ML031410401

Radiological Environmental Monitoring Program Report for 2002

ML031410401
Person / Time
Site:	Pilgrim
Issue date:	05/12/2003
From:	Riggs W Entergy Nuclear Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML031410401 (122)

Text

AQ E___

w Entergy Nuclear Operations, Inc.

te, aO1I Pilgrim Station

'g'~En trgy 600 Rocky Hill Road Plymouth, MA 02360 William J. Riggs Director, Nuclear Assessment May 12, 2003 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

SUBJECT:

Entergy Nuclear Operations, Inc.

Pilgrim Nuclear Power Station Docket No. 50-293 Radiological Environmental Monitoring Program Report for 2002 (Report #35)

LETTER NUMBER:

2.03.074

Dear Sir or Madam:

In accordance with Pilgrim Nuclear Power Station Technical Specification 5.6.2, Entergy Nuclear Operations, Inc. submits the annual "Radiological Environmental Monitoring Program Report" for 2002 (Report #35).

Sincerely, W.J. Riggs WGUdd

Attachment:

Radiological Environmental Monitoring Program Report for 2002 (Report #35) cc: U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Mr. Travis Tate, Project Manager Office of Nuclear Reactor Regulation Mail Stop: 0-8B-1 U.S. Nuclear Regulatory Commission 1 White Flint North 11555 Rockville Pike Rockville, MD 20852 203074

PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 Radiological Environmental Monitoring Program Report January 1 through December 31, 2002 Entegy

Prepared by:.

Reviewed by:

Reviewed by:

K.-8'jo,rA

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Coordiror: HP/Chemistry Support P.J. McNu107 Chemist uperintendent D.C. Perry Q

Radiation Protection-Ma Page 1 w Entergy PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT JANUARY 01 THROUGH DECEMBER 31, 2002 h

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Pilgrim Nuclear Power Station Radiological Environmental Monitoring Program Report January-December 2002 TABLE OF CONTENTS SECTION 1.0 1.1 1.2 1.3 1.4 1.5 2.0 2.1 2.2 2.3 2.4 2.5 2.6 2.7 2.8 2.9 2.10 2.11 2.12 2.13 2.14 2.15 2.16 2.17 3.0 4.0 APPENDIX A APPENDIX B APPENDIX C APPENDIX D APPENDIX E APPENDIX F SECTION TITLE EXECUTIVE

SUMMARY

INTRODUCTION Radiation and Radioactivity Sources of Radiation Nuclear Reactor Operations Radioactive Effluent Control Radiological Impact on Humans RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Pre-Operational Monitoring Results Environmental Monitoring Locations Interpretation of Radioactivity Analyses Results Ambient Radiation Measurements Air Particulate Filter Radioactivity Analyses Charcoal Cartridge Radioactivity Analyses Milk Radioactivity Analyses Forage Radioactivity Analyses VegetableNegetation Radioactivity Analyses Cranberry Radioactivity Analyses Soil Radioactivity Analyses Surface Water Radioactivity Analyses Irish Moss Radioactivity Analyses Shellfish Radioactivity Analyses Lobster Radioactivity Analyses Fish Radioactivity Analyses Sediment Radioactivity Analyses

SUMMARY

OF RADIOLOGICAL IMPACT ON HUMANS REFERENCES Special Studies Effluent Release Information Land Use Census Environmental Monitoring Program Discrepancies Framatome ANP Quality Assurance Program Results J A. Ftzpatrick Environmental Interlaboratory Comparison Program Page 2 PAGE 5

7 7

8 9

14 17 22 22 23 24 26 27 28 28 29 29 30 30 30 31 31 31 32 33 72 74 75 76 89 90 93 97

Pilgrim Nuclear Power Station Radiological Environmental Monitoring Program Report January-December 2002 LIST OF TABLES TABLE TABLE TITLE PAGE 1.2-1 Radiation Sources and Corresponding Doses 8

1.3-1 PNPS Operating Capacity Factor During 2002 9

2.2-1 Routine Radiological Environmental Sampling Locations 34 2.4-1 Offsite Environmental TLD Results 36 2.4-2 Onsite Environmental TLD Results 38 2.4-3 Average TLD Exposures By Distance Zone During 2002 39 2.4-4 Beach Survey Exposure Rate Measurements 40 2.5-1 Air Particulate Filter Radioactivity Analyses 41 2.6-1 Charcoal Cartridge Radioactivity Analyses 42 2.7-1 Milk Radioactivity Analyses 43 2.8-1 Forage Radioactivity Analyses 44 2.9-1 VegetableNegetation Radioactivity Analyses 45 2.10-1 Cranberry Radioactivity Analyses 46 2.11-1 Soil Radioactivity Analyses 47 2.12-1 Surface Water Radioactivity Analyses 48 2.13-1 Irish Moss Radioactivity Analyses 49 2.14-1 Shellfish Radioactivity Analyses 50 2.15-1 Lobster Radioactivity Analyses 51 2.16-1 Fish Radioactivity Analyses 52 2.17-1 Sediment Radioactivity Analyses 53 2.17-2 Sediment Plutonium Analyses 54 3.0-1 Radiation Doses From 2002 Pilgrim Station Operations 73 B.1 Supplemental Information 77 B.2-A Gaseous Effluents Summation of All Releases 79 B.2-B Gaseous Effluents - Elevated Releases 81 B.2-C Gaseous Effluents - Ground Level Releases 83 B.3-A Liquid Effluents Summation of All Releases 85 B.3-B Liquid Effluents: January-June 2002 87 E.1 Framatome ANP Intralaboratory And Interlaboratory Results - 2002 94 F.1 2002 QA Program Schedule 98 F.2 Ratio of Agreement 99 F.3 2002 Cr-51 Results 101 F.4 Nonconformity No. 02-08 Fe-59 Results 101 F.5 JAF Environmental Lab Summary 102 F.6 EML Summary QAP-56 Cs-134 in Water 103 F.7 Interlaboratory Comparison Program 104 Page 3

