ML14139A475

Pilgrim - Annual Radioactive Effluent Release Report for January 1 Through December 31, 2013

ML14139A475
Person / Time
Site:	Pilgrim
Issue date:	05/15/2014
From:	Lynch J R Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2.14.039
Download: ML14139A475 (128)

Text

EntergyEntergy Nuclear Operations, Inc.600 Rocky Hill RoadPlymouth, MA 02360Pilgrim Nuclear Power StationMay 15, 2014U.S. Nu'clear Regulatory CommissionAttn: Document Control DeskWashington, D.C. 20555

SUBJECT:

Entergy Nuclear Operations, Inc.Pilgrim Nuclear Power StationDocket No.: 50-293License No.: DPR-35Annual Radioactive Effluent Release Report for January 1through December 31, 2013LETTER NUMBER: 2.14.039

Dear Sir or Madam:

In accordance with Pilgrim Technical Specification 5.6.3, Entergy Nuclear Operations, Incsubmits the attached Annual Radioactive Effluent Release Report for January 1, 2013 throughDecember 31, 2013.This letter contains no commitments.Should you have questions or require additional information, I can be contacted at (508) 830-8403.Sincerely,Joseph R. LynchManager, Regulatory Assurance

Attachment:

Pilgrim Annual Radioactive Effluent Release Report for January 1, 2013 throughDecember 31, 2013cc: U.S. Nuclear Regulatory CommissionRegion 12100 Renaissance Blvd, Suite 100King of Prussia, PA 19406-2713USNRC Senior Resident InspectorPilgrim Nuclear Power StationMs. Nadiyah Morgan, Project ManagerDivision of Operating Reactor LicensingOffice of Nuclear Reactor RegulationU.S. Nuclear Regulatory CommissionMail Stop O-8-F211555 Rockville PikeRockville, MD. 20852 Letter Number 2.14.038Pilgrim Annual Radiological Environmental Operating Reportfor January 1, 2013 through December 31, 2013 PILGRIM NUCLEARPOWER STATIONFacility Operating License DPR-35Annual Radiological EnvironmentalOperating ReportJanuary 1 through December 31, 2013*-EntergyPage 1

-EntergyPILGRIM NUCLEAR POWER STATIONFacility Operating License DPR-35ANNUAL RADIOLOGICAL ENVIRONMENTALOPERATING REPORTJANUARY 01 THROUGH DECEMBER 31, 20130-;,- /A. -zo //-/Prepared by:Reviewed by:Reviewed by:K. J. 96k ( ""ajSenior HPTChemistry Specialist:6.\"43anke-nbillerChemis SuperintendentR BrewerRadiation Protection ManagerPage 2 Pilgrim Nuclear Power StationAnnual Radiological Environmental Operating ReportJanuary-December 2013TABLE OF CONTENTSSECTIONSECTION TITLE1.01.11.21.31.41.52.02.12.22.32.42.52.62.72.82.92.102.112.122.132.142.152.162.173.04.0APPENDIX AAPPENDIX BAPPENDIX CAPPENDIX DAPPENDIX EAPPENDIX FAPPENDIX GEXECUTIVE SUMMARYINTRODUCTIONRadiation and RadioactivitySources of RadiationNuclear Reactor OperationsRadioactive Effluent ControlRadiological Impact on HumansRADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAMPre-Operational Monitoring ResultsEnvironmental Monitoring LocationsInterpretation of Radioactivity Analyses ResultsAmbient Radiation MeasurementsAir Particulate Filter Radioactivity AnalysesCharcoal Cartridge Radioactivity AnalysesMilk Radioactivity AnalysesForage Radioactivity AnalysesVegetable/Vegetation Radioactivity AnalysesCranberry Radioactivity AnalysesSoil Radioactivity AnalysesSurface Water Radioactivity AnalysesSediment Radioactivity AnalysesIrish Moss Radioactivity AnalysesShellfish Radioactivity AnalysesLobster Radioactivity AnalysesFish Radioactivity AnalysesSUMMARY OF RADIOLOGICAL IMPACT ON HUMANSREFERENCESSpecial StudiesEffluent Release InformationLand Use CensusEnvironmental Monitoring Program DiscrepanciesEnvironmental Dosimetry Company Annual Quality AssuranceStatus ReportJ.A. Fitzpatrick Interlaboratory Comparison ProgramGEL Laboratories LLC 2013 Annual Quality Assurance ReportPAGE6889101618232324272829303031313232323333333434687071728283Page 3 Pilgrim Nuclear Power StationAnnual Radiological Environmental Operating ReportJanuary-December 2013LIST OF TABLESTABLE TABLE TITLE PAGE1.2-1 Radiation Sources and Corresponding Doses 91.3-1 PNPS Operating Capacity Factor During 2013 102.2-1 Routine Radiological Environmental Sampling Locations 352.4-1 Offsite Environmental TLD Results 372.4-2 Onsite Environmental TLD Results 392.4-3 Average TLD Exposures By Distance Zone During 2013 402.5-1 Air Particulate Filter Radioactivity Analyses 412.6-1 Charcoal Cartridge Radioactivity Analyses 422.7-1 Milk Radioactivity Analyses 432.8-1 Forage Radioactivity Analyses 442.9-1 Vegetable/Vegetation Radioactivity Analyses 452.10-1 Cranberry Radioactivity Analyses 462.12-1 Surface Water Radioactivity Analyses 472.13-1 Sediment Radioactivity Analyses 482.14-1 Irish Moss Radioactivity Analyses 492.15-1 Shellfish Radioactivity Analyses 502.16-1 Lobster Radioactivity Analyses 512.17-1 Fish Radioactivity Analyses 523.0-1 Radiation Doses From 2013 Pilgrim Station Operations 69B.1 Supplemental Information 73B.2-A Gaseous Effluents Summation of All Releases 74B.2-B Gaseous Effluents -Elevated Releases 75B.2-C Gaseous Effluents -Ground Level Releases 77B.3-A Liquid Effluents Summation of All Releases 79B.3-B Liquid Effluents: January-December 2013 80Page 4 Pilgrim Nuclear Power StationAnnual Radiological Environmental Operating ReportJanuary-December 2013LIST OF FIGURESFIGURE FIGURE TITLE PAGE1.3-1 Radioactive Fission Product Formation 121.3-2 Radioactive Activation Product Formation 131.3-3 Barriers to Confine Radioactive Materials 141.5-1 Radiation Exposure Pathways 202.2-1 Environmental TLD Locations Within the PNPS Protected Area 532.2-2 TLD and Air Sampling Locations: Within 1 Kilometer 552.2-3 TLD and Air Sampling Locations: 1 to 5 Kilometers 572.2-4 TLD and Air Sampling Locations: 5 to 25 Kilometers 592.2-5 Terrestrial and Aquatic Sampling Locations 612.2-6 Environmental Sampling and Measurement Control Locations 632.5-1 Airborne Gross Beta Radioactivity Levels: Near Station Monitors 652.5-2 Airborne Gross Beta Radioactivity Levels: Property Line Monitors 662.5-3 Airborne Gross Beta Radioactivity Levels: Offsite Monitors 67Page 5 EXECUTIVE SUMMARYENTERGY NUCLEARPILGRIM NUCLEAR POWER STATIONANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORTJANUARY 01 THROUGH DECEMBER 31, 2013INTRODUCTIONThis report summarizes the results of the Entergy Nuclear Radiological Environmental MonitoringProgram (REMP) conducted in the vicinity of Pilgrim Nuclear Power Station (PNPS) during the periodfrom January 1 to December 31, 2013. This document has been prepared in accordance with therequirements of PNPS Technical Specifications section 5.6.2.The REMP has been established to monitor the radiation and radioactivity released to theenvironment 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 ofPilgrim Station on the environment and on the general public.SAMPLING AND ANALYSISThe environmental sampling media collected in the vicinity of PNPS and at distant locations includeair particulate filters, charcoal cartridges, animal forage, vegetation, cranberries, seawater, sediment,Irish moss, shellfish, American lobster, and fishes.During 2013, there were 1,230 samples collected from the atmospheric, aquatic, and terrestrialenvironments. In addition, 431 exposure measurements were obtained using environmentalthermoluminescent dosimeters (TLDs).A small number of inadvertent issues were encountered during 2013 in the collection ofenvironmental samples in accordance with the PNPS Offsite Dose Calculation Manual (ODCM).Nine out of 440 TLDs were unaccounted for during the quarterly retrieval process. However, the 431TLDs that were collected provided the information necessary to assess ambient radiation levels inthe vicinity of Pilgrim Station. Equipment failures and power outages resulted in a small number ofinstances in which lower than normal volumes were collected at the airborne sampling stations. Insome cases, outages were of sufficient duration to yield no sample, and 563 of 572 air particulateand charcoal cartridges were collected and analyzed as required. A full description of anydiscrepancies encountered with the environmental monitoring program is presented in Appendix D ofthis report.There were 1,286 analyses performed on the environmental media samples. Analyses wereperformed by the J.A. Fitzpatrick Environmental Laboratory in Fulton, New York. Samples wereanalyzed as required by the PNPS ODCM.LAND USE CENSUSThe annual land use census in the vicinity of Pilgrim Station was conducted as required by thePNPS ODCM between September 09 and September 20, 2013. A total of 30 vegetable gardenshaving an area of more than 500 square feet were identified within five kilometers (three miles) ofPNPS. No new milk or meat animals were located during the census. Of the 30 garden locationsidentified, samples were collected at or near three of the gardens as part of the environmentalPage 6 monitoring program. Other samples of natural vegetation were also collected in predicted high-deposition areas.RADIOLOGICAL IMPACT TO THE ENVIRONMENTDuring 2013, samples (except charcoal cartridges) collected as part of the REMP at Pilgrim Stationcontinued to contain detectable amounts of naturally-occurring and man-made radioactive materials.No samples indicated any detectable radioactivity attributable to Pilgrim Station operations. Offsiteambient radiation measurements using environmental TLDs beyond the site boundary rangedbetween 40 and 76 milliRoentgens per year. The range of ambient radiation levels observed withthe TLDs is consistent with natural background radiation levels for Massachusetts.RADIOLOGICAL IMPACT TO THE GENERAL PUBLICDuring 2013, radiation doses to the general public as a result of Pilgrim Station's operationcontinued to be well below the federal limits and much less than the collective dose due to othersources 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 fromradioactive effluents and ambient radiation resulting from PNPS operations for 2013 was about 0.9mrem for the year. This conservative estimate is well below the EPA's annual dose limit to anymember of the general public and is a fraction of a percent of the typical dose received from naturaland man-made radiation.CONCLUSIONSThe 2013 Radiological Environmental Monitoring Program for Pilgrim Station resulted in thecollection and analysis of hundreds of environmental samples and measurements. The dataobtained were used to determine the impact of Pilgrim Station's operation on the environment andon the general public.An evaluation of direct radiation measurements, environmental sample analyses, and dosecalculations showed that all applicable federal criteria were met. Furthermore, radiation levels andresulting 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 thegeneral public due to Pilgrim Station's operation.Page 7

1.0 INTRODUCTION

The Radiological Environmental Monitoring Program for 2013 performed by Entergy NuclearCompany for Pilgrim Nuclear Power Station (PNPS) is discussed in this report. Since the operationof a nuclear power plant results in the release of small amounts of radioactivity and low levels ofradiation, the Nuclear Regulatory Commission (NRC) requires a program to be established tomonitor radiation and radioactivity in the environment (Reference 1). This report, which is required tobe published annually by Pilgrim Station's Technical Specifications section 5.6.2, summarizes theresults of measurements of radiation and radioactivity in the environment in the vicinity of the PilgrimStation and at distant locations during the period January 1 to December 31, 2013.The Radiological Environmental Monitoring Program consists of taking radiation measurements andcollecting samples from the environment, analyzing them for radioactivity content, and interpretingthe results. With emphasis on the critical radiation exposure pathways to humans, samples from theaquatic, atmospheric, and terrestrial environments are collected. These samples include, but are notlimited to: air, animal forage, vegetation, cranberries, seawater, sediment, Irish moss, shellfish,American lobster, and fish. Thermoluminescent dosimeters (TLDs) are placed in the environment tomeasure gamma radiation levels. The TLDs are processed and the environmental samples areanalyzed to measure the very low levels of radiation and radioactivity present in the environment asa result of PNPS operation and other natural and man-made sources. These results are reviewedby PNPS's Chemistry staff and have been reported semiannually or annually to the NuclearRegulatory 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 isbelieved that this information will assist the reader in understanding the radiological impact on theenvironment and humans from the operation of Pilgrim Station.1.1 Radiation and RadioactivityAll matter is made of atoms. An atom is the smallest part into which matter can be broken down andstill maintain all its chemical properties. Nuclear radiation is energy, in the form of waves or particlesthat is given off by unstable, radioactive atoms.Radioactive material exists naturally and has always been a part of our environment. The earth'scrust, for example, contains radioactive uranium, radium, thorium, and potassium. Someradioactivity is a result of nuclear weapons testing. Examples of radioactive fallout that is normallypresent in environmental samples are cesium-137 and strontium-90. Some examples of radioactivematerials released from a nuclear power plant are cesium-1 37, iodine-1 31, strontium-90, and cobalt-60.Radiation is measured in units of millirem, much like temperature is measured in degrees. A milliremis a measure of the biological effect of the energy deposited in tissue. The natural and man-maderadiation 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 produce37,000,000,000 nuclear disintegrations per second. This is an extremely large amount ofradioactivity in comparison to environmental radioactivity. That is why radioactivity in theenvironment is measured in picocuries. One picocurie is equal to one trillionth of a curie.Page 8 1.2 Sources of RadiationAs mentioned previously, naturally occurring radioactivity has always been a part of ourenvironment. Table 1.2-1 shows the sources and doses of radiation from natural and man-madesources.Table 1.2-1Radiation Sources and Corresponding Doses (1)NATURAL MAN-MADERadiation Dose Radiation DoseSource (millirem/year) Source (millirem/year)Internal, inhalation(2) 230 Medica1(3) 300External, space 30 Consumerý4) 12Internal, ingestion 30 Industrial(5) 0.6External, terrestrial 20 Occupational 0.6Weapons Fallout < 1Nuclear Power Plants < 1Approximate Total 310 Approximate Total 315Combined Annual Average Dose: Approximately 620 to 625 milliremryear(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) andconventional 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 researchCosmic radiation from the sun and outer space penetrates the earth's atmosphere and continuouslybombards us with rays and charged particles. Some of this cosmic radiation interacts with gasesand particles in the atmosphere, making them radioactive in turn. These radioactive byproducts fromcosmic ray bombardment are referred to as cosmogenic radionuclides. Isotopes such as beryllium-7and carbon-14 are formed in this way. Exposure to cosmic and cosmogenic sources of radioactivityresults 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), theground we walk on (about 20 millirem/yr) and the air we breathe (about 230 millirem/yr). The majorityof a person's annual dose results from exposure to radon and thoron in the air we breathe. Thesegases 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 andthoron levels vary greatly with location, primarily due to changes in the concentration of uranium andthorium in the soil. Residents at some locations in Colorado, New York, Pennsylvania, and NewJersey 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 totaldose of about 310 mrem per year.In addition to natural radiation, we are normally exposed to radiation from a number of man-madesources. The single largest doses from man-made sources result from therapeutic and diagnosticapplications of x-rays and radiopharmaceuticals. The annual dose to an individual in the U.S. frommedical and dental exposure is about 300 mrem. Consumer activities, such as smoking, commercialair travel, and building materials contribute about 13 mrem/yr. Much smaller doses result fromweapons fallout (less than 1 mrem/yr) and nuclear power plants. Typically, the average person inthe United States receives about 314 mrem per year from man-made sources. The collective dosefrom naturally-occurring and man-made sources results in a total dose of approximately 620 mrem/yrto the average American.1.3 Nuclear Reactor OperationsPilgrim Station generates about 700 megawatts of electricity at full power, which is enough electricityto supply the entire city of Boston, Massachusetts. Pilgrim Station is a boiling water reactor whosenuclear steam supply system was provided by General Electric Co. The nuclear station is located ona 1600-acre site about eight kilometers (five miles) east-southeast of the downtown area ofPlymouth, Massachusetts. Commercial operation began in December 1972.Pilgrim Station was operational during most of 2013, with the exception of the refueling outage thatoccurred between mid-April through May. The resulting monthly capacity factors are presented inTable 1.3-1.TABLE 1.3-1PNPS OPERATING CAPACITY FACTOR DURING 2013(Based on rated reactor thermal power of 2028 Megawatts-Thermal)Month Percent CapacityJanuary 69.3%February 68.8%March 92.8%April 38.9%May 1.8%June 97.0%July 99.6%August 76.8%September 67.7%October 76.7%November 99.0%December 86.8%Annual Average 72.9%Page 10 Nuclear-generated electricity is produced at Pilgrim Station by many of the same techniques used forconventional oil and coal-generated electricity. Both systems use heat to boil water to producesteam. The steam turns a turbine, which turns a generator, producing electricity. In both cases, thesteam passes through a condenser where it changes back into water and recirculates back throughthe 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 heatused to boil the water. Conventional plants bum fossil fuels in a boiler, while nuclear plants makeuse of uranium in a nuclear reactor.Inside the reactor, a nuclear reaction called fission takes place. Particles, called neutrons, strike thenucleus 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 thencollide with and split other uranium atoms, thus making more heat and releasing even moreneutrons, and on and on until the uranium fuel is depleted or spent. This process is called a chainreaction.The operation of a nuclear reactor results in the release of small amounts of radioactivity and lowlevels of radiation. The radioactivity originates from two major sources, radioactive fission productsand radioactive activation products.Radioactive fission products, as illustrated in Figure 1.3-1 (Reference 5), originate from the fissioningof the nuclear fuel. These fission products get into the reactor coolant from their release by minuteamounts of uranium on the outside surfaces of the fuel cladding, by diffusion through the fuel pelletsand cladding and, on occasion, through defects or failures in the fuel cladding. These fissionproducts circulate along with the reactor coolant water and will deposit on the internal surfaces ofpipes 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 11 Nuclear FissionFission is the splitting of the uranium-235 atom by a neutron torelease heat and more neutrons, creating a chain reaction.Radiation and fission products are by-products of the process.RadiationUraniumNeutronsNeutronRadiationS( NeutronsUraniumUraniumFission ProductsFigure 1.3-1Radioactive Fission Product FormationPage 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 internalsof any piping system or component are subject to minute yet constant corrosion from the reactorcooling water. These minute metallic particles (for example: nickel, iron, cobalt, or magnesium) aretransported through the reactor core into the fuel region, where neutrons may react with the nuclei ofthese particles, producing radioactive products. So, activation products are nothing more thanordinary 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 theinternal surfaces of pipes and equipment. The radioactive activation products on the pipes andequipment 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).Co-59 C0-60NeutronStableCobalt NucleusRadioactiveCobalt NucleusFigure 1.3-2Radioactive Activation Product FormationAt Pilgrim Nuclear Power Station there are five independent protective barriers that confine theseradioactive materials. These five barriers, which are shown in Figure 1.3-3 (Reference 5), are:* fuel pellets;* fuel cladding;* reactor vessel and piping;* primary containment (drywell and torus); and," secondary containment (reactor building).Page 13

