is in the interest to GEL's clients.

Accuracy (or Bias) is measured through laboratory control samples and/or matrix spikes, as well as surrogates and internal standards. The UCLs and LCLs for accuracy are plus or minus three times the standard deviation from the mean of a series of recoveries. The static limit for radiochemical analyses is 75 - 125%. Specific instructions for out-of-control situations are provided in the applicable analytical SOP.

GEL's Laboratory Control Standard (LCS) is an aliquot of reagent water or other blank matrix to which known quantities of the method analytes are added in the laboratory. The LCS is analyzed exactly like a sample, and its purpose is to determine whether the methodology is in control, and whether the laboratory is capable of making accurate and precise measurements. Some methods may refer to these

MLaboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 9 of 64 samples as Laboratory Fortified Blanks (LFB). The requirement for recovery is between 75 and 125%

for radiological analyses excluding drinking water matrix.

Bias (%) = (observed concentration)

• 100 %

(known concentration)

Precision is a data quality indicator of the agreement between measurements of the same property, obtained under similar conditions, and how well they conform to themselves. Precision is usually expressed as standard deviation, variance or range in either absolute or relative (percentage) terms.

GEL's laboratory duplicate (DUP or LCSD) is an aliquot of a sample taken from the same container and processed in the same manner under identical laboratory conditions. The aliquot is analyzed independently from the parent sample and the results are compared to measure precision and accuracy.

If a sample duplicate is analyzed, it will be reported as Relative Percent Difference (RPD). The RPD must be 20 percent or less, if both samples are greater than 5 times the MDC. If both results are less than 5 times MDC, then the RPD must be equal to or less than 100%. If one result is above the MDC and the other is below the MDC, then the RPD can be calculated using the MDC for the result of the one below the MDC. The RPD must be 100% or less. In the situation where both results are above the MDC but one result is greater than 5 times the MDC and the other is less than 5 times the MDC, the RPD must be less than or equal to 20%. If both results are below MDC, then the limits on % RPD are not applicable.

Difference (%) = (high duplicate result - low duplicate result)

• 100 %

(average of results)

7. Summary of Data Results During 2013, forty-four (44) radioisotopes associated with seven (7) 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 Graphs are provided in Figures 1-9 of this report to allow for the evaluation of trends or biases. These graphs include radioisotopes Cobalt-60, Cesium-137, Tritium, Strontium-90, Gross Alpha, Gross Beta, Iodine-131, Americium-241, and Plutonium-238.

8. Summary of Participation in the Eckert & Ziegler Analytics Environmental Cross-Check Program

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 10 of 64 Eckert & Ziegler Analytics provided samples for sixty-nine (69) 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%).

9. Summary of Participation in the MAPEP Monitoring Program MAPEP Series 30 and 31 were analyzed by the laboratory. Of the one hundred thirty-eight (138) analyses, 97.8% (135 out of 138) of all results fell within the PT provider's acceptance criteria. Three analytical failures occurred: Uranium-234/233 and Uranium-238 in Soil and Uranium-238 in vegetation.

For the corrective actions associated with MAPEP Series 30, refer to CARR 140605-879 which is detailed in Table 8.

10. Summary of Participation in the ERA MRaD PT Program The ERA MRad program provided samples (MRAD-20 and MRAD-21) for one hundred eighty-eight (188) individual environmental analyses. One hundred eighty-seven (187) of the 188 analyses fell within the PT provider's acceptance criteria (99.4%). One analytical failure occurred: Americium-241 in water.

For the corrective actions associated with MRAD-20, refer to CARR140520-874 which are detailed in Table 8.

11. Summary of Participation in the ERA PT Program The ERA program provided samples (RAD-96, RAD-98, and 01 1014L) for fifty (50) individual environmental analyses. Of the 50 analyses, 96.0% (48 out of 50) of all results fell within the PT provider's acceptance criteria. One isotope failure occurred: Strontium-89 in water.

For the corrective actions associated with RAD-98 refer to corrective actions CARR140825-902 (Table 8).

12. 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.

N Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 11 of 64 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.

Table 8 provides the status of CARRs for radiological performance testing during 2014. It has been determined that causes of the failures did not impact any data reported to our clients.

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 12 of 64

13. References

1. GEL Quality Assurance Plan, GL-QS-B-001

2. GEL Standard Operating Procedure for the Conduct of Quality Audits, GL-QS-E-001

3. GEL Standard Operating Procedure for Conducting Corrective/Preventive Action and Identifying Opportunities for Improvement, GL-QS-E-002

4. GEL Standard Operating Procedure for AlphaLIMS Documentation of Nonconformance Reporting and Dispositioning and Control of Nonconforming Items, GL-QS-E-004

5. GEL Standard Operating Procedure for Handling Proficiency Evaluation Samples, GL-QS-E-01 3

6. GEL Standard Operating Procedure for Quality Assurance Measurement Calculations and Processes, GL-QS-E-014

7. 40 CFR Part 136 Guidelines Establishing Test Procedures for the Analysis of Pollutants

8. ISO/IEC 17025-2005, General Requirements for the Competence of Testing and Calibration Laboratories

9. ANSI/ASQC E4-1994, Specifications and Guidelines for Quality Systems for Environmental Data Collection and Environmental Technology Programs, American National Standard

10. 2003 NELAC Standard, National Environmental Laboratory Accreditation Program

11. 2009 TNI Standard, The NELAC Institute, National Environmental Accreditation Program

12. MARLAP, Multi-Agency Radiological Laboratory Analytical Protocols

13. 10 CFR Part 21, Reporting of Defects and Noncompliance

14. 10 CFR Part 50 Appendix B, Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants

15. 10 CFR Part 61, Licensing Requirements for Land Disposal and Radioactive Waste

16. NRC REG Guide 4.15 and NRC REG Guide 4.8

Ee Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 13 of 64 TABLE 1 2014 RADIOLOGICAL PROFICIENCY TESTING RESULTS AND ACCEPTANCE CRITERIA I ERA 2014 1 02/24/14 96 Water pCi/L I Barium-133 I 80.6 76.2 63.8-83.8 I Acceptable 1st/ RAD-ERA 2014 02/24/14 96 Water pCVL Cesium-134 64.7 66.8 54.4-73.5 Acceptable 1st/ RAD-ERA 2014 02/24/14 96 Water pCi/L Cesium-137 112.0 109 98.1-122 Acceptable 1st/ RAD-ERA 2014 02/24/14 96 Water pCi/L Cobalt-60 95.0 88.7 79.8-99.9 Acceptable 1st/ RAD-ERA 2014 02/24/14 96 Water pCVL Zinc-65 200 185 166-218 Acceptable 1st/ RAD-ERA 2014 02/24/14 96 Water pCVL Gross Alpha 34.8 36.1 18.6-46.4 Acceptable 1st / RAD-ERA 2014 02/24/14 96 Water pCVL Gross Beta 19.6 22.3 13.5-30.4 table 1st / RAD-ERA 2014 02/24/14 96 Water pCVL Gross Alpha 34.6 36.1 18.6-46.4 Acceptable 1st / RAD-ERA 2014 02/24/14 96 Water pCi/L Radium-226 16.2 16.8 12.5-19.2 Acceptable 1st / RAD -

ERA 2014 02/24/14 96 Water pCi/L Radium-228 4.62 5.04 3.01-6.67 Acceptable 1st / RAD - Uranium ERA 2014 02/24/14 96 Water pCi/L (Nat) 7.39 7.23 5.51-8.53 Acceptable 1st / RAD - Uranium ERA 2014 02/24/14 96 Water ug/L (Nat) mass 11.00 10.6 8.07-12.5 Acceptable 1st / RAD -

ERA 2014 02/24/14 96 Water pCVL Radium-226 15.10 16.8 12.5-19.2 Acceptable 1st/ RAD -

ERA 2014 02/24/14 96 Water pCi/L Radium-228 4.66 5.04 3.01-6.67 Acceptable 1st / RAD - Uranium ERA 2014 02/24114 96 Water pCi/L (Nat) 7.47 7.23 5.51-8.53 Acceptable 1st / RAD - Uranium ERA 2014 02/24/14 96 Water ug/L (Nat) mass 11.4 10.6 8.07-12.5 Acceptable lst / RAD -

ERA 2014 02/24/14 96 Water pCi/L Tritium 3320 3580 3030-3950 1st / RAD - Strontium-ERA 2014 02/24/14 96 Water pCi/L 89 44.1 44.4 34.4-51.6 Acceptable 1st / RAD - Strontium-ERA 2014 02/24/14 96 Water pCi/L 90 34.2 30.3 22.1-35.2 Acceptable 1st: / RAD - Strontium-ERA 2014 02/24/14 96 Water pCi/L 89 38.9 44.4 34.4-51.6 1st / RAD - Strontium-ERA 2014 02/24/14 96 Water pCi/L 90 27.1 30.3 22.1-35.2 Acceptable 1st / Strontium-ERA 2014 02/06/14 011014L Water pCVL 89 42.3 38.7 29.3-45.7 Acceptable 1st / Strontium-ERA 2014 02/06/14 011014L Water pCi/L 89 42.2 38.7 29.3-45.7 lst / RAD -

ERA 2014 02/24/14 96 Water pCi/L Iodine-1 31 25.2 24.4 20.2-28.9 Acceptable 1st / RAD -

ERA 2014 02/24/14 96 Water pCi/L Iodine-1 31 22.4 24.4 20.2-28.9 Acceptable EZA 1lst/2014 05/16/14 E10846 Cartridge pCi lodine-131 7.83E+01 7.50E+03 1.04 Acceptable Strontium-EZA lst/2014 05/16/14 E10847 Milk pCiL 89 9.14E+01 9.17E+01 1 Acceptable Strontium-EZA 1st/2014 05/16/14 E10847 Milk pCVL 90 1.27E+01 1.51E+01 0.84 Acceptable

I Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 14 of 64 1 St/Mu 1 K 1 1 Acceptable A

lst/2014 05/16114 E10848 K L Iodine- i Cerium-141 21.21E+02 19 94E+01 "* I I

1.02 1 Acceotable I T A 1lst/201405/16/14 E10848 pCi/L Cr-51 I 5.19E+02 4.91 E+02 1.06 I Acceotable A 1st/201 4 05/16/14 E10848 I PCiL I Cesium-134 I 1.79E+022 102 0.85 1Acce table A lst/2014 05/16/14 E10848 pCi/L Cesium-137 2.55E+02 2.53E+02 1.01 Acceptable a__ _ 1st/2014 05/16/14 E10848 R pCi/L Cobalt-58 2.58E+02 2.68E+02 0.96 Acceptable lst/2014 05/16/14 I E10848 Uilk~

Milk nfli/I rul P.An.3A K)ln-rA I ':AINI::.*..fl Ani r-+n,)

I OQ7*A' 1- 07C:+nl)- 4 Al i ni I

A #ýkl e 1st/201 4 lst/2014 lst/2014 05/16/14 05/16/14 05/16/14 E10848 E10848 E10848 Milk Milk Milk j

II...... I2.24E.

oCi/L CiL pCi/L Iron-59 Zinc-65 Cobalt-60 I lodine-131

..I2.19E.

I 2.24E+02 I 2.19E+02 3.45E+02 3.23E+02 3.39E+02 3.37E+02

.. 1... 1Acce 1 02 1.07 1.00

...tabl I Accr'.nt~ihle Acceptable Acceptable lst/2014 I 05/16/14 I E10849 Water t

pCi/L I4 9.24E+01 1I 8.99E+01 1-1.03 I4 Acceotable A lst/2014 1 05/16/14 I E10849 Water DCi/L I Cerium-141 I 8.19E+01 I 7.71E+01 1.06 I Acceotable j

A lst/2014 05/16/14 E10849 Water ;CVL Cr-51 3.32E+02 1 3.19E+02 1.04 lst/2014 1 05/16/14 I E10849 Water DCJ/L Cesium-134 I 1.27E+02 I 1i36E+02 0.93 r

EZA I lst/2014 1 05/16/14 I E10849 1

Water 1 ~4 4 oCVL I Cesium-137 I i.69E+02 I i64E+02 4 4 093 1.03 Ar'ce.ntablA EZA lst/2014 05/16/14 E10849 Water pCi/L Cobalt-58 1.75E+02 1.74E+02 1.01 Acceptable EZA Ist/2014 05/16/14 E10849 Water pCVL Mn-54 2.08E+02 1.93E+02 1.08 Acceptable EZA Ist/2014 05/16/14 E10849 Water pCi/L Iron-59 1.68E+02 1.42E+02 1.18 Acceptable EZA Ist/2014 05/16/14 E10849 Water pCi/L Zinc-65 2.25E+02 2.10E+02 1.07 Acceptable EZA 1st/2014 05/16/14 E10849 Water pCi/L Cobalt-60 2.31E+02 2.19E+02 1.02 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 GrF3O Filter Bg/sample Gross Alpha 1.980 1.77 0.53-3.01 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 GrF3O Filter Bq/sample Gross Beta 0.823 0.77 0.39-1.16 Acceptable MAPEP-14- Americium-MAPEP 2nd/2014 06/05/14 MaS3O Soil Bq/kg 241 65 68 47.6-88.4 Acceptable MAPEP-14- False Pos MAPEP 2nd/2014 06/05/14 MaS3O Soil Bq/kg Cesium-134 5.44 0 Test Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 MaS3O Soil Bq/ka Cesium-137 1270 1238 867-1609 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 MaS3O Soil Bq/kq Cobalt-57 947 966 676-1256 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 MaS3O Soil Bq/kg Cobalt-60 0.581 1.220 Sens. Eval. Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 MaS3O Soil Bq/kg Iron-55 580 643 444-824 Acceptable MAPEP-14- Manganese-MAPEP 2nd/2014 06/05/14 MaS3O Soil Bq/kg 54 1470 1430 1001-1859 Acceptable MAPEP-14- False Pos MAPEP 2nd/2014 06/05/14 MaS3O Soil Bq/kq Nickel-63 6.95 0 Test Acceptable MAPEP-14- Plutonium-MAPEP 2nd/2014 06/05/14 MaS3O Soil Bq/kg 238 89.7 96.0 67-125 Acceptable MAPEP-14- Plutonium-MAPEP 2nd/2014 06/05/14 MaS3O Soil Bq/kg 239/240 69.80 76.8 53.8-99.8 Acceptable MAPEP-14- Potassium-MAPEP 2nd/2014 06/05/14 MaS3O Soil Bq/kg 40 703 622 435-809 Acceptable MAPEP- Strontium- False Pos 2nd/2014 06/05/14 14-Soil Bq/kg 90 1.48 0 Test Acceptable

I Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 15 of 64 14- Technetium- False Pos MAPEP 2nd/2014 I 06/05/14 MaS30 Soil 99 37.1 0 Test Acceptable MAPEP-14- Not MAPEP 2nd/2014 06/05/14 MaS3O Soil Bq/kg U-234/233 30.5 81.0 57-105 Accept.

MAPEP-14- Uranium- Not MAPEP 2nd/2014 06/05/14 MaS3O Soil Bq/kg 238 35 83 58-108 Accept.