Pilgrim Nuclear Power Station Radiological Environmental Monitoring Program Report January-December 2002 LIST OF FIGURES FIGURE FIGURE TITLE PAGE 1.3-1 Radioactive Fission Product Formation 1 1 1.3-2 Radioactive Activation Product Formation 12 1.3-3 Barriers to Confine Radioactive Materials 13 1.5-1 Radiation Exposure Pathways 19 2.2-1 Environmental TLD Locations Within the PNPS Protected Area 55 2.2-2 TLD and Air/Soil Sampling Locations: Within 1 Kilometer 57 2.2-3 TLD and Air/Soil Sampling Locations: 1 to 5 Kilometers 59 2.2-4 TLD and Air/Soil Sampling Locations: 5 to 25 Kilometers 61 2.2-5 Terrestrial and Aquatic Sampling Locations 63 2.2-6 Environmental Sampling and Measurement Control Locations 65 2.4-1 Historical Beach Survey Exposure Rate Measurements 67 2.5-1 Airborne Gross Beta Radioactivity Levels: Near Station 68 2.5-2 Airborne Gross Beta Radioactivity Levels: Property Line 69 2.5-3 Airborne Gross Beta Radioactivity Levels: Offsite 70 2.7-1 Levels of Strontium-90 in Milk Samples 71 a

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EXECUTIVE

SUMMARY

ENTERGY NUCLEAR PILGRIM NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT JANUARY 01 THROUGH DECEMBER 31, 2002 INTRODUCTION This report summarizes the results of the Entergy Nuclear Radiological Environmental Monitoring Program (REMP) conducted in the vicinity of Pilgrim Nuclear Power Station (PNPS) during the period from January 1 to December 31, 2002. This document has been prepared in accordance with the requirements of PNPS Technical Specifications section 5.6.2.

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

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

During 2002, there were 1,418 samples collected from the atmospheric, aquatic and terrestrial environments.,In addition, 436 exposure measurements were obtained using environmental thermoluminescent dosimeters (TLDs), and six exposure rate measurements were performed using a high-pressure ion chamber.

Beginning in July 2002, Pilgrim Station began to use Entergy's J.A. Fitzpatrick Environmental Laboratory for analysis of environmental samples. Initially, air particulate and charcoal samples were submitted to the JAF Lab, and other sample streams were gradually shifted over during the second half of the year.

By the end of the year, all radioanalytical services were being performed by the JAF Lab, and only TLDs were being processed by Framatome ANP.

A small number of inadvertent issues were encountered during 2002 in the collection of environmental samples in accordance with the PNPS Offsite Dose Calculation Manual (ODCM).

Four out of 440 TLDs were unaccounted for during the quarterly retrieval process. However, the 436 TLDs that were collected provided the information necessary to assess ambient radiation levels in the vicinity of Pilgrim Station. Equipment failures and power outages resulted in a small number of instances in which lower than normal volumes were collected at the airborne sampling stations. However, 572 of 572 air particulate and charcoal cartridges were collected and analyzed as required. A full description of any discrepancies encountered with the environmental monitoring program is presented in Appendix D of this report.

There were 1,527 analyses performed on the environmental media samples. Analyses were performed by the Framatome ANP Environmental Laboratory in Westborough, Massachusetts, and the J.A. Fitzpatrick Environmental Laboratory in Fulton, New York. Samples were analyzed as required by the PNPS ODCM.

LAND USE CENSUS The annual land use census in the vicinity of Pilgrim Station was conducted as required by the PNPS ODCM between October 22 and 31, 2002. A total of 31 vegetable gardens having an Page

area of more than 500 square feet were identified within five kilometers (three miles) of PNPS.

No new milk or meat animals were located during the census. Of the 31 garden locations identified, samples were collected at or near five of the gardens as part of the environmental monitoring program.

RADIOLOGICAL IMPACT TO THE ENVIRONMENT During 2002, samples (except charcoal cartridges) collected as part of the REMP at Pilgrim Station continued to contain detectable amounts of naturally-occurring and man-made radioactive materials.

The only environmental media collected in 2002 which showed any detectable activity attributable to PNPS operations was shellfish, which indicated low-levels of Cs-137, yielding a maximum whole body dose to the maximum-exposed member of the public of 0.005 mrem. Offsite ambient radiation measurements using environmental TLDs and a high-pressure ion chamber ranged between 38 and 72 milliRoentgens per year. The range of ambient radiation levels observed with the TLDs is consistent with natural background radiation levels for Massachusetts as determined by the Environmental Protection Agency (EPA).

RADIOLOGICAL IMPACT TO THE GENERAL PUBLIC During 2002, radiation doses to the general public as a result of Pilgrim Station's operation continued to be well below the federal limits and much less than the dose due to other sources of man-made (e.g., X-rays, medical, fallout) and naturally-occurring (e.g., cosmic, radon) radiation.

The calculated total body dose to the maximally-exposed member of the general public from radioactive effluents and ambient radiation resulting from PNPS operations for 2002 was about 5.4 mrem for the year. This conservative estimate is well below the EPA's annual dose limit to any member,of the general public and is a fraction of a percent of the typicalPdose received from natural and man-made radiation.

CONCLUSIONS The 2002 Radiological Environmental Monitoring Program for Pilgrim Station resulted in the collection and analysis of hundreds of environmental samples and measurements. The data obtained were used to determine the impact of Pilgrim Station's operation on the environment and on the general public.