1. FUEL PELLETS2. FUEREACTORBUILDINGDRYWELLFigure 1.3-3Barriers To Confine Radioactive MaterialsPage 14 The ceramic uranium fuel pellets provide the first barrier. Most of the radioactive fission products areeither 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 intosmall 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 thatare types of radioactive fission products. This radioactivity can diffuse to a small extent through thefuel cladding into the reactor coolant water.The third barrier consists of the reactor pressure vessel, steel piping and equipment that confine thereactor cooling water. The reactor pressure vessel, which holds the reactor fuel, is a 65-foot high by19-foot diameter tank with steel walls about nine inches thick. This provides containment forradioactivity in the primary coolant and the reactor core. However, during the course of operationsand maintenance, small amounts of radioactive fission and activation products can escape throughvalve 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 drywellis a steel lined enclosure that is shaped like an inverted light bulb. An approximately five foot thickconcrete wall encloses the drywell's steel pressure vessel. The torus is a donut-shaped pressuresuppression chamber. The steel walls of the torus are nine feet in diameter with the donut itselfhaving an outside diameter of about 130 feet. Small amounts of radioactivity may be released fromprimary containment during maintenance.The fifth barrier is the secondary containment or reactor building. The reactor building is theconcrete building that surrounds the primary containment. This barrier is an additional safety featureto contain radioactivity that may escape from the primary containment. This reactor building isequipped with a filtered ventilation system that is used when needed to reduce the radioactivity thatescapes from the primary containment.The five barriers confine most of the radioactive fission and activation products. However, smallamounts of radioactivity do escape via mechanical failures and maintenance on valves, piping, andequipment associated with the reactor cooling water system. The small amounts of radioactiveliquids and gases that do escape the various containment systems are further controlled by the liquidpurification and ventilation filtration systems. Also, prior to a release to the environment, controlsystems exist to collect and purify the radioactive effluents in order to reduce releases to theenvironment to as low as is reasonably achievable. The control of radioactive effluents at PilgrimStation will be discussed in more detail in the next section.Page 15 1.4 Radioactive Effluent ControlThe small amounts of radioactive liquids and gases that might escape the five barriers are purified inthe liquid and gaseous waste treatment systems, then monitored for radioactivity, and released onlyif the radioactivity levels are below the federal release limits.Radioactivity released from the liquid effluent system to the environment is limited, controlled, andmonitored 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 waterby removing radioactive atoms and non-radioactive impurities that may become activated by neutronbombardment. A portion of the reactor coolant water is diverted from the primary coolant systemand is directed through ion exchange resins where radioactive elements, dissolved and suspendedin the water, are removed through chemical processes. The net effect is a substantial reduction ofthe radioactive material that is present in the primary coolant water and consequently the amount ofradioactive material that might escape from the system.Reactor cooling water that might escape the primary cooling system and other radioactive watersources are collected in floor and equipment drains. These drains direct this radioactive liquid wasteto large holdup tanks. The liquid waste collected in the tanks is purified again using the liquidradwaste treatment system, which consists of a filter and ion exchange resins.Processing of liquid radioactive waste results in large reductions of radioactive liquids dischargedinto Cape Cod Bay. Of all wastes processed through liquid radwaste treatment, 90 to 95 percent ofall 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 ifthe level of radioactivity is below the release limits and to quantify the total amount of radioactiveliquid effluent that would be released. If the levels are below the federal release limits, the tank isdrained to the liquid effluent discharge header.This liquid waste effluent discharge header is provided with a shielded radioactivity monitor. Thisdetector is connected to a radiation level meter and a strip chart recorder in the Control Room. Theradiation alarm is set so that the detector will alarm before radioactivity levels exceed the releaselimits. The liquid effluent discharge header has an isolation valve. If an alarm is received, the liquideffluent discharge valve will automatically close, thereby terminating the release to the Cape CodBay 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 maycontain very low levels of contamination, may be discharged directly to the discharge canal withoutpassing through the liquid radwaste discharge header. One such source of liquids is the neutralizingsump. However, prior to discharging such liquid wastes, the tank is thoroughly mixed and arepresentative 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 plantcooling water from the condenser with the liquid effluents in the discharge canal. This larger volumeof 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 effluentsreleased 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 otherparts of the building. This combined airflow is then directed to the reactor building ventilation plenumthat is located on the side of the reactor building. This plenum, which vents to the atmosphere, isequipped with a radiation detector. The radiation level meter and strip chart recorder for the reactorbuilding vent effluent radioactivity monitor is located in the Control Room. To supplement theinformation continuously provided by the detector, air samples are taken periodically from the reactorbuilding vent and are analyzed to quantify the total amount of tritium and radioactive gaseous andparticulate effluents released.If air containing elevated amounts of noble gases is routed past the reactor building vent's effluentradioactivity monitor, an alarm will alert the Control Room operators that release limits are beingapproached. The Control Room operators, according to procedure, will isolate the reactor buildingventilation system and initiate the standby gas treatment system to remove airborne particulates andgaseous halogen radioactivity from the reactor building exhaust. This filtration assembly consists ofhigh-efficiency particulate air filters and charcoal adsorber beds. The purified air is then directed tothe main stack. The main stack has dilution flow that further reduces concentration levels ofgaseous 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 ofthe air and passes it through a radioactivity monitoring system. This main stack effluent radioactivitymonitoring system continuously samples radioactive particulates, iodines, and noble gases. Grabsamples for a tritium analysis are also collected at this location. The system also containsradioactivity detectors that monitor the levels of radioactive noble gases in the stack flow and displaythe result on radiation level meters and strip chart recorders located in the Control Room. Tosupplement the information continuously provided by the detectors, the particulate, iodine, tritium,and gas samples are analyzed periodically to quantify the total amount of radioactive gaseouseffluent being released.The purpose of the augmented off-gas system is to reduce the radioactivity from the gases that areremoved from the condenser. This purification system consists of two 30-minute holdup lines toPage 17 reduce the radioactive gases with short half-lives, several charcoal adsorbers to remove radioactiveiodines and further retard the short half-life gases, and offgas filters to remove radioactiveparticulates. The recombiner collects free hydrogen and oxygen gas and recombines them intowater. This helps reduce the gaseous releases of short-lived isotopes of oxygen that have beenmade 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 thisdetector are also located in the Control Room. If a radiation alarm setpoint is exceeded, an audiblealarm will sound to alert the Control Room operators. In addition, the off-gas bypass and charcoaladsorber inlet valve will automatically re-direct the off-gas into the charcoal adsorbers if they aretemporarily being bypassed. If the radioactivity levels are not returned to below the alarm setpointwithin 13 minutes, the off-gas releases will be automatically isolated, thereby preventing anygaseous radioactivity from being released that may exceed the release limits.Therefore, for both liquid and gaseous releases, radioactive effluent control systems exist to collectand purify the radioactive effluents in order to reduce releases to the environment to as low as isreasonably achievable. The effluents are always monitored, sampled and analyzed prior to releaseto make sure that radioactivity levels are below the release limits. If the release limits are beingapproached, isolation valves in some of the waste effluent lines will automatically shut to stop therelease, or Control Room operators will implement procedures to ensure that federal regulatory limitsare always met.1.5 Radiological Impact on HumansThe final step in the effluent control process is the determination of the radiological dose impact tohumans and comparison with the federal dose limits to the public. As mentioned previously, thepurpose of continuous radiation monitoring and periodic sampling and analysis is to measure thequantities 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 effluentsare performed. The purpose of these calculations is to periodically assess the doses to the generalpublic resulting from radioactive effluents to ensure that these doses are being maintained as farbelow the federal dose limits as is reasonably achievable. This is the second stage for assessingreleases to the environment.The types and quantities of radioactive liquid and gaseous effluents released from Pilgrim Stationduring each given year are reported to the Nuclear Regulatory Commission annually. The 2013Radioactive Effluents are provided in Appendix B and will be discussed in more detail in Section 3 ofthis report. These liquid and gaseous effluents were well below the federal release limits and were asmall percentage of the PNPS ODCM effluent control limits.These measurements of the physical and chemical nature of the effluents are used to determinehow the radionuclides will interact with the environment and how they can result in radiationexposure to humans. The environmental interaction mechanisms depend upon factors such as thehydrological (water) and meteorological (atmospheric) characteristics in the area. Information on thewater flow, wind speed, wind direction, and atmospheric mixing characteristics are used to estimatehow 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 isdata 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, drinkingwater supplies, and other usage information are utilized to estimate the amount of radiation andradioactivity received by the general public.The radiation exposure pathway to humans is the path radioactivity takes from its release point atPilgrim Station to its effect on man. The movement of radioactivity through the environment and itstransport to humans is portrayed in Figure 1.5-1.Page 19 EXAMPLES OF PILGRIM STATION'S RADIATION EXPOSURE PATHWAYSLIQUIDEFFLUENTS-64. DIRECT RADIATION(SOIL DEPOSITION)1. SHORELINE DIRECT RADIATION(FISHING, PICNICJNG) _ 15. CONSUMPTION(VEGETATION)(AIR SUBMERSION)DEPOSITION2. DIRECT RADIATION(IMMERSION IN OCEAN,BOATING, SWIMMING)fDEPOSITIONINGESTION #N -I~(FISH, SHELLFISH)INIGESTIONFigure 1.5-1Radiation Exposure PathwaysPage 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 absorbedfrom 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 onvegetation or absorbed from the soil due to ground deposition of radioactive effluents; and,* internal radiation from consumption of milk and meat containing radioactivity deposited onforage that is eaten by cattle and other livestock.In addition, ambient (direct) radiation emitted from contained sources of radioactivity at PNPScontributes to radiation exposure in the vicinity of the plant. Radioactive nitrogen-16 contained in thesteam flowing through the turbine accounts for the majority of this "sky shine" radiation exposureimmediately adjacent to the plant. Smaller amounts of ambient radiation result from low-levelradioactive 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 ofradiation and radioactivity in the environment. When PNPS-related activity is detected in samplesthat 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 ofonly small amounts of radioactivity, and, as a result of dilution in the atmosphere and ocean, eventhe most sensitive radioactivity measurement and analysis techniques cannot usually detect thesetiny amounts of radioactivity above that which is naturally present in the environment. Therefore,radiation doses are calculated using radioactive effluent release data and computerized dosecalculations that are based on very conservative NRC-recommended models that tend to result inover-estimates of resulting dose. These computerized dose calculations are performed by or forEntergy Nuclear personnel. These computer codes use the guidelines and methodology set forth bythe NRC in Regulatory Guide 1.109 (Reference 6). The dose calculations are documented anddescribed 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 thatbecause of the very conservative assumptions made in the computer code calculations, themaximum hypothetical dose to an individual is considerably higher than the dose that would actuallybe received by a real individual.After dose calculations are performed, the results are compared to the federal dose limits for thepublic. The two federal agencies that are charged with the responsibility of protecting the publicfrom radiation and radioactivity are the Nuclear Regulatory Commission (NRC) and theEnvironmental Protection Agency (EPA).Page 21 The NRC, in 10CFR 20.1301 (Reference 8) limits the levels of radiation to unrestricted areasresulting from the possession or use of radioactive materials such that they limit any individual to adose of:0 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 farbelow the legal limits as is reasonably achievable.The NRC, in 10CFR 50 Appendix I (Reference 9) establishes design objectives for the dose to amember of the general public from radioactive material in liquid effluents released to unrestrictedareas 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-131, tritium, and all particulate radionuclideswith half-lives greater than 8 days in gaseous effluents is limited to:* less than or equal to 15 mrem per year to any organ.The EPA, in 40CFR190.10 Subpart B (Reference 10), sets forth the environmental standards for theuranium fuel cycle. During normal operation, the annual dose to any member of the public from theentire 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 2013 radiological impact for Pilgrim Station and comparison with the EPA doselimits and guidelines, as well as a comparison with natural/man-made radiation levels, is presentedin Section 3 of this report.The third stage of assessing releases to the environment is the Radiological EnvironmentalMonitoring Program (REMP). The description and results of the REMP at Pilgrim Nuclear PowerStation during 2013 is discussed in Section 2 of this report.Page 22 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM2.1 Pre-Operational Monitoring ResultsThe Radiological Environmental Monitoring Program (REMP) at Pilgrim Nuclear Power Station wasfirst initiated in August 1968, in the form of a pre-operational monitoring program prior to bringing thestation on-line. The NRC's intent (Reference 11) with performing a pre-operational environmentalmonitoring program is to:* measure background levels and their variations in the environment in the area surroundingthe licensee's station; and," evaluate procedures, equipment, and techniques for monitoring radiation and radioactivity inthe 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 levelsmeasured during this time period are as follows:* Airborne Radioactivity Particulate Concentration (gross beta): 0.02 -1.11 pCi/m3;* 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 inradiation 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 acomprehensive operational environmental monitoring program at Pilgrim Nuclear Power Station.This program (Reference 13) provides information on radioactivity and radiation levels in theenvironment for the purpose of:" demonstrating that doses to the general public and levels of radioactivity in the environmentare within established limits and legal requirements;* monitoring the transfer and long-term buildup of specific radionuclides in the environment torevise 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 theadequacy of containment, and the effectiveness of effluent treatment so as to provide amechanism of determining unusual or unforeseen conditions and, where appropriate, totrigger special environmental monitoring studies;* assessing the dose equivalent to the general public and the behavior of radioactivity releasedduring the unlikely event of an accidental release; and,Page 23

• determining whether or not the radiological impact on the environment and humans issignificant.The Nuclear Regulatory Commission requires that Pilgrim Station provide monitoring of the plantenvirons for radioactivity that will be released as a result of normal operations, including anticipatedoperational occurrences, and from postulated accidents. The NRC has established guidelines(Reference 14) that specify an acceptable monitoring program. The PNPS RadiologicalEnvironmental Monitoring Program was designed to meet and exceed these guidelines. Guidancecontained in the NRC's Radiological Assessment Branch Technical Position on EnvironmentalMonitoring (Reference 15) has been used to improve the program. In addition, the program hasincorporated the provisions of an agreement made with the Massachusetts Wildlife Federation(Reference 16). The program was supplemented by including improved analysis of shellfish andsediment at substantially higher sensitivity levels to verify the adequacy of effluent controls at PilgrimStation.2.2 Environmental Monitoring LocationsSampling locations have been established by considering meteorology, population distribution,hydrology, and land use characteristics of the Plymouth area. The sampling locations are dividedinto two classes, indicator and control. Indicator locations are those that are expected to showeffects from PNPS operations, if any exist. These locations were primarily selected on the basis ofwhere the highest predicted environmental concentrations would occur. While the indicator locationsare typically within a few kilometers of the plant, the control stations are generally located so as to beoutside the influence of Pilgrim Station. They provide a basis on which to evaluate fluctuations atindicator locations relative to natural background radiation and natural radioactivity and fallout fromprior nuclear weapons tests.The environmental sampling media collected in the vicinity of Pilgrim Station during 2013 included airparticulate 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 through2.2-4. The frequency of collection and types of radioactivity analysis are described in PilgrimStation's ODCM, Sections 3/4.5.The land-based (terrestrial) samples and monitoring devices are collected by Entergy personnel. Theaquatic samples are collected by Marine Research, Inc. The radioactivity analysis of samples andthe processing of the environmental TLDs are performed by Entergy's J.A. Fitzpatrick EnvironmentalLaboratory.The frequency, types, minimum number of samples, and maximum lower limits of detection (LLD) forthe analytical measurements, are specified in the PNPS ODCM. During 2003, a revision was madeto the PNPS ODCM to standardize it to the model program described in NUREG-1302 (Reference14) and the Branch Technical Position of 1979 (Reference 15). In accordance with thisstandardization, a number of changes occurred regarding the types and frequencies of samplecollections.In regard to terrestrial REMP sampling, routine collection and analysis of soil samples wasdiscontinued in lieu of the extensive network of environmental TLDs around PNPS, and the weeklycollection of air samples at 11 locations. Such TLD monitoring and air sampling would provide anearly indication of any potential deposition of radioactivity, and follow-up soil sampling could beperformed on an as-needed basis. Also, with the loss of the indicator milk sample at the PlymouthPage 24 County Farm and the lack of a sufficient substitute location that could provide suitable volumes foranalysis, 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. NRCguidance (Reference 14) contains provisions for collection of vegetation and forage samples in lieuof milk sampling. Such samples have historically been collected near Pilgrim Station as part of theroutine REMP program.In the area of marine sampling, a number of the specialized sampling and analysis requirementsimplemented 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, waspredicated 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 thetime, the requirements were continued. When the ODCM was revised in 1999 in accordance withNRC Generic Letter 89-01, the sampling program description was relocated to the ODCM. Whensteps were taken in 2003 to standardize the PNPS ODCM to the NUREG-1302 model, thespecialized marine sampling requirements were changed to those of the model program. Thesechanges 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 opposedto 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, asopposed to a specialized quarterly sampling interval.* Analysis of only the edible portions of shellfish (mussels and clams), as opposed tospecialized additional analysis of the shell portions.* Standard LLD levels of 130 to 260 pCi/kg were established for edible portions of shellfish, asopposed to specialized LLDs of 5 pCi/kg.The PNPS ODCM was revised in 2009. In conjunction with this revision, two changes were made tothe environmental sampling program. Due to damage from past storms to the rocky areas atManomet Point, there is no longer a harvestable population of blue mussels at this site. Severalattempts have been made over the past years to collect samples from this location, but all effortswere unsuccessful. Because of unavailability of mussels at this location as a viable humanfoodchain exposure pathway, this location was dropped from the sampling program. The otherchange involved the twice per year sampling of Group II fishes in the vicinity of the PNPS dischargeoutfall, represented by species such as cunner and tautog. Because these fish tend to move awayfrom the discharge jetty during colder months, they are not available for sampling at a six-monthsemi-annual sampling period. The sampling program was modified to reduce the sampling forGroup 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 theresults. If the radioactivity concentrations are above the reporting levels, the NRC must be notifiedwithin 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 for2013 special studies). Most importantly, if radioactivity levels in the environment become elevatedas a result of the station's operation, an investigation is performed and corrective actions arerecommended to reduce the amount of radioactivity to as far below the legal limits as is reasonablyachievable.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 theenvironment in the vicinity of the station to permit modification of the monitoring and samplinglocations. The results of the 2013 Garden and Milk Animal Census are reported in Appendix C.Page 25 The accuracy of the data obtained through Pilgrim Station's Radiological Environmental MonitoringProgram is ensured through a comprehensive Quality Assurance (QA) programs. PNPS's QAprogram has been established to ensure confidence in the measurements and results of theradiological 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 bythe NRC, American Nuclear Insurers, and by the PNPS Quality Assurance Department.The J.A. Fitzpatrick Environmental Laboratory conducts extensive quality assurance and qualitycontrol programs. The 2013 results of these programs are summarized in Appendix E. Theseresults indicate that the analyses and measurements performed during 2013 exhibited acceptableprecision and accuracy.Page 26 2.3 Interpretation of Radioactivity Analyses ResultsThe following pages summarize the analytical results of the environmental samples collected during2013. Data for each environmental medium are included in a separate section. A table thatsummarizes the year's data for each type of medium follows a discussion of the sampling programand results. The unit of measurement for each medium is listed at the top of each table. The lefthand column contains the radionuclides being reported, total number of analyses of thatradionuclide, and the number of measurements that exceed ten times the yearly average for thecontrol station(s). The latter are classified as "non-routine" measurements. The next column liststhe Lower Limit of Detection (LLD) for those radionuclides that have detection capabilityrequirements specified in the PNPS ODCM.Those sampling stations within the range of influence of Pilgrim Station and which could conceivablybe affected by its operation are called "indicator" stations. Distant stations, which are beyond plantinfluence, are called "control" stations. Ambient radiation monitoring stations are broken down intofour separate zones to aid in data analysis.For each sampling medium, each radionuclide is presented with a set of statistical parameters. Thisset of statistical parameters includes separate analyses for (1) the indicator stations, (2) the stationhaving the highest annual mean concentration, and (3) the control stations. For each of these threegroups 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 standarddeviation), out of the total number of measurements.Each single radioactivity measurement datum is based on a single measurement and is reported asa concentration plus or minus one standard deviation. The quoted uncertainty represents only therandom uncertainty associated with the measurement of the radioactive decay process (countingstatistics), 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, avegetation 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/kilogramwould be considered "negative", indicating no detectable cesium-137. The latter sample mayactually contain cesium-1 37, but the levels counted during its analysis were not significantly differentthan the background levels.As an example of how to interpret data presented in the results tables, refer to the first entry on thetable for air particulate filters (page 41). Gross beta (GR-B) analyses were performed on 563 routinesamples. None of the samples exceeded ten times the average concentration at the controllocation. The lower limit of detection (LLD) required by the ODCM is 0.01 pCi/m3.For samples collected from the ten indicator stations, 511 out of 511 samples indicated detectableactivity at the three-sigma (standard deviation) level. The mean concentration of gross beta activityin these 511 indicator station samples was 0.014 +/- 0.0049 (1.4E-2 +/- 4.9E-3) pCi/m3. Individualvalues ranged from 0.00047 to 0.035 (4.7E-4 -3.5E-2) pCi/m3.The monitoring station which yielded the highest mean concentration was the Control location EW(East Weymouth), which yielded a mean concentration of 0.014 +/- 0.0053 pCi/m3, based on 52Page 27 observations. Individual values ranged from 0.0044 to 0.030 pCi/m3.Fifty-two of the fifty-twosamples showed detectable activity at the three-sigma level.At the control location, 52 out of 52 samples yielded detectable gross beta activity, for an averageconcentration of 0.014 +/- 0.0043 pCi/m3.Individual samples at the control location ranged from0.0044 to 0.030 pCi/m3.Referring to the next-to-last entry row in the table, analyses for cesium-1 37 (Cs-1 37) were performed43 times (quarterly composites for 11 stations

• 4 quarters, minus one quarterly sample). Nosamples exceeded ten times the mean control station concentration. The required LLD value Cs-137 in the PNPS ODCM is 0.06 pCi/m3.At the indicator stations, all 40 of the Cs-137 measurements were below the detection level. Thesame was true for the four measurements made on samples collected from the control location.2.4 Ambient Radiation MeasurementsThe primary technique for measuring ambient radiation exposure in the vicinity of Pilgrim Stationinvolves posting environmental thermoluminescent dosimeters (TLDs) at given monitoring locationsand retrieving the TLDs after a specified time period. The TLDs are then taken to a laboratory andprocessed to determine the total amount of radiation exposure received over the period. AlthoughTLDs can be used to monitor radiation exposure for short time periods, environmental TLDs aretypically posted for periods of one to three months. Such TLD monitoring yields average exposurerate measurements over a relatively long time period. The PNPS environmental TLD monitoringprogram is based on a quarterly (three month) posting period, and a total of 110 locations aremonitored using this technique. In addition, 27 of the 110 TLDs are located onsite, within the PNPSprotected/restricted area, where the general public does not have access.Out of the 440 TLDs (110 locations

• 4 quarters) posted during 2013, 431 were retrieved andprocessed. Those TLDs missing from their monitoring locations were lost to storm damage, and/orbuilding renovation, and their absence is discussed in Appendix D. The results for environmentalTLDs 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. Inaddition to TLD results for individual locations, results from offsite TLDs were grouped according togeographic zone to determine average exposure rates as a function of distance. These results aresummarized in Table 2.4-3. All of the listed exposure values represent continuous occupancy (2190hr/qtr or 8760 hr/yr).Annual exposure rates measured at locations beyond the PNPS protected area boundary rangedfrom 40 to 154 mR/yr. The average exposure rate at control locations greater than 15 km fromPilgrim Station (i.e., Zone 4) was 60.2 +/- 10.9 mR/yr. When the 3-sigma confidence interval iscalculated based on these control measurements, 99% of all measurements of background ambientexposure would be expected to be between 27 and 93 mR/yr. The results for all TLDs within 15 km(excluding those Zone 1 TLDs posted within the site boundary) ranged from 40 to 81 mR/yr, whichcompares 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 withinthe PNPS protected/restricted area yield exposure measurements higher than the average naturalbackground. Such results are expected due to the close proximity of these locations to radiationsources onsite. The radionuclide nitrogen-16 (N-16) contained in steam flowing through the turbineaccounts for most of the exposure onsite. Although this radioactivity is contained within the turbineand is not released to the atmosphere, the "sky shine" which occurs from the turbine increases theambient radiation levels in areas near the turbine building.Page 28 A small number of offsite TLD locations in close proximity to the protected/restricted area indicatedambient radiation exposure above expected background levels. All of these locations are on PilgrimStation 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 BLEand BLW). Due to heightened security measures following September 11 2001, members for thegeneral public do not have access to such locations within the owner-controlled area.One TLD, located in the basement of the Plymouth Memorial Hall, indicated an annual exposure of76 mR in 2013. The higher exposure within the building at this location is due to the close proximityof stone building material, which contains higher levels of naturally-occurring radioactivity, as well asfrom the buildup of radon in this area of the building.It should be noted that several of the TLDs used to calculate the Zone 1 averages presented inTable 2.4-3 are located on Pilgrim Station property. If the Zone 1 value is corrected for the near-siteTLDs (those less than 0.6 km from the Reactor Building), the Zone 1 mean falls from a value of 71.6+/- 2113 mR/yr to 62.2 +/- 8.9 mR/yr. Additionally, exposure rates measured at areas beyond Entergy'scontrol did not indicate any increase in ambient exposure from Pilgrim Station operation. Forexample, the annual exposure rate calculated from the two TLDs adjacent to the nearest offsiteresidence 0.80 kilometers (0.5 miles) southeast of the PNPS Reactor Building was 62.1 +/- 7.7 mR/yr,which compares quite well with the average control location exposure of 62.2 +/- 8.9 mR/yr.In conclusion, measurements of ambient radiation exposure around Pilgrim Station do not indicateany significant increase in exposure levels. Although some increases in ambient radiation exposurelevel were apparent on Entergy property very close to Pilgrim Station, there were no measurableincreases at areas beyond Entergy's control.2.5 Air Particulate Filter Radioactivity AnalysesAirborne particulate radioactivity is sampled by drawing a stream of air through a glass fiber filter thathas a very high efficiency for collecting airborne particulates. These samplers are operatedcontinuously, and the resulting filters are collected weekly for analysis. Weekly filter samples areanalyzed for gross beta radioactivity, and the filters are then composited on a quarterly basis foreach location for gamma spectroscopy analysis. PNPS uses this technique to monitor 10 locationsin the Plymouth area, along with the control location in East Weymouth.Out of 572 filters (11 locations

• 52 weeks), 563 samples were collected and analyzed during 2013.Several air sampling stations lost power during winter storm Nemo during the week of 05-Febthrough 12-Feb 2014. Another problem occurred at location WR when tree trimming activities on 14-Aug-2012 resulted in damage to the electrical service and sampling station. The sampler was notrepaired until 28-Feb-2013, resulting in the loss of sampling capabilities at this location for the last 21weeks of 2012, and the first eight weeks of 2013. This event is described in Condition Report CR-PNP-2012-3545. There were also a few instances where power was lost or pumps failed during thecourse of the sampling period at some of the air sampling stations, resulting in lower than normalsample volumes. All of these discrepancies are noted in Appendix D.The results of the analyses performed on these 563 filter samples are summarized in Table 2.5-1.Trend plots for the gross beta radioactivity levels at the near station, property line, and offsiteairborne monitoring locations are shown in Figures 2.5-1, 2.5-2 and 2.5-3, respectively. Gross betaradioactivity was detected in 563 of the filter samples collected, including 52 of the 52 controllocation samples. This gross beta activity arises from naturally-occurring radionuclides such asradon decay daughter products. Naturally-occurring beryllium-7 was detected in 44 out of 44 of thequarterly composites analyzed with gamma spectroscopy. Naturally-occurring potassium-40 (K-40)was detected in 1 of 4 control samples. No airborne radioactivity attributable to Pilgrim Station wasPage 29 detected in any of the samples collected during 2013, and results of any detectable naturally-occurring radioactivity were similar to those observed in the preoperational monitoring program.2.6 Charcoal Cartrid-ge Radioactivity AnalysesAirborne radioactive iodine is sampled by drawing a stream of air through a charcoal cartridge after ithas 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 foranalysis. Weekly cartridge samples are analyzed for radioactive iodine. The same eleven locationsmonitored for airborne particulate radioactivity are also sampled for airborne radioiodine.Out of 572 cartridges (11 locations