MAPEP-14-MAPEP 2nd/2014 06/05/14 MaS3O Soil Bq/ko Zinc-65 766 695 487-904 Acceptable MAPEP-14- Americium-MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L 241 0.759 0.720 0.504-0.936 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L Cesium-134 21.4 23.1 16.2-30.0 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L Cesium-137 29.70 28.9 20.2-37.6 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L Cobalt-57 28.0 27.5 19.3-35.8 table MAPEP-14-MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L Cobalt-60 16.6 16.0 11.2-20.8 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L Hvdrooen-3 308 321 225-417 Acceptable MAPEP-14- False Pos MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L Iron-55 0.3 0.0 Test Acceptable MAPEP-14- Manganese-MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L 54 14.4 13.9 9.7-18.1 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L Nickel-63 31.4 34.0 23.8-44.2 Acceptable MAPEP-14- Plutonium-MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L 238 0.764 0.828 0.580-1.076 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L Pu-239/240 0.6590 0.6760 0.473-0.879 Acceptable MAPEP-14- Potassium- False Pos MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L 40 0.460 0 Test Acceptable MAPEP-14- Strontium-MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L 90 8.32 8.51 5.96-11.06 table MAPEP-14- Technetium-MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L 99 9.5 10.3 7.2-13.4 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L U-234/233 0.210 0.225 0.158-0.293 Acceptable MAPEP-14- Uranium-MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L 238 1.41 1.45 1.02-1.89 Acceptable MAPEP- IFalse Pos MAPEP 2nd/2014 06/05/14 14- Water Bq/L Zinc-65 -0.126 0.0 Test Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 16 of 64 14-MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L Gross Alpha 0.96 0.85 0.255-1.443 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L Gross Beta 4.7 4.2 2.10-6.29 Acceptable MAPEP-14- False Pos MAPEP 2nd/2014 06/05/14 MaW3O Water Bq/L Iodine-129 0.0227 0.00 Test Acceptable MAPEP-14- Uranium-MAPEP 2nd/2014 06/05/14 RdF3O Filter ug/sample 235 0.018 0.020 0.014-0.026 Acceptable MAPEP-14- Uranium-MAPEP 2nd/2014 06/05/14 RdF3O Filter ug/sample 238 8.77 10.4 7.3-13.5 Acceptable MAPEP-14- Uranium-MAPEP 2nd/2014 06/05/14 RdF3O Filter ug/sample Total 8.80 10.4 7.3-13.5 Acceptable MAPEP-14- Americium-MAPEP 2nd/2014 06/05/14 RdF3O Filter ug/sample 241 0.086 0.090 0.063-0.117 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 RdF3O Filter Bq/sample Cesium-134 1.85 1.91 1.34-2.48 Acceptable r MAPEP-14-MAPEP 2nd/2014 06/05/14 RdF3O Filter Bq/sample Cesium-137 1.81 1.76 1.23-2.29 Acceptable MAPEP-14- False Pos MAPEP 2nd/2014 06/05/14 RdF3O Filter Bq/sample Cobalt-57 0.0757 0.00 Test Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 RdF3O Filter Bq/sample Cobalt-60 1.490 1.39 0.97-1.81 Acceptable MAPEP-14- Manganese- False Pos MAPEP 2nd/2014 06/05/14 RdF3O Filter Bg/sample 54 0.0138 0.00 Test Acceptable MAPEP-14- Plutonium-MAPEP 2nd/2014 06/05/14 RdF3O Filter Bqlsample 238 0.000819 0.00090 Sens. Eval. Acceptable MAPDEP-14- 0.054-MAPEP 2nd/2014 06/05/14 RdF3O Filter Bg/sample Pu-239/240 0.071 0.7720 0.1004 Acceptable MAPEP-14- Strontium-MAPEP 2nd/2014 06/05/14 RdF3O Filter Bg/sample 90 1.19 1.18 0.83-1.53 Acceptable MAPEP-14- 0.0137-MAPEP 2nd/2014 06/05/14 RdF3O Filter Bq/sample U-234/233 0.0159 0.0195 0.0254 Acceptable MAPEP-14- Uranium-MAPEP 2nd/2014 06/05/14 RdF3O Filter Bq/sample 238 0.118 0.129 0.090-0.168 Acceptable MAPEP-14- False Pos MAPEP 2nd/2014 06/05/14 RdF3O Filter Bq/sam le Zinc-65 0.246 0.00 Test A MAPEP-14-MAPEP 2nd/2014 06/05/14 RdF3O Filter Bq/sample Gross Alpha 0.656 1.20 0.36-2.04 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 RdF3O Filter Bg/sample Gross Beta 0.95 0.85 0.43-1.28 Acceptable MAPEP- Americium-MAPEP 2nd/2014 06/05/14 14- Filter Bq/sample 241 0.106 0.104 0.073-0.135 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 17 of 64 14- Uranium- 0.0188- Not MAPEP 2nd/2014 06/05/14 RdV30 Veoetation I ua/samole 235 0.261 0.0268 0.0348 Acceot.

MAPEP-14- Uranium-MAPEP 2nd/2014 06/05/14 RdV3 egttion /sampll 238 12.7 13.3 9.3-17.3 table MAPEP-14- Uranium-MAPEP 2nd/2014 06/05/14 RdV3. Vegetation ug/ample Total 12.7 13.3 9.3-17.3 Acceptable MAPEP-14- Americium-MAPEP 2nd/2014 06/05/14 RdV3O Vegetation ug/sample 241 0.1100 0.108 0.076-0.140 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 RdV3O Vegetation Bq/sample Cesium-134 5.65 6.04 4.23-7.85 MAPEP-14-MAPEP 2nd/2014 06/05/14 RdV3O Vegetation Bg/sample Cesium-1 37 4.98 4.74 3.32-6.16 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 RdV3O Vegetation Bg/sample Cobalt-57 11.1 10.1 7.1-13.1 Acceptable MAPEP-14-MAPEP 2nd/2014 06/05/14 RdV3 Vegetaionl B /sample Cobalt-60 7.21 6.93 4.85-9.01 table MAPEP-14- Manganese-MAPEP 2nd/2014 06/05/14 RdV3O Vegetation Bo/sample 54 9.24 8.62 6.03-11.21 MAPEP-14- Plutonium-MAPEP 2nd/2014 06/05/14 RdV3O Vegetation Bg/sample 238 0.116 0.121 0.085-0.157 Acceptable MAPEP-14- 0.108-MAPEP 2nd/2014 06/05/14 RdV3 egttion B /sample Pu-239/240 0.134 0.154 0.0200 table MAPEP-14- Strontium-MAPEP 2nd/2014 06/05/14 RdV3O Vegetation Bo/sample 90 1.580 1.46 1.02-1.90 Acceptable MAPEP-14- 0.0177-MAPEP 2nd/2014 06/05/14 RdV3O V etation Bg/sample U-234/233 0.2640 0.2530 0.0329 Acceptable MAPEP-14- Uranium-MAPEP 2nd/2014 06/05/14 RdV3O Veetio B /sample 238 0.174 0.165 0.116-0.215 table MAPEP-14-MAPEP 2nd/2014 06/05/14 RdV3O Vegetation Bg/sample Zinc-65 8.87 7.00 4.38-8.13 Acceptable MRAD- Actinium-ERA 2nd/2014 05/16/14 20 Soil pCi/kg 228 1140 1240 795-1720 MRAD- Americium-ERA 2nd/2014 05/16/14 20 Soil pCi/kg 241 418 399 233-518 Acceptable MRAO- Bismuth-ERA 2nd/2014 05/16/14 20 Soil pCi/kg 212 976 1240 330-1820 Acceptable MRAD- Bismuth-ERA 2nd/2014 05/16/14 20 Soil pCi/kg 214 2290 1960 1180-2820 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Cesium-134 3080 3390 2220-4070 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Cesium-137 8310 8490 6510-10900 Acceptable MPAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Cobalt-60 6570 6830 4620-9400 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Lead-212 1330 1240 812-1730 Acceptable ERA 2nd/2014 05/16/14 MRAO- Soil pCi/kg Lead-214 2800 2070 1210-3090 Acceptable

I Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 18 of 64 MRAO- Manganese-ERA 2nd/2014 05/16/14 20 Soil pCi/kg 54 <44.3 <1000 0-1000 Acceptable MRAD- Plutonium-ERA 2nd/2014 05/16/14 20 Soil pCVkg 238 579 578 348-797 Acceptable MRAD- Plutonium-ERA 2nd/2014 05/16/14 20 Soil pCi/kg 239 488 471.00 308-651 Acceptable MRAD- Potassium-ERA 2nd/2014 05/16/14 20 Soil pCi/kg 40 10500 10500 7660-14100 Acceptabl MRAD- Strontium-ERA 2nd/2014 05/16/14 20 Soil pCUkg 90 2500 2780 1060-4390 MRAD- Thorium-ERA 2nd/2014 05/16/14 20 Soil pCi/kg 234 3420 3360 1060-6320 MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Zinc-65 5700 5400 4300-7180 Acceptable MRAD- Strontium-ERA 2nd/2014 05/16/14 20 Soil pCi/kg 90 6730 8530 3250-13500 MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Soil pCUkg 234 2602 3390 2070-4350 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Soil pCi/kg 238 2425 3360 2080-4260 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Total 5027 6910 3750-9120 Acceptable MRAO- Uranium-ERA 2nd/2014 05/16/14 20 Soil ug/kg TotaI(mass) 7110 10100 5570-12700 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Soil pCi/kg 234 3440 3390 2070-4350 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Soil pCikg 238 3680 3360 2080-4260 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Soil pCikg Total 7310 6910 3750-9120 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Soil ug/kg Total mass 11000 10100 5570-12700 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Soil pCUkg 234 3740 3390 2070-4350 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Soil pCUkg 238 3780 3360 2080-4260 Acceptable MRAO- Uranium-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Total 7683 6910 3750-9120 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Soil ug/kg Total(mass) 11300 10100 5570-12700 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Soil ug/kg Total(mass) 11200 10100 5570-12700 Acceptable MRAD- Americium-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg 241 1670 1490 911-1980 MRAD-ERA 2nd/2014 05/16/14 20 Veeaion pCi/kg Cesium-134 657 646 415-839 table MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Cesium-137 861 880 638-1220 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Cobalt-60 997 926 639-1290 Acceptable MRAO-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Curium-244 514 516 253-804 Acceptable MRAD- Manganese-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg 54 <62.2 <300 0.00-300 Acceptable MRAD- Plutonium-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg 238 2230 2110 1260-2890 Acceptable MRAO- Plutonium-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg 239 3810 3740 2300-5150 Acceptable MRAO- Potassium- 23000-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg 40 30800 31900 44800 Acceptable ERA 2nd/2014 05/16/14 MRAD- Vegetation pCVkg Strontium- 2330 2580 1470-3420 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 19 of 64 MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Vegetation pCVkg 234 1920 1760 1160-2260 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg 238 1970 1750 1170-2220 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Vegetation pCVkg Total 4025 3580 2430-4460 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Vegetation ug/kg Totallmass) 5920 5240 3510-6650 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Zinc-65 1030 919 663-1290 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Vegetation pCVkg 234 1730 1760 1160-2260 Acceptable MRAO- Uranium-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg 238 2000 1750 1170-2220 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Total 3817 3580 2430-4460 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Vegetation ug/kg Totallmass) 5990 5240 3510-6650 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Vegetation ug/kg Totaflmass) 5620 5240 3510-6650 Acceptable MRAD- Americium-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter 241 60.2 59.7 36.8-80.8 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Cesium-134 920 1010 643-1250 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Cesium-137 816 828 622-1090 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Cobalt-60 1130 1120 867-1400 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Iron-55 254 240 74.4-469 Acceptable MRAD- Manganese-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter 54 <6.64 <50.0 0-50.0 Acceptable MRAD- Plutonium-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter 238 51.3 56.3 38.6-74.0 Acceptable MRAD- Plutonium-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter 239 47.5 48.6 35.2-63.5 Acceptable MRAD- Strontium-ERA 2nd/2014 05/16/14 20 Filter pCiFilter 90 76.7 78.9 38.6-118 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter 234 33.8 36.4 22.6-54 Acceptable MRAO- Uranium-ERA 2nd/2014 05/16/14 20 Filter r 238 34.5 36.1 23.3-49.9 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Filter p Total 70.3 74.3 41.1-113 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Filter /ltr T 104 108 69.1-152 table MRAD-ERA 2nd/2014 05/16/14 20 Filter pCiFilter Zinc-65 737 667 478-921 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter 234 35.5 36.4 22.6-54 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Filter pC/Filter 238 35.3 36.1 23.3-49.9 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Filter _C/Filter Total 72.4 74.3 41.1-113 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Filter ug/Filter Total*mass) 105 108 69.1-152 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Filter ug/Filter Totallmass) 100 108 69.1-152 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCUFilter Gross Alpha 60.9 46 15.4-71.4 Acceptable ERA 2nd/2014 05/16/14 MRAD- Filter pCi/Filter Gross Beta 58.9 53.8 34.0-78.4 Acceptable

i Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 20 of 64 MRAD- Americium- Not ERA 2nd/2014 05/16/14 20 Water pCi/L 241 186 114 76.8-153 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Cesium-134 1540 1660 1220-1910 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCUL Cesium-137 2760 2690 2280-3220 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCUL Cobalt-60 1320 1270 1100-1490 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Iron-55 1230 1200 716-1630 Acceptable MRAD- Manganese-ERA 2nd/2014 05/16/14 20 Water pCi/L 54 <7.54 <100 0.00-100 MRAD- Plutonium-ERA 2nd/2014 05/16/14 20 Water pCi/L 238 37 44 32.6-54.9 Acceptable MRAD- Plutonium-ERA 2nd/2014 05/16/14 20 Water pCi/L 239 124 160 124-202 Acceptable MRAD- Strontium-ERA 2nd/2014 05/16/14 20 Water pCi/L 90 95 890 580-1180 Acceptable MRAO- Uranium-ERA 2nd/2014 05/16/14 20 Water pCi/L 234 77.8 82.4 61.9-106 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Water pCi/L 238 50.8 48.4 36.9-59.4 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16114 20 Water pCi/L Total 156 168 123-217 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Water ug/L Totai(mass) 233 245 195-296 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCUL Zinc-65 2030 1800 1500-2270 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Water pCi/L 234 82.1 82.4 61.9-106 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Water pCi/L 238 84.6 48.4 36.9-59.4 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Water pCi/L Total 170 168 123-217 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Water ug/L Totaffmass) 253 245 195-296 A MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Water pCi/L 234 80.5 82.4 61.9-106 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Water pCi/L 238 90.0 48.4 36.9-59.4 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Water pCi/L Total 175 168 123-217 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Water ug/L Totallmass) 269 245 195-296 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Water pCi/L 234 77.8 82.4 61.9-106 table MRAD- Uranium-ERA 2nd/2014 05116/14 20 Water pCi/L 238 78.3 48.4 36.9-59.4 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Water pCi/L Total 156 168 123-217 Acceptable MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Water ug/L Totai(mass) 233 245 195-296 MRAD- Uranium-ERA 2nd/2014 05/16/14 20 Water ug/L Totai(mass) 232 245 195-296 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Gross Alpha 141.0 133 47.2-206 Acceptable MIRAD-62nd/201420 0/16/14 Water pCi/L Gross Beta 172 174.0 99.6-258 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Tritium 5280 5580 3740-7960 Acceptable EZA 2nd/2014 08/08/14 E10897 Cartridge pCi lodine-131 8.73E+01 8.54E+01 1.02 Acceptable

i Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 21 of 64 2014 ANNUAL QUALITY ASSURANCE REPORT Page 21 of 64 EZA 2nd/2014 I 08/08/14 I E10898 Milk DCUiL 89 I9.84E+01 I 9.13E+01 1.08 I AcceDtable Strontium-EZA 2nd/2014 08/08/14 E10898 Milk pCi/L 90 1.44E+01 1.45E+01 0.99 Acceptable EZA 2nd/2014 08/08/14 E10899 Milk pCVL lodine-131 9.89E+01 9.09E+01 1.09 Acceptable EZA 2nd/2014 08/08/14 E10899 Milk pCVL Cerium-141 1.38E+02 1.24E+02 1.12 Acceptable Chromium-EZA 2nd12014 08/08/14 E10899 Milk pCi/L 51 2.68E+02 2.53E+02 1.06 EZA 2nd/2014 08/08/14 E10899 Milk pCVL Cesium-134 1.58E+02 1.62E+02 0.97 Acceptable EZA 2nd/2014 08/08/14 E10899 Milk pCVL Cesium-137 1.27E+02 1.20E+02 1.06 Acceptable EZA 2nd/2014 08108/14 E10899 Milk pCi/L Cobalt-58 1.20E+02 1.12E+02 1.07 Acceptable Manganese-EZA 2nd/2014 08/08/14 E10899 Milk pCi/L 54 1.67E+02 1.56E+02 1.07 Acceptable EZA 2nd12014 08/08/14 E10899 Milk pCVL Iron-59 1.02E+02 1.02E+02 1.00 EZA 2nd/2014 08/08/14 E10899 Milk pCVL Zinc-65 2.68E+02 2.52E+02 1.06 Acceptable EZA 2nd/2014 08/08/14 E10899 Milk pCVL Cobalt-60 2.42E+02 2.24E+02 1.08 Acceptable EZA 2nd/2014 08/08/14 E10900 Water pCVL lodine-131 1.13E+02 9.83E+01 1.15 Acceptable EZA 2nd/2014 08/08/14 E10900 Water pCi/L Cerium-141 1.52E+02 1.43E+02 1.06 Acceptable Chromium-EZA 2nd/2014 08/08114 E10900 Water pCUL 51 3.62E+02 2.94E+02 1.23 EZA 2nd/2014 08/08/14 E10900 Water pCi/L Cesium-134 1.69E+02 1.88E+02 0.90 Acceptable EZA 2nd/2014 08/08/14 E10900 Water pCYL Cesium-137 1.48E+02 1.39E+02 1.06 Acceptable EZA 2nd/2014 08/08/14 E10900 Water pCVL Cobalt-58 1.34E+02 1.30E+02 1.03 Manganese-EZA 2nd/2014 08/08/14 E10900 Water pCVL 54 1.88E+02 1.80E+02 1.04 EZA 2nd/2014 08/08/14 E10900 Water pCVL Iron-59 1.29E+02 1.19E+02 1.09 Acceptable EZA 2nd/2014 08/08/14 E10900 Water pCVL Zinc-65 3.29E+02 2.93E+02 1.12 Acceptable EZA 2nd/2014 08/08/14 E10900 Water pCiL Cobalt-60 2.74E+02 2.60E+02 1.05 Acceptable 3rd / RAD-ERA 2013 08/25/14 98 Water pCVL Barium-133 67.8 68.7 57.3-75.6 Acceptable 3rd/ RAD-ERA 2013 08/25/14 98 Water pCVL Cesium-134 71 72.3 59.0-79.5 3rd/ RAD-ERA 2013 08/25/14 98 Water pCi/L Cesium-137 161 163 147-181 Acceptable 3rd/ RAD-ERA 2013 08/25/14 98 Water pCi/L Cobalt-60 76.7 75.5 68.0-85.5 3rd/ RAD-ERA 2013 08/25/14 98 Water pCVL Zinc-65 92 82 73.8-98.5 Acceptable 3rd/ RAD-ERA 2013 08/25/14 98 Water pCVL Gross Alpha 45.3 45.4 23.6-57.4 Acceptable 3rd / RA-ERA 2013 08/25/14 98 Water pCVLL Gross Beta 32.3 33.4 21.7-41.1 Acceptable 3rd/ RAD-ERA 2013 08/25/14 98 Water pCVL Gross Alpha 48.6 45.4 23.6-57.4 3rd/ RAD-ERA 2013 08/25/14 98 Water pCVL Radium-226 8.26 9.06 6.80-10.6 Acceptable 3rd/ RAD-ERA 2013 08/25114 98 Water pCVL Radium-226 8.54 9.06 6.80-10.6 table 3rd / RAD -