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

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

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1.0 INTRODUCTION

The Radiological Environmental Monitoring Program for 2002 performed by Entergy Nuclear Company for Pilgrim Nuclear Power Station (PNPS) is discussed in this report.

Since the operation of a nuclear power plant results in the release of small amounts of radioactivity and low levels of radiation, the Nuclear Regulatory Commission (NRC) requires a program to be established to monitor radiation and radioactivity in the environment (Reference 1). This report, which is required to be published annually by Pilgrim Station's Technical Specifications section 5.6.2, summarizes the results of measurements of radiation and radioactivity in the environment in the vicinity of the Pilgrim Station and at distant locations during the period January 1 to December 31, 2002.

The Radiological Environmental Monitoring Program consists of taking radiation measurements and collecting samples from the environment, analyzing them for radioactivity content, and interpreting the results. With emphasis on the critical radiation exposure pathways to humans, samples from the aquatic, atmospheric, and terrestrial environments are collected. These samples include, but are not limited to: air, soil, seawater, shellfish, lobster, fishes, milk, cranberries, vegetables, and forage. Thermoluminescent dosimeters (TLDs) are placed in the environment to measure gamma radiation levels.

The TLDs are processed and the environmental samples are analyzed to measure the very low levels of radiation and radioactivity present in the environment as a result of PNPS operation and other natural and man-made sources. These results are reviewed by PNPS's radiological staff and have been reported semiannually or annually to the Nuclear Regulatory Commission and others since 1972.

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

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

Radioactive material exists naturally and has always been a part of our environment. The earth's crust, for example, contains radioactive uranium, radium, thorium, and potassium.

Some radioactivity is a result of nuclear weapons testing. Examples of radioactive fallout that is normally present in environmental samples are cesium-137 and strontium-90. Some examples of radioactive materials released from a nuclear power plant are cesium-137, iodine-131, strontium-90, and cobalt-60.

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Radiation is measured in units of millirem, much like temperature is measured in degrees. A millirem is a measure of the biological effect of the energy deposited in tissue. The natural and man-made radiation dose received in one year by the average American is 300 to 400 mrem (References 2, 3, 4).

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

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

Table 1.2-1 Radiation Sources and CorresDonding Doses NATURAL MAN-MADE Radiation Dose Radiation Dose Source (millirem/year)

Source (millirerVear)

Cosmic/cosmogenic 30 MedicaVDental X-Rays:

39 Internal 40 Nuclear Medicine 14 Terrestrial 30 Consumer Products 10 Radon/Thoron 200 Weapons Fallout 1

Nuclear Power Plants 1

Approximate Total 300 Approximate Total 60 Cosmic radiation from the sun and outer space penetrates the earth's atmosphere and continuously bombards us with rays and charged particles.

Some of this cosmic radiation interacts with gases and particles in the atmosphere, making them radioactive in tum. These radioactive byproducts from cosmic ray bombardment are referred to as cosmogenic radionuclides. Isotopes such as beryllium-7 and carbon-14 are formed in this way. Exposure to cosmic and cosmogenic sources of radioactivity results in about 30 mrem of radiation dose per year.

Additionally, natural radioactivity is in our body and in the food we eat (about 40 millirem/yr), the ground we walk on (about 30 millirem/yr) and the air we breathe (about 200 millirem/yr). The majority of a person's annual dose results from exposure to radon and thoron in the air we breathe. These gases and their radioactive decay products arise from the decay of naturally occurring uranium, thorium and radium in the soil and building products such as brick, stone, and concrete. Radon and thoron levels vary greatly with location, primarily due to changes in the concentration of uranium and thorium in the soil. Residents at some locations in Colorado, New York, Pennsylvania, and New Jersey have a higher annual dose as a result of higher Page 8

levels of radon/thoron gases in these areas.

In total, these various sources of naturally-occurring radiation and radioactivity contribute to a total dose of about 300 mrem per year.

In addition to natural radiation, we are normally exposed to radiation from a number of man-made sources. The single largest doses from man-made sources result from therapeutic and diagnostic applications of x-rays and radiopharmaceuticals. The annual dose to an individual in the U.S. from medical and dental exposure is about 50 mrem. Consumer products, such as televisions and smoke detectors, contribute about 10 mrem/yr. Much smaller doses result from weapons fallout (less than 1 mrem/yr) and nuclear power plants (less than 1 mrem/yr).

Typically, the average person in the United States receives about 60 mrem per year from man-made sources.

1.3 Nuclear Reactor Operations Pilgrim Station generates about 670 megawatts of electricity at full power, which is enough electricity to supply the entire city of Boston, Massachusetts. Pilgrim Station is a boiling water reactor whose nuclear steam supply system was provided by General Electric Co. The nuclear station is located on a 1600-acre site about eight kilometers (five miles) east-southeast of Plymouth Center. Commercial operation began in December 1972.

Pilgrim Station was operational during most of 2002. The resulting monthly capacity factors are presented in Table 1.3-1.

TABLE 1.3-1 PNPS OPERATING CAPACITY FACTOR DURING 2002 (Based on 670 megawatts electric)

Month Percent Capacity January 99.0%

February 99.7%

March 98.3%

April 99.5%

May 96.8%

June 96.4%

July 95.5%

August 99.6%

September 97.0%

October 99.3%

November 98.4%

December 98.2%

Annual Average 98.1%

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

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

Inside the reactor, a nuclear reaction called fission takes place.

Particles, called neutrons, strike the nucleus of a uranium-235 atom, causing it to split into fragments called radioactive fission products. The splitting of the atoms releases both heat and more neutrons. The newly-released neutrons then collide with and split other uranium atoms, thus making more heat and releasing even more neutrons, and on and on until the uranium fuel is depleted or spent. This process is called a chain reaction.