• 52 weeks), 563 samples were collected and analyzed during2013. Several air sampling stations lost power during winter storm Nemo during the week of 05-Febthrough 12-Feb 2014. Another problem occurred at location WR when tree trimming activities on 14-Aug-2012 resulted in damage to the electrical service and sampling station. The sampler was notrepaired until 28-Feb-2013, resulting in the loss of sampling capabilities at this location for the last 21weeks of 2012, and the first eight weeks of 2013. This event is described in Condition Report CR-PNP-2012-3545. There were also a few instances where power was lost or pumps failed during thecourse of the sampling period at some of the air sampling stations, resulting in lower than normalsample volumes. All of these discrepancies are noted in Appendix D. Despite such events during2013, required LLDs were met on 563 of the 563 cartridges collected during 2013.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 charcoalcartridges collected.2.7 Milk Radioactivity AnalysesIn July 2002, the Plymouth County Farm ceased operation of its dairy facility. This was historicallythe only dairy facility near Pilgrim Station, and had been sampled continuously since Pilgrim Stationbegan operation in 1972. Although attempts were made to obtain samples from an alternateindicator location within 5 miles as specified in NRC guidance (Reference 14), a suitable substitutelocation could not be found. Thus, milk collection at an indicator location was discontinued in July2002, but control samples of milk continued to be collected and analyzed in the event an indicatorlocation could be secured. In conjunction with the standardization of the ODCM during 2003, thedecision was made to remove milk sampling from the PNPS Radiological Environmental MonitoringProgram 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 2.5miles west of PNPS, in a relatively upwind direction. Due to the limited number of milk animalsavailable, this location is not able to provide the necessary volume of 4 gallons of milk every twoweeks to facilitate the milk sampling program and meet the required detection sensitivities. Althoughmilk sampling is not performed at Plimoth Plantation, effluent dose calculations are performed forthis location assuming the presence of a milk ingestion pathway, as part of the annual Effluent andWaste Disposal Report (Reference 17).As included in a provision in standard ODCM guidance in NUREG-1302 (Reference 13), samplingand analysis of vegetation from the offsite locations calculated to have the highest D/Q depositionfactor can be performed in lieu of milk sampling. Such vegetation sampling has been routinelyperformed at Pilgrim Station as part of the radiological environmental monitoring program, and theresults of this sampling are presented in Section 2.9.Page 30 2.8 Forage Radioactivity AnalysesSamples of animal forage (hay) had been collected in the past from the Plymouth County Farm, andfrom control locations in Bridgewater. However, due to the absence of any grazing animals within afive-mile radius of Pilgrim Station that are used for generation of food products (milk or meat), nosamples of forage were collected during 2013. A number of wild vegetation samples were collectedwithin a five mile radius of Pilgrim Station as part of the vegetable/vegetation sampling effort, andthe results of this sampling would provide an indication of any radioactivity potentially entering theforage-milk or forage-meat pathways. Results of the vegetable/vegetation sampling effort arediscussed in the following section.2.9 VecietableNegetation Radioactivity AnalysesSamples of vegetables and naturally-growing vegetation have historically been collected from thePlymouth County Farm and from the control locations in Bridgewater, Sandwich, and Norton. Inaddition, samples of vegetables or leafy vegetation were collected at or near a number of gardensidentified during the Annual Land Use Census. Results of this census are discussed in Appendix C.In addition to these garden samples, naturally-growing vegetation is collected from locations yieldingthe highest D/Q deposition factors. All of the various samples of vegetables/vegetation are collectedannually and analyzed by gamma spectroscopy.Twenty-three samples of vegetables/vegetation were collected and analyzed as required during2013. Results of the gamma analyses of these samples are summarized in Table 2.9-1. Naturally-occurring beryllium-7, potassium-40, radium-226, and actinium/thorium-228 were identified in severalof the samples collected. Cesium-137 was also detected in four out of 15 samples of vegetationcollected from indicator locations, and one of eight control samples collected, with concentrationsranging from non-detectable (<12 pCi/kg) up to 61 pCi/kg. The highest concentration of 61 pCi/kgwas detected in a sample of natural vegetation collected from the Pine Hills area of the Pine Hillssouth of PNPS. This Cs-137 result is within of the normal range of average values expected forweapons-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 detectableCs-137 from nuclear weapons tests up into the range of 300 to 400 pCi/kg, whereas soil samplesoften indicated concentrations in excess of 2000 pCi/kg. Cs-137 has a 30-year half-life, andmeasureable concentrations still remain in soil and vegetation as a result of atmospheric nuclearweapons testing performed during the 1950s through 1970s. Weekly particulate air filters collectedfrom the Cleft Rock sampling station within 400 meters of where the vegetation was sampledindicated no detectable Cs-137. A review of effluent data presented in Appendix B indicates thatthere were no measurable airborne releases of Cs-137 from Pilgrim Station during 2013 that couldhave attributed to this level. The sample with the highest level of Cs-137 also contained high levelsof Ra-226 and AcTh-228, indicating appreciable soil content on the vegetation. This sample ofnatural vegetation was analyzed "as is" without any measure to clean the samples as normally wouldbe performed prior to consuming vegetables, and would have detected any Cs-1 37 in soil adheringto those leaves collected. Certain species of plants such as sassafras are also known to concentratechemical elements like cesium, and this higher-than-expected level is likely due to a combination ofexternal soil contamination and bioconcentration in the leaves of the plants sampled. These levelsare not believed to be indicative of any releases associated with Pilgrim Station. No radioactivityattributable to Pilgrim Station was detected in any of the vegetable/vegetation samples collectedduring 2013, and results of any detectable naturally-occurring radioactivity were similar to thoseobserved in the preoperational monitoring program.Page 31 2.10 Cranberry Radioactivity AnalysesSamples of cranberries are normally collected from two bogs in the Plymouth area and from thecontrol location in Kingston. Samples of cranberries are collected annually and analyzed by gammaspectroscopy. In 2012, the bog on Bartlett Road ceased harvesting operations, and a sample wascollected from an alternate location along Beaver Dam Road. Samples were also not available fromthe historical control location in Halifax, and a substitute control sample was collected from a bog inKingston. These discrepancies are noted in Appendix D.Two samples of cranberries were collected and analyzed during 2013. One of the bogs normallysampled along Bartlett Road is no longer in production. Results of the gamma analyses of cranberrysamples are summarized in Table 2.10-1. Cranberry samples collected during 2013 yieldeddetectable levels of naturally-occurring beryllium-7, potassium-40, and radium-226. No radioactivityattributable to Pilgrim Station was detected in any of the samples collected during 2013, and resultsof any detectable naturally-occurring radioactivity were similar to those observed in thepreoperational monitoring program.2.11 Soil Radioactivity AnalysesIn the past, a survey of radioactivity in soil had been conducted once every three years at the 10 airsampling stations in the Plymouth area and the control location in East Weymouth. However, inconjunction with standardization of the ODCM during 2003, the soil survey effort was abandoned infavor 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 AnalysesSamples of surface water are routinely collected from the discharge canal, Bartlett Pond in Manometand from the control location at Powder Point Bridge in Duxbury. Grab samples are collected weeklyfrom the Bartlett Pond and Powder Point Bridge locations. Samples of surface water are compositedevery four weeks and analyzed by gamma spectroscopy and low-level iodine analysis. Thesemonthly composites are further composited on a quarterly basis and tritium analysis is performed onthese quarterly samples.A total of 36 samples (3 locations