ERA 2013 08/25/14 98 Water pCVL Radium-226 9.7 9.06 6.80-10.6 Acceptable 3rd / RAD -

ERA 2013 08/25/14 98 Water pCVL Radium-228 5.07 5.07 3.03-6.79 Acceptabl 3rd/ RAD -

ERA 2013 08/25/14 98 Water pCVL Radium-228 5.74 5.07 3.03-6.79 3rd / RAD - Uranium ERA 2013 08/25/14 98 Water pCi/L (Nat) 13.9 13.5 10.7-15.4 Acceptable 3rd / RAD - Uranium ERA 2013 08/25/14 98 Water ug/L (Nat) mass 22.25 19.8 15.6-22.6 Acceptable 3rd / RAD - Uranium 2013 08/25/14 98 Water PCi/L (Nat) 13 13.5 10.7-15.4 Acceptable 3rd / 08/25/14 RAD - Water ug/L Uranium 20.7 19.8 15.6-22.6 Acceptable

I Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 22 of 64 2014 ANNUAL QUALITY ASSURANCE REPORT Page 22 of 64 3rd / RAD -

ERA 2013 08/25/14 98 Water oCVL Tritium 10200 I 11200 9750-12300 I Acceptable 3rd/ RAD -

ERA 2013 08/25/14 98 Water pCVL Tritium 10400 11200 9750-12300 3rd / RAD - Strontium- Not ERA 2013 08/25/14 98 Water pCi/L 89 56.3 42.7 32.9-49.8 Acceptable 3rd / RAD - Strontium-ERA 2013 08/25/14 98 Water pCi/L 90 28.2 31.7 23.1-36.7 Acceptable 3rd / RAO - Strontium- Not ERA 2013 08/25/14 98 Water pCi/L 89 56.5 42.7 32.9-49.8 Acceptable 3rd / RAO - Strontium-ERA 2013 08/25/14 98 Water pCi/L 90 26 31.7 23.1-36.7 Acceptable 3rd / RAD -

ERA 2013 08/25/14 98 Water pCi/L Iodine-131 28.6 26.1 21.7-30.8 Acceptable 3rd / RAD -

ERA 2013 08/25/14 98 Water pCVL Iodine-131 22.3 26.1 21.7-30.8 Acceptable EZA 3rd/2014 11/22/14 E10993 Cartridge pci Iodine-131 9.47E+01 8.99E+01 1.05 Acceptable Strontium-EZA 3rd/2014 11/22/14 E10994 Milk pCVL 89 9.73E+01 9.69E+01 1.00 Acceptable Strontium-EZA 3rd/2014 11/22/14 E10994 Milk pCLiL 90 1.31E+01 1.64E+00 0.80 Acceptable EZA 3rd/2014 11/22/14 E10995 Milk pCVL Iodine-131 1.04E+02 9.76E+01 1.07 EZA 3rd/2014 11/22/14 E10995 Milk pCVL Cerium-141 1.28E+02 1.26E+02 1.01 Acceptable Chromium-EZA 3rd/2014 11/22/14 E10995 Milk pCi/L 51 3.12E+02 2.88E+02 1.08 A t EZA 3rd/2014 11/22/14 E10995 Milk pCVL Cesium-134 1.51E+02 1.58E+02 0.96 Acceptable EZA 3rd/2014 11/22/14 E10995 Milk pCi/L Cesium-137 2.03E+02 1.93E+02 1.05 Acceptable EZA 3rd/2014 11/22/14 E10995 Milk pCVL Cobalt-58 1.44E+02 1.43E+02 1.01 Acceptable Manganese-EZA 3rd/2014 11/22/14 E10995 Milk pCi/L 54 1.49E+02 1.42E+02 1.05 Accptable EZA 3rd/2014 11/22/14 E10995 Milk pCVL Iron-59 1.82E+02 1.58E+02 1.15 Acceptable EZA 3rd/2014 11/22/14 E10995 Milk pCi/L Zinc-65 7.41E+01 7.30E+01 1.01 Acceptable EZA 3rd/2014 11/22/14 E10995 Milk pCVL Cobalt-60 3.14E+02 2.94E+02 1.06 Acceptable EZA 3rd/2014 11/22/14 E10996 Water pCi/L Iodine-131 1.02E+02 9.88E+01 103 Acceptable EZA 3rd/2014 11/22/14 E10996 Water pCVL Cerium-141 1.30E+02 1.25E+02 104 Acceptable Chromium-EZA 3rd/2014 11/22/14 E10996 Water pCVL 51 2.75E+02 2.86E+02 0.96 Acceptable EZA 3rd/2014 11/22/14 E10996 Water pCi/L Cesium-134 1.45E+02 1.56E+02 0.93 Acceptable EZA 3rd/2014 11/22/14 E10996 Water pCVL Cesium-137 1.94E+02 1.92E+02 1.01 Acceptable EZA 3rd/2014 11/22/14 E10996 Water pCi/L Cobalt-58 1.43E+02 1.42E+02 1.01 Acceptable Manganese-EZA 3rd/2014 11/22/14 E10996 Water pCVL 54 1.46E+02 1.41E+02 1.04 EZA 3rd/2014 11/22/14 E10996 Water pCVL Iron-59 1.66E+02 1.57E+02 1.06 A t EZA 3rd/2014 11/22/14 E10996 Water pCVL Zinc-65 7.55E+01 7.24E+01 1.04 EZA 3rd/2014 11/22/14 E10996 Water pCi/L Cobalt-60 3.09E+02 2.95E+02 1.05 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 GrF3I Filter Bg/sample Gross Alpha 0.433 0.530 0.16-0.09 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 GrF31 Filter Bq/sample Gross Beta 1.060 1.060 0.53-1.59 Acceptable MAPEP-14- Americium-MAPEP 4th /2014 01/09/15 MaS31 Soil Bq/Kg 241 88.4 85.5 59.9-111.2 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 MaS3l Soil Bq/Kg Cesium-134 588 622 435-809 Acceptable MAPEP-14- False Pos MAPEP 4th /2014 01/09/15 MaS3l Soil Bq/Kg Cesium-1 37 1.67 Test Acceptable

I Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 23 of 64 14-MAPEP 4th/2014 I 01/09/15 I MaS31 Soil Ba/Ka Cobalt-57 1160 1116 781-1451 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 MaS31 Soil Bq/Kg Cobalt-60 821 779 545-1013 A MAPEP-14-MAPEP 4th /2014 01/09/15 MaS3I Soil Bq/Kg Iron-55 796 680 476-884 Acceptable MAPEP-14- Manganese-MAPEP 4th /2014 01/09/15 MaS31 Soil Bq/Kg 54 1060 1009 706-1312 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 MaS31 Soil Bq/Kg Nickel-63 924 980 686-1274 Acceptable MAPEP-14- Plutonium-MAPEP 4th /2014 01/09/15 MaS3l Soil Bq/Kg 238 0.92 0.48 Sens. Eval. Acceptable MAPEP-14- Plutonium-MAPEP 4th /2014 01/09/15 MaS3l Soil Bq/Kg 239/240 61.5 58.6 41.0-76.2 Acceptable MAPEP-14- Potassium-MAPEP 4th /2014 01/09/15 MaS31 Soil Bq/Kg 40 879 824 577-1071 Acceptable MAPEP-14- Strontium-MAPEP 4th /2014 01/09/15 MaS3l Soil Bq/Kg 90 891 858 601-1115 Acceptable MAPEP-14- Technetium-MAPEP 4th /2014 01/09/15 MaS3l Soil Bq/Kg 99 466 589 412-766 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 MaS3I Soil Bq/Kg U-234/233 905 89 62-116 Acceptable MAPEP-114- Uranium-MAPEP 4th /2014 01/09/15 MaS3l Soil Bq/Kg 238 257 259 181-337 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 MaS3l Soil Bq/Kg Zinc-65 605.0 541 379-703 Acceptable MAPEP-14- Americium-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L 241 0.915 0.880 0.62-1.14 ptable MAPEP-14- False Pos MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L Cesium-1 34 -0.06 Test Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L Cesium-137 18.4 18.4 12.9-23.9 Acptable MAPEP-14-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L Cobalt-57 25 24.7 17.3-32.1 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L Cobalt-60 12.5 12.4 8.7-16.1 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L H 216 208 146-270 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L Iron-55 34.0 31.5 22.1-41.0 Acceptable MAPEP-14- Manganese-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L 54 14.2 14.0 9.8-18.2 Acceptable

I Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 24 of 64 II+-

MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L Nickel-63 23.6 24.6 17.2-32.0 Acceptable MAPEP-1 14- Plutonium-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L 238 0.547 0.618 0.433-0.803 Acceptable MAPEP-14- Plutonium-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L 2391240 0.015 0.005 Sens. Eval. Acceptable MAPEP-14- Potassium-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L 40 174 161 113-209 Acceptable MAPEP-14- Strontium- False Pos MAPEP 4th /2014 01/09/15 MaW3I Water Bq/L 90 0.03 Test table MAPEP-14- Technetium-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L 99 6.92 6.99 4.89-9.09 Acceptable MAPEP-14- Uranium-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L 234/233 0.206 0.205 0.144-0.267 Acceptable MAPEP-14- Uranium-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L 238 1.280 1.420 0.99-1.85 MAPEP-14-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L Zinc-65 11.900 10.90 7.6-14.2 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L Gross Alpha 0.793 0.701 0.201-1.192 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 MaW3I Water Bq/L Gross Beta 6.220 5.94 2.97-8.91 Acceptable MAPEP-14- Uranium- 0.0278-MAPEP 4th /2014 01/09/15 RdF31 Filter up/sample 235 0.040 0.040 0.0516 MAPEP-14- Uranium-MAPEP 4th /2014 01/09/15 RdF31 Filter up/sample 238 19.3 20.3 14.2-26.4 Acceptable MAPEP-14- Uranium-MAPEP 4th /2014 01/09/15 RdF31 Filter ug/sample Total 19.00 20.4 14.3-26.5 MAPEP-14- Americium- 0.0472-MAPEP 4th /2014 01/09/15 RdF31 Filter ug/sample 241 0.0561 0.067 0.0876 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 RdF31 Filter Bq/sample Cesium-134 0.8640 0.96 0.67-1.25 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 RdF31 Filter Bq/sample Cesium-137 1.190 1.20 0.84-1.56 Acceptable MAPEP-14-MAPEP 4th /2014 01109/15 RdF31 Filter Bg/sample Cobalt-57 1.540 1.43 1.00-1.86 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 RdF31 Filter Bg/sample Cobalt-60 1.200 1.10 0.77-1.43 MAPEP-14- Manganese-MAPEP 4th /2014 01/09/15 RdF31 Filter q sample 54 0.808 0.75 0.53-0.98 Acceptable MAPEP-14- Plutonium-MAPEP 4th /2014 01/09/15 RdF31 Filter Ig/sample 238 0.155 0.107 0.075-0.139 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 25 of 64 14- Plutonium- 0.0328-MAPEP 4th /2014 01/09/15 RdF31 Filter Bq/sample 239/240 0.048 0.0468 0.0608 Acceptable MAPEP-1 14- Strontium-MAPEP 4th /2014 01109/15 RdF31 Filter Bq/sample 90 0.762 0.70 0.492-0.914 Acceptable MAPEP-14- Uranium- 0.0251-MAPEP 4th /2014 01/09/15 RdF3I Filter Bg/sample 234/233 0.037 0.0358 0.0465 Acceptable MAPEP-14- Uranium-MAPEP 4th /2014 01/09/15 RdF31 Filter Bg/sample 238 0.227 0.253 0.177-0.329 MAPEP-14-MAPEP 4th /2014 01/09/15 RdF31 Filter Bg/sample Zinc-65 0.779 0.76 0.53-0.99 Acceptable MAPEP-14- Americium-MAPEP 4th /2014 01/09/15 RdV31 Vegetation Bg/sample 241 0.226 0.19 0.135-0.251 Acceptable MAPEP-14-MAPEP 4th /2014 01/09115 RdV31 Vegetation Bq/sample Cesium-134 4.750 5.20 3.64-6.67 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 RdV31 Ži!on B Cesium-137 6.910 6.60 4.62-8.58 MAPEP-14- False Pos MAPEP 4th /2014 01/09/15 RdV31 Vegetation Bq/sample Cobalt-57 -0.002 0.00 Test Acceptable MAPEP-14- False Pos MAPEP 4th /2014 01/09/15 RdV31 Vegetation Bg/sample Cobalt-60 0.008 0.00 Test Acceptable MAPEP-14- Manganese-MAPEP 4th /2014 01/09/15 RdV31 Veon B /sample 54 7.980 7.88 5.52-10.24 table MAPEP-14- Plutonium-MAPEP 4th /2014 01/09/15 RdV3 V eetation Bq/sample 238 0.001 0.001 Sens. Eval. Acceptable MAPEP-14- Plutonium-MAPEP 4th /2014 01/09/15 RdV31 Vegetation Bq/sample 239/240 0.1510 0.171 0.120-0.222 Acceptable MAPEP-14- Strontium-MAPEP 4th /2014 01/09/15 RdV31 Vegetation BI/sample 90 2,330 2.32 1.62-3.02 Acceptable MAPEP-14- Uranium- 0.0326-MAPEP 4th /2014 01/09/15 RdV31 Veetation Bg/sample 234/233 0.046 0.047 0.0606 Acceptable MAPEP-14- Uranium-MAPEP 4th /2014 01/09/15 RdV31 Vegetation Bg/sample 238 0.332 0.324 0.227-0.421 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 RdV31 Vegetation Bg/sample Zinc-65 2.850 2.63 1.84-3.42 MAPEP-14-SrF- Strontium-MAPEP 4th /2014 01/09/15 31 Filter Bg/sample 89 3.62 3.79 2.65-4.93 Acceptable MAPEP-I 4-SrF- Strontium-MAPEP 4th /2014 01/09/15 31 Filter Bq/sample 90 3.62 3.79 2.65-4.93 Acceptable MAPEP-14-MAPEP 4th /2014 01/09/15 XaW-31 Water Bq/L Iodine-129 4.56 4.55 3.19-5.92 Acceptable 3rd / MRAD- SActinium-ERA 2014 11/25/14 21Soil pCi/kg 228 1280 1240 795-1720 Acceptable ERA 3rd / 11/25/14 MRAD- Soil pCi/kg Americium- 825 763 431-956 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 26 of 64 3rd / MRAD- Bismuth-ERA 2014 11/25/14 21 Soil DCilka 212 1620 1240 330-1820 I Acceptable 3rd /MRAD- Bismuth-ERA 2014 11/25/14 21 Soil pCi/kg 214 2900 2810 1690-4040 table 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCikg Cesium-134 1960 2140 1400-2570 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Cesium-137 6760 6550 5020-8430 Acceptable 3rd/ MRAD-ERA 2014 11/25/14 21 Soil pCikg Cobalt-60 4480 4260 2880-5860 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCVkg Lead-212 1260 1240 812-1730 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Lead-214 3480 2750 1610-4100 Acceptable 3rd / MRAD- Manganese-ERA 2014 11/25/14 21 Soil pCVkg 54 <30.0 <1000 0-1000 Acceptable 3rd I MRAD- Plutonium-ERA 2014 11/25/14 21 Soil pCi/kg 238 732 739 444-1020 Acceptable 3rd / MRAD- Plutonium-ERA 2014 11/25/14 21 Soil pCVkg 239 281 309 202-427 Acceptable 3rd / MRAD- Potassium-ERA 2014 11/25/14 21 Soil pCi/kg 40 11500 10700 7810-14400 Acceptable 3rd / MRAD- Strontium-ERA 2014 11/25/14 21 Soil pCVkg 90 8790 8420 3210-13300 Acceptable 3rd / MRAD- Thorium-ERA 2014 11/25/14 21 Soil pCi/kg 234 2000 2350 743-4420 Acceptable 3rd/I MRAD-ERA 2014 11/25/14 21 Soil pCVkg Zinc-65 3910 3270 2600-4350 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Soil pCikg 234 2280 2370 1450-3040 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Soil pCi/kg 238 2340 2350 1450-2980 table 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Soil pCi/kg Total 4762 4540 2360-6390 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Soil ug/kg Total(mass) 7020 7050 3890-8870 Acceptable 3rd / MRAD- Americium-ERA 2014 11/25/14 21 Vegetation pCi/kg 241 2260 2290 1400-3505 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 pCi/kg Cesium-134 837 849 545-1100 table 3rd/ MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Cesium-137 729 644 467-896 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Cobalt-60 818 784 541-1100 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Curium-244 361 367 180-572 Acceptable 3rd / MRAO- Manganese-ERA 2014 11/25/14 21 Vegetation pCi/kg 54 <25.3 <300 0-300 Acceptable 3rd /MRAD- Plutonium-ERA 2014 11/25/14 21 Vegetation pCi/kg 238 886 862 514-1180 Acceptable 3rd /MRAI- Plutonium-ERA 2014 11/25/14 21 Vegetation pCi/kg 239 675 701 430-965 Acceptable 3rd MRAD- Potassium- 22300-ERA 2014 11/25/14 21 Vegetation pCi/kg 40 35300 30900 43400 Acceptable 3rd /MRAD- Strontium-ERA 2014 11/25/14 21 Vegetation pCi/kg 90 1230 1710 975-2270 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Vegetation pCi/kg 234 1980 1780 1170-2290 Acceptable 3rd / MRAO- Uranium-ERA 2014 11/25/14 21 Vegetation pCi/kg 238 1970 1760 1170-2240 Acceptable ERA 3rd / 11/25/14 MRAD- Vegetation pCikg Uranium- 4038 3620 2450-4510 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 27 of 64 3rd / MRAD- Uranium-