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

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

Examples of some fission products are krypton-85 (Kr-85),

strontium-90 (Sr-90), iodine-131 (1-131), xenon-133 (Xe-133), and cesium-1 37 (Cs-1 37).

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

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

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

Radioactive activation products (see Figure 1.3-2), on the other hand, originate from two sources. The first is by neutron bombardment of the hydrogen, oxygen and other gas (helium, argon, nitrogen) molecules in the reactor cooling water. The second is a result of the fact that the internals of any piping system or component are subject to minute yet constant corrosion from the reactor cooling water. These minute metallic particles (for example: nickel, iron, cobalt, or magnesium) are transported through the reactor core into the fuel region, where neutrons may react with the nuclei of these particles, producing radioactive products.

So, activation products are nothing more than ordinary naturally-occurring atoms that are made unstable or radioactive by neutron bombardment.

These activation products circulate along with the reactor coolant water and will deposit on the intemal surfaces of pipes and equipment.

The radioactive activation products on the pipes and equipment emit radiation. Examples of some activation products are manganese-54 (Mn-54), iron-59 (Fe-59), cobalt-60 (Co-60), and zinc-65 (Zn-65).

Co-59 t.

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

fuel pellets; fuel cladding; reactor vessel and piping; primary containment (drywell and torus); and, secondary containment (reactor building).

Page 12 Neutron

X SIMPLIFIED DIAGRAM OF A BOILING WATER REACTOR

4. PRIMARY CONTAINMENT

3. REACTOR VESSEL

'ELLETS

2. FUEL CLADDING

5. SECONDARY CONTAINMENT DRYWELL Figure 1.3-3 Barriers To Confine Radioactive Materials Page 13

1. FUEL P REACTOR BUILDING

The ceramic uranium fuel pellets provide the first barrier.

Most of the radioactive fission products are either physically trapped or chemically bound between the uranium atoms, where they will remain.

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

The second barrier, the fuel cladding, consists of zirconium alloy tubes that confine the fuel pellets. The small gaps between the fuel and the cladding contain the noble gases and volatile iodines that are types of radioactive fission products. This radioactivity can diffuse to a small extent through the fuel cladding into the reactor coolant water.

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

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

Small amounts of radioactivity may be released from primary containment during maintenance.

The fifth barrier is the secondary containment or reactor building. The reactor building is the concrete building that surrounds the primary containment. This barrier is an additional safety feature to contain radioactivity that may escape from the primary containment.

This reactor building is equipped with a filtered ventilation system that is used when needed to reduce the radioactivity that escapes from the primary containment.

The five barriers confine most of the radioactive fission and activation products.

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

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

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

reactor water cleanup system; liquid radwaste treatment system; sampling and analysis of the liquid radwaste tanks; and, liquid waste effluent discharge header radioactivity monitor.

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

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

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

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

This liquid waste effluent discharge header is provided with a shielded radioactivity monitor.

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

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

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

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

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

reactor building ventilation system; reactor building vent effluent radioactivity monitor; sampling and analysis of reactor building vent effluents; standby gas treatment system; main stack effluent radioactivity monitor and sampling; sampling and analysis of main stack effluents; augmented off-gas system; steam jet air ejector (SJAE) monitor; and, off-gas radiation monitor.

The purpose of the reactor building ventilation system is to collect and exhaust reactor building air. Air collected from contaminated areas is filtered prior to combining it with air collected from other parts of the building.

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

If air containing elevated amounts of noble gases is routed past the reactor building vent's effluent radioactivity monitor, an alarm will alert the Control Room operators that release limits are being approached. The Control Room operators, according to procedure, will isolate the reactor building ventilation system and initiate the standby gas treatment system to remove airborne particulates and gaseous halogen radioactivity from the reactor building exhaust. This filtration assembly consists of high-efficiency particulate air filters and charcoal adsorber beds.

The purified air is then directed to the main stack. The main stack has dilution flow that further reduces concentration levels of gaseous releases to the environment to as far below the release limits as is reasonably achievable.

The approximately 330 foot tall main stack has a special probe inside it that withdraws a portion of the air and passes it through a radioactivity monitoring system. This main stack effluent radioactivity monitoring system continuously samples radioactive particulates, iodines, and noble gases.

Grab samples for a tritium analysis are also collected at this location. The system also contains radioactivity detectors that monitor the levels of radioactive noble gases in the stack flow and display the result on radiation level meters and strip chart recorders located in the Control Room. To supplement the information continuously provided by the detectors, the particulate, iodine, tritium, and gas samples are analyzed periodically to quantify the total amount of radioactive gaseous effluent being released.

The purpose of the augmented off-gas system is to reduce the radioactivity from the gases that are removed from the condenser. This purification system consists of two 30-minute holdup lines to reduce the radioactive gases with short half-lives, several charcoal adsorbers to remove radioactive iodines and further retard the short half-life gases, and offgas filters to remove Page 16

radioactive particulates.

The recombiner collects free hydrogen and oxygen gas and recombines them into water. This helps reduce the gaseous releases of short-lived isotopes of oxygen that have been made radioactive by neutron activation.

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

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

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

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

The types and quantities of radioactive liquid and gaseous effluents released from Pilgrim Station during each given year are reported to the Nuclear Regulatory Commission annually.

The 2002 Radioactive Effluents are provided in Appendix B and will be discussed in more detail in Section 3 of this report. These liquid and gaseous effluents were well below the federal release limits and were a small percentage of the PNPS ODCM effluent control limits.

These measurements of the physical and chemical nature of the effluents are used to determine how the radionuclides will interact with the environment and how they can result in radiation exposure to humans.

The environmental interaction mechanisms depend upon factors such as the hydrological (water) and meteorological (atmospheric) characteristics in the area.

Information on the water flow, wind speed, wind direction, and atmospheric mixing characteristics are used to estimate how radioactivity will distribute and disperse in the ocean and the atmosphere.