• 12 sampling periods) of surface water were collected andanalyzed as required during 2013. Results of the analyses of water samples are summarized inTable 2.12-1. Naturally-occurring potassium-40, radium-226, and actinium/thorium-228 weredetected in several of the samples, especially those composed primarily of seawater. Noradioactivity attributable to Pilgrim Station was detected in any of the surface water samplescollected during 2013.In response to the Nuclear Energy Institute Groundwater Protection Initiative, Pilgrim Stationinstalled a number of groundwater monitoring wells within the protected area in late 2007. Becauseall of these wells are onsite, they are not included in the offsite radiological monitoring program, andare not presented in this report. Details regarding Pilgrim Station's groundwater monitoring effortcan be found in the Annual Radioactive Effluent Release Report.Page 32 2.13 Sediment Radioactivity AnalysesSamples of sediment are routinely collected from the outfall area of the discharge canal and fromthree 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 areanalyzed by gamma spectroscopy.Twelve of twelve required samples of sediment were collected during 2013. Gamma analyses wereperformed on these samples. Results of the gamma analyses of sediment samples are summarizedin Table 2.13-1. Naturally-occurring beryllium-7, potassium-40, radium-226, and actinium/thorium-228 were detected in a number of the samples. No radioactivity attributable to Pilgrim Station wasdetected in any of the samples collected during 2013, and results of any detectable naturally-occurring radioactivity were similar to those observed in the preoperational monitoring program.2.14 Irish Moss Radioactivity AnalysesSamples of Irish moss are collected from the discharge canal outfall and two other locations in thePlymouth area (Manomet Point, Ellisville), and from a control location in Marshfield (Brant Rock). Allsamples are collected on a semiannual basis, and processed in the laboratory for gammaspectroscopy analysis.Eight samples of Irish moss scheduled for collection during 2013 were obtained and analyzed.Results of the gamma analyses of these samples are summarized in Table 2.14-1. Naturally-occurring potassium-40 and radium-226 were detected in a number of the samples. No radioactivityattributable to Pilgrim Station was detected in any of the samples collected during 2013, and resultsof any detectable naturally-occurring radioactivity were similar to those observed in thepreoperational monitoring program.2.15 Shellfish Radioactivity AnalysesSamples of blue mussels, soft-shell clams and quahogs are collected from the discharge canaloutfall and one other location in the Plymouth area (Plymouth Harbor), and from control locations inDuxbury and Marshfield. All samples are collected on a semiannual basis, and edible portionsprocessed in the laboratory for gamma spectroscopy analysis.Ten of the 10 required samples of shellfish meat scheduled for collection during 2013 were obtainedand analyzed. Results of the gamma analyses of these samples are summarized in Table 2.15-1.Naturally-occurring potassium-40 and radium-226 were detected in a number of the samples. Noradioactivity attributable to Pilgrim Station was detected in any of the samples collected during 2013,and results of any detectable naturally-occurring radioactivity were similar to those observed in thepreoperational monitoring program.Page 33 2.16 Lobster Radioactivity AnalysesSamples of lobsters are routinely collected from the outfall area of the discharge canal and fromcontrol locations in Cape Cod Bay and Vineyard Sound. Samples are collected monthly from thedischarge canal outfall from June through September and once annually from the control locations.All lobster samples are normally analyzed by gamma spectroscopy.Five samples of lobsters were collected as required during 2013. Results of the gamma analyses ofthese samples are summarized in Table 2.16-1. Naturally-occurring potassium-40 and radium-226were detected in a number of the samples. No radioactivity attributable to Pilgrim Station wasdetected in any of the samples collected during 2013, and results of any detectable naturally-occurring radioactivity were similar to those observed in the preoperational monitoring program.2.17 Fish Radioactivity AnalysesSamples of fish are routinely collected from the area at the outfall of the discharge canal and fromthe control locations in Cape Cod Bay and Buzzard's Bay. Fish species are grouped into four majorcategories according to their biological requirements and mode of life. These major categories andthe 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, MackerelGroup I fishes are sampled on a semiannual basis from the outfall area of the discharge canal, andon an annual basis from a control location. Group II, Ill, and IV fishes are sampled annually from thedischarge canal outfall and control location. All samples of fish are analyzed by gammaspectroscopy.Eight samples of fish were collected during 2013. The autumn sample of Group I Fish (flounder)was not available during the October sampling period due to seasonal unavailability as the fishmoved away from the Discharge Outfall to deeper water. Results of the gamma analyses of fishsamples collected are summarized in Table 2.17-1. The only radionuclides detected in any of thesamples were naturally-occurring potassium-40 and radium-226. No radioactivity attributable toPilgrim Station was detected in any of the samples collected during 2013, and results of anydetectable naturally-occurring radioactivity were similar to those observed in the preoperationalmonitoring program.Page 34 Table 2.2-1Routine Radioloqical Environmental Samplingq LocationsPilgrim Nuclear Power Station, Plymouth, MADescription Code Distance DirectionAir Particulate Filters, Charcoal CartridgesMedical Building WS 0.2 km SSEEast Rocky Hill Road ER 0.9 km SEWest Rocky Hill Road WR 0.8 km WNWProperty Line PL 0.5 km NNWPedestrian Bridge PB 0.2 km NOverlook Area OA 0.1 km WEast Breakwater EB 0.5 km ESECleft Rock CR 1.3 km SSWPlymouth Center PC 6.7 km WManomet Substation MS 3.6 km SSEEast Weymouth Control EW 40 km NWForaePlymouth County Farm CF 5.6 km WHansen Farm Control HN 35 km WVegetationPlymouth County Farm CF 5.6 km WHansen Farm Control HN 35 km WCranberriesBartlett Road Bog BT 4.3 km SSEBeaverdam Road Bog MR 3.4 km SHollow Farm Bog Control HF 16 km WNWPage 35 Table 2.2-1 (continued)Routine Radioloqical Environmental Sampling LocationsPil.rim Nuclear Power Station, Plymouth, MADescription Code Distance DirectionSurface WaterDischarge Canal DIS 0.2 km NBartlett Pond BP 2.7 km SEPowder Point Control PP 13 km NNWSedimentDischarge Canal Outfall DIS 0.8 km NEPlymouth Harbor Ply-H 4.1 km WDuxbury Bay Control Dux-Bay 14 km NNWPlymouth Beach PLB 4.0 km WNWManomet Point MP 3.3 km ESEGreen Harbor Control GH 16 km NNWIrish MossDischarge Canal Outfall DIS 0.7 km NNEManomet Point MP 4.0 km ESEEllisville EL 12 km SSEBrant Rock Control BR 18 km NNWShellfishDischarge Canal Outfall DIS 0.7 km NNEPlymouth Harbor Ply-H 4.1 km WDuxbury Bay Control Dux-Bay 13 km NNWManomet Point MP 4.0 km ESEGreen Harbor Control GH 16 km NNWLobsterDischarge Canal Outfall DIS 0.5 km NPlymouth Harbor Ply-H 6.4 km WNWDuxbury Bay Control Dux-Bay 11 km NNWFishesDischarge Canal Outfall DIS 0.5 km NPriest Cove Control PC 48 km SWJones River Control JR 13 km WNWVineyard Sound Control MV 64 km SSWBuzzard's Bay Control BB 40 km SSWCape Cod Bay Control CC-Bay 24 km ESEPage 36 Table 2.4-1Offsite Environmental TLD ResultsTLD Station TLD Location* Quarterl Exposure -mR/quarter (Value +/- Std.Dev.)2013 Annual-ID Description Distance/Direction Jan-Mar Apr-Jun Jul-Sep Oct-Dec ExposureI I mR/yearZone 1 TLDs: 0-3 km 0-3 km 17.1 +/- 5.1 16.5 +/- 4.8 18.4 +/- 5.8 19.6 +/- 5.2 71.6 +/- 21.3BLW BOAT LAUNCH WEST 0.11 km E 32.6+/- 1.6 33.1 +/- 1.0 35.5+/-2.1 34.4_+/-2.9 135.6+/-6.7OA OVERLOOK AREA 0.15kmW 37.9+/-2.0 30.3+/- 1.4 42.9+/-2.5 43.2+/- 1.7 154.3+/-24.3TC HEALTH CLUB 0.15 km WSW 18.4 +/- 0.8 16.5 +/- 0.6 20.5 +/- 0.8 20.6 +/- 0.9 76.0 +/- 7.9BLE BOAT LAUNCH EAST 0.16 km ESE 27.0 +/- 1.9 31.7 +/- 2.4 31.8 +/- 1.2 29.1 +/- 1.8 119.5 +/-9.9PB PEDESTRIAN BRIDGE 0.21 km N 26.2 +/- 1.4 24.4 +/- 0.8 26.9 +/- 1.1 27.4 +/- 1.5 104.9 +/- 5.9P01 SHOREFRONT SECURITY 0.22 km NNW 15.9 +/- 0.8 16.5 +/- 0.7 18.1 +/- 1.2 18.6 +/- 1.0 69.1 +/- 5.5WS MEDICAL BUILDING 0.23 km SSE 18.6 +/- 1.2 18.2 +/- 0.8 20.0 +/- 1.0 21.0 +/- 1.0 77.8 +/- 5.5CT PARKING LOT 0.31 km SE 19.2 +/- 1.3 18.2 +/- 0.6 20.9 +/- 0.8 19.0 +/- 0.7 77.3 +/- 4.9PA SHOREFRONT PARKING 0.35 km NNW 16.3 +/- 0.9 17.8 +/- 0.7 19.7 +/- 1.0 18.7 +/- 0.9 72.5 +/- 6.0A STATION A 0.37 km WSW 14.6 +/- 1.5 14.4 +/- 0.8 16.5 +/- 0.8 18.9 +/- 0.9 64.4 +/- 8.6F STATION F 0.43 km NW 15.0 +/- 0.7 14.0 +/- 0.8 16.4 +/- 0.7 18.8 +/- 1.0 64.2 +/- 8.4EB EAST BREAKWATER 0.44 km ESE 16.0 +/- 0.9 17.5 +/- 1.0 18.6 +/- 0.7 19.0 +/- 0.9 71.1 +/- 5.7B STATION B 0.44 km S 22.7 +/- 0.9 18.6 +/- 0.7 21.5 +/- 1.2 23.4 +/- 1.2 86.2 +/- 8.7PMT PNPS MET TOWER 0.44 km WNW 17.3 +/- 0.9 15.7 +/- 1.0 17.7 +/- 0.7 20.8 +/- 1.1 71.5 +/- 8.7H STATION H 0.47 km SW 17.7 +/- 1.4 16.6 +/- 0.6 19.6 +/- 1.0 21.9 +/- 1.1 75.8 +/- 9.5I STATION I 0.48 km WNW 15.9 +/- 1.0 13.9 +/- 0.7 16.9 +/- 0.8 19.5 +/- 0.9 66.2 +/- 9.5L STATION L 0.50 km ESE 15.4 +/- 0.7 18.6 +/- 0.7 19.2 +/- 0.8 18.5 +/- 1.0 71.7 +/- 7.0G STATION G 0.53 kmW 15.3+/-0.9 14.1+/-0.8 16.1 +/-0.7 16.2+/-0.8 61.8+/-4.2D STATION D 0.54 km NNW 18.5 +/- 0.9 15.5 +/- 0.6 17.3 +/- 1.0 20.2 +/- 1.0 71.5 +/- 8.1PL PROPERTY LINE 0.54 km NW 15.4+/-0.8 15.9+/-0.8 16.6+/- 1.1 16.8+/-0.9 64.7+/-3.2C STATION C 0.57 km ESE 16.0 +/- 0.8 14.7 +/- 0.6 18.4 +/- 1.2 17.8 +/- 0.9 66.8 +/- 6.9HB HALL'S BOG 0.63 km SE 14.6 +/- 0.8 17.3 +/- 0.6 19.1 +/- 1.0 Missing 67.9 +/- 9.2GH GREENWOOD HOUSE 0.65 km ESE 16.4 +/- 0.9 17.0 +/- 0.7 Missing 17.7 +/- 0.8 68.1 +/- 3.4WR W ROCKY HILL ROAD 0.83 km WNW 19.6 +/- 0.8 19.2 +/- 0.9 20.9 +/- 0.9 20.8 +/- 1.0 80.5 +/- 3.8ER E ROCKY HILL ROAD 0.89 km SE 14.0 +/- 0.9 14.2 +/- 0.7 14.4 +/- 0.8 15.2 +/- 0.8 57.8 +/- 2.6MT MICROWAVE TOWER 1.03 km SSW 14.4 +/- 0.6 18.0 +/- 0.7 16.0 +/- 0.8 16.9-+/- 0.9 65.2 +/- 6.4CR CLEFT ROCK 1.27 km SSW 18.3 +/- 0.8 17.5 +/- 0.9 15.9 +/- 1.1 17.3 +/- 1.2 68.9 +/- 4.4BD BAYSHORE/GATE RD 1.34 km WNW 14.9 +/- 0.7 14.8 +/- 0.6 16.7 +/- 0.8 17.8 +/- 0.9 64.2 +/- 6.0MR MANOMET ROAD 1.38 km S 16.0 +/- 0.7 15.2 +/- 0.6 17.4 +/- 0.7 20.3 +/- 1.0 68.9 +/- 9.2DR DIRT ROAD 1.48 km SW 12.9+/-0.6 11.7+/-0.5 13.4+/-0.6 16.8+/- 1.2 54.8+/-8.9EM EMERSON ROAD 1.53 km SSE 15.9 +/- 0.8 14.2 +/- 0.6 16.1 +/- 0.7 16.9 +/- 1.0 63.1 +/- 4.8EP EMERSON/PRISCILLA 1.55 km SE Missing 14.5 +/- 0.8 16.4 +/- 0.9 17.4 +/- 0.9 64.5 +/- 6.2AR EDISON ACCESS ROAD 1.59 km SSE 13.1 +/- 0.7 12.8 +/- 0.6 14.3 +/- 0.7 17.2 +/- 0.8 57.5 +/- 8.2BS BAYSHORE 1.76 km W 16.1 +/- 0.8 15.4 +/- 0.8 17.3 +/- 0.7 20.3 +/- 1.0 69.1 +/- 8.9E STATION E 1.86 km S 15.1 +/- 0.7 13.7 +/- 0.5 15.6 +/- 0.6 17.9 +/- 1.0 62.3 +/- 7.2JG JOHN GAULEY 1.99 km W 15.4 +/- 0.7 14.6 +/- 0.6 16.4 +/- 0.8 18.1 +/- 1.2 64.5 +/- 6.2J STATION J 2.04 km SSE 13.5 +/- 0.7 13.1 +/- 0.5 15.1 +/- 1.2 17.4 +/- 0.8 59.2 +/- 8.0WH WHITEHORSE ROAD 2.09 km SSE 15.6 +/- 0.6 14.5 +/- 0.5 16.2 +/- 0.8 17.1 +/- 0.8 63.4 +/- 4.7RC PLYMOUTH YMCA 2.09 km WSW 14.0_+/-0.6 14.0_+/-0.6 15.3+/-0.7 18.8+/- 1.0 62.1 +/-9.2K STATION K 2.17 krn S 13.5 +/- 0.6 13.1 +/- 0.8 14.2 +/- 0.8 17.0 +/- 0.8 57.9 +/- 7.1TT TAYLOR/THOMAS 2.26 km SE 15.2 +/- 0.8 12.8 +/- 0.7 15.0 +/- 0.7 16.0 +/- 1.0 59.0 +/- 5.6YV YANKEE VILLAGE 2.28 km WSW 14.7 +/- 0.6 14.4 +/- 0.6 15.2 +/- 1.3 18.6 +/- 0.9 62.9 +/- 8.0GN GOODWIN PROPERTY 2.38 km SW 11.2+/- 0.8 10.1+/-0.6 11.5+/- 0.5 14.9+/- 1.0 47.8+/- 8.4RW RIGHT OF WAY 2.83 km S 12.7+/-0.8 11.4+/-0.9 12.9+/-0.6 13.0+/-+0.7 50.0_+/-3.4TP TAYLORIPEARL 2.98 km SE 15.0 +/- 0.7 12.6 +/- 0.6 15.0 +/- 1.4 15.3 +/- 0.9 57.8+/- 5.4Distance 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 ResultsTLD Station TLD Location* Quarterl, Exposure -mR/quarter (Value +/- Std.Dev.)2013 Annual-ID Description Distance/Direction Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure/ 1mR/yearZone 2 TLDs: 3-8km 3-8km 14.2+/-2.3 13.0+/- 1.9 14.8+/-2.0 15.9+/-2.0 57.8+/-9.0VR VALLEY ROAD 3.26 km SSW 14.2 +/- 0.8 11.7 +/- 0.6 14.3 +/- 0.9 Missing 53.6 +/- 6.2ME MANOMET ELEM 3.29 km SE 14.8 +/- 0.7 13.1 +/- 0.8 15.4 +/- 0.7 Missing 57.8 +/- 5.0WC WARREN/CLIFFORD 3.31 km W 12.7 +/- 0.6 12.3 +/- 0.7 Missing 16.9 +/- 0.9 55.9 + 10.5BB RT.3A/BARTLETT RD 3,33 km SSE 14.9 +/- 0.8 13.5 +/- 0.5 14.9 +/- 0.6 18.1 +/- 1.1 61.4 7.9MP MANOMET POINT 3.57 km SE 15.0 +/- 0.7 13.0 +/- 1.0 15.1 +/- 0.7 14.9 +/- 0.8 57.9 +/-4.3MS MANOMET SUBSTATION 3.60 km SSE 16.9 +/- 0.6 17.1 +/- 0.9 17.5 +/- 0.8 17.8 +/- 0.9 69.2 +/- 2.3BW BEACHWOOD ROAD 3.93 km SE 15.6 +/- 0.7 12.6 +/- 0.7 15.6 +/- 0.8 16.4 +/- 1.1 60.3 +/- 6.9PT PINES ESTATE 4.44 km SSW 13.2 +/- 0.7 11.6 +/- 0.6 14.1 +/- 0.7 14.2 +/- 0.8 53.2 +/-4.9EA EARL ROAD 4.60 km SSE 11.9+/-0.6 12.1+/-0.6 12.8+/- 1.0 16.4+/- 1.1 53.2+/-8.7SP S PLYMOUTH SUBST 4.62 km W 15.8 +/- 1.1 13.4 +/- 0.5 15.8 +/- 1.2 15.6 +/- 0.8 60.6 5.1RP ROUTE 3 OVERPASS 4.81 km SW 15.8 +/- 1.2 13.6 +/- 0.6 16.0 +/- 0.7 15.8 +/- 0.7 61.2++/-5.0RM RUSSELL MILLS RD 4.85 km WSW 14.3 +/- 1.2 12.4 +/- 0.6 14.9 +/- 0.7 15.1 +/- 0.8 56.7 +/- 5.3HD HILLDALE ROAD 5,18 km W 13.8 +/- 1.0 13.6 +/- 0.9 15.2 +/- 0.9 17.7 +/- 0.9 60.2 +/- 7.7MB MANOMET BEACH 5,43 km SSE 15.7 +/- 0.8 13.4 +/- 0.6 15.7 +/- 1.0 16.3 +/- 0.9 61.2 +/- 5.4BR BEAVERDAM ROAD 5.52 km S 15.0 +/- 1.3 13.4 +/- 0.6 15.7 +/- 1.5 16.0 +/- 0.8 60.1 +/- 5.0PC PLYMOUTH CENTER 6.69 km W 9.7 +/- 0.7 9.9 +/- 0.6 9.9 +/- 0.8 11.0 +/- 0.6 40.5 +/- 2.7LD LONG POND/DREW RD 6.97 km WSW 10.9 +/- 0.5 14.0 +/- 0.6 13.7 +/- 0.6 16.5 +/- 0.9 55.2 +/- 9.2HR HYANNIS ROAD 7.33 km SSE Missing Missing 14.0 +/- 0.7 15.0 +/- 0.7 57.9 +/- 3.4SN SAQUISH NECK 7.58 km NNW 10.6 +/- 1.1 9.2 +/- 0.4 11.8 +/-0.9 12.8 +/- 0.9 44.6 +/- 6.5MH MEMORIAL HALL 7.58 km WNW 19.1 +/- 0.7 17.6 +/- 0.7 19.4 0.8 19.9 +/- 0.9 76.0 +/- 4.2CP COLLEGE POND 7.59 km SW 13.3 +/- 0.7 13.3 +/- 0.6 14.3 +/- 0.8 Missing 54.4 +/- 3.0Zone3TLDs: 8-15km 8-15 km 13.8+/- 1.1 13.0+/- 1.7 14.1 +/- 1.7 15.9+/- 1.9 56.7+/-7.6DW DEEP WATER POND 8.59 km W 15.3 +/- 0.9 14.4 +/- 0.5 16.9 +/- 1.1 18.8 +/- 1.4 65.3 +/- 8.0LP LONG POND ROAD 8.88 km SSW 13.2 +/- 0.7 12.2 +/- 0.6 13.1 +/- 0.6 14.8 +/- 0.7 53.3 +/- 4.5NP NORTH PLYMOUTH 9.38 km WNW 15.3 +/- 0.7 17.4 +/- 1.0 17.3 +/- 1.0 19.5 +/- 1.5 69.4 +/- 7.3SS STANDISH SHORES 10.39 krn NW 13.3+/-0.6 11.9+/-0.6 13.5+/-0.7 15.1 +/- 1.0 53.9+/-5.4EL ELLISVILLE ROAD 11.52 km SSE 14.6 +/- 0.9 12.7 +/- 0.6 14.0 +/- 0.9 15.3 +/- 0.8 56.7 +/- 4.6UC UP COLLEGE POND RD 11.78 kmSW 11.7+/- 1.5 11.6+/-0.4 12.2+/-0.8 13.7+/-0.8 49.2+/-4.3SH SACRED HEART 12.92 km W 14.3 +/- 0.8 12.6 +/- 0.8 13.8 +/- 0.6 15.7 +/- 0.8 56.5 +/- 5.4KC KING CAESAR ROAD 13.11 km NNW 13.6 +/- 0.8 12.1 +/- 0.5 13.4 +/- 0.6 15.8 +/- 0.8 54.8 +/- 6.3BE BOURNE ROAD 13.37 km S 13.4 +/- 0.7 12.1 +/- 0.5 12.9 +/- 0.5 14.4 +/- 1.1 52.8 +/- 4.0SA SHERMAN AIRPORT 13.43 km WSW 13.1 +/- 0.6 12.5 +/- 0.7 13.5 +/- 0.7 15.8 +/- 1.0 54.9 +/- 5.9Zone 4 TLDs: >15 km >15 km 14.7 +/- 2.9 13.9 +/- 3.0 15.2 +/- 2.6 16.4 +/- 2.5 60.2 +/-10.9CS CEDARVILLE SUBST 15.93 km S 15.8 +/- 0.7 13.9 +/- 0.6 16.3 +/- 0.8 17.3 +/- 1.4 63.3 +/- 6.1KS KINGSTON SUBST 16.15 km WNW 15.3 +/- 0.8 14.3 +/- 0.5 15.2 +/- 0.7 16.6 +/- 0.9 61.4 +/-4.1LR LANDING ROAD 16.46 km NNW 13.4 +/- 0.9 12.8 +/- 0.5 14.6 +/- 0.7 15.2 +/- 0.9 56.0 +/- 4.6CW CHURCH/WEST 16.56 km NW 9.1 +/-0.5 8.5 0.5 10.4 +/- 0.9 11.7 +/- 0.7 39.7 +/-5.9MM MAIN/MEADOW 17.02 km WSW 14.4 +/-0.7 13.4 +/-0.8 14.5 +/- 1.0 16.7 +/- 1.3 59.0 +/-5.8DMF DIV MARINE FISH 20.97 km SSE 17.5 +/-0.9 17.8 +/-1.3 17.6 +/- 0.7 19.4 +/- 0.9 72.4 +/-4.0EW E WEYMOUTH SUBST 39.69 km NW 17.6 +/- 1.0 16.4 +/- 0.9 17.9 +/- 0.7 18.0 +/- 1.2 69.9 +/- 3.5* 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 2.4-2Onsite Environmental TLD ResultsTLD Station TLD Location* Quarterl Exposure- mR/quarter (Value+/- Std.Dev.)2013 Annual-ID Description Distance/Direction Jan-Mar Apr-Jun Jul-Sep Oct-Dec ExposureI I I 1mR/yearOnsite TLDsP21 O&M/RXB. BREEZEWAY 50 m SE 28.2 +/- 1.2 29.0 +/- 1.2 26.5 +/- 1.2 24.5 +/- 1.1 108.2 +/-8.4P24 EXEC.BUILDING 57 m W 42.7 +/- 1.5 41.1 +/- 1.5 47.7 +/- 2.4 50.8 +/- 2.8 182.4 +/- 18.5P04 FENCE-R SCREENHOUSE 66 m N 36.5 +/- 1.3 41.2 +/- 2.0 43.4 +/- 1.8 44.0 +/- 1.8 165.2 +/- 14.1P20 O&M -2ND W WALL 67 m SE 27.3 +/- 1.7 24.1 +/- 0.8 28.0 +/- 2.2 28.3 +/- 1.9 107.7 +/-8.4P25 EXEC.BUILDING LAWN 76 m WNW 33.9 +/- 1.7 43.0 +/- 2.1 43.1 +/- 2.5 47.4 +/- 3.2 167.4 +/- 23.2P05 FENCE-WATER TANK 81 m NNE 21.1 +/- 0.9 21.7 +/- 1.0 22.5 +/- 0.9 24.2 +/- 0.9 89.4 +/- 5.6P06 FENCE-OIL STORAGE 85m NE 29.4+/- 1.2 29.4+/- 1.4 30.3+/- 1.8 31.5+/-2.4 120.6+/-5.4P19 O&M -2ND SW CORNER 86 m S 20.2 +/- 1.0 19.8 +/- 0.8 20.8 +/- 1.2 22.4 +/- 1.1 83.2 +/-4.9P18 O&M -1ST SW CORNER 90mS 24.3+/- 1.4 23.5+/-0.8 29.8+/- 1.1 31.3+/-2.0 108.9+/- 15.8P08 COMPRESSED GAS STOR 92 rn E 31.9 +/- 2.4 31.5 +/- 2.5 32.4 +/- 1.3 34.2 +/- 1.6 130.0 +/- 6.2P03 FENCE-L SCREENHOUSE 100 m NW 33.7 +/- 1.2 29.0 +/- 0.9 32.8 +/- 1.2 35.0 +/- 2.4 130.5 +/- 10.7P17 FENCE-EXEC.BUILDING 107 m W 51.0 +/- 2.9 42.9 +/- 3.3 52.5.+/- 2.1 52.9 +/- 1.9 199.3+/- 19.4P07 FENCE-INTAKE BAY 121 rn ENE 25.4 +/- 1.3 25.5 +/- 1.3 28.7 +/- 1.2 28.2 +/- 1.1 107.8 +/- 7.5P23 O&M- 2ND S WALL 121 mSSE 26.0+/- 1.3 23.4+/-0.9 27.1 +/- 1.4 29.2_+/- 1.4 105.8+/- 10.0P26 FENCE-WAREHOUSE 134 m ESE 28.3 +/- 1.2 31.1 +/- 1.2 29.6 +/- 1.7 30.4 +/- 1.7 119.4 +/-5.7P02 FENCE-SHOREFRONT 135m MNW 25.4 +/- 1.2 23.5 +/- 0.8 28.7 +/- 1.7 29.7 +/- 1.2 107.4+/- 11.8P09 FENCE-W BOAT RAMP 136 m E 26.1 +/- 1.2 25.9 +/- 1.5 27.5 +/- 1.6 26.5 +/- 1.5 106.0 +/- 4.1P22 O&M -2ND N WALL 137 m SE 20.6 +/- 1.1 20.7 +/- 0.8 21.8 +/- 0.9 22.2 +/- 1.2 85.3 +/- 3.7P16 FENCE-W SWITCHYARD 172 m SW 69.1 +/- 2.7 56.4 +/- 3.3 76.1 +/- 4.0 75.4 +/- 5.0 276.9 37.3P11 FENCE-TCF GATE 183 m ESE 40.1 +/- 1.7 53.0 +/- 1.6 51.5 +/- 3.0 38.4 +/- 1.8 183.0+/- 30.5P27 FENCE-TCF/BOAT RAMP 185 m ESE 21.8+/- 1.0 23.6+/- 1.1 25.0+/- 1.9 23.5+/- 1.3 93.9+/-5.8P12 FENCE-ACCESS GATE 202 m SE 23.9 +/- 1.0 21.8 +/- 0.7 23.5 +/- 1.3 25.3 +/- 1.3 94.6 +/- 6.2P15 FENCE-E SWITCHYARD 220 m S 22.0 +/- 1.1 21.7 +/- 1.0 24.5 +/- 0.9 25.1 +/- 1.7 93.2 +/- 7.4P10 FENCE-TCF/INTAKE BAY 223 m E 24.9 +/- 1.7 28.6 +/- 1.2 29.6 +/- 1.6 24.8 +/- 1.1 107.9 +/- 10.2P13 FENCE-MEDICAL BLDG. 224 m SSE 21.5+/- 1.2 20.3+/- 1.5 22.9+/- 1.4 24.7+/- 1.4 89.4+/-8.1P14 FENCE-BUTLER BLDG 228 m S 20.8 +/- 0.9 18.9 +/- 1.1 21.1 +/- 0.9 22.9 +/- 1.3 83.7 +/- 6.7P28 FENCE-TCF/PRKNG LOT 259 m ESE 68.2 +/- 2.3 53.1 +/- 2.8 80.0 +/- 4.7 55.7 +/- 2.1 257.1 +/- 50.0* 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 2.4-3Average TLD Exposures By Distance Zone During 2013Average Exposure +/- Standard Deviation: mR/)eriodExposure Zone 1* 1 Zone 2 Zone 3 Zone 4Period 0-3 km 3-8 km 8-15 km >15 kmJan-Mar 17.1 +/- 5.1 14.2 +/- 2.3 13.8 +/- 1.1 14.7 +/- 2.9Apr-Jun 16.5 +/- 4.8 13.0 +/- 1.9 13.0 +/- 1.7 13.9 +/- 3.0Jul-Sep 18.4 +/- 5.8 14.8 +/- 2.0 14.1 +/- 1.7 15.2 +/- 2.6Oct-Dec 19.6 +/- 5.2 15.9 +/- 2.0 15.9 +/- 1.9 16.4 +/- 2.5Jan-Dec 71.6 +/- 21.3** 57.8 +/- 9.0 56.7 +/- 7.6 60.2 +/- 10.9Zone 1 extends from the PNPS restricted/protected area boundary outward to 3 kilometers (2miles), and includes several TLDs located within the site boundary.When corrected for TLDs located within the site boundary, the Zone 1 annual average iscalculated to be 62.2 +/- 8.9 mR/yr.Page 40 Table 2.5-1Air Particulate Filter Radioactivity AnalysesRadiological Environmental Program SummaryPilgrim Nuclear Power Station, Plymouth, MA(January -December 2013)KAr-n1"KA* W, ADj 9 Fj_Indicator Stations Station with Highest Mean Control StationsMean +/- Std.Dev. Station: Mean +/- Std.Dev. Mean +/- Std.Dev.No. Analyses Required Range Range RangeRadionuclide Non-routine* LLD Fraction>LLD Fraction>LLD Fraction>LLDGross Beta 563 0.01 1.3E-2 +/- 4.9E-3 EW: 1.4E-2 +/- 5.3E-3 1.4E-2 +/- 5.3E-30 4.7E-4 -3.5E-2 4.4E-3 -3.OE-2 4.4E-3 -3.OE-2511/511 52/52 52/52Be-7 43 1.0E-1 +/- 1.gE-2 EW: 1.2E-1 +/- 1.9E-2 1.2E-1 +/- 1.9E-20 6.3E 1.4E-1 1.0E-1 -1.4E-1 1.0E-1 -1.4E-140/40 4/4 4/4K-40 43 <LLD 5.9E-2 +/- 1.3E-2 5.9E-2 +/- 1.3E-20 <LLD <LLD -5.gE-2 <LLD -5.9E-20/40 1/4 1/4Cs-134 43 0.05 <LLD <LLD <LLD0 <LLD <LLD <LLD0/40 0/40 0/4Cs-137 43 0.06 <LLD <LLD <LLD0 <LLD <LLD <LLD0/40 0/40 0/4Ra-226 43 <LLD <LLD <LLD0 <LLD <LLD <LLD1 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 2.6-1Charcoal Cartridge Radioactivity AnalysesRadiological Environmental Program SummaryPilgrim Nuclear Power Station, Plymouth, MA(January -December 2013)MEDIUM: Charcoal Cartridae (CF) UNITS: DCi/cubic meterIndicator Stations Station with Highest Mean Control StationsMean +/- Std.Dev. Station: Mean +/- Std.Dev. Mean +/- Std.Dev.No. Analyses Required Range Range RangeRadionuclide Non-routine* LLD Fraction>LLD Fraction>LLD Fraction>LLD1-131 563 0.07 <LLD <LLD <LLD0 <LLD <LLD <LLD1 0/511 0/52 0/52* Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.Page 42 Table 2.7-1Milk Radioactivity AnalysesRadiological Environmental Program SummaryPilgrim Nuclear Power Station, Plymouth, MA(January -December 2013)No milk sampling was performed during 2013, as no suitable indicator locations for milk productionwere available for sampling within 5 miles of Pilgrim Station.Page 43 Table 2.8-1Forage Radioactivity AnalysesRadiological Environmental Program SummaryPilgrim Nuclear Power Station, Plymouth, MA(January -December 2013)No forage sampling was performed during 2013, as no grazing animals used for food productswere available at any indicator locations within 5 miles of Pilgrim Station.Page 44 Table 2.9-1Vegetable/Vegetation Radioactivity AnalysesRadiological Environmental Program SummaryPilgrim Nuclear Power Station, Plymouth, MA(January -December 2013)IIA- X/-lf~fir-" C-r-"Kirre -; 11IVI UIU VI. V L L "I j h! -I Q,,lll W. '., J liW Indicator Stations Station with Highest Mean Control StationsMean +/- Std.Dev. Station: Mean +/- Std.Dev. Mean +/- Std.Dev.No. Analyses Required Range Range RangeRadionuclide Non-routine LLD Fraction>LLD Fraction>LLD Fraction>LLDBe-7 23 1.5E+3 +/- 8.9E+2 DMF: 3.5E+3 +/- 1.3E+2 2.OE+3 +/- 1.5E+30 <LLD -2.8E+3 3.5E+3 -3.5E+3 <LLD -3.5E+310/15 1/1 3/8K-40 23 3.2E+3 +/- 8.7E+2 Norton: 7.7E+3 +/- 2.5E+2 3.7E+3 +/- 2.2E+30 2.1E+3 -5.3E+3 7.7E+3 -7.7E+3 1.OE+3 -7.7E+315/15 1/1 8/81-131 23 60 <LLD <LLD <LLD0 <LLD <LLD <LLD0/15 0/15 0/8Cs-134 23 60 <LLD <LLD <LLD0 <LLD <LLD <LLD0/15 0/15 0/8Cs-137 23 80 3.7E+1 +/- 1.9E+1 Pine Hills: 6.1E+1 +/- 7.1E+0 9.2E+0 +/- 4.1E+00 <LLD -6.1E+1 6.1E+1 -6.1E+1 <LLD -9.2E+04/15 1/1 1/8Ra-226 23 4.8E+2 +/- 3.6E+2 Ply Cnty: 7.4E+2 +/- 1.3E+2 4.OE+2 +/- 2.OE+20 <LLD -7.4E+2 <LLD -7.4E+2 <LLD -5.7E+22/15 1/4 4/8AcTh-228 23 2.5E+2 +/- 2.6E+2 Greenwood: 6.4E+2 +/- 3.OE+1 1.IE+2 +/- 6.4E+10 <LLD -6.4E+2 6.4E+2 -6.4E+2 <LLD -1.7E+24/15 1/1 3/8* Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.Page 45 Table 2.10-1Cranberry Radioactivity AnalysesRadiological Environmental Program SummaryPilgrim Nuclear Power Station, Plymouth, MA(January -December 2013)RA~rnllIKA. Pr' k PDI K -1I 0t 1 ..IVraInVI e D L Jl , myL I~Iwe,Indicator Stations Station with Highest Mean Control StationsMean +/- Std.Dev. Station: Mean +/- Std.Dev. Mean +/- Std.Dev.No. Analyses Required Range Range RangeRadionuclide Non-routine* LLD Fraction>LLD Fraction>LLD Fraction>LLDBe-7 2 2.7E+2 +/- 4.8E+1 BvdamRd: 2.7E+2 +/- 4.8E+1 <LLD0 2.7E+2 -2.7E+2 2.7E+2 -2.7E+2 <LLD1/1 1/1 0/1K-40 2 8.4E+2 +/- 9.2E+1 HollowBog: 9.7E+2 +/- 8.5E+1 9.7E+2 +/- 8.5E+10 8.4E+2 -8.4E+2 9.7E+2 -9.7E+2 9.7E+2 -9.7E+21/1 1/1 1/11-131 2 60 <LLD <LLD <LLD0 <LLD <LLD <LLD0/1 0/1 0/1Cs-134 2 60 <LLD <LLD <LLD0 <LLD <LLD <LLD0/1 0/1 0/1Cs-137 2 80 <LLD <LLD <LLD0 <LLD <LLD <LLD0/1 0/1 0/1Ra-226 2 2.3E+2 +/- 1.OE+2 HollowBog: 3.5E+2 1.2E+2 3.5E+2 +/- 1.2E+20 2.3E+2 -2.3E+2 3.5E+2 -3.5E+2 3.5E+2 -3.5E+2______ _____ ____1/1 1/1 1/1AcTh-228 2 <LLD <LLD <LLD0 <LLD <LLD <LLD0/1 0/1 0/1* Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.Page 46 Table 2.12-1Surface Water Radioactivity AnalysesRadiological Environmental Program SummaryPilgrim Nuclear Power Station, Plymouth, MA(January -December 2013)MEDIUM: Surface Water MWS) UNITS: oCi/keRadionuclide No. Analyses Required Indicator Stations Station with Highest Mean Control StationsH-3 12 3000 <LLD <LLD <LLD0 <LLD <LLD <LLD0/24 #N/A 0/4Be-7 36 <LLD <LLD <LLD0 <LLD <LLD <LLD0/24 0/12 0/12K-40 36 2.8E+2 +/- 1.5E+2 PP: 3.9E+2 +/- 8.3E+1 3.9E+2 +/- 8.3E+10 <LLD -5.8E+2 3.OE+2 -5.2E+2 3.0E+2 -5.2E+220/24 12/12 12/12Mn-54 36 15 <LLD <LLD <LLD0 <LLD <LLD <LLD0/24 0/12 0/12Fe-59 36 30 <LLD <LLD <LLD0 <LLD <LLD <LLD0/24 0/12 0/12Co-58 36 15 <LLD <LLD <LLD0 <LLD <LLD <LLD0/24 0/12 0/12Co-60 36 15 <LLD <LLD <LLD0 <LLD <LLD <LLD0/24 0/12 0/12Zn-65 36 30 <LLD <LLD <LLD0 <LLD <LLD <LLD0/24 0/12 0/12Zr-95 36 30 <LLD <LLD <LLD0 <LLD <LLD <LLD0/24 0/12 0/12Nb-95 36 15 <LLD <LLD <LLD0 <LLD <LLD <LLD0/24 0/12 0/121-131 36 15 <LLD <LLD <LLD0 <LLD <LLD <LLD0/24 0/12 0/12Cs-134 36 15 <LLD <LLD <LLD0 <LLD <LLD <LLD0/24 0/12 0/12Cs-137 36 18 <LLD <LLD <LLD0 <LLD <LLD <LLD0/24 0/12 0/12Ba-140 36 60 <LLD <LLD <LLD0 <LLD <LLD <LLD0/24 0/12 0/12La-140 36 15 <LLD <LLD <LLD0 <LLD <LLD <LLD0/24 0/12 0/12Ra-226 36 9.2E+1 1 2.7E+1 PP: 9.8E+1 +/- 2.9E+1 9.8E+1 +/- 2.9E+10 <LLD -1.5E+2 <LLD -1.5E+2 <LLD -1.5E+218/24 9/12 9/12AcTh-228 36 8.2E+0 +/- 2.2E+0 DIS: 8.7E+0 +/- 2.6E+0 8.4E+0 +/- 3.1E+00 <LLD- 1.2E+1 <LLD- 1.2E+1 <LLD -1.4E+18/24 5/12 9/12Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.Page 47 Table 2.13-1Sediment Radioactivity AnalysesRadiological Environmental Program SummaryPilgrim Nuclear Power Station, Plymouth, MA(January -December 2013)R A =r'%l "KA Qý; 0 =" KIITo. .-fWL6 A..IVI[,- Im eVI OlJll:lL l -I -.l l I L -t II l yJIndicator Stations Station with Highest Mean Control StationsMean + Std.Dev. Station: Mean +/- Std.Dev. Mean +/- Std.Dev.No. Analyses Required Range Range RangeRadionuclide Non-routine* LLD Fraction>LLD Fraction>LLD Fraction>LLDBe-7 12 4.4E+2 +/- 1.1E+2 Manmt Pt: 4.4E+2 +/- 1.1E+2 <LLD0 <LLD -4.4E+2 <LLD -4.4E+2 <LLD1/8 1/2 0/4K-40 12 9.4E+3 +/- 1.5E+3 Gm Hrbr: 1.1E+4 +/- 5.OE+3 1.1E+4 +/- 3.OE+30 6.8E+3- 1.2E+4 7.5E+3- 1.5E+4 7.5E+3 -1.5E+48/8 2/2 4/4Cs-134 12 150 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/2 0/2Cs-137 12 180 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/2 0/2Ra-226 12 5.5E+2 +/- 3.6E+2 Manmt Pt: 8.7E+2 +/- 2.6E+2 5.1E+2 +/- 4.1E+20 <LLD -9.8E+2 <LLD -8.7E+2 <LLD -9.6E+26/8 1/2 3/4AcTh-228 12 4.1E+2 +/- 1.2E+2 Ply Hbr: 5.2E+2 +/- 1.1E+2 3.9E+2 +/- 1.3E+20 <LLD -5.9E+2 4.5E+2 -5.9E+2 2.5E+2 -5.4E+2I 1 5/8 2/2 4/4* Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.Page 48 Table 2.14-1Irish Moss Radioactivity AnalysesRadiological Environmental Program SummaryPilgrim Nuclear Power Station, Plymouth, MA(January -December 2013)MEDIUM: Irsh Moss (AL) UNITS: oCi/ka wetIndicator Stations Station with Highest Mean Control StationsMean +/- Std.Dev. Station: Mean +/- Std.Dev. Mean + Std.Dev.No. Analyses Required Range Range RangeRadionuclide Non-routine* LLD Fraction>LLD Fraction>LLD Fraction>LLDBe-7 8 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/2 0/2K-40 8 6.OE+3 +/- 1.5E+3 Ellisville: 7.4E+3 +/- 1.8E+3 5.4E+3 +/- 1.9E+30 4.2E+3 -8.7E+3 6.2E+3 -8.7E+3 4.1E+3 -6.8E+36/6 2/2 2/2Mn-54 8 130 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/2 0/2Fe-59 8 260 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/2 0/2Co-58 8 130 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/2 0/2Co-60 8 130 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/2 0/2Zn-65 8 260 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/2 0/21-131 8 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/2 0/2Cs-134 8 130 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/2 0/2Cs-137 8 150 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/2 0/2Ra-226 8 4.2E+2 +/- 1.4E+2 Ellisville: 4.5E+2 + 1.6E+2 3.3E+2 +/- 1.4E+20 <LLD -4.5E+2 <LLD -4.5E+2 <LLD -3.3E+22/6 1/2 1/2AcTh-228 8 <LLD <LLD <LLD0 <LLD <LLD <LLDI _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 2.15-1Shellfish Radioactivity AnalysesRadiological Environmental Program SummaryPilgrim Nuclear Power Station, Plymouth, MA(January -December 2013)hK4nII IA" Ch,-lif.~ K Q CI .k I : 61- a XLESIndicator Stations Station with Highest Mean Control StationsMean +/- Std.Dev. Station: Mean +/- Std.Dev. Mean +/- Std.Dev.No. Analyses Required Range Range RangeRadionuclide Non-routine* LLD Fraction>LLD Fraction>LLD Fraction>LLDBe-7 10 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/4 0/4K-40 10 2.3E+3+/-9.9E+2 PlyHrbr:2.5E+3+/-1.1E+3 1.6E+3+/- 1.7E+30 1.2E+3 -3.8E+3 1.5E+3 -3.8E+3 1.3E+2 -3.2E+36/6 4/4 4/4Mn-54 10 130 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/4 0/4Fe-59 10 260 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/4 0/4Co-58 10 130 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/4 0/4Co-60 10 130 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/4 0/4Zn-65 10 260 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/4 0/4Cs-134 10 130 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/4 0/4Cs-137 10 150 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/4 0/4Ra-226 10 5.9E+2 +/- 2.8E+2 Gm Hrbr: 7.3E+2 +/-3.OE+2 7.3E+2 +/- 3.OE+20 <LLD -5.9E+2 <LLD -7.3E+2 <LLD -7.3E+21/6 1/2 1/4AcTh-228 10 <LLD <LLD <LLD0 <LLD <LLD <LLD0/6 0/4 0/4* Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.Page 50 Table 2.16-1Lobster Radioactivity AnalysesRadiological Environmental Program SummaryPilgrim Nuclear Power Station, Plymouth, MA(January -December 2013)MEDIfHI : iFrA I IW-IAI IMITC- U.-'jI/,, LIi~~l~~l~l~~l, M1e1 1 L I I .1 VVLIndicator Stations Station with Highest Mean Control StationsMean +/- Std.Dev. Station: Mean +/- Std.DevR Mean +/- Std.Dev.No. Analyses Required Range Range RangeRadionuclide Non-routine* LLD Fraction>LLD Fraction>LLD Fraction>LLDBe-7 5 <LLD <LLD <LLD0 <LLD <LLD <LLD0/4 0/4 0/1K-40 5 2.8E+3+/- 5.4E+2 DIS: 2.8E+3+/- 5.4E+2 1.7E+3+/- 2.4E+20 2.1E+3 -3.4E+3 2.1E+3 -3.4E+3 1.7E+3 -1.7E+34/4 4/4 1/1Mn-54 5 130 <LLD <LLD <LLD0 <LLD <LLD <LLD0/4 0/4 0/1Fe-59 5 260 <LLD <LLD <LLD0 <LLD <LLD <LLD0/4 0/4 0/1Co-58 5 130 <LLD <LLD <LLD0 <LLD <LLD <LLD0/4 0/4 0/1Co-60 5 130 <LLD <LLD <LLD0 <LLD <LLD <LLD0/4 0/4 0/1Zn-65 5 260 <LLD <LLD <LLD0 <LLD <LLD <LLD0/4 0/4 0/1Cs-134 5 130 <LLD <LLD <LLD0 <LLD <LLD <LLD0/4 0/4 0/1Cs-137 5 150 <LLD <LLD <LLD0 <LLD <LLD <LLD0/4 0/4 0/1Ra-226 5 6.7E+2 +/- 2.3E+2 DIS: 6.7E+2 +/- 2.3E+2 5.4E+2 +/- 3.OE+20 <LLD -7.OE+2 <LLD -7.OE+2 5.4E+2 -5.4E+22/4 2/4 1/1AcTh-228 5 <LLD <LLD <LLD0 <LLD <LLD <LLD0/4 0/4 0/1* Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.Page 51 Table 2.17-1Fish Radioactivity AnalysesRadiological Environmental Program SummaryPilgrim Nuclear Power Station, Plymouth, MA(January -December 2013)RA~i[1 IIA- M ke CU'W1 111170 rý fl,Indicator Stations Station with Highest Mean Control StationsMean +/- Std.Dev. Station: Mean +/- Std.Dev. Mean +/- Std.Dev.No. Analyses Required Range Range RangeRadionuclide Non-routine* LLD Fraction>LLD Fraction>LLD Fraction>LLDBe-7 8 <LLD <LLD <LLD0 <LLD <LLD <LLD0/5 0/5 0/4K-40 8 4.8E+3 +/- 8.1E+2 DIS: 4.8E+3 +/- 8.1E+2 4.5E+3 +/- 5.2E+20 3.9E+3 -5.7E+3 3.9E+3 -5.7E+3 3.9E+3 -4.9E+34/4 4/4 4/4Mn-54 8 130 <LLD <LLD <LLD0 <LLD <LLD <LLD0/5 0/5 0/4Fe-59 8 260 <LLD <LLD <LLD0 <LLD <LLD <LLD0/5 0/5 0/4Co-58 8 130 <LLD <LLD <LLD0 <LLD <LLD <LLD0/5 0/5 0/4Co-60 8 130 <LLD <LLD <LLD0 <LLD <LLD <LLD0/5 0/5 0/4Zn-65 8 260 <LLD <LLD <LLD0 <LLD <LLD <LLD0/5 0/5 0/4Cs-134 8 130 <LLD <LLD <LLD0 <LLD <LLD <LLD0/5 0/5 014Cs-137 8 150 <LLD <LLD <LLD0 <LLD <LLD <LLD0/5 0/5 0/4Ra-226 8 1.3E+3+/- 5.7E+2 DIS: 1.3E+3+/- 5.7E+2 8.1E+2+/- 1.8E+20 <LLD -1.7E+3 <LLD -1.7E+3 <LLD -8.8E+22/4 2/4 3/4AcTh-228 8 <LLD <LLD <LLD0 <LLD <LLD <LLD0/5 0/5 0/4* Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.Page 52 Figure 2.2-1Environmental TLD Locations Within the PNPS Protected AreaTLD Station Location*Description Code Distance/DirectionTLDs Within Protected AreaO&M/RXB. BREEZEWAY P21 50 m SEEXEC.BUILDING P24 57 m WFENCE-R SCREENHOUSE P04 66 m NO&M-2NDW WALL P20 67 m SEEXEC.BUILDING LAWN P25 76 m WNWFENCE-WATER TANK P05 81 m NNEFENCE-OIL STORAGE P06 85 m NEO&M- 2ND SW CORNER P19 86 m SO&M -1ST SW CORNER P18 90 m SCOMPRESSED GAS STOR P08 92 m EFENCE-L SCREENHOUSE P03 100 m NWFENCE-EXEC.BUILDING P17 107 m WO&M -2ND S WALL P23 121 m ENEFENCE-INTAKE BAY P07 121 m SSEFENCE-WAREHOUSE P26 134 m ESEFENCE-SHOREFRONT P02 135 m NWFENCE-W BOAT RAMP P09 136 m EO&M- 2ND N WALL P22 137 m SEFENCE-W SWITCHYARD P16 172 m SWFENCE-TCF GATE Pll 183 m ESEFENCE-TCF/BOAT RAMP P27 185 m ESEFENCE-ACCESS GATE P12 202 m SEFENCE-E SWITCHYARD P15 220 m SFENCE-TCF/INTAKE BAY P10 223 m EFENCE-MEDICAL BLDG. P13 224 m SSEFENCE-BUTLER BLDG P14 228 m SFENCE-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 AreaPage 54 Figure 2.2-2TLD and Air Sampling Locations: Within 1 KilometerTLD Station Location* Air Sampling Station Location*Description Code Distance/Direction Description Code Distance/DirectionZone 1 TLDs: 0-3 kmBOAT LAUNCH WEST BLW 0.11 km E OVERLOOK AREA OA 0.15 km WOVERLOOK AREA OA 0.15 km W PEDESTRIAN BRIDGE PB 0.21 km NHEALTH CLUB TC 0.15 km WSW MEDICAL BUILDING WS 0.23 km SSEBOAT LAUNCH EAST BLE 0.16 km ESE EAST BREAKWATER EB 0.44 km ESEPEDESTRIAN BRIDGE PB 0.21 km N PROPERTY LINE PL 0.54 km NNWSHOREFRONT SECURITY P01 0.22 km NNW W ROCKY HILL ROAD WR 0.83 km WNWMEDICAL BUILDING WS 0.23 km SSE E ROCKY HILL ROAD ER 0.89 km SEPARKING LOT CT 0.31 krn SESHOREFRONT PARKING PA 0.35 km NNWSTATION A A 0.37 kmn WSWSTATION F F 0.43 km NWSTATION B B 0.44 krn SEAST BREAKWATER EB 0.44 km ESEPNPS MET TOWER PMT 0.44 km WNWSTATION H H 0.47 km SWSTATION I I 0.48 km WNWSTATION L L 0.50 km ESESTATION G G 0.53 km WSTATION D D 0.54 km NWPROPERTY LINE PL 0.54 km NNWSTATION C C 0.57 km ESEHALL'S BOG HB 0.63 km SEGREENWOOD HOUSE GH 0.65 km ESEW ROCKY HILL ROAD WR 0.83 km WNWE ROCKY HILL ROAD ER 0.89 km SE JPage 55 Figure 2.2-2 (continued)TLD and Air Sampling Locations: Within 1 KilometerPage 56 Figure 2.2-3TLD and Air Sampling Locations: 1 to 5 KilometersTLD Station Location* Air Sampling Station Location*Description Code Distance/Direction Description Code Distance/DirectionZone 1 TLDs: 0-3 kmMICROWAVE TOWER MT 1.03 km SSW CLEFT ROCK CR 1.27 km SSWCLEFT ROCK CR 1.27 km SSW MANOMET SUBSTATION MS 3.60 km SSEBAYSHORE/GATE RD BD 1.34 km WNWMANOMET ROAD MR 1.38 km SDIRT ROAD DR 1.48 km SWEMERSON ROAD EM 1.53 km SSEEMERSON/PRISCILLA EP 1.55 km SEEDISON ACCESS ROAD AR 1.59 km SSEBAYSHORE BS 1.76 km WSTATION E E 1.86 km SJOHN GAULEY JG 1.99 km WSTATION J J 2.04 km SSEWHITEHORSE ROAD WH 2.09 km SSEPLYMOUTH YMCA RC 2.09 km WSWSTATION K K 2.17 km STAYLOR/THOMAS TT 2.26 km SEYANKEE VILLAGE YV 2.28 km WSWGOODWIN PROPERTY GN 2.38 km SWRIGHT OF WAY RW 2.83 km STAYLOR/PEARL TP 2.98 km SEZone 2 TLDs: 3-8 kmVALLEY ROAD VR 3.26 km SSWMANOMET ELEM ME 3.29 km SEWARREN/CLIFFORD WC 3.31 km WRT.3A/BARTLETT RD BB 3.33 km SSEMANOMET POINT MP 3.57 km SEMANOMET SUBSTATION MS 3.60 km SSEBEACHWOOD ROAD BW 3.93 km SEPINES ESTATE PT 4.44 km SSWEARL ROAD EA 4.60 km SSES PLYMOUTH SUBST SP 4.62 km WROUTE 3 OVERPASS RP 4.81 km SWRUSSELL MILLS RD RM 4.85 km WSWDistance 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 KilometersPage 58 Figure 2.2-4TLD and Air Sampling Locations: 5 to 25 KilometersTLD Station Location* Air Sampling Station Location*Description Code Distance/Direction Description Code Distance/DirectionZone 2 TLDs: 3-8 kmHILLDALE ROAD HD 5.18 km W PLYMOUTH CENTER PC 6.69 km WMANOMET BEACH MB 5.43 km SSEBEAVER DAM ROAD BR 5.52 km SPLYMOUTH CENTER PC 6.69 km WLONG POND/DREW RD LD 6.97 km WSWHYANNIS ROAD HR 7.33 km SSEMEMORIAL HALL MH 7.58 km WNWSAQUISH NECK SN 7.58 km NNWCOLLEGE POND CP 7.59 km SWZone 3TLDs7 8-15 kmDEEP WATER POND DW 8.59 km WLONG POND ROAD LP 8.88 km SSWNORTH PLYMOUTH NP 9.38 km WNWSTANDISH SHORES SS 10.39 km NWELLISVILLE ROAD EL 11.52 km SSEUP COLLEGE POND RD UC 11.78 km SWSACRED HEART SH 12.92 km WKING CAESAR ROAD KC 13.11 km NNWBOURNE ROAD BE 13.37 km SSHERMAN AIRPORT SA 13.43 km WSWZone4TLDs >15kmCEDARVILLE SUBST CS 15.93 km SKINGSTON SUBST KS 16.15 km WNWLANDING ROAD LR 16.46 km NNWCHURCH/WEST CW 16.56 km NWMAIN/MEADOW MM 17.02 km WSWDIV 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 KilometersPage 60 Figure 2.2-5Terrestrial and Aquatic Sampling LocationsDescription Code Distance/Direction* Description Code Distance/Direction*FORAGEPlymouth County FarmBridgewater ControlHanson Farm ControlVEGETABLES/VEGETATIONSite Boundary CSite Boundary BRocky Hill RoadSite Boundary DSite Boundary AClay Hill RoadBrook RoadBeaver Dam RoadPlymouth County FarmHanson Farm ControlNorton ControlCRANBýRRIESBartlett Road BogBeaverdam Road BogHollow Farm Bog ControlCFBFHN5.6 kn W31 km W34 km WBCBBRHBdBACHBKBDCFHNNCBTMRHF0.50.50.91.11.51.62.93.45.634504.33.416kmkmkmkmkmkmkmTkmkmkmkmkmkmkmSWESESESSSWWSSESWWWSSESWNWSURFACE WATERDischarge CanalBartlett PondPowder Point ControlSEDIMENTDischarge Canal OutfallPlymouth BeachManomet PointPlymouth HarborDuxbury Bay ControlGreen Harbor ControlIRISH MOSSDischarge Canal OutfallManomet PointEllisvilleBrant Rock ControlSHELLFISDischarge Canal OutfallPlymouth HarborManomet PointDuxbury Bay ControlPowder Point ControlGreen Harbor ControlLOBSTERDischarge Canal OutfallPlymouth BeachPlymouth HarborDuxbury Bay ControlFISHESDischarge Canal OutfallPlymouth BeachJones River ControlCape Cod Bay ControlN River-Hanover ControlCataumet ControlProvincetown ControlBuzzards Bay ControlPriest Cove ControlNantucket Sound ControlAtlantic Ocean ControlVineyard Sound ControlDISBPPPDISPLBMPPLY-HDUX-BAYGHDISMPELBKDISPLY-HMPDUX-BAYPPGHDISPLBPLY-HDUX-BAYDISPLBJRCC-BAYNRCAPTBBPCNSAOMV0.2 km N2.7 km SE13 km NNW0.8 km4.0 km3.3 km4.1 km14 km16 km0.7 km4.0 km12 km18 km0.7 kIn4.1 km4.0 km13 km13 km16 km0.5 km4.0 km6.4 km11 km0.5 km4.0 km13 km24 km24 km32 km32 km40 km48 km48 km48 km64 kmNEWESEWNNWNNWNNEESESSENNWNNEWESENNWNNWNNWNWWNWNNWNWWNWESENNWSSWNESSWSWSSEESSW* 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 Samplinq LocationsSYMBOL KEYSHELLFISH(M BLUE MUSSEL)(S SOFT-SHELL)(H HARD-SHELL)Q IRISH MOSSLOBSTERFISHESU SURFACE WATERD SEDIMENTcZ CRANBERRYf VEGETATION0 MILES 2SCALE31 KILOMETERSWSITIfMTR34 EILOMETEBSWEST50 KILOM ETERS32 KILOMETERSNORTHEASTK5 METEESEASTWHITEHORSE BEACH'Ef 24 C-BAYSH 24KILOMETERSEAST-SOUTHEAST48 KILOMETERS,."w SOUTHWEST40 KILOMET' SSOUTH-SOUTHWEST45 KILOMETERSSOUTH-SOUTHEASTPage 62 Figure 2.2-6Environmental Sampling And Measurement Control LocationsDescription Code Distance/Direction* Descriotion Code Distance/Direction*ILDCedarville SubstationKingston SubstationLanding RoadChurch & West StreetMain & Meadow StreetDiv. Marine FisheriesEast Weymouth SubstationAIRSAMPLEEEast Weymouth SubstationFORAGEBridgewater ControlHanson Farm ControlVEGETABLESNEGETATIONHanson Farm ControlNorton ControlCRANBERRIESHollow Farm Bog ControlCSKSLRCWMMDMFEW16161617172140kmkmkmkmkmkmkmSWNWNNWNWWSWSSENWEW 40 km NWBFHN31 km W34 km WSURFACE WATERPowder Point ControlSEDIMENTDuxbury Bay ControlGreen Harbor ControlIRISH MOSSBrant Rock ControlSHELLFISHDuxbury Bay ControlPowder Point ControlGreen Harbor ControlLOBSTERDuxbury Bay ControlFISHESJones River ControlCape Cod Bay ControlN River-Hanover ControlCataumet ControlProvincetown ControlBuzzards Bay ControlPriest Cove ControlNantucket Sound ControlAtlantic Ocean ControlVineyard Sound ControlDUX-BAYPPGHPP 13 km NNWDUX-BAY 14 km NNWGH 16 km NNWBK 18 km NNW13 km NNW13 km NNW16 km NNWDUX-BAY 11 km NNWHN 34 km WNC 50 km WHF 16 km WNWJRCC-BAYNRCAPTBBPCNSAOMV13 km24 km24 km32 km32 km40 km48 km48 km48 km64 kmWNWESENNWSSWNESSWSWSSEESSW* 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 LocationsMAS5ACHUS=-T5 BAYSYMBOL KEY(M BLUE MUSSEL)(S SOFrT-SHLRL CLAM)(H HARD-SHELL CLAM)o I-,u MoSs[I LOBSTMR<cX FL~S\7 ] SEDIMENT(3 CRANBERRYVEGETATIONIFORAGEC AIR SAMPLER© TLD0 MILES 10SCALEIICAPE COD BAY<ZBAYPage 64 Airborne Gross-Beta Radioactivity LevelsNear-Station Monitors(DE0..0Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov DecMonth -2013-. AP-00 Warehouse = AP-07 Pedestrian Bridge-AP-08 Overlook Area -V-- AP-09 East BreakwaterU AP-21 East Weymouth ControlFigure 2.5-1Airborne Gross-Beta Radioactivity Levels: Near Station MonitorsPage 65 Airborne Gross-Beta Radioactivity LevelsProperty Line MonitorsEC.2(Da)00CLJan Feb Mar Apr May Jun Jul Aug Sep Oct Nov DecMonth -2013AP-01 E. Rocky Hill Road -- AP-03 W. Rocky Hill Road-AP-06 Property Line -u-AP-21 East Weymouth ControlFigure 2.5-2Airborne Gross-Beta Radioactivity Levels: Property Line MonitorsPage 66 Airborne Gross-Beta Radioactivity LevelsOffsite Monitors5.OE-024.OE-02S3.OE-02E4.)A.).0 2.OE-021.OE-02O.OE+00 .Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov DecMonth -2013-AP-10 Cleft Rock w AP-15 Plymouth Center--AP-17 Manomet Substation -x- AP-21 East Weymouth ControlFigure 2.5-3Airborne Gross-Beta Radioactivity Levels: Offsite MonitorsPage 67 3.0 SUMMARY OF RADIOLOGICAL IMPACT ON HUMANSThe radiological impact to humans from the Pilgrim Station's radioactive liquid and gaseous releaseshas 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 throughthe environment to humans (Reference 7). The second method is based on actual measurements ofradioactivity in the environmental samples and on dose conversion factors recommended by theNuclear Regulatory Commission. The measured types and quantities of radioactive liquid andgaseous effluents released from Pilgrim Station during 2013 were reported to the NuclearRegulatory Commission, copies of which are provided in Appendix B. The measured levels ofradioactivity 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 radiationexposure 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 radiationexposure 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" forthe period of January 1 through December 31, 2013 (Reference 17).Page 68 Table 3.0-1Radiation Doses from 2013 Pilgrim Station OperationsMaximum Individual Dose From Exposure Pathway -mrem/yrGaseous Liquid AmbientReceptor Effluents* Effluents Radiation** TotalTotal Body 0.032 0.0027 0.43 0.47Thyroid 0.037 0.00027 0.43 0.47Max. Organ 0.066 0.0021 0.43 0.50* Gaseous effluent exposure pathway includes combined dose from particulates, iodines and tritiumin addition to noble gases, calculated at the nearest residence.** Ambient radiation dose for the hypothetical maximum-exposed individual at a location on PNPSproperty yielding highest ambient radiation exposure value as measured with TLDs.Two federal agencies establish dose limits to protect the public from radiation and radioactivity. TheNuclear Regulatory Commission (NRC) specifies a whole body dose limit of 100 mrem/yr to bereceived by the maximum exposed member of the general public. This limit is set forth in Section1301, Part 20, Title 10, of the U.S. Code of Federal Regulations (10CFR20). By comparison, theEnvironmental Protection Agency (EPA) limits the annual whole body dose to 25 mrem/yr, which isspecified in Section 10, Part 190, Title 40, of the Code of Federal Regulations (40CFR190).Another useful "gauge" of radiation exposure is provided by the amount of dose a typical individualreceives each year from natural and man-made sources of radiation. Such radiation doses aresummarized 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 2013, all values arewell within the federal limits specified by the NRC and EPA. In addition, the calculated doses fromPNPS operation represent only a fraction of a percent of doses from natural and man-maderadiation.In conclusion, the radiological impact of Pilgrim Station operations, whether based on actualenvironmental measurements or calculations made from effluent releases, would yield doses wellwithin any federal dose limits set by the NRC or EPA. Such doses represent only a smallpercentage 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 Criteria64.2) Donald T. Oakley, "Natural Radiation Exposure in the United States." U. S. EnvironmentalProtection Agency, ORP/SID 72-1, June 1972.3) National Council on Radiation Protection and Measurements, Report No. 93, "Ionizing RadiationExposures of the Population of the United States," September 1987.4) United States Nuclear Regulatory Commission, Regulatory Guide 8.29, "Instructions ConcerningRisks 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 AnnualDoses to Man from Routine Releases of Reactor Effluents for the Purpose of EvaluatingCompliance 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 MonitoringRadioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975.12) ICNFTracerlab, "Pilgrim Nuclear Power Station Pre-operational Environmental Radiation SurveyProgram, Quarterly Reports," August 1968 to June 1972.13) International Commission of Radiological Protection, Publication No. 43, "Principles ofMonitoring for the Radiation Protection of the Population," May 1984.14) United States Nuclear Regulatory Commission, NUREG-1302, "Offsite Dose Calculation ManualGuidance: Standard Radiological Effluent Controls for Boiling Water Reactors," April 1991.15) United States Nuclear Regulatory Commission, Branch Technical Position, "An AcceptableRadiological Environmental Monitoring Program," Revision 1, November 1979.16) Settlement Agreement Between Massachusetts Wildlife Federation and Boston EdisonCompany Relating to Offsite Radiological Monitoring -June 9, 1977.17) Pilgrim Nuclear Power Station, "Annual Radioactive Effluent Release Report", May 2013.Page 70 APPENDIX ASPECIAL STUDIESThere were no environmental samples collected during 2013 that contained plant-related radioactivity.Therefore, no special studies were required to estimate dose from plant-related activity.Page 71 APPENDIX BEffluent Release InformationTABLE TITLE PAGEB.1 Supplemental Information 73B.2-A Gaseous Effluents Summation of All Releases 74B.2-B Gaseous Effluents -Elevated Releases 75B.2-C Gaseous Effluents -Ground Level Releases 77B.3-A Liquid Effluents Summation of All Releases 79B.3-B Liquid Effluents 80Page 72 Table B.1Pilgrim Nuclear Power StationAnnual Radioactive Effluent Release ReportSupplemental InformationJanuary-December 2013FACILITY: PILGRIM NUCLEAR POWER STATIONLICENSE: DPR-351. REGULATORY LIMITSa. Fission and activation gases: 500 mrem/yr total body and 3000 mrem/yr for skinat site boundaryb,c. lodines, particulates with half-life: 1500 mrem/yr to any organ at site boundary>8 days, tritiumd. Liquid effluents: 0.06 mrem/month for whole body and0.2 mrem/month for any organ(without radwaste treatment)2. EFFLUENT CONCENTRATION LIMITSa. Fission and activation gases: 10CFR20 Appendix B Table IIb. lodines: 10CFR20 Appendix B Table IIc. Particulates with half-life > 8 days: 1OCFR20 Appendix B Table IId. Liquid effluents: 2E-04 i.tCi/mL for entrained noble gases;10CFR20 Appendix B Table II values for all otherradionuclides3. AVERAGE ENERGY Not Applicable4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITYa. Fission and activation gases: High purity germanium gamma spectroscopy for allb. lodines: gamma emitters; radiochemistry analysis for H-3,c. Particulates: Fe-55 (liquid effluents), Sr-89, and Sr-90d. Liquid effluents:5. BATCH RELEASES Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec_ 2013 2013 2013 2013 2013a. Liquid Effluents1. Total number of releases: 5.OOE+00 1.20E+01 N/A 4.OOE+00 2.10E+012. Total time period (minutes): 6.29E+02 1.18E+03 N/A 2.36E+03 4.16E+033. Maximum time period 1.70E+02 1.22E+02 N/A 6.35E+02 6.35E+02(minutes):4. Average time period (minutes): 1.26E+02 9.81E+01 N/A 5.89E+02 2.71E+025. Minimum time period (minutes): 9.90E+01 7.50E+01 N/A 5.20E+02 7.50E+016. Average stream flowduring periods of release ofefflueint peintos a lowingest1.20E+06 9.39E+05 N/A 1.17E+06 1.11E+06effluents into a flowing stream(Liters/min):b. Gaseous Effluents None None None None None6. ABNORMAL RELEASESa. Liquid Effluents None None None None Noneb. Gaseous Effluents None None None None NonePage 73 Table B.2-APilgrim Nuclear Power StationAnnual Radioactive Effluent Release ReportGaseous Effluents -Summation of All ReleasesJanuary-December 2013Est.RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Total2013 2013 2013 2013 2013 ErrorA. FISSION AND ACTIVATION GASESTotal Release: Ci 0.00E+00 0.OOE+00 2.91 E-01 O.OOE+00 2.91E-01Average Release Rate: i.tCi/sec 0.00E+00 0.00E+00 3.69E-02 0.00E+00 9.23E-03 +/-+22%Percent of Effluent Control Limit* ...EB. IODINE-131Total Iodine-131 Release: Ci J 1.84E-04 9.29E-05 5.91E-05 1.71E-04 5.08E-04Average Release Rate: .Ci/sec 2.34E-05 1.18E-05 7.50E-06 2.17E-05 1.61E-05 +/-20%Percent of Effluent Control Limit* .....C. PARTICULATES WITH HALF-LIVES > 8 DAYSTotal Release: Ci 2.78E-04 1.72E-04 5.50E-05 1.62E-04 6.67E-04Average Release Rate: l.LCi/sec 3.53E-05 2.18E-05 6.97E-06 2.05E-05 2.12E-05Percent of Effluent Control Limit* ......Gross Alpha Radioactivity: Ci NDA NDA NDA NDA NDAD. TRITIUMTotal Release: Ci 6.24E+00 6.44E+00 2.34E+01 2.79E+01 6.40E+01Average Release Rate: iiCi/sec 7.91 E-01 8.17E-01 2.97E+00 3.53E+00 2.03E+00 +/-20%Percent of Effluent Control Limit* .....E. CARBON-14Total Release: Ci 1.51E+00 9.73E-01 1.90E+00 1.87E+00 6.26E+00Average Release Rate: ptCi/sec 1.91 E-01 1.23E-01 2.41 E-01 2.38E-01 1.98E-01 N/APercent of Effluent Control Limit* .....Notes for Table B.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-BPilgrim Nuclear Power StationAnnual Radioactive Effluent Release ReportGaseous Effluents -Elevated ReleaseJanuary-December 2013CONTINUOUS MODE RELEASES FROM ELEVATED RELEASE POINTNuclide Released I Jan-Mar 2013 Apr-Jun2013 Jul-Sep2013 Oct-Dec2013 Jan-Dec20131. FISSION AND ACTIVATION GASES: CiAr-41 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Kr-85 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00Kr-85m 0.OOE+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00Kr-87 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Kr-88 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00 0.OOE+00Xe-131m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Xe-133 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Xe-133m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Xe-135 0.OOE+00 0.OOE+00 2.91 E-01 0.OOE+00 2.91 E-01Xe-135m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Xe-137 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Xe-1 38 0.00E+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Total for Period 0.OOE+00 0.OOE+00 2.91 E-01 0.OOE+00 2.91E-012. IODINES: Ci1-131 1.24E-05 1.52E-06 4.34E-06 3.90E-06 2.21 E-051-133 1.14E-05 0.OOE+00 0.OOE+00 0.OOE+00 1.14E-05Total for Period 2.38E-05 1.52E-06 4.34E-06 3.90E-06 3.35E-053. PARTICULATES WITH HALF-LIVES > 8 DAYS: CiCr-51 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00Mn-54 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Fe-59 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Co-58 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Co-60 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Zn-65 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Sr-89 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Sr-90 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Ru-103 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Cs-134 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Cs-137 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Ba/La-140 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Total for Period 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+004. TRITIUM: CiH-3 1.53E-02 2.97E-02 5.30E-02 3.77E-02 1.36E-015. CARBON-14: CiC-14 1.46E+00 9.43E-01 1.85E+00 1.82E+00 6.07E+00Notes for Table B.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/cclodines: 1 E-12 p.Ci/ccParticulates: 1E-1i1 iCi/ccPage 75 Table B.2-B (continued)Pilgrim Nuclear Power StationAnnual Radioactive Effluent Release ReportGaseous Effluents -Elevated ReleaseJanuary-December 2013BATCH MODE RELEASES FROM ELEVATED RELEASE POINTNuclide Released I Jan-Mar 2013 Apr-Jun 2013 Jul-Sep2013 I Oct-Dec 2013 Jan-Dec 20131. FISSION AND ACTIVATION GASES: CiAr-41 N/A N/A N/A N/A N/AKr-85 N/A N/A N/A N/A N/AKr-85m N/A N/A N/A N/A N/AKr-87 N/A N/A N/A N/A N/AKr-88 N/A N/A N/A N/A N/AXe-131 m N/A N/A N/A N/A N/AXe- 133 N/A N/A N/A N/A N/AXe-133m N/A N/A N/A N/A N/AXe- 135 N/A N/A N/A N/A N/AXe-135m N/A N/A N/A N/A N/AXe-137 N/A N/A N/A N/A N/AXe-138 N/A N/A N/A N/A N/ATotal for period N/A N/A N/A N/A N/A2. IODINES: Ci1-131 N/A N/A N/A N/A N/A1-133 N/A N/A N/A N/A N/ATotal for period N/A N/A N/A N/A N/A3. PARTICULATES WITH HALF-LIVES > 8 DAYS: CiCr-51 N/A N/A N/A N/A N/AMn-54 N/A N/A N/A N/A N/AFe-59 N/A N/A N/A N/A N/ACo-58 N/A N/A N/A N/A N/ACo-60 N/A N/A N/A N/A N/AZn-65 N/A N/A N/A N/A N/ASr-89 N/A N/A N/A N/A N/ASr-90 N/A N/A N/A N/A N/ARu-1 03 N/A N/A N/A N/A N/ACs-134 N/A N/A N/A N/A N/ACs-137 N/A N/A N/A N/A N/ABa/La-140 N/A N/A N/A N/A N/ATotal for period N/A N/A N/A N/A N/A4. TRITIUM: CiH-3 N/A N/A N/A N/A N/A5. CARBON-14: CiC-14 N/A N/A N/A N/A N/ANotes for Table B.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: 1 E-04 lICi/cclodines: 1 E-12 iLCi/ccParticulates: 1 E-1 1 jiCi/ccPage 76 Table B.2-CPilgrim Nuclear Power StationAnnual Radioactive Effluent Release ReportGaseous Effluents -Ground-Level ReleaseJanuary-December 2013CONTINUOUS MODE RELEASES FROM GROUND-LEVEL RELEASE POINTNuclide Released I Jan-Mar2013 Apr-Jun2013 Jul-Sep2013 Oct-Dec2013 Jan-Dec20131. FISSION AND ACTIVATION GASES: CiAr-41 0.00E+00 O.OOE+00 0.00E+00 0.OOE+00 O.OOE+00Kr-85 O.OOE+00 0.00E+00 O.OOE+00 O.OOE+00 0.00E+00Kr-85m O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 0.00E+00Kr-87 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00Kr-88 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00Xe-131m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Xe-133 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00Xe-133m 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00 0.OOE+00Xe-135 0.OOE+00 O.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00Xe-135m 0.OOE+00 0.OOE+00 0.00E+00 0.00E+00 0.OOE+00Xe-137 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00Xe-138 O.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00Total for period O.OOE+00 O.OOE+00 o.OOE+00 O.OOE+00 0.OOE+002. IODINES: Ci1-131 1.72E-04 9.14E-05 5.48E-05 1.68E-04 4.85E-041-133 6.23E-04 1.39E-04 1.80E-04 5.21 E-04 1.46E-03Total for period 7.94E-04 2.30E-04 2.35E-04 6.89E-04 1.95E-033. PARTICULATES WITH HALF-LIVES > 8 DAYS: CiCr-51 0.OOE+00 2.1OE-05 0.OOE+00 O.OOE+00 2.1OE-05Mn-54 2.84E-06 1.56E-05 5.08E-06 1.42E-05 3.77E-05Fe-59 0.OOE+00 0.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00Co-58 O.OOE+00 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00Co-60 0.OOE+00 6.34E-05 1.63E-05 2.74E-05 1.07E-04Zn-65 0.OOE+00 1.73E-05 O.OOE+00 6.14E-06 2.34E-05Sr-89 O.OOE+00 0.OOE+00 1.02E-05 1.96E-05 2.98E-05Sr-90 0.OOE+00 O.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00Ru-103 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00 O.OOE+00Cs-134 0.OOE+00 O.OOE+00 0.OOE+00 O.OOE+00 O.OOE+00Cs-137 0.OOE+00 0.OOE+00 0.OOE+00 0.00E+00 0.OOE+00Ba/La-140 2.75E-04 5.47E-05 2.34E-05 9.45E-05 4.48E-04Total for period 2.78E-04 1.72E-04 5.50E-05 1.62E-04 6.67E-044. TRITIUM: CiH-3 6.22E+00 6.41 E+00 2.34E+01 2.78E+01 6.38E+015. CARBON-14: CiC-14 4.53E-02 2.92E-02 5.71E-02 5.62E-02 1.88E-01Notes.for Table B.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/cclodines: 1 E-12 lICi/ccParticulates: 1 E-1 1 liCi/ccPage 77 Table B.2-C (continued)Pilgrim Nuclear Power StationAnnual Radioactive Effluent Release ReportGaseous Effluents -Ground-Level ReleaseJanuary-December 2013BATCH MODE RELEASES FROM GROUND-LEVEL RELEASE POINTNuclide Released I Jan-Mar 2013 Apr-Jun 2013 Jul-Sep 2013 Oct-Dec 2013 Jan-Dec 20131. FISSION AND ACTIVATION GASES: CiAr-41 N/A N/A N/A N/A N/AKr-85 N/A N/A N/A N/A N/AKr-85m N/A N/A N/A N/A N/AKr-87 N/A N/A N/A N/A N/AKr-88 N/A N/A N/A N/A N/AXe-131m N/A N/A N/A N/A N/AXe- 133 N/A N/A N/A N/A N/AXe-133m N/A N/A N/A N/A N/AXe- 135 N/A N/A N/A N/A N/AXe-135m N/A N/A N/A N/A N/AXe-137 N/A N/A N/A N/A N/AXe-138 N/A N/A N/A N/A N/ATotal for period N/A N/A N/A N/A N/A2. IODINES: Ci1-131 N/A N/A N/A N/A N/A1-133 N/A N/A N/A N/A N/ATotal for period N/A N/A N/A N/A N/A3. PARTICULATES WITH HALF-LIVES > 8 DAYS: CiCr-51 N/A N/A N/A N/A N/AMn-54 N/A N/A N/A N/A N/AFe-59 N/A N/A N/A N/A N/ACo-58 N/A N/A N/A N/A N/ACo-60 N/A N/A N/A N/A N/AZn-65 N/A N/A N/A N/A N/ASr-89 N/A N/A N/A N/A N/ASr-90 N/A N/A N/A N/A N/ARu-1 03 N/A N/A N/A N/A N/ACs-1 34 N/A N/A N/A N/A N/ACs-1 37 N/A N/A N/A N/A N/ABa/La-140 N/A N/A N/A N/A N/ATotal for period N/A N/A N/A N/A N/A4. TRITIUM: CiH-3 N/A N/A N/A N/A N/A5. CARBON-14: CiC-14 N/A N/A N/A N/A N/ANotes for Table B.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 piCi/cclodines: 1 E-12 itCi/ccParticulates: 1 E-11 [tCi/ccPage 78 Table B.3-APilgrim Nuclear Power StationAnnual Radioactive Effluent Release ReportLiquid Effluents -Summation of All ReleasesJanuary-December 2013Est.RELEASE PERIOD Jan-Mar Apr-Jun Jul-Sep Oct-Dec Jan-Dec Total2013 2013 2013 2013 1 2013 jErrorA. FISSION AND ACTIVATION PRODUCTSTotal Release (not including 3.98E-06 1.89E-02 N/A 2.93E-05 1.89E-02tritium, gases, alpha): CiAverage Diluted Concentration 2.73E-14 1.74E-10 N/A 1.89E-13 3.36E-11 +/-12%During Period: lCi/mLPercent of EffluentConcentraion Eflimt 9.11 E-08% 2.47E-03% N/A 1.32E-05% 4.81 E-04%Concentration Limit*B. TRITIUMTotal Release: Ci 8.10E-01 5.25E+00 N/A 1.57E-01 6.21E+00Dunverag ioutd: Cioncentration___________Average Diluted Concentration 5.57E-09 4.81E-08 N/A 1.01E-09 1.1OE-08During Period: ýtCi/mL_ +/-9.4%Concentraion Eflmt* 5.57E-04% 4.81 E-03% N/A 1.01 E-04% 1.1 OE-03%Concentration Limit*C. DISSOLVED AND ENTRAINED GASESTotal Release: Ci NDA NDA N/A NDA NDAAverage Diluted Concentration NDA NDA N/A NDA NDADuring Period: ý.Ci/mL_ +/-16%Percent of Effluent_ __I_ _I _ _ __Pecn0fEfun .00E+00% 0.00E+00% N/A 0.00E+00% 0.00E+00%Concentration Limit*D. GROSS ALPHA RADIOACTIVITYTotal Release: Ci NDA N/A N/A N/A NDA +/-34%E. VOLUME OF WASTE RELEASED PRIOR TO DILUTIONWaste Volume: Liters 2.11E+05 8.30E+05 N/A 1.37E+05 1.18E+06 I +/-5.7%F. VOLUME OF DILUTION WATER USED DURING PERIODDilution Volume: Liters 1.46E+11 1.09E+11 I 1.55E+11 1.55E+11 5.65E+11 I +/-10%Notes for Table B.3-A:* Additional percent of Effluent Control Limit values based on dose assessments are provided in Section 6 ofthis 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 ýLCi/mL.4. LLD for liquid gross alpha activity listed as NDA is 1 E-07 ý.Ci/mL.Page 79 Table B.3-BPilgrim Nuclear Power StationAnnual Radioactive Effluent Release ReportLiquid EffluentsJanuary-December 2013CONTINUOUS MODE RELEASESNuclide Released Jan-Mar 2013 Apr-Jun 2013 Jul-Sep 2013 Oct-Dec 2013 Jan-Dec 20131. FISSION AND ACTIVATION PRODUCTS: CiCr-51 N/A N/A N/A N/A N/AMn-54 N/A N/A N/A N/A N/AFe-55 N/A N/A N/A N/A N/AFe-59 N/A N/A N/A N/A N/ACo-58 N/A N/A N/A N/A N/ACo-60 N/A N/A N/A N/A N/AZn-65 N/A N/A N/A N/A N/AZn-69m N/A N/A N/A N/A N/ASr-89 N/A N/A N/A N/A N/ASr-90 N/A N/A N/A N/A N/AZr/Nb-95 N/A N/A N/A N/A N/AMo/Tc-99 N/A N/A N/A N/A N/AAg-110m N/A N/A N/A N/A N/ASb-124 N/A N/A N/A N/A N/A1-131 N/A N/A N/A N/A N/A1-133 N/A N/A N/A N/A N/ACs-1 34 N/A N/A N/A N/A N/ACs-1 37 N/A N/A N/A N/A N/ABa/La-140 N/A N/A N/A N/A N/ACe-141 N/A N/A N/A N/A N/ATotal for period N/A N/A N/A N/A N/A2. DISSOLVED AND ENTRAINED GASES: CiXe-1 33 N/A N/A N/A N/A N/AXe-1 35 N/A N/A N/A N/A N/ATotal for period N/A N/A N/A N/A N/ANotes for Table B.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 gCi/mLlodines: 1 E-06 ZCi/mLNoble Gases: 1E-05 ýiCi/mLAll Others: 5E-07 ItCi/mLPage 80 Table B.3-B (continued)Pilgrim Nuclear Power StationAnnual Radioactive Effluent Release ReportLiquid EffluentsJanuary-December 2013BATCH MODE RELEASESNuclide Released Jan-Mar 2013 Apr-Jun 2013 Jul-Sep 2013 Oct-Dec 2013 Jan-Dec 20131. FISSION AND ACTIVATION PRODUCTS: CiNa-24 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+00Cr-51 0.00E+00 4.50E-03 N/A 0.OOE+00 4.50E-03Mn-54 3.98E-06 3.73E-03 N/A 3.02E-06 3.74E-03Fe-55 0.OOE+00 5.72E-04 N/A 0.00E+00 5.72E-04Fe-59 0.OOE+00 1.11E-03 N/A 0.OOE+00 1.11E-03Co-58 0.OOE+00 4.89E-04 N/A 0.OOE+00 4.89E-04Co-60 0.OOE+00 5.73E-03 N/A 8.86E-06 5.74E-03Zn-65 0.OOE+00 1.57E-03 N/A 0.OOE+00 1.57E-03Zn-69m 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+00Sr-89 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+00Sr-90 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+00Zr/Nb-95 0.OOE+00 4.69E-05 N/A 0.OOE+00 4.69E-05Mo/Tc-99 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+00Ag-110m 0.OOE+00 1.08E-03 N/A 0.00E+00 1.08E-03Sb-124 0.OOE+00 9.60E-05 N/A 0.OOE+00 9.60E-051-131 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+001-133 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+00Cs-1 34 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+00Cs-137 0.OOE+00 0.OOE+00 N/A 1.74E-05 1.74E-05Ba/La-140 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+00Ce-141 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+00Ce-144 0.OOE+00 0.OOE+00 N/A 0.OOE+00 0.OOE+00Total for period 3.98E-06 1.89E-02 N/A 2.93E-05 1.89E-022. DISSOLVED AND ENTRAINED GASES: CiXe-1 33 NDA NDA N/A NDA NDAXe-1 35 NDA NDA N/A NDA NDATotal for period NDA NDA N/A NDA NDANotes for Table B.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 piCi/mLlodines: 1E-06 4.Ci/m LNoble Gases: 1E-05 4Ci/mLAll Others: 5E-07 pCi/mLPage 81 APPENDIX CLAND USE CENSUS RESULTSThe annual land use census for gardens and milk and meat animals in the vicinity of Pilgrim Stationwas performed between September 09 and September 20, 2013. The census was conducted bydriving along each improved road/street in the Plymouth area within 5 kilometers (3 miles) of PilgrimStation to survey for visible gardens with an area of greater than 500 square feet. In compasssectors where no gardens were identified within 5 km (SSW, WNW, NW, and NNW sectors), thesurvey was extended to 8 km (5 mi). A total of 30 gardens were identified in the vicinity of PilgrimStation. In addition, the Town of Plymouth Animal Inspector was contacted for information regardingmilk and meat animals.Atmospheric deposition (D/Q) values at the locations of the identified gardens were compared tothose for the existing sampling program locations. These comparisons enabled PNPS personnel toascertain the best locations for monitoring for releases of airborne radionuclides. Gardens yieldinghigher D/Q values than those currently in the sampling program were also sampled as part of theradiological environmental monitoring program.Based on assessment of the gardens identified during the 2013 land use census, samples ofgarden-grown vegetables or naturally-growing vegetation (e.g. grass, leaves from bushes or trees,etc.) were collected at or near the closest gardens in each of the following landward compasssectors. These locations, and their distance and direction relative to the PNPS Reactor Building, areas follows:Rocky Hill Road 0.9 km SERocky Hill Road 1.8 km SSEClay Hill Road 1.6 km WAdditional samples of naturally-growing vegetation were collected at the site boundary in the ESEand SE sectors to monitor for atmospheric deposition in the vicinity of the nearest resident in the SEsector.In addition to these special sampling locations identified and sampled in conjunction with the 2013land use census, samples were also collected at or near the Plymouth County Farm (5.6 km W), andfrom 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 boundarylocations yielding the highest deposition (D/Q) factors for each of the two release points. Theselocations, and their distance and direction relative to the PNPS Reactor Building, are as follows:Highest Main Stack D/Q: 1.5 km SSWHighest Reactor Building Vent D/Q: 0.5 km ESE2n highest D/Q, both release points: 1.1 km SNo new milk or meat animals were identified during the land use census. In addition, the Town ofPlymouth Animal Inspector stated that their office is not aware of any animals at locations other thanthe Plimoth Plantation. Although milk sampling is not performed at Plimoth Plantation, effluent dosecalculations are performed for this location assuming the presence of a milk ingestion pathway, aspart of the Annual Radioactive Effluent Release Report (Reference 17).Page 82 APPENDIX DENVIRONMENTAL MONITORING PROGRAM DISCREPANCIESThere were a number of instances during 2013 in which inadvertent issues were encountered in thecollection of environmental samples. All of these issues were minor in nature and did not have anadverse effect on the results or integrity of the monitoring program. Details of these variousproblems are given below.During 2013, nine offsite thermoluminescent dosimeters (TLD) were not recovered from theirassigned locations during the quarterly retrieval process. Degradation of the plastic cages housingthe TLDs resulted in the loss of the following TLDs: Emerson & Priscilla -EP (Qtr 1); GreenwoodHouse -GH (Qtr 3); Warren & Clifford -WC (Qtr 3); Hall's Bog -HB (Qtr 4); Manomet Elementary -ME (Qtr 4); and College Pond -CP (Qtr 4). In each of these cases, the plastic cage holding the TLDwere replaced and a new TLD posted. The TLD at Hyannis Road -HR was vandalized during boththe 1st and 2nd quarters of 2013. The TLD at this location was relocated a short distance to be lessconspicuous. Turing the 4th Quarter exchange of TLDs in early January- 2014, the TLD at ValleyRoad -VR could not be retrieved due to snow-covered roads leading to this remote location. TheTLD was recovered during the retrieval of 1t Quarter 2014 TLDs in April 2014, and will be analyzedto determine the average dose at that location during the two periods represented by that TLD.Despite these losses, the 431 TLDs that were collected (98.0%) allowed for adequate assessment ofthe ambient radiation levels in the vicinity of Pilgrim Station.Within the air sampling program, there were a few instances in which continuous sampling wasinterrupted at the eleven airborne sampling locations during 2013. Most of these interruptions weredue 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 ofthe weekly sampling period). Such events did not have any significant impact on the scope andpurpose of the sampling program, and lower limits of detection (LLDs) were met for both airborneparticulates and iodine-1 31 on 563 of the 563 filters/cartridges collected.Out of 572 filters (11 locations