')AIA ')1 r:DA 11/9 K/1 *L \/=ttDf=f;nn .rn/l~n Ko1In 195n -2L4.n.u71nl I Ar~nf~hl=

,) 14 ______ M1.+/-.+/-'+/-1+/-

y--to uWITdb

/k' ro- r.. '1r'nA71 n A- .

3rd ,, MRAD- Uranium-ERA 2014 11/25/14 21 Vegetation pCi/kg 234 1670 1780 1170-2290 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Vegetation pCi/kg 238 1800 1760 1170-2240 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Vegetation pCi/kg Total 3556 3620 2450-4510 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Vegetation ug/kg Totallmass) 5390 5280 3540-6710 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Vegetation ug/kg Total(mass) 5860 5280 3540-6710 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Zinc-65 1930 1570 1130-2200 Acceptable 3rd / MRAD- Americium-ERA 2014 11/25/14 21 Filter pCi/Filter 241 41.4 38.6 23.8-52.2 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Cesium-134 742 765.0 487-949 Acceptable 3rd/ MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Cesium-137 677 647 486-850 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter .y/ilter Cobalt-60 543 523 405-653 table 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Iron-55 117 120.0 37.2-234 Acceptable 3rd / MRAD- Manganese-ERA 2014 11/25/14 21 Filter pCi/Filter 54 <5.87 <50 0.00-50.0 Acceptable 3rd / MRAD- Plutonium-ERA 2014 11/25/14 21 Filter ug/Filter 238 32.9 35.7 24.5-46.9 Acceptable 3rd / MRAD- Plutonium-ERA 2014 11/25/14 21 Filter pCi/Filter 239 26.8 29.1 21.1-38.0 Acceptable 3rd / MRAD- Strontium-ERA 2014 11/25/14 21 Filter pCi/Filter 90 187 168 82.1-252 Acceptable 3rd / MRAO- Uranium-ERA 2014 11/25/14 21 Filter pCi/Filter 234 26 28 27.8-41.9 Acceptable 3rd / MRAO- Uranium-ERA 2014 11/25/14 21 Filter pCi/Filter 238 28 27.60 17.8-38.2 3rd / MRAO- Uranium-ERA 2014 11/25/14 21 Filter pCi/Filter Total 56 57 31.4-86.3 Acceptable 3rd / MRAI- Uranium-ERA 2014 11/25/14 21 Filter Ug/Filter Total(mass) 82.6 82.7 52.9-116 Acceptable 3rd/ MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Zinc-65 629 547 392-755 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Filter pCVFilter 234 28 28 27.8-41.9 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Filter pCi/Filter 238 25 27.60 17.8-38.2 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Filter pCi/Filter Total 55 57 31.4-86.3 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Filter ug/Filter Totaltmass) 75.1 82.7 52.9-116 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Filter ug/Filter Totallmass) 90.7 82.7 52.9-116 Acceptable 3rd/ MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Gross Alpha 47.4 36,9 12.4-57.3 Acceptable 3rd/ MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Gross Beta 27.2 21.1 13.3-30.8 Acceptable 3rd / MRAD- Americium-ERA 2014 11/25/14 21 Water pCi/L 241 72.4 68.6 46.2-92.0 Acceptable 3rdI MRAD-ERA 2014 11/25/14 21 Water pCVL Cesium-134 816.0 850 624-977 Acceptable ERA 3rd / 11/25/14 MRAD- Water pCVL Cesium-137 1310 1240 1060-1490 Acceptable

cLaboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 28 of 64 2014 ANNUAL QUALITY ASSURANCE REPORT Page 28 of 64 ERA 2014 11125/14 21 Water DCi/L I Cobalt-60 1130 1070 930-1250 I Accentable 3rd MRAD-ERA 2014 11/25/14 21 Water pC/L Iron-55 130 134 79.9-182 3rd I MRA/- Manganese-ERA 2014 11/25/14 21 Water pCi/L 54 <6.34 <100 0.00-100 Acceptable 3rd / MRAD- Plutonium-ERA 2014 11/25/14 21 Water pCi/L 238 35 33 24.6-41.4 Acceptable 3rd / MRAD- Plutonium-ERA 2014 11/25/14 21 Water pCi/L 239 46.4 51 39.7-64.4 Acceptable 3rd / MRAD- Strontium-ERA 2014 11/25/14 21 Water pCi/L 90 300 254 165-336 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Water pCi/L 234 42 44 32.9-56.5 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Water pCi/L 238 50 43.50 33.2-53.4 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Water pCi/L Total 92 89 65.5-115 Acceptable 3rd / MRAD- uranium-ERA 2014 11/25/14 21 Water ug/L Total(mass) 137 130 104-157 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCVL Zinc-65 1070 921 768-1160 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Water pCi/L 234 43 44 32.9-56.5 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Water pCi/L 238 45 43.50 33.2-53.4 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Water pCi/L Total 90 89 65.5-115 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Water ug/L Total(mass) 134 130 104-157 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Water pCi/L 234 49 44 32.9-56.5 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Water pCi/L 238 42 43.50 33.2-53.4 Acceptable 3rd /MRAD- Uranium-ERA 2014 11/25/14 21 Water pCi/L Total 93 89 65.5-115 Acceptable 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Water ug/L Totaltmass) 126 130 104-157 Accptble 3rd / MRAD- Uranium-ERA 2014 11/25/14 21 Water ug/L Total(mass) 144 130 104-157 Acceptable r 3rd/ MRAD-ERA 2014 11/25/14 21 Water pCVL GrossAlpha 96.2 98 34.8-152 Acceptable 3rd / MRAD-E 2014 11/25/14 21 Water pCi/L Gross Beta 86.1 77.5 44.4-115 Acceptable 3rd1/ MRAD-ERA 2014 ,11/25/14 ,21 Water pCi/L Tritium 5490 5500 3680-7840 Acceptable

Ke: I Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 29 of 64 TABLE 2 2014 ECKERT &ZIEGLER ANALYTICS PERFORMANCE EVALUATION RESULTS EZA lst/2014 05116/14 E10846 Cartridge DU Ilodine-131 7.83E+U1 7.b2E+01 1.U4 Acceptable Strontium-EZA 1st/2014 05/16/14 E10847 Milk pCi/L 89 9.14E+01 9.17E+01 1 Acceptable Strontium-EZA ls/2014 05/16/14 E10847 Milk pCi/L 90 1.27E+01 1.51E+01 0.84 Acceptable EZA Ist/2014 05/16/14 E10848 Milk pCVL Iodine-131 9,84E+01 9.85E+01 1 Acceptable EZA 1st/2014 05/16/14 E10848 Milk pCVL Cerium-141 1.21E+02 1.19E+02 1.02 Acceptable EZA 1st/2014 05/16/14 E 10848 Milk pCi/L Cr-51 5.19E+02 4.91E+02 1.06 Acceptable EZA lst/2014 05/16/14 E10848 Milk pCi/L Cesium-134 1.79E+02 2.10E+02 0.85 Acceptable EZA 1st12014 05/16/14 E10848 Milk pCi/L Cesium-137 2.55E+02 2.53E+02 1.01 Acceptable EZA lst/2014 05/16/14 E10848 Milk pCi/L Cobalt-58 2.58E+02 2.68E+02 0.96 Acceptable EZA lst/2014 05/16/14 E10848 Milk pCi/L Mn-54 3.01E+02 2.97E+02 1.01 Acceptable EZA lst/2014 05/16/14 E10848 Milk pCi/L Iron-59 2.24E+02 2.19E+02 1.02 Acceptable EZA lst/2014 05/16/14 E10848 Milk pCi/L Zinc-65 3.45E+02 3.23E+02 1.07 Acceptable EZA lst/2014 05/16/14 E10848 Milk pCi/L Cobalt-60 3.39E+02 3.37E+02 1.00 Acceptable EZA lst/2014 05/16/14 E10849 Water pCi/L Iodine-131 9.24E+01 8.99E+01 1.03 Acceptable EZA 1st12014 05/16/14 E10849 Water pCi/L Cerium-141 8.19E+01 7.71E+01 1.06 Acceptable EZA lst/2014 05/16/14 E10849 Water pCi/L Cr-51 3.32E+02 3.19E+02 1.04 Acceptable EZA Ist/2014 05/16/14 E10849 Water pCi/L Cesium-134 1.27E+02 1.36E+02 0.93 Acceptable EZA lst/2014 05/16/14 E10849 Water pCi/L Cesium-137 1.69E+02 1.64E+02 1.03 Acceptable EZA lst/2014 05/16/14 E10849 Water pCi/L Cobalt-58 1.75E+02 1.74E+02 1.01 Acceptable EZA lst/2014 05/16/14 E10849 Water pCi/L Mn-54 2,08E+02 1.93E+02 1.08 Acceptable EZA lst/2014 05/16114 E10849 Water pCi/L Iron-59 1.68E+02 .10E+02 1.42E+02 .07 11.18 Acceptable Acceptable pCi/L Zinc-65 2.25 2+02 2 05/16/14 E10849 Water EZA 1st2014 1.02 Acceptable 1st/2014 05/16/14 E10849 Water pCi/L Cobalt-60 2.31E+02 2.19E+02 EZA EZA 2nd/2014 08/08/14 E10897 Cartridge pC Iodine-1 31 8.73E+01 8.54E+01 1.02 Acceptable Strontium-EZA 2nd/2014 08/08/14 E10898 Milk pCi/L 89 9.84E+01 9.13E+01 1.08 Acceptable Strontium-EZA 2nd/2014 08/08/14 E10898 Milk pCi/L 90 1.44E+01 1.45E+01 0.99 Acceptable EZA 2nd/2014 08/08/14 E10899 Milk pCi/L Iodine-131 9.89E+01 9.09E+01 1.09 Acceptable EZA 2nd/2014 08/08/14 E10899 Milk pCi/L Cerium-141 1.38E+02 1.24E+02 1.12 Acceptable Chromium-EZA 2nd/2014 08/08/14 E10899 Milk pCi/L 51 2.68E+02 2.53E+02 1.06 Acceptable EZA 2nd/2014 08/08/14 E10899 Milk pCi/L Cesium-134 1.58E+02 1.62E+02 0.97 Acceptable EZA 2nd/2014 08/08/14 E10899 Milk pCi/L Cesium-137 1.27E+02 1.20E+02 1.06 Acceptable EZA 2nd/2014 08/08/14 E10899 Milk pCi/L Cobalt-58 1.20E+02 1.12E+02 1.07 Acceptable Manganese-EZA 2nd/2014 08/08/14 E10899 Milk pCi/L 54 1.67E+02 1.56E+02 1.07 Acceptable EZA 2nd/2014 08/08/14 E10899 Milk pCi/L Iron-59 1.02E+02 1.02E+02 1.00 Acceptable EZA 2nd/2014 08/08/14 E10899 Milk pCi/L Zinc-65 2.68E+02 2.52E+02 1.06 Acceptable EZA 2nd/2014 08/08/14 E10899 Milk pCi/L Cobalt-60 2.42E+02 2.24E+02 1.08 Acceptable EZA 2nd/2014 08/08/14 E10900 Water pCi/L lodine-131 1.13E+02 9.83E+01 1.15 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 30 of 64 EZA 2nd/2014 08/08/14 E10900 Water pCVL Cerium-141 1.52E+02 1.43E+02 1.06 Acceptable Chromium-EZA 2nd/2014 08/08/14 E10900 Water pCi/L 51 3.62E+02 2.94E+02 1.23 Acceptable EZA 2nd/2014 08/08/14 E10900 E10900 Water Water pCi/L pCi/L Cesium-134 Cesium-137 1.69E+02 1.48E+02 1.88E+02 1.39E+02 0.90 1.06 Acceptable EZA 2nd/2014 08/08/14 EZA 2nd/2014 08/08/14 E10900 Water pCi/L Cobalt-58 1.34E+02 1.30E+02 1.03 Acceptable Manganese-EZA 2nd/2014 08/08/14 E10900 Water pCi/L 54 1.88E+02 1.80E+02 1.04 Acceptable EZA 2nd/2014 08/08/14 E10900 Water pCi/L Iron-59 1.29E+02 1.19E+02 1.09 Acceptable EZA 2nd/2014 08/08/14 E10900 Water pCi/L Zinc-65 3.29E+02 2.93E+02 1.12 Acceptable EZA 2nd/2014 08/08/14 E10900 Water pCi/L Cobalt-60 2.74E+02 2.60E+02 1.05 Acceptable EZA 3rd/2014 11/22/14 E10993 Cartridge pCi Iodine-131 9.47E+01 8.99E+01 1.05 Acceptable Strontium-EZA 3rd/2014 11/22/14 E10994 Milk pCi/L 89 9.73E+01 9.69E+01 1.00 Acceptable Strontium-EZA 3rd/2014 11/22/14 E10994 Milk pCi/L 90 1.31E+01 1.64E+01 0.80 Acceptable EZA 3rd/2014 11/22/14 E10995 Milk pCi/L Iodine-1 31 1.04E+02 9.76E+01 1.07 Acceptable EZA 3rd/2014 11/22/14 E10995 Milk pCViL Cerium-141 1.28E+02 1.26E+02 1.01 Acceptable Chromium-EZA 3rd/2014 11/22/14 E10995 Milk pCi/L 51 3.12E+02 2.88E+02 1.08 Acceptable EZA 3rd/2014 11/22/14 E10995 Milk pCi/L Cesium-134 1.51E+02 1.58E+02 0.96 Acceptable EZA 3rd/2014 11/22/14 E10995 Milk pCV/L Cesium-137 2.03E+02 1.93E+02 1.05 Acceptable EZA 3rd/2014 11/22/14 E10995 Milk pCi/L Cobalt-58 1.44E+02 1.43E+02 1.01 Acceptable Manganese-EZA 3rd/2014 11/22/14 E10995 Milk pCiL 54 1.49E+02 1.42E+02 1.05 Acceptable EZA 3rd/2014 11/22/14 E10995 Milk pCi/L Iron-59 1.82E+02 1.58E+02 1.15 Acceptable EZA 3rd/2014 11/22/14 E10995 Milk pCi/L Zinc-65 7.41E+01 7.30E+01 1.01 Acceptable EZA 3rd/2014 11/22/14 E10995 Milk pCi/L Cobalt-60 3.14E+02 2.94E+02 1.06 Acceptable EZA 3rd/2014 11/22/14 E10996 Water pCi/L Iodine-131 1.02E+02 9.88E+01 103 Acceptable EZA 3rd/2014 11/22/14 E10996 Water pCi/L Cerium-141 1.30E+02 1.25E+02 104 Acceptable Chromium-EZA 3rd/2014 11/22/14 E10996 Water pCi/L 51 2.75E+02 2.86E+02 0.96 Acceptable EZA 3rd/2014 11/22/14 E10996 Water pCi/L Cesium-134 1.45E+02 1.56E+02 0.93 Acceptable EZA 3rd/2014 11/22/14 E10996 Water pCi/L Cesium-137 1.94E+02 1.92E+02 1.01 Acceptable EZA 3rd/2014 11/22/14 E10996 Water pCi/L Cobalt-58 1.43E+02 1.42E+02 1.01 Acceptable Manganese-EZA 3rd/2014 11/22/14 E10996 Water pCi/L 54 1.46E+02 1.41E+02 1.04 Acceptable EZA 3rd/2014 11/22/14 E10996 Water pCi/L Iron-59 1.66E+02 1.57E+02 1.06 Acceptable EZA 3rd/2014 11/22/14 E10996 Water pCi/L Zinc-65 7.55E+01 7.24E+01 1.04 Acceptable EZA 3rd/2014 11/22/14 E10996 Water pCi/L Cobalt-60 3.09E+02 2.95E+02 1.05 Acceptable

MLaboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 31 of 64 TABLE 3 2014 DEPARTMENT OF ENERGY MIXED ANALYTE PERFORMANCE EVALUATION PROGRAM (MAPEP) RESULTS

,_-I MAPEP 2nd/2014 1 06/05/14 1 GrF30 Filter Bq/sample Gross Alpha 1 1.980 1.77 0.53-3.01 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 GrF30 Filter Bg/sample Gross Beta 0.823 0.77 0.39-1.16 Acceptable MAPEP Americium-MAPEP 2nd/2014 06/05/14 MaS30 Soil Bq/kg 241 65 68 47.6-88.4 Acceptable MAPEP False Pos MAPEP 2nd/2014 06/05/14 MaS30 Soil Bo/kg Cesium-134 5.44 0 Test Acceptable MAPEP MAPEP 2nd/2014 06/05/14 MaS30 Soil Bq/kg Cesium-137 1270 1238 867-1609 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 MaS30 Soil Bq/kg Cobalt-57 947 966 676-1256 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 MaS30 Soil Bl/kl Cobalt-60 0.581 1.220 Sens. Eval. Acceptable MAPEP MAPEP 2nd/2014 06/05/14 MaS30 Soil Bq/kg Iron-55 580 643 444-824 Acceptable MAPEP Manganese-MAPEP 2nd/2014 06/05/14 MaS30 Soil Bq/kg 54 1470 1430 1001-1859 Acceptable MAPEP False Pos MAPEP 2nd/2014 06/05/14 MaS30 Soil Ba/kg Nickel-63 6.95 0 Test Acceptable MAPEP Plutonium-MAPEP 2nd/2014 06/05/14 MaS30 Soil Bq/kg 238 89.7 96.0 67-125 Acceptable MAPEP Plutonium-MAPEP 2nd/2014 06/05/14 MaS30 Soil Be/kg 239/240 69.80 76.8 53.8-99.8 Acceptable MAPEP Potassium-MAPEP 2nd/2014 06/05/14 MaS30 Soil Bg/kg 40 703 622 435-809 Acceptable MAPEP Strontium- False Pos MAPEP 2nd/2014 06/05/14 MaS30 Soil Bq/kg 90 1.48 0 Test Acceptable MAPEP Technetium- False Pos MAPEP 2nd/2014 06/05/14 MaS30 Soil Bq/kg 99 37.1 0 Test Acceptable MAPEP Not MAPEP 2nd/2014 06/05/14 MaS30 Soil Ba/ko U-234/233 30.5 81.0 57-105 Accept.

MAPEP Uranium- Not MAPEP 2nd/2014 06/05/14 MaS30 Soil Bq/kg 238 35 83 58-108 Accept.

MAPEP MAPEP 2nd/2014 06/05/14 MaS30 Soil Bq/kg Zinc-65 766 695 487-904 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 MaW30 Water BI/L Am-241 0.759 0.720 0.504-0.936 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L Cesium-134 21.4 23.1 16.2-30.0 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L Cesium-137 29.70 28.9 20.2-37.6 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L Cobalt-57 28.0 27.5 19.3-35.8 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L Cobalt-60 16.6 16.0 11.2-20.8 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L Hydrogen-3 308 321 225-417 Acceptable MAPEP False Pos MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L tron-55 0.3 0.0 Test Acceptable MAPEP Manganese-MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L 54 14.4 13.9 9.7-18.1 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L Nickel-63 31.4 34.0 23.8-44.2 Acceptable MAPEP Plutonium-MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L 238 0.764 0.828 0.580-1.076 Acceptable

[M Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 32 of 64 MAPEP 2nd/2014 1 06/05/14 1 MaW30 Water Bq/L Pu-239/240 0.6590 0.6760 0.473-0.879 Acceptable MAPEP Potassium- False Pos MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L 40 0.460 0 Test Acceptable MAPEP Strontium-MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L 90 8.32 8.51 5.96-11.06 Acceptable MAPEP Technetium-MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L 99 9.5 10.3 7.2-13.4 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L U-234/233 0.210 0.225 0.158-0.293 Acceptable MAPEP Uranium-MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L 238 1.41 1.45 1.02-1.89 Acceptable MAPEP False Pos MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L Zinc-65 -0.126 0.0 Test Acceptable MAPEP MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L Gross Alpha 0.96 0.85 0.255-1.443 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L Gross Beta 4.7 4.2 2.10-6.29 Acceptable MAPEP False Pos MAPEP 2nd/2014 06/05/14 MaW30 Water Bq/L Iodine-129 0.0227 0.00 Test Acceptable MAPEP Uranium-MAPEP 2nd/2014 06/05/14 RdF30 Filter ug/sample 235 0.018 0.020 0.014-0.026 Acceptable MAPEP Uranium-MAPEP 2nd/2014 06/05/14 RdF30 Filter ug/sample 238 8.77 10.4 7.3-13.5 Acceptable MAPEP Uranium-MAPEP 2nd/2014 06/05/14 RdF30 Filter ug/sample Total 8.80 10.4 7.3-13.5 Acceptable MAPEP Americium-MAPEP 2nd/2014 06/05/14 RdF30 Filter ug/sample 241 0.086 0.090 0.063-0.117 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 RdF30 Filter Bq/sample Cesium-134 1.85 1.91 1.34-2.48 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 RdF30 Filter Bq/sample Cesium-137 1.81 1.76 1.23-2.29 Acceptable MAPEP False Pos MAPEP 2nd/2014 06/05/14 RdF30 Filter Bq/sample Cobalt-57 0.0757 0.00 Test Acceptable MAPEP MAPEP 2nd/2014 06/05/14 RdF30 Filter Bq/sample Cobalt-60 1.490 1.39 0.97-1.81 Acceptable MAPEP Manganese- False Pos MAPEP 2nd/2014 06/05/14 RdF30 Filter Bq/sample 54 0.0138 0.00 Test Acceptable MAPEP Plutonium-MAPEP 2nd/2014 06/05/14 RdF30 Filter Bq/sample 238 0.000819 0.00090 Sens. Eval. Acceptable MAPEP 0.054-MAPEP 2nd/2014 06/05/14 RdF30 Filter Bq/sample Pu-239/240 0.071 0.7720 0.1004 Acceptable MAPEP Strontium-MAPEP 2nd/2014 06/05/14 RdF30 Filter Bq/sample 90 1.19 1.18 0.83-1.53 Acceptable MAPEP 0.0137-MAPEP 2nd/2014 06/05/14 RdF30 Filter Bq/sample U-234/233 0.0159 0.0195 0.0254 Acceptable MAPEP Uranium-MAPEP 2nd/2014 06/05/14 RdF30 Filter Bq/sample 238 0.118 0.129 0.090-0.168 Acceptable MAPEP False Pos MAPEP 2nd/2014 06/05/14 RdF30 Filter Bq/sample Zinc-65 0.246 0.00 Test Acceptable MAPEP MAPEP 2nd/2014 06/05/14 RdF30 Filter Bq/sample Gross Alpha 1.980 1.77 0.53-3.01 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 RdF30 Filter Bq/sample Gross Beta 0.83 0.77 0.39-1.16 Acceptable MAPEP Americium-MAPEP 2nd/2014 06/05/14 RdF30 Filter Bq/sample 241 0.106 0.104 0.073-0.135 Acceptable MAPEP Uranium- 0.0188- Not MAPEP 2nd/2014 06/05/14 RdV30 Vegetation ug/sample 235 0.261 0.0268 0.0348 Accept.

MAPEP Uranium-MAPEP 2nd/2014 06/05/14 RdV30 Vegetation ug/sample 238 12.7 13.3 9.3-17.3 Acceptable MAPEP Uranium-MAPEP 2nd/2014 06/05/14 RdV30 Vegetation ug/sample Total 12.7 13.3 9.3-17.3 Acceptable MAPEP Americium-MAPEP 2nd/2014 06/05/14 RdV30 Vegetation ug/sample 241 0.1100 0.108 0.076-0.140 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 33 of 64 I MAPEP 2nd/2014 06/05/14 KdV3U Vegetation I Bq/sample Cesium-134 5.65 6.04 4.23-7.85 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 RdV30 Vegetation Bq/sample Cesium-137 4.98 4.74 3.32-6.16 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 RdV30 Vegetation Bg/sample Cobalt-57 11.1 10.1 7.1-13.1 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 RdV30 Vegetation Bq/sample Cobalt-60 7.21 6.93 4.85-9.01 Acceptable MAPEP Manganese-MAPEP 2nd/2014 06/05/14 RdV30 Vegetation Bq/sample 54 9.24 8.62 6.03-11.21 Acceptable MAPEP Plutonium-MAPEP 2nd/2014 06/05/14 RdV30 Vegetation Bg/sample 238 0.116 0.121 0.085-0.157 Acceptable MAPEP 0.108-MAPEP 2nd/2014 06/05/14 RdV30 Vegetation Bq/sample Pu-239/240 0.134 0.154 0.0200 Acceptable MAPEP Strontium-MAPEP 2nd/2014 06/05/14 RdV30 Vegetation Bg/sample 90 1.580 1.46 1.02-1.90 Acceptable MAPEP 0.0177-MAPEP 2nd/2014 06/05/14 RdV30 Vegetation Bg/sample U-234/233 0.2640 0.2530 0.0329 Acceptable MAPEP Uranium-MAPEP 2nd/2014 06/05/14 RdV30 Vegetation Bq/sample 238 0.174 0.165 0.116-0.215 Acceptable MAPEP MAPEP 2nd/2014 06/05/14 RdV30 Vegetation Bq/sample Zinc-65 8.87 7.00 4.38-8.13 Acceptable MAPEP MAPEP 4th /2014 01/09/15 GrF31 Filter Bg/sample Gross Alpha 0.433 0.530 0.16-0.09 Acceptable MAPEP MAPEP 4th /2014 01/09/15 GrF31 Filter Bq/sample Gross Beta 1.060 1.060 0.53-1.59 Acceptable MAPEP Americium-MAPEP 4th /2014 01/09/15 MaS31 Soil Bq/Kg 241 88.4 85.5 59.9-111.2 Acceptable MAPEP MAPEP 4th /2014 01/09/15 MaS31 Soil Bq/Kg Cesium-134 588 622 435-809 Acceptable MAPEP False Pos MAPEP 4th /2014 01/09/15 MaS31 Soil Bq/Kg Cesium-137 1.67 Test Acceptable MAPEP MAPEP 4th/2014 01/09/15 MaS31 Soil Ba/Kg Cobalt-57 1160 1116 781-1451 Acceptable MAPEP MAPEP 4th /2014 01/09/15 MaS31 Soil Bq/Kg Cobalt-60 821 779 545-1013 Acceptable MAPEP MAPEP 4th /2014 01/09/15 MaS31 Soil BQ/Kg Iron-55 796 680 476-884 Acceptable MAPEP Manganese-MAPEP 4th /2014 01/09/15 MaS31 Soil Ba/Kg 54 1060 1009 706-1312 Acceptable MAPEP MAPEP 4th /2014 01/09/15 MaS31 Soil Bg/Kg Nickel-63 924 980 686-1274 Acceptable MAPEP Plutonium-MAPEP 4th /2014 01/09/15 MaS31 Soil Bq/Kg 238 0.92 0.48 Sens. Eval. Acceptable MAPEP Plutonium-MAPEP 4th /2014 01/09/15 MaS31 Soil Bg/Ko 239/240 61.5 58.6 41.0-76.2 Acceptable MAPEP Potassium-MAPEP 4th /2014 01/09/15 MaS31 Soil Bq/Kg 40 879 824 577-1071 Acceptable MAPEP Strontium-MAPEP 4th /2014 01/09/15 MaS31 Soil Bq/Kg 90 891 858 601-1115 Acceptable MAPEP Technetium-MAPEP 4th /2014 01/09/15 MaS31 Soil Bg/Kg 99 466 589 412-766 Acceptable MAPEP MAPEP 4th /2014 01/09115 MaS31 Soil Bq/Kq U-234/233 905 89 62-116 Acceptable MAPEP Uranium-MAPEP 4th /2014 01/09/15 MaS31 Soil Bq/Kg 238 257 259 181-337 Acceptable MAPEP MAPEP 4th /2014 01/09/15 MaS31 Soil Bg/Kg Zinc-65 605.0 541 379-703 Acceptable MAPEP Americium-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L 241 0.915 0.880 0.62-1.14 Acceptable MAPEP False Pos MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L Cesium-134 -0.06 Test Acceptable MAPEP MAPEP 4th /2014 01/09/15 MaW31 Water Bg/L Cesium-137 18.4 18.4 12.9-23.9 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 34 of 64 MAPLP MAPEP 4th /2014 01109/15 1MAW31 Water Ba/L Cobalt-57 25 24.7 17.3-32.1 Acceptable MAPEP MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L Cobalt-60 12.5 12.4 8.7-16.1 Acceptable MAPEP MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L Hydrogen-3 216 208 146-270 Acceptable MAPEP MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L Iron-55 34.0 31.5 22.1-41.0 Acceptable MAPEP Manganese-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L 54 14.2 14.0 9.8-18.2 Acceptable MAPEP MAPEP 4th /2014 01/09/15 MaW31 Water Bcq/L Nickel-63 23.6 24.6 17.2-32.0 Acceptable MAPEP Plutonium-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L 238 0.547 0.618 0.433-0.803 Acceptable MAPEP Plutonium-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L 239/240 0.015 0.005 Sens. Eval. Acceptable MAPEP Potassium-MAPEP 4th /2014 01/09/15 MaW31 Water BI/L 40 174 161 113-209 Acceptable MAPEP Strontium- False Pos MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L 90 0.03 Test Acceptable MAPEP Technetium-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L 99 6.92 6.99 4.89-9.09 Acceptable MAPEP Uranium-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L 234/233 0.206 0.205 0.144-0.267 Acceptable MAPEP Uranium-MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L 238 1.280 1.420 0.99-1.85 Acceptable MAPEP MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L Zinc-65 11.900 10.90 7.6-14.2 Acceptable MAPEP MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L Gross Alpha 0.793 0.701 0.201-1.192 Acceptable MAPEP MAPEP 4th /2014 01/09/15 MaW31 Water Bq/L Gross Beta 6.220 5.94 2.97-8.91 Acceptable MAPEP Uranium- 0.0278-MAPEP 4th /2014 01/09/15 RdF31 Filter ug/sample 235 0.040 0.040 0.0516 Acceptable MAPEP Uranium-MAPEP 4th /2014 01/09/15 RdF31 Filter ug/sample 238 19.3 20.3 14.2-26.4 Acceptable MAPEP Uranium-MAPEP 4th /2014 01/09/15 RdF31 Filter ug/sample Total 19.00 20.4 14.3-26.5 Acceptable MAPEP Americium- 0.0472-MAPEP 4th /2014 01/09/15 RdF31 Filter ug/sample 241 0.0561 0.067 0.0876 Acceptable MAPEP MAPEP 4th /2014 01/09/15 RdF31 Filter Bq/sample Cesium-1 34 0.8640 0.96 0.67-1.25 Acceptable MAPEP MAPEP 4th /2014 01/09/15 RdF31 Filter Bq/sample Cesium-137 1.190 1.20 0.84-1.56 Acceptable MAPEP MAPEP 4th /2014 01/09/15 RdF31 Filter Bq/sample Cobalt-57 1.540 1.43 1.00-1.86 Acceptable MAPEP MAPEP 4th /2014 01/09/15 RdF31 Filter Bq/sample Cobalt-60 1.200 1.10 0.77-1.43 Acceptable MAPEP Manganese-MAPEP 4th /2014 01/09/15 RdF31 Filter Bq/sample 54 0.808 0.75 0.53-0.98 Acceptable MAPEP Plutonium-MAPEP 4th /2014 01/09/15 RdF31 Filter Bq/sample 238 0.115 0.107 0.075-0.139 Acceptable MAPEP Plutonium- 0.0328-MAPEP 4th /2014 01/09/15 RdF31 Filter Bq/sample 239/240 0.048 0.0468 0.0608 Acceptable MAPEP Strontium-MAPEP 4th /2014 01/09/15 RdF31 Filter Bq/sample 90 0.762 0.70 0.492-0.914 Acceptable MAPEP Uranium- 0.0251-MAPEP 4th /2014 01/09/15 RdF31 Filter Bq/sample 234/233 0.037 0.0358 0.0465 Acceptable MAPEP Uranium-MAPEP 4th /2014 01/09/15 RdF31 Filter Bq/sample 238 0,227 0.253 0.177-0.329 Acceptable MAPEP MAPEP 4th /2014 01/09/15 RdF31 Filter Bq/sample Zinc-65 0.779 0.76 0.53-0.99 Acceptable MAPEP Americium-MAPEP 4th /2014 01/09/15 RdV31 Vegetation Bq/sample 241 0.226 0.19 0.135-0.251 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 35 of 64 MAPEP 4th /2014 01/09/15 1 RdV31 Vegetation Bq/sample Cesium-134 4.750 5.20 3.64-6.67 Acceptable MAPEP MAPEP 4th /2014 01/09/15 RdV31 Vegetation Bq/sample Cesium-137 6.910 6.60 4.62-8.58 Acceptable MAPEP False Pos MAPEP 4th /2014 01/09/15 RdV31 Vegetation Bg/sample Cobalt-57 -0.002 0.00 Test Acceptable MAPEP False Pos MAPEP 4th /2014 01/09/15 RdV31 Vegetation Bq/sample Cobalt-60 0.008 0.00 Test Acceptable MAPEP Manganese-MAPEP 4th /2014 01/09/15 RdV31 Vegetation Bq/sample 54 7.980 7.88 5.52-10.24 Acceptable MAPEP Plutonium-MAPEP 4th /2014 01/09/15 RdV31 Vegetation Bq/sample 238 0.001 0.001 Sens. Eval. Acceptable MAPEP Plutonium-MAPEP 4th /2014 01/09/15 RdV31 Vegetation Bq/sample 239/240 0.1510 0.171 0.120-0.222 Acceptable MAPEP Strontium-MAPEP 4th /2014 01/09115 RdV31 Vegetation Bq/sample 90 2.330 2.32 1.62-3.02 Acceptable MAPEP Uranium- 0.0326-MAPEP 4th /2014 01/09/15 RdV31 Vegetation Ba/sample 234/233 0.046 0.047 0.0606 Acceptable MAPEP Uranium-MAPEP 4th /2014 01/09/15 RdV31 Vegetation Bq/sample 238 0.332 0.324 0.227-0.421 Acceptable MAPEP MAPEP 4th /2014 01/09/15 RdV31 Vegetation Bq/sample Zinc-65 2.850 2.63 1.84-3.42 Acceptable MAPEP Strontium-MAPEP 4th /2014 01/09/15 SrF-31 Filter Bq/sample 89 3.62 3.79 2.65-4.93 Acceptable MAPEP Strontium-MAPEP 4th /2014 01/09/15 SrF-31 Filter Bq/sample 90 3.62 3.79 2.65-4.93 Acceptable MAPEP MAPEP 4th /2014 01/09/15 XaW-31 Water Bq/L Iodine-129 4.56 4.55 3.19-5.92 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 36 of 64 TABLE 4 2014 ERA PROGRAM PERFORMANCE EVALUATION RESULTS ERA 2014 02/24/14 96 Water I pCi/L Barium-133 80.6 76.2 63.8-83.8 1 Acceptable 1st / RAD -