Page 17

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

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

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

extemal radiation from liquid effluents that deposit and accumulate on the shoreline; external radiation from immersion in ocean water containing radioactive liquids; and, internal radiation from consumption of fish and shellfish containing radioactivity absorbed from the liquid effluents.

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

external radiation from an airborne plume of radioactivity; internal radiation from inhalation of airbome 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 absorbed from the soil due to ground deposition of radioactive effluents; and, internal radiation from consumption of milk and meat containing radioactivity deposited on forage that is eaten by cattle and other livestock.

In addition, ambient (direct) radiation emitted from contained sources of radioactivity at PNPS contributes to radiation exposure in the vicinity of the plant. Radioactive nitrogen-16 contained in the steam flowing through the turbine accounts for the majority of this "sky shine" radiation exposure immediately adjacent to the plant. Smaller amounts of ambient radiation result from low-level radioactive waste stored at the site prior to shipping and disposal.

To the extent possible, the radiological dose impact on humans is based on direct measurements of radiation and radioactivity in the environment. When PNPS-related activity is detected in samples that represent a plausible exposure pathway, the resulting dose from such exposure is assessed (see Appendix A).

However, the operation of Pilgrim Nuclear Power Station results in releases of only small amounts of radioactivity, and, as a result of dilution in the atmosphere and ocean, even the most sensitive radioactivity measurement and analysis techniques cannot usually detect these tiny amounts of radioactivity above that which is naturally present in the environment.

Therefore, radiation doses are calculated using radioactive effluent release data and computerized dose calculations that are based on very conservative NRC-recommended models that tend to result in over-estimates of resulting dose.

These computerized dose calculations are performed by or for Entergy Nuclear personnel.

These computer codes use the guidelines and methodology set forth by the NRC in Regulatory Guide 1.109 (Reference 6). The dose calculations are documented and described in detail in the Pilgrim Nuclear Power Station's Offsite Dose Calculation Manual (Reference 7) which has been reviewed by the NRC.

Page 18

lI EXAMPLES OF PILGRIM STATION'S RADIATION EXPOSURE PATHWAYS LIQUID EFFLUENTS

4.

DIRECT RADIATION Q

(SOIL DEPOSITION)

1. SHORELINE DIRECT RADIATI(

(FISHING, PICNICING)

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

INGESTION (AIR SUBMERSION)

LtX

5. CONSUMPTION (VEGETATION)

DEPOSITION

6. CONSUMPTION (MILK AND MEAT)

DEPOSITION

3. CONSUMPTION (FISH, SHELLFISH)

INGESTION Figure 1.5-1 Radiation Exposure Pathways Page 1 9 g:2:N0;

~~~~~~~~~~~~~~~~~..........

~~~~

5 5 <

3 aS

' 0 -5_>~~~~~~~~~~~~~~...

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

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

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

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

In addition to this dose limit, the NRC has established design objectives for nuclear plant licensees. Conformance to these guidelines ensures that nuclear power reactor effluents are maintained as far below the legal limits as is reasonably achievable.

The NRC, in 1 OCFR 50 Appendix I (Reference 9) establishes design objectives for the dose to a member of the general public from radioactive material in liquid effluents released to unrestricted areas to be limited to:

less than or equal to 3 mrem per year to the total body; and, less than or equal to 10 mrem per year to any organ.

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

less than or equal to 10 mrad per year for gamma radiation; and, less than or equal to 20 mrad per year for beta radiation.

The dose to a member of the general public from iodine-131, tritium, and all particulate radionuclides with half-lives greater than 8 days in gaseous effluents is limited to:

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

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The EPA, in 40CFR190.10 Subpart B (Reference 10), sets forth the environmental standards for the uranium fuel cycle. During normal operation, the annual dose to any member of the public from the entire uranium fuel cycle shall be limited to:

less than or equal to 25 mrem per year to the total body; less than or equal to 75 mrem per year to the thyroid; and, less than or equal to 25 mrem per year to any other organ.

The summary of the 2002 radiological impact for Pilgrim Station and comparison with the EPA dose limits and guidelines, as well as a comparison with natural/man-made radiation levels, is presented in Section 3 of this report.

The third stage of assessing releases to the environment is the Radiological Environmental Monitoring Program (REMP).

The description and results of the REMP at Pilgrim Nuclear Power Station during 2002 is discussed in Section 2 of this report.

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

measure background levels and their variations in the environment in the area surrounding the licensee's station; and, evaluate procedures, equipment, and techniques for monitoring radiation and radioactivity in the environment.

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

Airborne Radioactivity Particulate Concentration (gross beta): 0.02 - 1.11 pCVm3; Ambient Radiation (TLDs): 4.2 - 22 micro-R/hr (37 - 190 mR/yr);

Seawater Radioactivity Concentrations (gross beta): 12 - 31 pCiliter; Fish Radioactivity Concentrations (gross beta): 2,200 - 11,300 pCVkg; Milk Radioactive Cesium-1 37 Concentrations: 9.3 - 32 pCiliter; Milk Radioactive Strontium-90 Concentrations: 4.7 - 17.6 pCi/liter; Cranberries Radioactive Cesium-137 Concentrations: 140 - 450 pCi/kg; Forage Radioactive Cesium-1 37 Concentrations: 150 - 290 pCVkg.