• 52 weeks), 563 samples were collected and analyzed during 2013.A problem occurred at location WR when tree trimming activities on 14-Aug-2012 resulted indamage to the electrical service and sampling station. The sampler was not repaired until 28-Feb-2013, resulting in the loss of sampling capabilities at this location for the last 21 weeks of 2012, andthe first eight weeks of 2013. This event is described in Condition Report CR-PNP-2012-3545.There were also a few instances where power was lost or pumps failed during the course of thesampling period at some of the air sampling stations, resulting in lower than normal sample volumes.All required LLDs were achieved on these samples. Winter Storm Nemo resulted in wide-scale lossof power during the week of 05-Feb through 12-Feb-2103. Power interruptions of greater than 24-hours occurred from this storm at Property Line, Pedestrian Bridge, Cleft Rock, Manomet Substation,East Rocky Hill Road, East Breakwater; and Medical Building.The configuration of air samplers that had been in use at Pilgrim Station since the early 1980s, wasreplaced 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, thenew configuration is still subject to trips of the ground fault interrupt circuit (GFCI). Such problemscan be encountered at air samplers located at the East Breakwater and Pedestrian Bridge. Both ofthese locations are immediately adjacent to the shoreline and are subject to significant wind-blownsalt water, and are prone to tripping of the GFCI. The following table contains a listing of largerproblems encountered with air sampling stations during 2013, many of which resulted in loss of morethan 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> in a sampling period.Page 83 Location Sampling Period Sampling Problem DescriptionHours LostWR 01/02 to 02/28 1375 of 1375 Sampling station damaged during tree trimming activitiesin Aug-2012; condition report CR-PNP-2012-3545;repaired 02/28/2013PL 02/05 to 02/12 36.1 of 174.9 Power loss from Winter Storm NemoPB 02/05 to 02/12 57.4 of 170.3 Power loss from Winter Storm NemoCR 02/05 to 02/12 33.3 of 170.5 Power loss from Winter Storm NemoMS 02/05 to 02/12 30.7 of 170.3 Power loss from Winter Storm NemoER 02/05 to 02/12 90.8 of 173.9 Power loss from Winter Storm NemoEB 02/05 to 02/12 36.1 of 170.5 Power loss from Winter Storm NemoWS 02/05 to 02/12 36.1 of 168.8 Power loss from Winter Storm NemoOA 04/22 to 05/01 72.1 of 220 Load shed activity of power feed from Main Stack duringrefueling outage.WS 06/11 to 06/17 139 of 139 Faulty circuit breaker feeding power to sampling station.WR 6/25 to 07/09 None Filter left on for 2-week period due to inaccessibility at0.0 of 336.5 location of samplerPB 10/14 to 10/21 39.3 of 156.3 Loss of offsite power caused GFCI outlet to tripPB 10/21 to 10/29 23.1 of 191.2 Trip of GFCI outletPB 12/10 to 12/17 60.5 of 168.0 Trip of GFCI outletCR 12/10 to 12/23 None Filter left on for 2-week period due to inaccessibility at0.0 of 311.3 location of samplerPB 12/17 to 12/23 134.5 of 143.3 Pump experienced mechanical failureDespite the lower-than-normal sampling volumes in the various instances involving powerinterruptions and equipment failures, required LLDs were met on 563 of the 563 particulate filters,and 563 of the 563 of the iodine cartridges collected during 2013. When viewed collectively duringthe entire year of 2013, the following sampling recoveries were achieved in the airborne samplingprogram:LocationRecoveryLocationRecoveryLocationRecoveryLoato -Re ---- Loato ----WSERWRPL98.7%98.9%84.2%99.5%PBOAEBCR96.1%98.0%99.6%99.5%PCMSEW99.9%99.6%99.9%An alternate location had to be found for sampling control vegetable samples in the Bridgewaterarea. In past years, samples had been collected at the Bridgewater County Farm, associated withthe 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, locatedin the same compass sector, and at approximately the same distance as the Bridgewater CountyFarm. Additional samples of naturally-occurring vegetation were collected from distant controllocations in Sandwich and Norton. As expected for control samples, vegetables and vegetationcollected 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 2013. Crops which hadnormally been sampled in the past (lettuce, tomatoes, potatoes, and onions) were not grown at thePlymouth County Farm (CF) during 2013. Leafy material from pumpkin plants and corn plants weresubstituted 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 twoother locations in the immediate vicinity of Pilgrim Station. No radionuclides attributed to PNPSoperations were detected in any of the samples.Page 84 Naturally-growing leafy vegetation (grass, leaves from trees and bushes, etc.) was collected nearsome gardens identified during the annual land use census. Due to the unavailability of crops grownin several of these gardens, these substitute samples were collected as near as practicable to thegardens of interest. No radionuclides attributed to PNPS operations were detected in any of thesamples. 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 highestatmospheric deposition would be predicted to occur. Some of these samples indicated Cs-137 atconcentrations ranging from non-detectable up to 61 pCi/kg. The highest concentration of 61 pCi/kgwas detected in a sample of natural vegetation collected from the Pine Hills area of the Pine Hillssouth of PNPS. This Cs-137 result is within of the normal range of average values expected forweapons-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 detectableCs-137 from nuclear weapons tests up into the range of 300 to 400 pCi/kg, whereas soil samplesoften indicated concentrations in excess of 2000 pCi/kg. Cs-137 has a 30-year half-life, andmeasureable concentrations still remain in soil and vegetation as a result of atmospheric nuclearweapons testing performed during the 1950s through 1970s. A review of effluent data presented inAppendix B indicates that there were no measurable airborne releases of Cs-137 from PilgrimStation during 2013 that could have attributed to these detectable levels. The sample with thehighest level of Cs-137 also contained high levels of Ra-226 and AcTh-228, indicating appreciablesoil content on the vegetation. This sample of natural vegetation was analyzed "as is" without anymeasure to clean the samples as normally would be performed prior to consuming vegetables, andwould have detected any Cs-1 37 in soil adhering to those leaves collected. Certain species of plantssuch 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 bioconcentrationin the leaves of the plants sampled. These levels are not believed to be indicative of any releasesassociated with Pilgrim Station. No radioactivity attributable to Pilgrim Station was detected in any ofthe vegetable samples collected during 2013, and results of any detectable naturally-occurringradioactivity were similar to those observed in the preoperational monitoring program.The cranberry bog at Pine Street Bog in Halifax was not in production during 2013, so a samplecould not be obtained from this location. A substitute sample was collected from a bog (Hollow Bog)in Kingston, beyond the influence of Pilgrim Station. In addition, the cranberry bog along BartlettRoad suspended operation during 2013, and was not producing cranberries. Samples werecollected from a single indicator location located along Beaverdam Road.During the week of 05-Feb through 12-Feb-2013, water samples could not be collected from thesampling locations at the Pedestrian Bridge and Bartlett Pond. Both areas were inaccessible due todamage from Winter Storm Nemo.Additional problems were encountered with composite water samples collected from the DischargeCanal during the weeks of 12-Feb to 19-Feb-2013, and 16-Apr to 22-Apr-2013 when the lift pumpsuspended in the Discharge Canal failed and water was not provided to the composite sampler.Grab samples were obtained at the time of filter collection to substitute for the normal compositesamples that would have been collected during the week. No radioactive liquid discharges wereoccurring during either of these two periods.Failure of the peristaltic tubing in the composite sampler also occurred during the weeks of 18-Mar to25-Mar, and 01-May to 07-May-2013, and grab samples were also substituted for the compositesamples. One radioactive liquid discharge of 9686 gallons containing 0.086 Curies of tritiumoccurred during the week of 18-Mar to 25-Mar, but the dilution in the discharge canal would haveresulted in a tritium concentration of about 7.3 pCi/L, which is well below the detection sensitivity fortritium in REMP samples. No tritium was detected in the quarterly composite for the second quarterof 2013. No radioactive liquid discharges occurred during the period covered by the compositesample for the week of 01-Mat to 07-May.Page 85 Group I fishes, consisting of winter flounder or yellow-tail flounder are normally collected twice eachyear in the spring and in the autumn from the vicinity of the Discharge Canal Outfall. When fishsampling occurred in the September to November collection period, no samples of Group I fish couldbe collected, as the species had already moved to deeper water for the upcoming winter. Repeatedand concerted efforts were made to collect these species, but failed to produce any samples.In summary, the various problems encountered in collecting and analyzing environmental samplesduring 2013 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 discrepanciesresulted in an adverse impact on the overall monitoring program.Page 86 APPENDIX EENVIRONMENTAL DOSIMETRY COMPANYAnnual Quality Assurrance Status ReportJanuary -December 2013 ENVIRONMENTAL DOSIMETRY COMPANYANNUAL QUALITY ASSURANCE STATUS REPORTJanuary -December 2013Prepared By:Approved By:A/Date: z?Date: --A24{+/-L..Environmental Dosimetry Company10 Ashton LaneSterling, MA 01564 TABLE OF CONTENTSPageLIST O F TABLES ....................................................................................................................... iiiEXECUTIVE SUMMARY .................................................................................................... ivI. INTRODUCTION ............................................................................................................ 1A. QC Program .................................................................................................. 1B. QA Program .................................................................................................. 1II. PERFORMANCE EVALUATION CRITERIA ............................................................... 1A. Acceptance Criteria for Internal Evaluations ..................................................... 1B. QC Investigation Criteria and Result Reporting .............................................. 3C. Reporting of Environmental Dosimetry Results to EDC Customers .................. 3Ill. DATA SUMMARY FOR ISSUANCE PERIOD JANUARY-DECEMBER 2013 ............. 3A. General Discussion ......................................................................................... 3B. Result Trending .............................................................................................. 4IV. STATUS O F EDC CONDITION REPO RTS (CR) ...................................................... 4V, STATUS OF AUDITS/ASSESSM ENTS ..................................................................... 4A .In te rn a l ................................................................................................................ 4B. External ........................................................................................................ 4VI. PROCEDURES AND MANUALS REVISED DURING JANUARY -DECEMBER 2013... 4VII. CONCLUSION AND RECOM M ENDATIONS ............................................................ 4VIII. REFERENCES ............................................................................................................... 4APPENDIX A DOSIMETRY QUALITY CONTROL TRENDING GRAPHS-ii-LIST OF TABLESPaqe1. Percentage of Individual Analyses Which Passed EDC Internal Criteria,January -December 2013 52. Mean Dosimeter Analyses (n=6), January -December 2013 53. Summary of Independent QC Results for 2013 5-iii-EXECUTIVE SUMMARYRoutine quality control (QC) testing was performed for dosimeters issued by the EnvironmentalDosimetry Company (EDC).During this annual period, 100% (72/72) of the individual dosimeters, evaluated against the EDCinternal performance acceptance criteria (high-energy photons only), met the criterion foraccuracy 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 acceptancecriteria (Table 2) and 100% (6/6) of independent testing passed the performance criteria (Table3). Trending graphs, which evaluate performance statistic for high-energy photon irradiationsand co-located stations are given in Appendix A.One internal assessment was performed in 2013. There were no findings.-iv-