ERA 2014 02/24/14 96 Water pCi/L Cesium-134 64.7 66.8 54.4-73.5 Acceptable 1st / RAD -

ERA 2014 02/24/14 96 Water pCi/L Cesium-137 112.0 109 98.1-122 Acceptable 1st/ RAD-ERA 2014 02/24/14 96 Water pCi/L Cobalt-60 95.0 88.7 79.8-99.9 Acceptable 1st / RAD-ERA 2014 02/24/14 96 Water pCi/L Zinc-65 200 185 166-218 Acceptable 1st / RAD-ERA 2014 02/24/14 96 Water pCi/L Gross Alpha 34.8 36.1 18.6-46.4 Acceptable 1st / RAD-ERA 2014 02/24/14 96 Water pCi/L Gross Beta 19.6 22.3 13.5-30.4 Acceptable 1st / RAD -

ERA 2014 02/24/14 96 Water pCi/L Gross Alpha 34.6 36.1 18.6-46.4 Acceptable 1st / RAD -

ERA 2014 02/24/14 96 Water pCi/L Radium-226 16.2 16.8 12.5-19.2 Acceptable 1st / RAD-ERA 2014 02/24/14 96 Water pCi/L Radium-228 4.62 5.04 3.01-6.67 Acceptable 1st / RAD-ERA 2014 02/24/14 96 Water pCL Uranium (Nat) 7.39 7.23 5.51-8.53 Acceptable 1st / RAD - Uranium (Nat)

ERA 2014 02/24/14 96 Water ug/L mass 11.00 10.6 8.07-12.5 Acceptable 1st / RAD-ERA 2014 02/24/14 96 Water pCi/L Radium-226 15.10 16.8 12.5-19.2 Acceptable 1st / RAD -

ERA 2014 02/24/14 96 Water pCi/L Radium-228 4.66 5.04 3.01-6.67 Acceptable 1st / RAD -

ERA 2014 02/24/14 96 Water pCi/L Uranium (Nat) 7.47 7.23 5.51-8.53 Acceptable 1st / RAD - Uranium (Nat)

ERA 2014 02/24/14 96 Water ug/L mass 11.4 10.6 8.07-12.5 Acceptable 1st / RAD -

ERA 2014 02/24/14 96 Water pCi/L Tritium 3320 3580 3030-3950 Acceptable 1st / RAD -

ERA 2014 02/24/14 96 Water pCi/L Strontium-89 44.1 44.4 34.4-51.6 Acceptable 1st / RAD -

ERA 2014 02/24/14 96 Water pCi/L Strontium-90 34.2 30.3 22.1-35.2 Acceptable 1st / RAD -

ERA 2014 02/24/14 96 Water pCi/L Strontium-89 38.9 44.4 34.4-51.6 Acceptable 1st / RAD -

ERA 2014 02/24/14 96 Water pCi/L Strontium-90 27.1 30.3 22.1-35.2 Acceptable 1st /

ERA 2014 02/06/14 01 1014L Water pCi/L Strontium-89 42.3 38.7 29.3-45.7 Acceptable 1st /

ERA 2014 02/06/14 01 1014L Water pCi/L Strontium-89 42.2 38.7 29.3-45.7 Acceptable 1st / RAD -

ERA 2014 02/24/14 96 Water pCi/L Iodine-131 25.2 24.4 20.2-28.9 Acceptable 1st / RAD -

ERA 2014 02/24/14 96 Water pCi/L Iodine-1 31 22.4 24.4 20.2-28.9 Acceptable 3rd / RAD -

ERA 2014 08/25/14 98 Water pCi/L Barium-133 67.8 68.7 57.3-75.6 Acceptable 3rd / RAD -

ERA 2014 08/25/14 98 Water pCi/L Cesium-134 71 72.3 59.0-79.5 Acceptable 3rd / RAD -

ERA 2014 08/25/14 98 Water pCi/L Cesium-137 161 163 147-181 Acceptable 3rd / RAD -

ERA 2014 08/25/14 98 Water pCi/L Cobalt-60 76.7 75.5 68.0-85.5 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 37 of 64 ERA alU 1 I Water I oCi/L Zinc-65 92 82 73.8-98.5 IAcnal 3rd RAD -

ERA 2014 08/25/14 98 Water pCi/L Gross Alpha 45.3 45.4 23.6-57.4 Acceptable 3rd RAD -

ERA 2014 08/25/14 98 Water pCi/L Gross Beta 32.3 33.4 21.7-41.1 Acceptable 3rd RAD -

ERA 2014 08/25/14 98 Water pCi/L Gross Alpha 48.6 45.4 23.6-57.4 Acceptable 3rd / RAD -

ERA 2014 08/25/14 98 Water pCi/L Radium-226 8.26 9.06 6.80-10.6 Acceptable 3rd / RAD -

ERA 2014 08/25/14 98 Water pCi/L Radium-226 8.54 9.06 6.80-10.6 Acceptable 3rd / RAD -

ERA 2014 08/25/14 98 Water pCiL Radium-226 9.7 9.06 6.80-10.6 Aeble 3rd / RAD -

ERA 2014 08/25/14 98 Water pCi/L Radium-228 5.07 5.07 3.03-6.79 Acceptable 3rd / RAD -

ERA 2014 08/25/14 98 Water pCiL Radium-228 5.74 5.07 3.03-6.79 Acceptable 3rd / RAD -

ERA 2014 08/25/14 98 Water pCi/L Uranium (Nat) 13.9 13.5 10.7-15.4 Acceptable 3rd / RAD - Uranium (Nat)

ERA 2014 08/25/14 98 Water ua/L mass 22.25 19.8 15.6-22.6 Acceptable 3rd / RAD -

ERA 2014 08/25/14 98 Water pCi/L Uranium (Nat) 13 13.5 10.7-15.4 Acceptable 3rd / RAD - Uranium (Nat)

ERA 2014 08/25/14 98 Water ug/L mass 20.7 19.8 15.6-22.6 Acceptable 3rd / RAD -

ERA 2014 08/25114 98 Water pCi/L Tritium 10200 11200 9750-12300 Acceptable 3rd / RAD -

ERA 2014 08/25/14 98 Water pCi/L Tritium 10400 11200 9750-12300 Acceptable 3rd / RAD - Not ERA 2014 08/25/14 98 Water pCi/L Strontium-89 56.3 42.7 32.9-49.8 Acceptable 3rd / RAD -

ERA 2014 08/25/14 98 Water pCi/L Strontium-90 14.3 31.7 23.1-36.7 Acceptable 3rd / RAD - Not ERA 2014 08/25/14 98 Water pCi/L Strontium-89 56.5 42.7 32.9-49.8 Acceptable 3rd / RAD -

ERA 2014 08/25/14 98 Water pCiL Strontium-90 26 31.7 23.1-36.7 Acceptable 3rd / RAD -

ERA 2014 08/25/14 98 Water pCi/L Iodine-131 28.6 26.1 21.7-30.8 Acceptable 3rd / RAD -

ERA 2014 08/25/14 98 Water pCi/L Iodine-131 22.3 26.1 21.7-30.8 Acceptable

MLaboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 38 of 64 TABLE 5 2014 ERA PROGRAM (MRAD) PERFORMANCE EVALUATION RESULTS ERA 2nd/2014 1 05/16/14 1 20 Soil pCVkg Actinium-228 1140 1 1240 1 795-1720 1 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Americium-241 418 399 233-518 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Bismuth-212 976 1240 330-1820 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Bismuth-214 2290 1960 1180-2820 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Cesium-134 3080 3390 2220-4070 Acceptable MRAD- 6510-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Cesium-137 8310 8490 10900 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Cobalt-60 6570 6830 4620-9400 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Lead-212 1330 1240 812-1730 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Lead-214 2800 2070 1210-3090 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Manganese-54 <44.3 <1000 0-1000 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCVkg Plutonium-238 579 578 348-797 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Plutonium-239 488 471.00 308-651 Acceptable MRAD- 7660-ERA 2nd/2014 05/16/14 20 Soil pCVkg Potassium-40 10500 10500 14100 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Strontium-90 2500 2780 1060-4390 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Thorium-234 3420 3360 1060-6320 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Zinc-65 5700 5400 4300-7180 Acceptable MRAD- 3250-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Strontium-90 6730 8530 13500 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Uranium-234 2602 3390 2070-4350 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Uranium-238 2425 3360 2080-4260 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCikg Uranium-Total 5027 6910 3750-9120 Acceptable MRAD- 5570-ERA 2nd/2014 05/16/14 20 Soil ug/kg Uranium-Totaffmass) 7110 10100 12700 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Uranium-234 3440 3390 2070-4350 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Uranium-238 3680 3360 2080-4260 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Uranium-Total 7310 6910 3750-9120 Acceptable MRAD- 5570-ERA 2nd/2014 05/16/14 20 Soil ug/kg Uranium-Total(mass) 11000 10100 12700 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Uranium-234 3740 3390 2070-4350 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Uranium-238 3780 3360 2080-4260 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Soil pCi/kg Uranium-Total 7683 6910 3750-9120 Acceptable MRAD- 5570-ERA 2nd/2014 05/16/14 20 Soil ug/kg Uranium-Total(mass) 11300 10100 12700 Acceptable

i Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 39 of 64 I 9nd19A IA I Rnil I m~km 11 9flfl lnlnn I *Tflf Arrpnt~hI~

MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Am-241 1670 1490 911-1980 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Cesium-134 657 646 415-839 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Cesium-137 861 880 638-1220 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Cobalt-60 997 926 639-1290 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Curium-244 514 516 253-804 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Manganese-54 <62.2 <300 0.00-300 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Plutonium-238 2230 2110 1260-2890 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Plutonium-239 3810 3740 2300-5150 Acceptable MRAD- 23000-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Potassium-40 30800 31900 44800 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Strontium-90 2330 2580 1470-3420 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Uranium-234 1920 1760 1160-2260 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Uranium-238 1970 1750 1170-2220 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Uranium-Total 4025 3580 2430-4460 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation ug/kg Uranium-Totaitmass) 5920 5240 3510-6650 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Zinc-65 1030 919 663-1290 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Uranium-234 1730 1760 1160-2260 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Uranium-238 2000 1750 1170-2220 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation pCi/kg Uranium-Total 3817 3580 2430-4460 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation ug/kg Uranium-Total(mass) 5990 5240 3510-6650 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Vegetation ug/kg Uranium-Total(mass) 5620 5240 3510-6650 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Americium-241 60.2 59.7 36.8-80.8 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Cesium-134 920 1010 643-1250 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Cesium-137 816 828 622-1090 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Cobalt-60 1130 1120 867-1400 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Iron-55 254 240 74.4-469 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Manganese-54 <6.64 <50.0 0-50.0 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Plutonium-238 51.3 56.3 38.6-74.0 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Plutonium-239 47.5 48.6 35.2-63.5 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Strontium-90 76.7 78.9 38.6-118 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Uranium-234 33.8 36.4 22.6-54 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Uranium-238 34.5 36.1 23.3-49.9 Acceptable

i Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 40 of 64 ERA 2nd/2014 1 05/16/14 1 20 Filter pCi/Filter Uranium-Total 70.3 1 74.3 1 41.1-113 1 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter ug/Filter Uranium-Total(mass) 104 108 69.1-152 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Zinc-65 737 667 478-921 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Uranium-234 35.5 36.4 22.6-54 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Uranium-238 35.3 36.1 23.3-49.9 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Uranium-Total 72.4 74.3 41.1-113 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter ug/Filter Uranium-Total(mass) 105 108 69.1-152 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter ug/Filter Uranium-Total(mass) 100 108 69.1-152 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Gross Alpha 60.9 46 15.4-71.4 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Filter pCi/Filter Gross Beta 58.9 53.8 34.0-78.4 Acceptable MRAD- Not ERA 2nd/2014 05/16/14 20 Water pCi/L Americium-241 186 114 76.8-153 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Cesium-134 1540 1660 1220-1910 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Cesium-137 2760 2690 2280-3220 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Cobalt-60 1320 1270 1100-1490 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Iron-55 1230 1200 716-1630 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCiL Manganese-54 <7.54 <100 0.00-100 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Plutonium-238 37 44 32.6-54.9 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Plutonium-239 124 160 124-202 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Strontium-90 95 890 580-1180 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Uranium-234 77.8 82.4 61.9-106 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Uranium-238 50.8 48.4 36.9-59.4 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Uranium-Total 156 168 123-217 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water ug/L Uranium-Total(mass) 233 245 195-296 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Zinc-65 2030 1800 1500-2270 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pC/L Uranium-234 82.1 82.4 61.9-106 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Uranium-238 84.6 48.4 36.9-59.4 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCVL Uranium-Total 170 168 123-217 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water ug/L Uranium-Totaltmass) 253 245 195-296 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Uranium-234 80.5 82.4 61.9-106 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Uranium-238 90.0 48.4 36.9-59.4 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Uranium-Total 175 168 123-217 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water ug/L Uranium-Total(mass) 269 245 195-296 Acceptable