This information from the pre-operational phase.is used as a basis for evaluating changes in radiation and radioactivity levels in the vicinity of the plant following plant operation. In April 1972, just prior to initial reactor startup (June 12, 1972), Boston Edison Company implemented a comprehensive operational environmental monitoring program at Pilgrim Nuclear Power Station. This program (Reference 13) provides information on radioactivity and radiation levels in the environment for the purpose of:

demonstrating that doses to the general public and levels of radioactivity in the environment are within established limits and legal requirements; monitoring the transfer and long-term buildup of specific radionuclides in the environment to revise the monitoring program and environmental models in response to changing conditions; checking the condition of the station's operation, the adequacy of operation in relation to the adequacy of containment, and the effectiveness of effluent treatment so as to provide a mechanism of determining unusual or unforeseen conditions and, where appropriate, to trigger special environmental monitoring studies; Page 22

assessing the dose equivalent to the general public and the behavior of radioactivity released during the unlikely event of an accidental release; and, determining whether or not the radiological impact on the environment and humans is significant.

The Nuclear Regulatory Commission requires that Pilgrim Station provide monitoring of the plant environs for radioactivity that will be released as a result of normal operations, including anticipated operational occurrences, and from postulated accidents. The NRC has established guidelines (Reference 14) that specify an acceptable monitoring program.

The PNPS Radiological Environmental Monitoring Program was designed to meet and exceed these guidelines.

Guidance contained in the NRC's Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 15) has been used to improve the program.

In addition, the program has incorporated the provisions of an agreement made with the Massachusetts Wildlife Federation (Reference 16).

The program was supplemented by including improved analysis of shellfish and sediment at substantially higher sensitivity levels to verify the adequacy of effluent controls at Pilgrim Station.

2.2 Environmental Monitoring Locations Sampling locations have been established by considering meteorology, population distribution, hydrology, and land use characteristics of the Plymouth area.

The sampling locations are divided into two classes, indicator and control. Indicator locations are those that are expected to show effects from PNPS operations, if any exist. These locations were primarily selected on the basis of where the highest predicted environmental concentrations would occur. While the indicator locations are typically within a few kilometers of the plant, the control stations are generally located so as to be outside the influence of Pilgrim Station. They provide a basis on which to evaluate fluctuations at indicator locations relative to natural background radiation and natural radioactivity and fallout from prior nuclear weapons tests.

The environmental sampling media collected in the vicinity of Pilgrim Station during 2002 included air particulate filters, charcoal cartridges, seawater, shellfish, Irish moss, American lobster, fishes, sediment, milk, cranberries, vegetation, and forage. The sampling medium, station description, station number, distance, and direction for indicator and control samples are listed in Table 2.2-1.

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

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

The land-based (terrestrial) samples and monitoring devices are collected by Entergy personnel. The aquatic samples are collected by Marine Research, Inc.

Personnel from Framatome/DE&S conduct the direct radiation measurements and soil radioactivity measurements, respectively. The radioactivity analysis of samples and the processing of the environmental TLDs are performed by Framatome ANP Environmental Laboratory and Entergy's J.A. Fitzpatrick Environmental Laboratory.

The frequency, types, minimum number of samples, and maximum lower limits of detection (LLD) for the analytical measurements, are specified in the PNPS ODCM.

Upon receipt of the analysis results from the analytical laboratories, the PNPS staff reviews the results. If the radioactivity concentrations are above the reporting levels, the NRC must be notified within 30 days. For radioactivity that is detected that is attributable to Pilgrim Station's operation, calculations are performed to determine the cumulative dose contribution for the Page 23

current year. Depending upon the circumstances, a special study may also be completed (see Appendix A for 2002 special studies). Most importantly, if radioactivity levels in the environment become elevated as a result of the station's operation, an investigation is performed and corrective actions are recommended to reduce the amount of radioactivity to as far below the legal limits as is reasonably achievable.

The radiological environmental sampling locations are reviewed annually, and modified if necessary. A garden and milk animal census is performed every year to identify changes in the use of the environment in the vicinity of the station to permit modification of the monitoring and sampling locations. The results of the 2002 Garden and Milk Animal Census are reported in Appendix C.

The accuracy of the data obtained through Pilgrim Station's Radiological Environmental Monitoring Program is ensured through a comprehensive Quality Assurance (QA) programs.

PNPS's QA program has been established to ensure confidence in the measurements and results of the radiological monitoring program through:

Regular surveillances of the sampling and monitoring program; An annual audit of the analytical laboratory by the sponsor companies; Participation in the United States Environmental Protection Agency and other cross-check programs; Use of blind duplicates for comparing separate analyses of the same sample; and,

'Spiked sample analyses by the analytical laboratory.

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

Both the Framatome ANP Environmental Laboratory and J.A. Fitzpatrick Environmental Laboratory conduct extensive quality assurance and quality control programs.

The 2002 results of these programs are summarized in Appendices E and F. These results indicate that the analyses and measurements performed during 2002 exhibited acceptable precision and accuracy.

2.3 Interpretation of Radioactivity Analyses Results The following pages summarize the analytical results of the environmental samples collected during 2002. Data for each environmental medium are included in a separate section. A table that summarizes the year's data for each type of medium follows a discussion of the sampling program and results. The unit of measurement for each medium is listed at the top of each table.

The left hand column contains the radionuclides being reported, total number of analyses of that radionuclide, and the number of measurements that exceed ten times the yearly average for the control station(s).

The latter are classified as "non-routine" measurements.

The next column lists the Lower Limit of Detection (LLD) for those radionuclides that have detection capability requirements specified in the PNPS ODCM.

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

Page 24

For each sampling medium, each radionuclide is presented with a set of statistical parameters.

This set of statistical parameters includes separate analyses for (1) the indicator stations, (2) the station having the highest annual mean concentration, and (3) the control stations. For each of these three groups of data, the Duke Engineering and Services ERMAP computer program calculates:

The mean value of all concentrations, including negative values and values below LLD; The standard deviation of the measurements; The lowest and highest concentrations; and, The number of positive measurements (activity which is three times greater than the standard deviation), out of the total number of measurements.