1. INTRODUCTIONThe TLD systems at the Environmental Dosimetry Company (EDC) are calibrated andoperated to ensure consistent and accurate evaluation of TLDs. The quality of thedosimetric results reported to EDC clients is ensured by in-house performance testingand independent performance testing by EDC clients, and both internal and clientdirected program assessments.The purpose of the dosimetry quality assurance program is to provide performancedocumentation of the routine processing of EDC dosimeters. Performance testingprovides a statistical measure of the bias and precision of dosimetry processing againsta reliable standard, which in turn points out any trends or performance changes. Twoprograms are used:A. QC ProgramDosimetry quality control tests are performed on EDC Panasonic 814Environmental dosimeters. These tests include: (1) the in-house testing programcoordinated by the EDC QA Officer and (2) independent test perform by EDCclients. In-house test are performed using six pairs of 814 dosimeters, a pair isreported 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 instrumentationchecks represent an important aspect of the quality assurance program, they arenot included as process checks in this report. Instrumentation checks representbetween 5-10% of the TLDs processed.B. QA ProgramAn internal assessment of dosimetry activities is conducted annually by theQuality Assurance Officer (Reference 1). The purpose of the assessment is toreview procedures, results, materials or components to identify opportunities toimprove or enhance processes and/or services.I1. PERFORMANCE EVALUATION CRITERIAA. Acceptance Criteria for Internal Evaluations1. BiasFor each dosimeter tested, the measure of bias is the percent deviation ofthe reported result relative to the delivered exposure. The percentdeviation relative to the delivered exposure is calculated as follows:H.' -H.'-100Hiwhere:H' the corresponding reported exposure for the imdosimeter (i.e., the reported exposure)H= the exposure delivered to the ith irradiateddosimeter (i.e., the delivered exposure)1 of 6