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 41 of 64 MRAI ERA 2nd/2014 05/16/14 20 Water DCi/L Uranium-234 77.8 82.4 61.9-106 Accentable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Uranium-238 78.3 48.4 36.9-59.4 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCVL Uranium-Total 156 168 123-217 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water ug/L Uranium-Totaltmass) 233 245 195-296 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water ug/L Uranium-Totalrmass) 232 245 195-296 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Gross Alpha 141.0 133 47.2-206 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Gross Beta 172 174.0 99.6-258 Acceptable MRAD-ERA 2nd/2014 05/16/14 20 Water pCi/L Tritium 5280 5580 3740-7960 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Actinium-228 1280 1240 795-1720 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Americium-241 825 763 431-956 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Bismuth-212 1620 1240 330-1820 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Bismuth-214 2900 2810 1690-4040 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Cesium-134 1960 2140 1400-2570 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Cesium-137 6760 6550 5020-8430 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Cobalt-60 4480 4260 2880-5860 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCikg Lead-212 1260 1240 812-1730 table 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Lead-214 3480 2750 1610-4100 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Manganese-54 <30.0 <1000 0-1000 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Plutonium-238 732 739 444-1020 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Plutonium-239 281 309 202-427 Acceptable 3rd / MRAD- 7810-ERA 2014 11/25/14 21 Soil pCi/kg Potassium-40 11500 10700 14400 Acceptable 3rd/ MRAD- 3210-ERA 2014 11/25/14 21 Soil pCi/kg Strontium-90 8790 8420 13300 Acceptable 3rd/ MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Thorium-234 2000 2350 743-4420 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Zinc-65 3910 3270 2600-4350 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Uranium-234 2280 2370 1450-3040 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Uranium-238 2340 2350 1450-2980 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil pCi/kg Uranium-Total 4762 4540 2360-6390 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Soil ug/kg Uranium-Total(mass) 7020 7050 3890-8870 Acceptable 3rd / MRAD-ERA 2014 11125/14 21 Vegetation pCi/kg Am-241 2260 2290 1400-3505 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Cesium-134 837 849 545-1100 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Cesium-137 729 644 467-896 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Cobalt-60 818 784 541-1100 Acceptable

w:4 Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 42 of 64 3rd / M1H ERA 2014 11/25/14 21 Veoetation I DCUka Curium-244 361 1 367 180-572 1 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Manganese-54 <25.3 <300 0-300 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Plutonium-238 886 862 514-1180 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Plutonium-239 675 701 430-965 Acceptable 3rd / MRAD- 22300-ERA 2014 11/25/14 21 Vegetation pCi/kg Potassium-40 35300 30900 43400 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Strontium-90 1230 1710 975-2270 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Uranium-234 1980 1780 1170-2290 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Uranium-238 1970 1760 1170-2240 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCVkg Uranium-Total 4038 3620 2450-4510 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation ug/kg Uranium-Totallmass) 5910 5280 3540-6710 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Uranium-234 1670 1780 1170-2290 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Uranium-238 1800 1760 1170-2240 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Uranium-Total 3556 3620 2450-4510 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation ug/kg Uranium-Total(mass) 5390 5280 3540-6710 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation ug/kg Uranium-Totalmass) 5860 5280 3540-6710 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Vegetation pCi/kg Zinc-65 1930 1570 1130-2200 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Americium-241 41.4 38.6 23.8-52.2 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Cesium-134 742 765.0 487-949 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Cesium-137 677 647 486-850 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Cobalt-60 543 523 405-653 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Iron-55 117 120.0 37.2-234 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Manganese-54 <5.87 <50 0.00-50.0 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter ug/Filter Plutonium-238 32.9 35.7 24.5-46.9 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Plutonium-239 26.8 29.1 21.1-38.0 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Strontium-90 187 168 82.1-252 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Uranium-234 26 28 27.8-41.9 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Uranium-238 28 27.60 17.8-38.2 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Uranium-Total 56 57 31.4-86.3 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter ug/Filter Uranium-Totallmass) 82.6 82.7 52.9-116 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Zinc-65 629 547 392-755 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Uranium-234 28 28 27.8-41.9 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Uranium-238 25 27.60 17.8-38.2 Acceptable

10 Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 43 of 64 3rd I MRAU-ERA 2014 11/25/14 21 Filter DCi/Filter Uranium-Total 55 1 57 1 31.4-86.3 1 Acceptable 3rd/ MRAD-ERA 2014 11/25/14 21 Filter ug/Filter Uranium-Totallmass) 75.1 82.7 52.9-116 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter ug/Filter Uranium-Totallmass) 90.7 82.7 52.9-116 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Filter pCi/Filter Gross Alpha 47.4 36.9 12.4-57.3 Acceptable MRAD-3rd /

ERA 2014 11/25/14 21 Filter pCi/Filter Gross Beta 27.2 21.1 13.3-30.8 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Americium-241 72.4 68.6 46.2-92.0 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Cesium-134 816.0 850 624-977 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Cesium-137 1310 1240 1060-1490 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Cobalt-60 1130 1070 930-1250 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Iron-55 130 134 79.9-182 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Manganese-54 <6.34 <100 0.00-100 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Plutonium-238 35 33 24.6-41.4 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Plutonium-239 46.4 51 39.7-64.4 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Strontium-90 300 254 165-336 Acceptable 3rd/ MRAD-ERA 2014 11/25/14 21 Water pCi/L Uranium-234 42 44 32.9-56.5 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Uranium-238 50 43.50 33.2-53.4 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Uranium-Total 92 89 65.5-115 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water ug/L Uranium-Totallmass) 137 130 104-157 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Zinc-65 1070 921 768-1160 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Uranium-234 43 44 32.9-56.5 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Uranium-238 45 43.50 33.2-53.4 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Uranium-Total 90 89 65.5-115 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water ug/L Uranium-Total(mass) 134 130 104-157 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Uranium-234 49 44 32.9-56.5 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCiL Uranium-238 42 43.50 33.2-53.4 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Uranium-Total 93 89 65.5-115 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water ug/L Uranium-Total(mass) 126 130 104-157 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water ug/L Uranium-Total(mass) 144 130 104-157 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Gross Alpha 96.2 98 34.8-152 Acceptable 3rd / MRAD-ERA 2014 11/25/14 21 Water pCi/L Gross Beta 86.1 77.5 44.4-115 Acceptable ERA 3rd /

2014 11/25/14 MRAD-21 Water pCi/L Tritium 5490 5500 3680-7840 Acceptable

1 Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 44 of 64 FIGURE 1 COBALT-60 PERFORMANCE EVALUATION RESULTS AND % BIAS 2014 Cobalt-60 Performance Evaluation Results and % Bias 100.0 75.0 50.0 Co-60 25.0 IA Lower Control A! Limit 0.0

- - - - Upper Control Limit

-25.0

-50.0

-75.0

-100.0 January 2014- December 2014

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 45 of 64 FIGURE 2 CESIUM-137 PERFORMANCE EVALUATION RESULTS AND % BIAS 2014 Cesiumrr137 Performance Evaluation Results and % Bias 100.0 75.0 50.0 Cs-1 37 25.0 U) w - --- Lower Control ca e 0.0 Limit

---

Upper Control

-25.0 Limit

-50.0

-75.0

-100.0 January2014- December 2014

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 46 of 64 FIGURE 3 TRITIUM PERFORMANCE EVALUATION RESULTS AND % BIAS 2014 Tritium Performance Evaluation Results and % Bias 100.0 75.0 50.0 H-3 25.0

---

Lower Control 0.0 Limit J -.--.- Upper Control

-25.0 Limit

-50.0

-75.0

-100.0 January 2014- December 2014

! Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 47 of 64 FIGURE 4 STRONTIUM-90 PERFORMANCE EVALUATION RESULTS AND % BIAS 2014 Strontium-90 Performance Evaluation Results and % Bias 100.0 50.0 Strontium-90 I 0.0

- - Lower Control Limit

- - Upper Control Limit

-50.0

-100.0 January 2014- December 2014

I Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 48 of 64 FIGURE 5 GROSS ALPHA PERFORMANCE EVALUATION RESULTS AND % BIAS 2014 Gross Alpha Performance Evaluation Results and % Bias 100.0 50.0 Gross Alpha I 0.0

- -. Lower Control Limit

- - - - Upper Control Limit

-50.0 -

-100.0 January 2014- December 2014

i Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 49 of 64 FIGURE 6 GROSS BETA PERFORMANCE EVALUATION RESULTS AND % BIAS 2014 Gross Beta Performance Evaluation Results and % Bias 100.0 50.0

-.- Gross Beta UA

---

Lower Control 0.0 Limit

. Upper Control Limit

-50.0

-100.0 January 2014- December 2014

lLaboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 50 of 64 FIGURE 7 IODINE-131 PERFORMANCE EVALUATION RESULTS AND % BIAS 2014 lodine-1 31 Performance Evaluation Results and % Bias 100.0 75.0 50.0 Iodine-131 25.0 tA

- --- Lower Control 0.0 Limit

- --- Upper Control

-25.0 Limit

-50.0

-75.0

-100.0 January2014- December 2014

I Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 51 of 64 FIGURE 8 AMERICIUM-241 PERFORMANCE EVALUATION RESULTS AND % BIAS 2014 Americium-241 Performance Evaluation Results and % Bias 100.0 75.0 50.0

-.- Am-241 25.0 0R - Lower Control 0.0 Limit

- Upper Control

-25.0 Limit

-50.0

-75.0

-100.0 January 2014- December 2014

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 52 of 64 FIGURE 9 PLUTONIUM-238 PERFORMANCE EVALUATION RESULTS AND % BIAS 2014 Plutonium-238 Performance Evaluation Results and %Bias 100.0 75.0 50.0

- Plutonium-238 25.0 Ce Ul - -- - Lower Control 0.0 Limit

---

Upper Control

-25.0 Limit

-50.0

-75.0

-100.0 January 2014- December 2014

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 53 of 64 TABLE 6 REMP INTRA-LABORATORY DATA St Gas Flow Sr 2nd count 36 1 _0 1_36 1 0 Gas Flow Total Strontium 23 0 23 0 Gamma Spec Liquid RAD A-013 with Ba La 48 0 109 0 LSC Iron-55 3 0 _ 3 0 Gamma Spec Solid RAD A-013 30 0 43 0 LSC Nickel 63 3 0 3 0 Gas Flow Sr 2nd count 5 0 5 0 Gas Flow Total Strontium 5 0 5_0 Gamma Spec Solid RAD A-013 with Ba. La 2 0 8 0 Gamma-013 with Iodine 6 0 7 0 Gas Flow Sr 2nd Count 5 0 5 0 Gross A & B 429 0 429 0 Gas Flow Sr-90 1 0 1 0 SecFilter45 0 47 0 Alpha Spec Uranium 1 0 2 0 Tritium 206 0 205 0 Plutonium 1 0 1 0 LSC Iron-55 12 0 12 0 LSC Nickel 63 13 0 13 0 Gamma Spec Liquid RAD A-013 4 0 4 0 Alpha Spec Am243 6 0 6 0 Gamma Iodine-131 28 0 28 0 Alpha Spec Plutonium 10 0 10 0 Gas Flow Sr 2nd count 15 0 15 0 Alpha Spec Am241 Curium 8 0 8 0 Gas Flow Total Strontium 30 0 31 0 Gross Alpha Non Vol Beta 45 0 45 0 Gamma Spec Liquid RAD A-013 with Ba, La 84 0 159 0 Gamma Sec 40 0 40 0 Gamma Spec Solid RAD A-013 48 0 46 0 Gas Flow Sr 2nd count 8 0 8 0 Gas Flow Total Strontium 17 0 17 0 Gamma Spec Solid RAD A-013 with Ba, La 10 0 10 0

I Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 54 of 64 Gamma SDec Solid RAD A-013 with Iodine 23 0 22 0 LSC Iron-55 5 0 6 0 LSC Nickel 63 5 0 6 0 Gas Flow Total Strontium 6 0 6 0 Gross Alpha Non Vol Beta 6 0 6 0 Gamma Spec Liquid RAD A-013 with Iodine 7 0 11 0 Gas Flow Sr 2nd count 10 0 10 0 Gamma SecS 86 0 96 0 Gamma Iodine 131 RAD A-013 560 0 606 0 Carbon-14 (Ascarite/Soda Lime Filter per Lie)28 0 28 0 Tritium 39 0 40 0 LSC Iron-55 17 0 16 0 LSC Nickel 63 16 0 15 0 Gamma Iodine-131 27 0 26 0 Gas Flow Sr 2nd count 12 0 12 0 Gas Flow Total Strontium 19 0 18 0 Gross Alpha Non Vol Beta 72 0 73 0 0

Gamma Spec Liquid RAD A-013 with Ba, La 35 0 75 Total 2200 2456 Note 1: The RPD must be 20 percent or less, if both samples are greater than 5 times the MDC. If both results are less than 5 times MDC, then the RPD must be equal to or less than 100%. If one result is above the MDC and the other is below the MDC, then the RPD can be calculated using the MDC for the result of the one below the MDC. The RPD must be 100% or less. In the situation where both results are above the MDC but one result is greater than 5 times the MDC and the other is less than 5 times the MDC, the RPD must be less than or equal to 20%. If both results are below MDC, then the limits on % RPD are not applicable.

I Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 55 of 64 TABLE 7 ALL RADIOLOGICAL INTRA-LABORATORY DATA

SUMMARY

BIAS AND PRECISION BY MATRIX:

Gamma Iodine-129 0 0 1 0 Gamma Iodine-131 36 0 110 0 Gas Flow Sr 2nd count 36 0 36 0 Gas Flow Strontium 90 5 0 5 0 Gas Flow Total Strontium 23 0 23 0 Gamma Spec Liquid RAD A-013 with Ba, La 48 0 109 0 Gamma S ec Li uid RAD A-013 with Iodine 3 0 4 0 Gamma Percent Leach 5 0 0 0 Gas Flow Radium 228 16 0 20 0 Tritium 211 0 247 0 Tritium by Combustion 1 0 1 0 Carbon-14 130 0 181 0 LSC Iron-55 103 0 121 0 Alpha Spec Polonium Solid 52 0 54 0 Gamma Nickel 59 RAD A-022 99 0 117 0 LSC Chlorine-36 in Solids 4 0 4 0 Gamma Spec Ra226 RAD A-013 21 0 24 0 Gamma Spec Solid RAD A-013 649 0 812 0 LSC Nickel 63 141 0 154 0 LSC Plutonium 181 0 202 0 Technetium-99 224 0 250 0 Gamma Spec Liquid PAD A-013 2 0 2 0 ICP-MS Technetium-99 in Soil 61 0 60 0 LSC Selenium 79 11 0 11 0 Total Activity, 4 0 4 0 Tritium 16 0 17 0 Alpha Spec Am243 23 0 37 0 Gamma Iodine-129 100 0 120 0 Gas Flow Lead 210 6 0 6 0 Total Uranium KPA 7 0 10 0 Alpha Spec Uranium 214 0 309 0 LSC Promethium 147 2 0 2 0 LSC, Rapid Strontium 89 and 90 42 0 61 0 Alpha Spec Thorium 152 0 196 0 ICP-MS Uranium-233, 234 in Solid 49 0 47 0 Alpha Spec Plutonium 231 0 240 0 ICP-MS Technetium-99 Prep in Soil 62 0 61 0 Alpha Spec Neptunium 213 0 237 0 Alpha Spec Plutonium 158 0 206 0 Gamma Spec Solid with Ra226, Ra228 9 0 13 0