Each single radioactivity measurement datum is based on a single measurement and is reported as a concentration plus or minus one standard deviation. The quoted uncertainty represents only the random uncertainty associated with the measurement of the radioactive decay process (counting statistics), and not the propagation of all possible uncertainties in the sampling and analysis process. A sample or measurement is considered to contain detectable radioactivity if the measured value (e.g., concentration) exceeds three times its associated standard deviation. For example, a milk sample with a strontium-90 concentration of 3.5 +/- 0.8 pCiliter would be considered "positive" (detectable Sr-90), whereas another sample with a concentration of 2.1 +/- 0.9 pCi/liter would be considered "negative", indicating no detectable strontium-90.

The latter sample may actually contain strontium-90, but the levels counted during its analysis were not significantly different than background levels.

The Framatome ANP Environmental Laboratory uses background-subtract corrections when analyzing samples for radioactivity content. This method involves analyzing a representative "clean" sample of the given material under similar conditions as a true sample, and storing the results of this analysis. When a true sample is analyzed, the results of the "clean" background sample are subtracted from the results to correct for any naturally-occurring radioactivity that may be present in the sample. If the true sample undergoing analysis has radioactivity count data which is lower than the "clean' background sample, the method can result in a arithmetically-negative value, yielding a concentration value less than zero.

As an example of how to interpret data presented in the results tables, refer to the first entry on the table for air particulate filters (page 41). Gross beta (GR-B) analyses were performed on 572 routine samples (11 stations/wk

• 52 weeks). None of the samples exceeded ten times the average concentration at the control location. The lower limit of detection (LLD) required by the ODCM is 0.01 pCVm3.

For samples collected from the ten indicator stations, 520 out of 520 samples indicated detectable activity at the three-sigma (standard deviation) level. The mean concentration of gross beta activity in these 518 indicator station samples was 0.017 +/- 0.005 (1.7E-2 +/- 5.4 E-3) pCVm3. Individual values ranged from 0.0036 to 0.034 (3.6E 3.4E-2 E-4) pCim 3.

The monitoring station which yielded the highest mean concentration was station EW (East Weymouth Control), which yielded a mean concentration of 0.018 +/- 0.005 pCi/m3, based on 52 observations. Individual values ranged from 0.0072 to 0.035 pCim/3.

Fifty-two of the fifty-two samples showed detectable activity at the three-sigma level.

At the control location, 52 out of 52 samples yielded detectable gross beta activity, for an average concentration of 0.018 +/- 0.005 pCi/m.

Individual samples at the control location ranged from 0.0072 to 0.035 pCi/m3.

Page 25

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

• 4 quarters, plus one special analysis). No samples exceeded ten times the mean control station concentration. The required LLD value Cs-137 in the PNPS ODCM is 0.01 pCi/m3.

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

2.4 Ambient Radiation Measurements The primary technique for measuring ambient radiation exposure in the vicinity of Pilgrim Station involves posting environmental thermoluminescent dosimeters (TLDs) at given monitoring locations and retrieving the TLDs after a specified time period. The TLDs are then taken to a laboratory and processed to determine the total amount of radiation exposure received over the period. Although TLDs can be used to monitor radiation exposure for short time periods, environmental TLDs are typically posted for periods of one to three months. Such TLD monitoring yields average exposure rate measurements over a relatively long time period.

The PNPS environmental TLD monitoring program is based on a quarterly (three month) posting period, and a total of 110 locations are monitored using this technique. In addition, 27 of the 110 TLDs are located onsite, within the PNPS protected/restricted area.

Out of the 440 TLDs (110 locations

• 4 quarters) posted during 2002, 436 were retrieved and processed. Those TLDs missing from their monitoring locations were lost to storm damage vandalism, and/or replacement of the utility poles to which they were attached, and their absence is discussed in Appendix D. The results for environmental TLDs located offsite, beyond the PNPS protected/restricted area fence, are presented in Table 2.4-1. Results from onsite TLDs posted within the restricted area presented in Table 2.4-2. In addition to TLD results for individual locations, results from offsite TLDs were grouped according to geographic zone to determine average exposure rates as a function of distance.

These results are summarized in Table 2.4-3. All of the listed exposure values represent continuous occupancy (2190 hr/qtr or 8760 hr/yr).

Annual exposure rates measured at offsite locations ranged from 38 to 637 mR/yr.

The average exposure rate at control locations greater than 15 km from Pilgrim Station (i.e., Zone 4) was 56.6 +/- 8.2 mR/yr. When the 3-sigma confidence interval is calculated based on these control measurements, 99% of all measurements of backiround ambient exposure would be expected to be between 32 and 81 mR/yr.

Inspection of onsite TLD results listed in Table 2.4-2 indicates that all of those TLDs located within the PNPS protected/restricted area yield exposure measurements higher than the expected background. These increases are due to the close proximity of these locations to radiation sources onsite.

The radionuclide nitrogen-16 (N-16) contained in steam flowing through the turbine accounts for most of the exposure onsite. Although this radioactivity is contained within the turbine and is not released to the atmosphere, the "sky shine" which occurs from the turbine increases the ambient radiation levels in areas near the turbine building.

Only three TLDs located within the PNPS protected area exhibited a significant (>20%)

increase in exposure since 2000. TLDs near the Executive Building (P17) and at the southwest corner of the O&M Building (P18) showed an increase of about 21 % since 2001. This is largely attributed to the fact that PNPS was shut down for several weeks for refueling during 2001, and the "sky shine" from station operation was diminished when compared to a year at normal power operations, such as 2002. The TLD on the fence near the TCF Boat Ramp (P27) showed a 50% increase, due largely to movement of radioactive wastes near this TLD as the waste is transited to the Trash Compaction Facility from the process buildings.