2. Mean BiasFor each group of test dosimeters, the mean bias is the average percentdeviation of the reported result relative to the delivered exposure. Themean percent deviation relative to the delivered exposure is calculated asfollows:H'H 1-1 100where:H; = the corresponding reported exposure for the ithdosimeter (i.e., the reported exposure)Hi = the exposure delivered to the ith irradiated testdosimeter (i.e., the delivered exposure)n = the number of dosimeters in the test group3. PrecisionFor a group of test dosimeters irradiated to a given exposure, themeasure of precision is the percent deviation of individual results relativeto the mean reported exposure. At least two values are required for thedetermination of precision. The measure of precision for the ith dosimeteris:100where:HI' =the reported exposure for the ith dosimeter (i.e., thereported exposure)H = the mean reported exposure; i.e., H = in = the number of dosimeters in the test group4. EDC Internal Tolerance LimitsAll evaluation criteria are taken from the "EDC Quality System Manual,"(Reference 2). These criteria are only applied to individual testdosimeters irradiated with high-energy photons (Cs-1 37) and are asfollows for Panasonic Environmental dosimeters: +/- 15% for bias and +12.8% for precision.2 of 6 B. QC Investigation Criteria and Result ReportingEDC Quality System Manual (Reference 2) specifies when an investigation isrequired due to a QC analysis that has failed the EDC bias criteria. The criteriaare as follows:1. No investigation is necessary when an individual QC result falls outsidethe QC performance criteria for accuracy.2. Investigations are initiated when the mean of a QC processing batch isoutside the performance criterion for bias.C. Reporting of Environmental Dosimetry Results to EDC Customers1. All results are to be reported in a timely fashion.2. If the QA Officer determines that an investigation is required for aprocess, the results shall be issued as normal. If the QC results,prompting the investigation, have a mean bias from the known of greaterthan +/-20%, the results shall be issued with a note indicating that theymay be updated in the future, pending resolution of a QA issue.3. Environmental dosimetry results do not require updating if theinvestigation has shown that the mean bias between the original resultsand the corrected results, based on applicable correction factors from theinvestigation, does not exceed +/-20%.Ill. DATA SUMMARY FOR ISSUANCE PERIOD JANUARY-DECEMBER 2013A. General DiscussionResults of performance tests conducted are summarized and discussed in thefollowing sections. Summaries of the performance tests for the reporting periodare given in Tables 1 through 3 and Figures 1 through 4.Table 1 provides a summary of individual dosimeter results evaluated against theEDC internal acceptance criteria for high-energy photons only. During this period,100% (72/72) of the individual dosimeters, evaluated against these criteria metthe 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) ofdosimeters evaluated against the internal tolerance criteria. Overall,100%(12/12) of the dosimeter sets evaluated against the internal toleranceperformance criteria met these criteria. A graphical interpretation is provided inFigures 3Table 3 presents the independent blind spike results for dosimeters processedduring this annual period. All results passed the performance acceptancecriterion. Figure 4 is a graphical interpretation of Seabrook Station blind co-located station results.3 of 6 B. Result TrendingOne of the main benefits of performing quality control tests on a routine basis isto identify trends or performance changes. The results of the Panasonicenvironmental dosimeter performance tests are presented in Appendix A. Theresults are evaluated against each of the performance criteria listed in Section II,namely: individual dosimeter accuracy, individual dosimeter precision, and meanbias.All of the results presented in Appendix A are plotted sequentially by processingdate.IV. STATUS OF EDC CONDITION REPORTS (CR)No condition reports were issued during this annual period.V. STATUS OF AUDITS/ASSESSMENTSA. InternalEDC Internal Quality Assurance Assessment was conducted during the fourthquarter 2013. There were not any findings as a result of this assessment.B. ExternalNo external assessments were conducted in 2013.VI. PROCEDURES AND MANUALS REVISED DURING JANUARY -DECEMBER 2013No procedures or manuals were revised in 2013.VII. CONCLUSION AND RECOMMENDATIONSThe quality control evaluations continue to indicate the dosimetry processing programsat the EDC satisfy the criteria specified in the Quality System Manual. The EDCdemonstrated the ability to meet all applicable acceptance criteria.VIII. REFERENCES1. EDC Quality Control and Audit Assessment Schedule, 2013.2. EDC Manual 1, Quality System Manual, Rev. 3, August 1, 2012.4 of 6 TABLE 1PERCENTAGE OF INDIVIDUAL DOSIMETERS THAT PASSED EDC INTERNAL CRITERIAJANUARY- DECEMBER 2013(1)' (2)DNumber% % Passed PrecisionDosimeter Type Tested %PassedBiasCriteria CriteriaPanasonic Environmental 72 100 100(1)This table summarizes results of tests conducted by EDC.(2)Environmental dosimeter results are free in air.TABLE 2MEAN DOSIMETER ANALYSES (N=6)JANUARY- DECEMBER 2013(1)' (2)Standard ToleranceProcess Date Mean Bias % Deviation % Limit +1-15%4/22/2013 4.1 1.9 Pass4/24/2013 4.5 1.2 Pass5/23/2013 -1.1 1.9 Pass7/24/2013 0.8 1.0 Pass8/4/2013 -1.1 1.6 Pass8/6/2013 0.1 2.3 Pass10/31/2013 1.5 1.2 Pass11/10/2013 0.1 1.7 Pass11/15/2013 -1.8 1.0 Pass1/27/2014 3.7 2.3 Pass1/31/2014 2.6 0.9 Pass2/5/2014 0.7 0.6 Pass(1-This table summarizes results of tests conducted by EDC for TLDs issued in 2013.(2)Environmental dosimeter results are free in air.TABLE 3SUMMARY OF INDEPENDENT DOSIMETER TESTINGJANUARY -DECEMBER 2013(')' (2)Standard Pass I FailIssuance Period Client Mean Bias% Deviation %2nd Qtr.2013 Millstone 0.7 1.5 Pass27_ Qtr.2013 Seabrook -2.3 2.7 Pass3r' Qtr. 2013 Millstone -4.7 4.0 Pass4t' Qtr.2013 Seabrook -0.9 0.9 Pass(1)Performance criteria are +/- 30%.(2)Blind spike irradiations using Cs-1375 of 6 APPENDIX ADOSIMETRY QUALITY CONTROL TRENDING GRAPHSISSUE PERIOD JANAURY -DECEMBER 20136 of 6 INDIVIDUAL ACCURACY ENVIRONMENTALFIGURE 116-144i1210-8-06 -'4-!00S ** *@0 00Tarn~t = 00 ** 5 0 o0 * *

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APPENDIX FJ.A. Fitzpatrick Interlaboratory Comparison ProgramJanuary -December 2013 8.0 QUALITY ASSURANCE / QUALITY CONTROL PROGRAM8.1 PROGRAM DESCRIPTIONThe Offsite Dose Calculation Manual (ODCM), Part 1, Section 5.3 requires that the licenseeparticipate in an Interlaboratory Comparison Program. The Interlaboratory Comparison Programshall include sample media for which samples are routinely collected and for which comparisonsamples are commercially available. Participation in an Interlaboratory Comparison Program ensuresthat independent checks on the precision and accuracy of the measurement of radioactive material inthe environmental samples are performed as part of the Quality Assurance Program for environmentalmonitoring. To fulfill the requirement for an Interlaboratory Comparison Program, the James A.FitzPatrick Nuclear Power Plant (JAF) Environmental Laboratory has engaged the services of Eckert& Ziegler Analytics, Incorporated in Atlanta, Georgia.Eckert & Ziegler Analytics supplies sample media as blind sample spikes, which contain certifiedlevels of radioactivity unknown to the analysis laboratory. These samples are prepared andanalyzed by the JAF Environmental Laboratory using standard laboratory procedures. Eckert &Ziegler Analytics issues a statistical summary report of the results. The JAF EnvironmentalLaboratory uses predetermined acceptance criteria methodology for evaluating the laboratory'sperformance.The JAF Environmental Laboratory also analyzes laboratory blanks. The analysis of laboratoryblanks provides a means to detect and measure radioactive contamination of analytical samples.The analysis of analytical blanks also provides information on the adequacy of backgroundsubtraction. Laboratory blank results are analyzed using control charts.8-1 Laboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 36 of 58FIGURE 1COBALT-60 PERFORMANCE EVALUATION RESULTS AND % BIAS2013 Cobalt-60 Performance Evaluation Results and % Bias100.075.050.025.00.0-25.0-50.0-75.0-100.0.. ..Co-60SLower ControlLimitUpper ControlLim itJanuary 2013 -December 2013 Laboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 37 of 58FIGURE 2CESIUM-1 37 PERFORMANCE EVALUATION RESULTS AND % BIAS2013 Cesium-137 Performance Evaluation Results and % BiasCD0'100.075.050.025.00.0-25.0-50.0-75.0-100.0Cs-1 37---- Lower ControlLimit--Upper ControlLimitJanuary 2013- December 2013 Laboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 38 of 58FIGURE 3TRITIUM PERFORMANCE EVALUATION RESULTS AND % BIAS2013 Tritium Performance Evaluation Results and % Bias100.075.050.025.0-R0.0S-- H-3---- Lower ControlLimitUpper ControlLim it-25.0-50.0-75.0-100.0January 2013 -December 2013 Laboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 39 of 58FIGURE 4STRONTIUM-90 PERFORMANCE EVALUATION RESULTS AND % BIAS2013 Strontium-90 Performance Evaluation Results and % Bias100.050.0In0.0-Strontium-90---- Lower ControlLimit---- Upper ControlLimit-50.0-100.0January 2013 -December 2013 Laboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 40 of 58FIGURE 5GROSS ALPHA PERFORMANCE EVALUATION RESULTS AND % BIAS2013 Gross Alpha Performance Evaluation Results and % Bias100.050.0CoCu0.0Gross Alpha.....-Lower ControlLimit----Upper ControlLimit-50.0-100.0January 2013 -December 2013 Laboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 41 of 58FIGURE 6GROSS BETA PERFORMANCE EVALUATION RESULTS AND % BIAS2013 Gross Beta Performance Evaluation Results and % Bias100.050.0IA0.0-Gross Beta---- Lower ControlLimit---- Upper ControlLimit-50.0-100.0January 2013 -December 2013 Laboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 42 of 58FIGURE 7IODINE-131 PERFORMANCE EVALUATION RESULTS AND % BIAS2013 Iodine-131 Performance Evaluation Results and % BiasInw5100.075.050.025.00.0-25.0-50.0-75.0-100.0Iodine-131... .Lower ControlLimit---- Upper ControlLim itJanuary 2013 -December 2013 I Laboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 43 of 58FIGURE 8AMERICIUM-241 PERFORMANCE EVALUATION RESULTS AND % BIAS2013 Americium-241 Performance Evaluation Results and % Biasw100.075.050.025.00,0-25.0-50.0-75.0.100.0-.- Am-241---- Lower ControlLim it---Upper ControlLim itJanuary 2013 -December 2013 Laboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 44 of 58FIGURE 9PLUTONIUM-238 PERFORMANCE EVALUATION RESULTS AND % BIAS2013 Plutonium-238 Performance Evaluation Results and %Bias100.075.050.025.00.0-25.0-50,0(IPlutonium-238-- --Lower ControlLimitUpper ControlLimit-750-1000January 2013 -December 2013 MLaboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 45 of 58TABLE 6REMP INTRA-LABORATORY DATA SUMMARY: BIAS AND PRECISION BY MATRIXBias Criteria Precision CriteriaREMP 2013 (+ / -25%/) (Note1WITHIN OUTSIDE WITHIN OUTSIDECRITERIA CRITERIA CRITERIA CRITERIAMILKGamma Iodine-131 41 0 131 0Gas Flow Sr 2nd count 46 0 49 0Gas Flow Total Strontium 35 0 35 0Gamma Spec Liquid RAD A-013 withBa, La 61 0 120 0SOLIDLSC Iron-55 5 0 5 0Gamma Spec Solid RAD A-013 28 0 31 0LSC Nickel 63 5 0 5 0Gas Flow Sr 2nd count 4 0 4 0Gas Flow Total Strontium 8 0 8 0Gamma Spec Solid RAD A-013 with Ba,La 7 0 10 0Gamma Spec Solid RAD A-013 withIodine 6 0 7 0FILTERGamma Spec Filter RAD A-013 4 0 4 0Gas Flow Sr 2nd Count 5 0 5 0Alpha Spec Am241Curium 3 0 3 0Gas Flow Total Strontium 3 0 3 0Gross A & B 526 0 527 0Gamma Spec Filter 45 0 51 0LIQUIDAlpha Spec Uranium 8 0 9 0Tritium 336 0 337 0Plutonium 1 0 1 0LSC Iron-55 40 0 42 0LSC Nickel 63 41 0 43 0Gamma Spec Liquid RAD A-013 7 0 7 0Gamma Iodine-131 33 0 33 0Alpha Spec Plutonium 10 0 10 0Gas Flow Sr 2nd count 20 0 20 0Alpha Spec Am241 Curium 17 0 17 0Gas Flow Total Strontium 161 0 163 0Gross Alpha Non Vol Beta 102 0 104 0Gamma Spec Liquid RAD A-013 withBa, La 129 0 209 0Gamma Spec Liquid RAD A-013 withIodine 56 0 85 0TISSUE MLaboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 46 of 58Gamma SDec Solid RAD A-013450480LSC Nickel 63 2 0 2 0Gas Flow Sr 2nd count 10 0 10 0Gas Flow Total Strontium 17 0 17 0Gamma Spec Solid RAD A-013 with Ba,La 6 0 5 0Gamma Spec Solid RAD A-013 withIodine 17 0 17 0SEA WATERLSC Iron-55 2 0 2 0LSC Nickel 63 2 0 2 0Gas Flow Total Strontium 1 0 1 0Gross Alpha Non Vol Beta 1 0 1 0Gamma Spec Liquid RAD A-013 withIodine 1 0 1 0VEGETATIONGas Flow Sr 2nd count 9 0 9 0Gamma Spec Solid RAD A-013 withIodine 91 0 93 0AIR CHARCOALGamma Iodine 131 RAD A-013 623 0 645 0Carbon-14 (Ascarite/Soda Lime Filterper Liter) 46 0 47 0DRINKING WATERTritium 51 0 52 0LSC Iron-55 24 0 22 0LSC Nickel 63 23 0 21 0Gamma Iodine-131 38 0 38 0Gas Flow Sr 2nd count 16 0 16 0Gas Flow Total Strontium 31 0 31 0Gross Alpha Non Vol Beta 103 0 103 0Gamma Spec Liquid RAD A-013 with 0Ba, La 44 0 98Total29963359Note 1: The RPD must be 20 percent or less, if both samples are greater than 5 times the MDC. If both resultsare less than 5 times MDC, then the RPD must be equal to or less than 100%. If one result is above the MDC andthe other is below the MDC, then the RPD can be calculated using the MDC for the result of the one below theMDC. The RPD must be 100% or less. In the situation where both results are above the MDC but one result isgreater than 5 times the MDC and the other is less than 5 times the MDC, the RPD must be less than or equal to20%. If both results are below MDC, then the limits on % RPD are not applicable.