1 Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 56 of 64 Gas Flow Sr 2nd count 21 0 25 0 Gas Flow Strontium 90 195 0 201 0 Gas Flow Total Radium 2 0 3 0 Lucas Cell Radium 226 38 0 47 0 Total Activity Screen 9 0 10 0 Alpha Spec Am241 Curium 304 0 339 0 Alpha Spec Total Uranium 4 0 8 0 Gas Flow Total Strontium 43 0 46 0 Gross Alpha Non Vol Beta 1 0 1 0 ICP-MS Uranium-233, 234 Prep in Solid 49 0 48 0 ICP-MS Uranium-235, 236, 238 in Solid 60 0 81 0 Gamma Spec Solid RAD A-013 with Ba, La 2 0 8 0 Gamma Spec Solid PAD A-013 with Iodine 6 0 7 0 GFC Chlorine-36 in Solids 3 0 3 0 Gamma Spec Solid RAD A-013 (pCi/Sample) 2 0 2 0 Tritium 8 0 8 0 Alpha Spec Am241 (pCi/Sample) 2 0 2 0 ICP-MS Uranium-234, 235, 236, 238 in Solid 148 0 132 0 ICP-MS Uranium-235, 236, 238 Prep in Solid 50 0 49 0 Alpha Spec Thorium 1 0 1 0 Alpha Spec Uranium 1 0 1 0 Gross Alpha/Beta 235 0 316 3 Alpha Spec Neptunium 1 0 1 0 Gas Flow Sr 2nd count 2 0 1 0 Gross Alpha/Beta (Americium Calibration) Solid 2 0 3 0 ICP-MS Uranium-234 235 236 238 Pre in Solid 69 0 65 0 Alpha Spec Uranium 14 0 18 0 Alpha Spec Polonium 1 0 5 0 Gamma 1-131, filter 4 0 4 0 LSC Plutonium Filter 84 0 102 0 Tritium 76 0 112 0 Carbon-14 35 0 66 0 Nickel-63 0 0 8 0 LSC Iron-55 69 0 84 0 Gamma Nickel 59 PAD A-022 55 0 68 0 LSC Nickel 63 60 0 78 0 Technetium-99 51 0 75 0 Gamma Spec Filter PAD A-013 143 0 174 6 Alphaspec Np Filter per Liter 8 0 13 0 Alphaspec Pu Filter per Liter 11 0 22 0 Gamma Iodine-125 5 0 0 0 Gamma Iodine-129 46 0 60 0 Gross Alpha/Beta 5 0 5 0 Alpha Spec Am243 10 0 28 0 Gas Flow Lead 210 0 0 4 0 LSC Plutonium Filter per Liter 9 0 15 0 Total Uranium KPA 9 0 14 0

lc i Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 57 of 64 Aloha Snec Uranium 55 0 96 0 LSC Promethium 147 1 0 2 0 LSC, Rapid Strontium 89 and 90 72 0 94 0 Alpha Spec Thorium 42 0 66 0 Gas Flow Radium 228 1 0 1 0 Alpha Spec Plutonium 81 0 98 0 ICP-MS Uranium-233, 234 in Filter 0 0 3 0 Alpha Spec Neptunium 62 0 83 0 Alpha Spec Plutonium 66 0 96 0 Alpha Spec Polonium,(Filter/Liter) 0 0 14 0 Alpha Spec Radium 226 0 0 2 0 Gas Flow Sr 2nd Count 72 0 81 1 Gas Flow Strontium 90 61 0 68 0 Lucas Cell Radium-226 1 0 1 0 Alpha Spec Am24lCurium 95 0 117 0 Gas Flow Total Strontium 5 0 5 0 ICP-MS Uranium-233, 234 Prep in Filter 0 0 3 0 ICP-MS Uranium-235, 236, 238 in Filter 0 0 6 0 Total Activity in Filter, 1 0 10 0 Alphaspec Am241 Curium Filter per Liter 15 0 20 0 Tritium 86 0 89 0 Gamma Spec Filter RAD A-013 Direct Count 6 0 6 0 Carbon-14 12 0 12 0 GFC Chlorine-36 in Filters PL 1 0 1 0 Direct Count-Gross Alpha/Beta 48 0 1 0 Gross Alpha/Beta 48 0 60 0 ICP-MS Uranium-234, 235, 236, 238 in Filter 4 0 6 0 ICP-MS Uranium-235, 236, 238 Prep in Filter 0 0 3 0 Alpha Spec U 13 0 35 0 Gross A & B 497 0 473 0 LSC Iron-55 8 0 19 0 Technetium-99 7 0 13 0 Gas Flow Sr-90 6 0 13 0 LSC Nickel 63 14 0 19 0 Gas Flow Pb-210 8 0 22 0 Gas Flow Ra-228 5 0 10 0 Gamma Iodine 129 8 0 8 0 ICP-MS Uranium-234, 235, 236, 238 Prep in Filter 2 0 3 0 Gamma Spec Filter 97 0 117 0 Lucas Cell Ra-226 8 0 23 0 Al ha S ec Thorium 7 0 22 0 Alpha Spec Uranium 390 0 553 0 Alpha Spec Polonium 4 0 7 0 Electrolytic Tritium 14 0 25 0 Tritium 1125 0 1177 0 Carbon-14 149 0 161 0

1 Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 58 of 64 Plutonium 43 0 63 0 Iodine-131 3 0 4 0 LSC Iron-55 192 0 233 0 Gamma Nickel 59 RAD A-022 18 0 21 0 Gamma Iodine 131 RAD A-013 2 0 2 0 Gamma Radium 228 RAD A-013 3 0 3 0 LSC Nickel 63 209 0 236 0 LSC Radon 222 18 0 21 0 Technetium-99 377 0 425 0 Gamma Spec Liquid RAD A-013 702 0 732 0 Alpha Spec Total U RAD A-011 31 0 56 0 LSC Selenium 79 2 0 2 0 Alpha Spec Am243 17 0 18 0 Gamma Iodine-129 80 0 92 0 Gamma Iodine-131 28 0 28 0 ICP-MS Technetium-99 in Water 8 0 31 0 Gas Flow Lead 210 19 0 19 0 Total Uranium KPA 101 0 203 0 LSC Promethium 147 4 0 4 0 LSC, Rapid Strontium 89 and 90 7 0 8 0 Alpha Spec Thorium 145 0 186 0 Gas Flow Radium 228 171 0 206 0 Gas Flow Radium 228 40 0 37 0 Gas Flow Radium 228 1 0 1 0 Alpha Spec Plutonium 288 0 387 0 LSC Sulfur 35 1 0 1 0 Alpha Spec Neptunium 90 0 141 0 Alpha Spec Plutonium 21 0 49 0 Alpha Spec Radium 226 7 0 7 0 Gas Flow Sr 2nd count 191 0 199 0 Gas Flow Strontium 90 365 0 422 0 Gas Flow Strontium 90 1 0 1 0 Gas Flow Total Radium 78 0 103 0 ICP-MS Technetium-99 Prep in Water 8 0 32 0 ICP-MS Uranium-233, 234 in Liquid 6 0 11 0 LSC Calcuim 45 1 0 1 0 Lucas Cell Radium 226 310 0 366 0 Lucas Cell Radium-226 10 0 10 0 Total Activity Screen 7 0 7 0 Chlorine-36 in Liquids 13 0 14 0 Alpha Spec Am241 Curium 217 0 333 0 Gas Flow Total Strontium 112 0 116 0 Gross Alpha Non Vol Beta 980 0 1167 0 LSC Phosphorus-32 2 0 3 0 Lucas Cell Radium 226 by Method Ra-04 2 0 2 0 ICP-MS Uranium-233, 234 Prep in Liquid 6 0 11 0 Tritium in Drinking Water by EPA 906.0 9 0 12 0 Gamma Spec Liquid RAD A-013 with Ba, La 84 0 159 0 Gamma Spec Liquid RAD A-013 with Iodine 162 0 189 0

Ke:4 Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 59 of 64 Gas Flow Strontium 89 & 90 5 0 3 0 ICP-MS Uranium-235, 236, 238 in Liquid 10 0 18 0 Gas Flow Total Alpha Radium 6 0 7 0 Gross Alpha Co-precipitation 3 0 13 0 1CP-MS Uranium-235, 236, 238 Prep in Liquid 6 0 11 0 ICP-MS Uranium-234, 235, 236, 238 in Liquid 31 0_74 0 Gross Alpha Beta (Americium Calibration) Liquid 32 0 46 0 ICP-MS Uranium-234, 235, 236, 238 Prep in Liquid 15 0 38 0 Alpha/Beta (Americium Calibratio Dinking Water 23 0 18 0 Carbon-14 3 0 3 0 Gamma Spec Solid RAD A-013 76 0 78 0 Technetium-99 4 0 4 0 Tritium 1 0 1 0 Alpha Spec Uranium 5 0 8 0 Alpha Spec Plutonium 5 0 10 0 Gas Flow Sr 2nd count 8 0 8 0 Gas Flow Strontium 90 11 0 12 0 Alpha Spec Am241 Curium 2 0 2 0 Gas Flow Total Strontium 17 0 17 0 Gamma Spec Solid RAD A-013 with Ba_ La 10 0 10 0 Gamma Spec Solid RAD A-013 with Iodine 23 0 22 0 Gross AlpaBt 2 0 2 0 LSC Iron-55 5 0 6 0 LSC Nickel 63 5 0 6 0 Gas Flow Total Strontium 6 0 6 0 Gross Alpha Non Vol Beta 6 0 6 0 Gamma STec Liquid RAD A-013 with Iodine 7 0 11 0 LSC Iron-55 2 0 2 0 Gamma Nickel 59 RAD A-022 1 0 0 0 Gamma Spec Solid RAD A-013 26 0 25 0 LSC Nickel 63 2 0 1 0 LSC Plutonium 1 0 1 0 Technetium-99 4 0 3 0 Tritium 11 0 11 0 Gamma Iodine-129 1 0 0 0 Gas Flow Lead 210 2 0 3 0 Total Uranium KPA 4 0 4 0 Alpha Spec Uranium 22 0 22 0 Alpha Spec Thorium 5 0 5 0 Alpha Spec Plutonium 13 0 11 0 Alpha Spec Neptunium 1 0 1 0 Alpha Spec Plutonium 1 0 1 0 Gas Flow Sr 2nd count 10 0 10 0

iLaboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 60 of 64 Gas Flow Strontium 90 12 0 11 0 Gas Flow Total Radium 2 0 2 0 Alpha Spec Am241 Curium 6 0 6 0 Gamma Spec Solid RAD A-013 with Iodine 86 0 96 0 Gamma Spec Solid RAD A-013 (pCi/Sample) 2 0 2 0 Alpha Spec Am241 (pCi/Sample) 1 0 2 0 ICP-MS Uranium-234C 235, 236, 238 in Solid 12 0 7 0 Alpha Spec Uranium 0 0 2 0 Gross Alpha/Beta 7 0 9 0 Alpha Spec Plutonium 0 0 2 0 Gas Flow Strontium 90 4 0 2 0 ICP-MS Uranium-234, 235, 236F 238 Prep in Solid 7 0 4 0 Gamma Iodine 131 RAD A-013 560 0 606 0 Gamma Iodine-129 7 0 6 0 Carbon-14 7 0 7 0 Carbon-14 (Ascarite/Soda Lime Filter per Liter) 28 0 28 0 Gamma Iodine 129 7 0 73 0 Gamma Spec Filter 7 0 7 0 Alpha Spec Uranium 4 0 5 0 Alpha Spec Polonium 1 0 25 0 Tritium 39 0 40 0 Carbon-14 3 0 2 0 Iodine-131 2 0 2 0 LSC Iron-55 17 0 16 0 LSC Nickel 63 16 0 15 0 LSC Radon 222 13 0 13 0 Technetium-99 2 0 1 0 Gamma Spec Liquid RAD A-013 17 0 18 0 Gamma Iodine-129 2 0 4 0 Gamma Iodine-131 27 0 26 0 Gas Flow Lead 210 4 0 3 0 Total Uranium KPA 17 0 34 0 Alpha Spec Thorium 1 0 1 0 Gas Flow Radium 228 22 0 26 0 Alpha Spec Plutonium 3 0 3 0 Gas Flow Sr 2nd count 12 0 12 0 Gas Flow Strontium 90 20 0 22 0 LSC Calcuim 45 2 0 2 0 Lucas Cell Radium-226 23 0 49 0 Alpha Spec Am241 Curium 2 0 2 0 Gas Flow Total Strontium 19 0 18 0 Gross Alpha Non Vol Beta 247 0 214 0 Tritium in Drinking Water by EPA 906.0 28 0 26 0 Gamma Spec Liquid RAID A-013 with Ba, La 35 0 75 0 Gas Flow Strontium 89 & 90 17 011 0 Gas Flow Total Alpha Radium 1 0 1 0

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 61 of 64 2014 ANNUAL QUALITY ASSURANCE REPORT Page 61 of 64 Giross Alohai Co-orecinitation 99 0 qi 0 Alpha/Beta (Americium Calibration) Drinking Water 16 0 16 0 0

ECLS-R-GA N.J 48 Hr Rapid Gross Alpha707 Total 16535 19734 Note 1: The RPD must be 20 percent or less, if both samples are greater than 5 times the MDC. If both results are less than 5 times MDC, then the RPD must be equal to or less than 100%. Ifone result is above the MDC and the other is below the MDC, then the RPD can be calculated using the MDC for the result of the one below the MDC. The RPD must be 100% or less. In the situation where both results are above the MDC but one result is greater than 5 times the MDC and the other is less than 5 times the MDC, the RPD must be less than or equal to 20%. If both results are below MDC, then the limits on % RPD are not applicable.

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 62 of 64 TABLE 8 2014 CORRECTIVE ACTION REPORT

SUMMARY

CORRECTIVE ACTION ID#

& DISPOSITION PE FAILURE CARR140605-879 Root Cause Analysis of MAPEP-14-RdV28 in vegetation for Uranium-235 by ICP/MS ISO Documentation of PT Failures in MAPEP-14-RdV30 for Uranium 235 in The root cause of this failure was human error and inattention Vegetation by ICP/MS and 14-MaS30 to detail. The QAO inadvertently entered the incorrect activity Uranium-233/234 and Uranium 238 by for this parameter when she was entering the results on the Alpha Spec. MAPEP website. 0.261 ug/sample instead of 0.0261 ug/sample was entered. The data entry error was not caught during the GL review process. MAPEP results only are peer reviewed by the GL of the applicable area to ensure that the data was entered correctly.

A second PT was successfully analyzed for this matrix.

Uranium-234/233, and Uranium-238 in soil by Alpha Spec:

Following reviews of our process and data and conversations with personnel from the affected laboratories, it was determined that all failures were due to an incomplete sample digestion. A total digestion technique using Hydrofluoric Acid was performed on the sample. However, this digestion was not vigorous enough to extract all the U-234 and U-238 from the soil because the analytes were fused into the soil at an extremely high temperature. Due to the high number of labs that received a Not Acceptable rating for this analysis, MAPEP has posted an explanation on the preparation of the Uranium Soil standard on their website.

Permanent Corrective/Preventive Actions or Improvements:

Upon notification of the failure, the sample was re-digested using a Sodium Hydroxide fusion method prior to ion-exchange separation chemistry. The results for both the U-234 and U-238 fall within acceptable range. In the future, all MAPEP soil samples will be analyzed with a NaOH fusion dissolution technique. Our analytical procedures provide the flexibility to Derform different extraction techniques (leachina.

M Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 63 of 64 HF dissolution) based on client requests. For our DOE clients, complete dissolution using HF has been the approved method for Uranium. Some clients also ask for the Uranium analysis using a leach procedure. In all cases, GEL performs the required contractual procedure for the analysis.

A second PT was successfully analyzed for this matrix.

CARR140520-874 Root Cause Analysis ISO Documentation of PT Failures in After a thorough review of all data, a definite reason for the

-MRAD-20 for Americium-241 in failure could not be determined.

water.

The following steps were taken to prove that this elevated bias was an isolated occurrence and that our overall process is within control.

1. The batch quality control samples were reviewed and found to be compliant. The recoveries in the Laboratory Control Sample (LCS) recovered at 98.2%. Two sample duplicates were also prepared in the batch. The RPDs were 4.8 and 8.6.

2. The sample was re-analyzed in duplicate after the report was received. One with our normal Am-243 tracer, and another with Cm-244 tracer. Both of the reanalysis confirm the original reported result (which is outside the range of acceptable results).

Control charts for all Am tracer recoveries were also reviewed to determine if there may be an issue with the tracers. While there is a slight bias in the average LCS recovery, it was not significant enough to consider abnormal, and did not come close to accounting for the high result on this analysis.

Additionally, since the sample was reanalyzed using two different tracers and achieved the same result, a tracer issue was ruled out as the potential culprit Permanent Corrective/Preventive Actions or Improvements :

The laboratory must assume unidentified random error caused the elevated bias because all quality control criteria were met for the batch. Additionally, a well characterized performance evaluation sample from another vendor was prepped and analyzed a few weeks after this sample. The Am-241 recovered at 105% for this sample and fell well within its acceptance range.

A second PT was successfully analyzed for this matrix.

Laboratories LLC P.O. Box 30712, Charleston, SC 29417 2014 ANNUAL QUALITY ASSURANCE REPORT Page 64 of 64 CARR140825-902 For Failures of RAD-98 for Strontium- Root Cause Analysis of Strontium-89 (Sr-89) 89 in Water After a review of the data, an apparent reason for this discrepancy could not be determined. The following steps were taken to prove that this high bias was an isolated occurrence and that our overall process is within control.

1. The batch quality control samples were reviewed and found to be compliant. The LCS recovered at 103%.

2. Laboratory control data were also reviewed for trends. None was noted.

3. The instrument calibrations were reviewed for positive biases that could have attributed to this failure. None were noted.

4. Sample duplicates were also prepared and counted along with the reported result. All results fell within the method's acceptance range for duplicates.

Permanent CorrectivelPreventive Actions or Improvements The laboratory must assume an unidentified random error caused the high bias for this batch. While the LCS recovered outside to its acceptance range, the matrix spike (MS) recovery fell within both the acceptance range for the MS (80%-120%) and the acceptance range for the LCS (90%-

110%). The result was also confirmed using Method LAB PBMS-A-004. The lab will continue to monitor the recoveries of this radionuclide to ensure that there are no issues.

A second PT was successfully analyzed for this matrix.