MI Laboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 47 of 58TABLE 7ALL RADIOLOGICAL INTRA-LABORATORY DATA SUMMARY:BIAS AND PRECISION BY MATRIXBias Criteria Precision Criteria(+ / 25/o (Noe 1)WITHIN OUTSIDE WITHIN J OUTSIDEENVIRONMENTAL 2013 CRITERIA CRITERIA CRITERIA CRITERIAMILKGamma Spec Liquid RAD A-013 8 0 8 0Gamma Iodine-129 1 0 1 0Gamma Iodine-131 41 0 131 0Gas Flow Sr 2nd count 50 0 51 0Gas Flow Strontium 90 10 0 10 0Gas Flow Total Strontium 35 0 35 0Gamma Spec Liquid RAD A-013 withBa, La 61 0 120 0Gamma Spec Liquid RAD A-013 withIodine 5 0 3 0SOLIDGas Flow Radium 228 29 0 29 0Tritium 266 0 312 0Carbon-14 136 0 227 0LSC Iron-55 146 0 165 0Alpha Spec Polonium Solid 19 0 22 0Gamma Nickel 59 RAD A-022 138 0 157 0LSC Chlorine-36 in Solids 8 0 13 0Gamma Spec Ra226 RAD A-013 35 0 42 0Gamma Spec Solid RAD A-013 701 0 893 0LSC Nickel 63 176 0 201 0LSC Plutonium 223 0 245 0Technetium-99 309 0 339 0Gamma Spec Liquid RAD A-013 4 0 4 0ICP-MS Technetium-99 in Soil 75 0 74 0LSC Selenium 79 5 0 5 0Total Activity, 2 0 3 0Tritium 5 0 5 0Alpha Spec Am243 33 0 42 0Gamma Iodine-129 172 0 199 0Gas Flow Lead 210 18 0 19 0Total Uranium KPA 10 0 18 0Alpha Spec Uranium 278 0 380 0LSC Promethium 147 4 0 4 0LSC, Rapid Strontium 89 and 90 106 0 120 0Alpha Spec Thorium 207 0 288 0Gas Flow Radium 228 2 0 2 0ICP-MS Uranium-233, 234 in Solid 6 0 5 0 MLaboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 48 of 58Alpha Spec Plutonium 242 0 263 0ICP-MS Technetium-99 Prep in Soil 78 0 74 0LSC Calcium 45 2 0 2 0Alpha Spec Neptunium 234 0 256 0Alpha Spec Plutonium 157 0 195 0Alpha Spec Radium 226 7 0 8 0Gamma Spec Solid with Ra226, Ra228 5 0 6 0Gas Flow Sr 2nd count 15 0 18 0Gas Flow Strontium 90 187 0 207 0Gas Flow Total Radium 1 0 1 0Lucas Cell Radium 226 71 0 93 0Total Activity Screen 10 0 13 0Alpha Spec Am241 Curium 292 0 336 0Alpha Spec Total Uranium 5 0 6 0Gas Flow Total Strontium 40 0 44 0Gross Alpha Non Vol Beta 3 0 3 0ICP-MS Uranium-233, 234 Prep in Solid 5 0 5 0ICP-MS Uranium-235, 236, 238 in Solid 7 0 8 0Alpha Spec Polonium Solid 6 0 4 0Gamma Spec Solid RAD A-013 with Ba,La 7 0 10 0Gamma Spec Solid RAD A-013 withIodine 6 0 7 0Gamma Spec Solid RAD A-013(pCi/Sample) 0 0 2 0Tritium 3 0 3 0ICP-MS Uranium-234, 235, 236, 238 inSolid 245 0 234 0ICP-MS Uranium-235, 236, 238 Prep inSolid 5 0 5 0Gross Alpha/Beta 297 0 405 0Gross Alpha/Beta (AmericiumCalibration) Solid 0 0 1 0ICP-MS Uranium-234, 235, 236, 238Prep in Solid 122 0 115 0Lucas Cell Radium 226 by DOE HASL300 Ra-04 Solid 2 0 2 0FILTERAlpha Spec Uranium 18 0 24 0Alpha Spec Polonium 0 0 54 0Gamma 1-131, filter 4 0 4 0LSC Plutonium Filter 143 0 169 3Tritium 134 0 201 0Carbon-14 82 0 140 0Nickel-63 0 0 4 0LSC Iron-55 147 0 161 0Gamma Nickel 59 RAD A-022 140 0 159 0Gamma Iodine 131 RAD A-013 2 0 2 0 MLaboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 49 of 58LSC Nickel 63 138 0 162 0Technetium-99 103 0 137 0Gamma Spec Filter RAD A-013 195 0 245 0AIphaspec Np Filter per Liter 30 0 42 0AIphaspec Pu Filter per Liter 14 0 29 0Gamma Iodine-125 13 0 0 0Gamma Iodine-129 114 0 127 0Gross Alpha/Beta 0 0 1 0Alpha Spec Am243 13 0 42 0Gas Flow Lead 210 0 0 4 0LSC Plutonium Filter per Liter 36 0 43 0Total Uranium KPA 11 0 18 0Alpha Spec Uranium 83 0 114 0LSC, Rapid Strontium 89 and 90 144 0 168 0Alpha Spec Thorium 45 0 57 0Gas Flow Radium 228 0 0 2 0Alpha Spec Plutonium 107 0 123 0Alpha Spec Neptunium 112 0 129 0Alpha Spec Plutonium 142 0 183 0Alpha Spec Polonium,(Filter/Liter) 0 0 10 0Alpha Spec Radium 226 0 0 1 0Gas Flow Sr 2nd Count 93 0 101 0Gas Flow Strontium 90 59 0 78 0Gas Flow Total Radium 0 0 4 0Lucas Cell Radium-226 0 0 2 0Alpha Spec Am24lCurium 157 0 198 0Gas Flow Total Strontium 5 0 5 0Total Activity in Filter, 0 0 7 0Alphaspec Am241 Curium Filter perLiter 33 0 42 0Tritium 106 0 108 0Gamma Spec Filter PAD A-013 DirectCount 7 0 8 0Carbon-14 44 0 44 0Direct Count-Gross Alpha/Beta 72 0 0 0Gross Alpha/Beta 74 0 81 0ICP-MS Uranium-234, 235, 236, 238 inFilter 8 0 4 0Alpha Spec U 31 0 60 0Gross A & B 639 0 584 0LSC Iron-55 39 0 51 0Technetium-99 37 0 55 0Gas Flow Sr-90 29 0 35 0LSC Nickel 63 37 0 44 0Carbon-14 (Ascarite/Soda Lime Filterper Liter) 2 0 2 0Gas Flow Pb-210 25 0 46 0Gas Flow Ra-228 24 0 35 0 MLaboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 50 of 58Gamma Iodine 129 47 0 47 0ICP-MS Uranium-234, 235, 236, 238Prep in Filter 6 0 3 0Gamma Spec Filter 142 0 163 0Lucas Cell Ra-226 32 0 47 0Alpha Spec Thorium 27 0 46 0IJQUIDDAlpha Spec Uranium 418 0 607 0Alpha Spec Polonium 2 0 3 0Electrolytic Tritium 19 0 29 0Tritium 1415 0 1503 0Tritium by Combustion 1 0 1 0Carbon-14 181 0 204 0Plutonium 81 0 89 0Chlorine-36 in Liquids 2 0 3 0Iodine-131 6 0 3 0LSC Iron-55 290 0 347 0Gamma Nickel 59 RAD A-022 29 0 33 0Gamma Iodine 131 RAD A-013 3 0 3 0Gamma Radium 228 RAD A-013 1 0 1 0LSC Nickel 63 328 0 370 0LSC Radon 222 5 0 12 0Technetium-99 303 0 365 0Gamma Spec Liquid RAD A-013 874 0 875 0Alpha Spec Total U RAD A-011 0 0 2 0LSC Selenium 79 1 0 1 0Total Activity, 6 0 6 0Alpha Spec Am243 12 0 20 0Gamma Iodine-129 84 0 117 0Gamma Iodine-131 33 0 33 0ICP-MS Technetium-99 in Water 5 0 28 0Gas Flow Lead 210 83 0 94 0Total Uranium KPA 96 0 226 2LSC Promethium 147 3 0 3 0LSC, Rapid Strontium 89 and 90 15 0 15 0Alpha Spec Thorium 205 0 278 0Gas Flow Radium 228 244 0 318 0Gas Flow Radium 228 36 0 35 0Gas Flow Radium 228 1 0 1 0Alpha Spec Plutonium 317 0 436 0Alpha Spec Neptunium 110 0 127 0Alpha Spec Plutonium 61 0 86 0Alpha Spec Radium 226 0 0 1 0Gas Flow Sr 2nd count 283 0 316 0Gas Flow Strontium 90 499 0 568 0Gas Flow Strontium 90 2 0 2 0Gas Flow Total Radium 92 0 129 0ICP-MS Technetium-99 Prep in Water 5 0 28 0 MLaboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 51of 58ICP-MS Uranium-233, 234 in Uquid 1 0 1 0Lucas Cell Radium 226 372 0 487 0Lucas Cell Radium-226 17 0 21 0Total Activity Screen 3 0 3 0Chlorine-36 in Liquids 4 0 10 0Alpha Spec Am241 Curium 307 0 405 0Gas Flow Total Strontium 231 0 241 0Gross Alpha Non Vol Beta 1313 0 1554 0LSC Phosphorus-32 2 0 2 0Lucas Cell Radium 226 by Method Ra-04 3 0 3 0ICP-MS Uranium-233, 234 Prep inLiquid 1 0 1 0Tritium in Drinking Water by EPA 906.0 11 0 14 0Gamma Spec Liquid RAD A-013 withBa, La 131 0 211 0Gamma Spec Liquid RAD A-013 withIodine 159 0 205 0Gas Flow Strontium 89 & 90 6 0 0 0ICP-MS Uranium-235, 236, 238 inLiquid 2 0 2 0Gas Flow Total Alpha Radium 13 0 11 0Gross Alpha Co-precipitation 7 0 9 0ICP-MS Uranium-235, 236, 238 Prep inLiquid 1 0 1 0ICP-MS Uranium-234, 235, 236, 238 inLiquid 22 0 98 0Gross Alpha Beta (AmericiumCalibration) Liquid 16 0 21 0ICP-MS Uranium-234, 235, 236, 238Prep in Liquid 14 0 51 0Alpha/Beta (Americium Calibration)Drinking Water 5 0 4 0TISSUECarbon-14 2 0 2 0LSC Iron-55 3 0 3 0Gamma Nickel 59 RAD A-022 2 0 2 0Gamma Spec Solid RAD A-013 71 0 79 0LSC Nickel 63 4 0 4 0LSC Plutonium 1 0 1 0Technetium-99 2 0 2 0Tritium 1 0 1 0Gamma Iodine-129 2 0 2 0Gas Flow Lead 210 2 0 2 0Alpha Spec Uranium 5 0 5 0Alpha Spec Thorium 2 0 2 0Alpha Spec Plutonium 10 0 10 0Alpha Spec Neptunium 4 0 4 0Alpha Spec Plutonium 2 0 2 0Gas Flow Sr 2nd count 10 0 10 0 MLaboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 52 of 58Gas Flow Strontium 90 20 0 23 0Alpha Spec Am241 Curium 9 0 9 0Gas Flow Total Strontium 19 0 19 0Gamma Spec Solid RAD A-013 with Ba,La 6 0 5 0Gamma Spec Solid RAD A-013 withIodine 17 0 17 0Gross Alpha/Beta 2 0 2 0SEA WATERLSC Iron-55 2 0 2 0LSC Nickel 63 2 0 2 0Gas Flow Total Strontium 1 0 1 0Gross Alpha Non Vol Beta 1 0 1 0Gamma Spec Liquid RAID A-013 withIodine 1 0 1 0VEGETAT-IONGamma Nickel 59 RAD A-022 3 0 3 0Gamma Spec Solid RAD A-013 31 0 31 0LSC Nickel 63 3 0 3 0LSC Plutonium 1 0 1 0Technetium-99 6 0 6 0Tritium 9 0 9 0Gamma Iodine-129 1 0 1 0Gas Flow Lead 210 8 0 7 0Total Uranium KPA 4 0 4 0Alpha Spec Uranium 23 0 21 0Alpha Spec Thorium 7 0 7 0Alpha Spec Plutonium 15 0 12 0Alpha Spec Neptunium 1 0 1 0Alpha Spec Plutonium 1 0 1 0Gas Flow Sr 2nd count 9 0 9 0Gas Flow Strontium 90 19 0 18 0Gas Flow Total Radium 2 0 3 0Alpha Spec Am241 Curium 11 0 8 0Gamma Spec Solid RAID A-013 withIodine 91 0 93 0Gamma Spec Solid RAID A-013(pCi/Sample) 5 0 3 0Alpha Spec Am241 (pCi/Sample) 3 0 2 0ICP-MS Uranium-234, 235, 236, 238 inSolid 9 0 7 0Alpha Spec Uranium 1 0 17 0Gross Alpha/Beta 4 0 4 0Alpha Spec Plutonium 2 0 2 0Gas Flow Strontium 90 4 0 2 0ICP-MS Uranium-234, 235, 236, 238Prep in Solid 7 0 5 0AIR CHARCOALGamma Iodine 131 RAD A-013 623 0 645 0 Laboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 53 of 58Gamma Iodine-129 0 0 1 0Carbon-14 (Ascarite/Soda Lime Filterper Liter) 89 0 88 0DRINKING WATERAlpha Spec Uranium 7 0 8 0Tritium 51 0 52 0Iodine-131 1 0 2 0LSC Iron-55 24 0 22 0LSC Nickel 63 23 0 21 0LSC Radon 222 96 0 96 0Gamma Spec Liquid RAD A-013 24 0 24 0Total Activity, 2 0 2 0Gamma Iodine-129 2 0 2 0Gamma Iodine-131 38 0 38 0Total Uranium KPA 15 0 28 0Gas Flow Radium 228 42 0 42 0Alpha Spec Plutonium 6 0 6 0Gas Flow Sr 2nd count 16 0 16 0Gas Flow Strontium 90 25 0 24 0Lucas Cell Radium-226 58 6 78 0Alpha Spec Am241 Curium 6 0 6 0Gas Flow Total Strontium 31 0 31 0Gross Alpha Non Vol Beta 343 0 287 0Tritium in Drinking Water by EPA 906.0 37 0 34 0Gamma Spec Liquid RAD A-013 withBa, La 44 0 98 0Gas Flow Strontium 89 & 90 20 0 13 0Gas Flow Total Alpha Radium 1 0 1 0Gross Alpha Co-precipitation 105 0 87 0Alpha/Beta (Americium Calibration)Drinking Water 13 0 13 0ECLS-R-GA NJ 48 Hr Rapid Gross Alpha 8 0 8 0Total2014823892Note 1: The RPD must be 20 percent or less, if both samples are greater than 5 times the MDC. If both resultsare less than 5 times MDC, then the RPD must be equal to or less than 100%. If one result is above the MDC andthe other is below the MDC, then the RPD can be calculated using the MDC for the result of the one below theMDC. The RPD must be 100% or less. In the situation where both results are above the MDC but one result isgreater than 5 times the MDC and the other is less than 5 times the MDC, the RPD must be less than or equal to20%. If both results are below MDC, then the limits on % RPD are not applicable.

MLaboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 54 of 58TABLE 82013 CORRECTIVE ACTION REPORT SUMMARYCORRECTIVE ACTION ID#& DISPOSITIONPE FAILURECARR130513-789ISO Documentation of PT Failures inMAPEP-13-RdV28 for Uranium inVegetation by ICP/MS and AlphaSpecRoot Cause Analysis of MAPEP-1 3-RdV28Uranium-234/233, Uranium-235, Uranium-238 and TotalUraniumFollowing reviews of our process and data and conversationswith personnel from the affected laboratories, it wasdetermined that all failures were due to an analyst error duringsample preparation. Glass instead of Teflon beakers wereused during the sample digestion which containedHydrofluoric (HF) acid. Per Standard Operating ProcedureSOP) GL-RAD-A-015 section 11.2.4, the sample should havebeen transferred to a Teflon beaker. In this instance, this stepwas omitted. The digestion was performed in glass beakersso trace amounts of Uranium were leached from the glass intothe sample, resulting in high bias in the results. Normalprocedure dictates that glass is not used when using HF inthe digestion process due to the presence of natural Uraniumin the glassware.In order to prove that this was an isolated incident and thatour overall process is in control a series of digestions wereperformed in the glass beakers to confirm our conclusion.* HCL /HNO3 only digestion -Uranium was notdetected." HCL, HNO3, and HF digestion -Enough Uraniumactivity was detected to account for the high bias (asmany as 70 counts in a 16 hour1.851852e-4 days <br />0.00444 hours <br />2.645503e-5 weeks <br />6.088e-6 months <br /> and 40 minute count)." HF only digestion -Results similar to HCL, HNO3, andHF were observedA second PT was successfully analyzed for this matrix.CARR130522-791 Following a review of our processes, the data andconversations with personnel from the affected laboratories, itISO Documentation of PT Failures in was determined that our normal procedure for preparing soil-MRAD-18 for Cesium-1 34, Cesium- samples is not sufficient for this soil matrix. Per the Standard137 and Zinc-65 in Soil Operating Procedure (SOP) GL-RAD-A-021, the sample was

[Laboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORT Page 55 of 58dried, homogenized, and passed through a 28 mesh sieve.However, approximately 20-30% of the sample consists ofparticles greater than the 28 mesh sieve size. These largerparticles were not affected by our normal homogenizationprocess. In accordance with the SOP, the larger particleswere removed prior to preparing the container for gammacounting.Upon receipt of the graded report, the following steps weretaken to prove that this was an isolated incident and that ouroverall process is in control.1. A recount of the initially prepared sample performedand confirmed the originally reported results.2. A new container was then prepared from the originalsample but omitting the preparation step and counted.This produced acceptable results.3. A second sample was prepared per the SOP;however, only a portion of the sample was removedduring the sieving steps. This sample producedsimilar high biased results.An aliquot of the sample was then pulverized prior to gammacounting. This approach also produced acceptable results.Permanent Corrective/Preventive Actions orImprovements:In the future, these samples will be pulverized to ensure thatall the material passes through the 28 mesh sieve; thus,eliminating the need to remove any of the original sample. Acomment has been added to the set-up for the solid matrix.A second PT was successfully analyzed for this matrix.

ILaboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 56 of 58CARR130826-810For Failures of RAD-94 for GrossAlpha/Bea and Strontium 89/90 inWaterRoot Cause Analysis of Gross AlphaAfter a review of the data, an apparent reason for thisdiscrepancy could not be determined. The following stepswere taken to prove that this high bias was an isolatedoccurrence and that our overall process is within control.1. The batch quality control samples were reviewedand found to be compliant. The LCS recovered at110%. While the recovery is slightly elevated, it iswell within the 80%-120% acceptance range.2. Laboratory control data were also reviewed fortrends. None were noted.3. The instrument calibrations were reviewed forpositive biases that could have attributed to thisfailure. None were noted.4. Two sample duplicates were also prepared andcounted along with the reported result. Both resultsfell within the method's acceptance range forduplicate. One of the results also fell within theacceptance range of the study.5. The original sample was also recounted and theresults fell within the acceptance range.Root Cause Analysis of Strontiurn-89 (Sr-89)LAB PBMS A-004After a review of the data, an apparent reason for thisdiscrepancy could not be determined. The following stepswere taken to prove that this high bias was an isolatedoccurrence and that our overall process is within control.1. The batch quality control samples were reviewedand found to be compliant. The LCS recovered at98.1%.2. Laboratory control data were also reviewed fortrends. None were noted.3. The instrument calibrations were reviewed forpositive biases that could have attributed to thisfailure. None were noted.4. Sample duplicates were also prepared and countedalong with the reported result. Duplicate results fellwithin the acceptance range of the study.Root Cause Analysis of Strontium-89 (Sr-89)EPA 905.0After a review of the data, an apparent reason for thisdiscrepancy could not be determined. The following stepswere taken to prove that this high bias was an isolated Laboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORT Page 57 of 58occurrence and that our overall process is within control.1. The batch quality control samples were reviewedand found to be compliant. The LCS recovered at102%.2. Laboratory control data were also reviewed fortrends. None was noted.3. The instrument calibrations were reviewed forpositive biases that could have attributed to thisfailure. None were noted.4. Sample duplicates were also prepared and countedalong with the reported result. All results fell withinthe method's acceptance range for duplicates.Permanent CorrectivelPreventive Actions orImprovements:Gross AlphaThe laboratory must assume an unidentified random errorcaused the high bias because all quality control criteria weremet for the batch. The lab will continue to monitor therecoveries of this radionuclide to ensure that there are noissues.Strontium-89 (Sr-89)LAB PBMS A-004 and EPA 905.0To summarize our efforts (including the initial result), thelaboratory had 3 analysts, two different methods, processedwith 2 calibrations and two separate Y carriers used in theanalysis of this sample and only one acceptable result for Sr-89. All LCS results have met acceptance criteria. This leadsthe laboratory to conclude that there is possibly an error in theoriginal make-up of the PT sample. The instructions liststable Sr and Y as being included but they are not at levelsgreater than are normally listed so we suspect that the makeup of the sample was the cause. The laboratory will continueto monitor the recoveries from these two methods to ensurethat there are no issues.

[Laboratories LLCP.O. Box 30712, Charleston, SC 294172013 ANNUAL QUALITY ASSURANCE REPORTPage 58 of 58CARRI 31205-845For failures of MRAD-19 for Uranium-234 and Total Uranium in VegetationRoot Cause AnalysisThese elevated results were obtained following our routineprocedure. The reported result for U-234 was less than theMDA and had a elevated uncertainty. This high U-234 resultalso attributed to the high Total-U result.Upon receipt of the graded report, the following steps weretaken to prove that this was an isolated incident and that ouroverall process is in control.* A recount of the initially prepared sample performedand confirmed the originally reported results." The sample was reanalyzed using a larger aliquot andresults that fell within the acceptance range wereachieved.Permanent CorrectivelPreventive Actions orImprovementsIn the future when the result is below the MDA and are notcompatible with other analytical technologies, the laboratorywill attempt to use a larger sample aliquot with hopes ofachieve a result above the MDA or with a lower uncertainty. Ifthe matrix and larger sample size do not provide useabledata, the results may not be report.