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A small number of offsite TLD locations in close proximity to the protected/restricted area indicated ambient radiation exposure above expected background levels. All of these locations are on Pilgrim Station controlled property, and experience exposure increases due to turbine sky shine (e.g., locations OA, TC, P01, and WS) and/or transit and storage of radwaste onsite (e.g., location BLW). A hypothetical maximum exposed member of the public accessing these near-site areas on Pilgrim Station controlled property for limited periods of time would receive a maximum dose of about 2.7 mrem/yr above their average ambient background dose of 57 mrem/yr.

One TLD, normally located in the basement of the Plymouth Memorial Hall, indicated an annual exposure of 38 mR in 2002. Construction in this building led PNPS personnel to relocate the TLD outside the building during construction.

It was relocated within the basement of the building during the fourth quarter, which caused the exposure to increase from about 7 mR/quarter during the first 3 quarters of the year, to about 17 mR/quarter during the Oct-Dec period. The exposure within the building at this location is due to the close proximity of stone building material, which contains higher levels of naturally-occurring radioactivity, as well as from 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 in Table 2.4-3 are located on Pilgrim Station property. If the Zone 1 value is corrected for the near-site TLDs (those less than 0.6 km from the Reactor Building), the Zone 1 mean falls from a value of 90.6 +/- 92.1 mR/yr to 57.7 +/- 7.0 mR/yr. Additionally, exposure rates measured at areas beyond Entergy's control did not indicate any increase in ambient exposure from Pilgrim Station operation.

For example, the annual exposure rate near the nearest offsite resident (location HB, 0.6 km SE) was 60.2 +/- 5.4 mR/yr, which compares quite well with the average control location exposure of 56.6 +/- 8.2 mR/yr.

M A second technique for measuring ambient radiation exposure utilizes a sensitive high-pressure ion chamber to make "real time" exposure rate measurements.

This technique allows for instantaneous assessments, with the instrument providing a direct readout of exposure rates.

Such monitoring with a high-pressure ion chamber can be used to perform rapid, short-term measurements at locations where it may be impractical to post long-term TLD monitors.

Annual measurements are taken with a high-pressure ion chamber at five locations on beaches in the Plymouth area, and at the control location in Duxbury. Results of these measurements (Reference 17) are listed in Table 2.4-4. These values, as well as historical measurements, are depicted graphically in Figure 2.4-1. There are no apparent trends in exposure levels at these locations.

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

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

Page 27

Out of 572 filters (11 locations

• 52 weeks), 572 samples were collected and analyzed during 2002. There were a few instances where power was lost or pumps failed during the course of the sampling period at some of the air sampling stations, resulting in lower than normal sample volumes. These discrepancies are noted in Appendix D. These occurrences did not adversely affect the monitoring results.

The results of the analyses performed on these 572 filter samples are summarized in Table 2.5-1. Trend plots for the gross beta radioactivity levels at the near station, property line, and offsite airbome monitoring locations are shown in Figures 2.5-1, 2.5-2 and 2.5-3, respectively.

Gross beta radioactivity was detected in 572 of the filter samples collected, including 52 of the 52 control location samples. This gross beta activity arises from naturally-occurring radionuclides such as radon decay daughter products.

Naturally-occurring beryllium-7 was detected in all 44 of the quarterly composites analyzed with gamma spectroscopy.

Naturally-occurring potassium-40 (K-40) was detected in 10 of 40 indicator samples, and in one of four control samples. No airborne radioactivity attributable to Pilgrim Station was detected in any of the samples collected during 2002.

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

The same eleven locations monitored for airborne particulate radioactivity are also sampled for airborne radioiodine.

Out of 572 cartridges (11 locations

• 52 weeks), 572 samples were collected and analyzed during 2002. There were a few instances where power was lost or pumps failed during the course of the sampling period at some of the air sampling stations, resulting in lower than normal sample volumes. These discrepancies are noted in Appendix D. Despite such events during 2002, required LLDs were met on all 572 filters collected during 2002.

The results of the analyses performed on these 572 charcoal cartridges are summarized in Table 2.6-1.

No airbome radioactive iodine was detected in any of the charcoal cartridges collected.

2.7 Milk Radioactivity Analvses Samples of unprocessed milk are collected from the Plymouth County Farm and from the control location in Whitman. The Annual Land Use Census conducted within five kilometers of Pilgrim Station did not identify any additional milk animals requiring sampling. Results of this census are summarized in Appendix C. Milk samples are collected monthly from November through April, and once every two weeks when animals are assumed to be on pasture during the period May through October. These milk samples are analyzed by gamma spectroscopy, as well as low-level analysis for radioiodine and strontium-89 and -90.

Thirty-seven samples scheduled for collection during the year were obtained and analyzed. In July 2002, the Plymouth County Farm ceased operation of its dairy facility. This was historically the only dairy facility near Pilgrim Station, and had been sampled continuously since Pilgrim Station began operation in 1972. Although attempts were made to obtain samples from an alternate indicator location, a suitable substitute could not be found. Thus, milk collection at an Page 28

indicator location was discontinued in July, but control samples of milk continued to be collected and analyzed in the event an indicator location could be secured.

The results of the analyses performed on the 37 milk samples are summarized in Table 2.7-1.

Naturally-occurring potassium-40 was detected in all 37 samples. No radioactive iodine was detected in any of the samples.

Strontium-90 was detected in 6 of the 9 samples from Plymouth County Farm, and in 4 of the 15 samples collected from the control location in Whitman.

Cesium-137 was not detected in any of the samples collected during the year.

Concentrations of Sr-90 as a function of time are shown in Figure 2.7-1.

The highest concentration of Sr-90, 4.4 pCi/liter, was observed in a sample collected from the indicator location at Plymouth County Farm. The highest concentration of Sr-90 in samples collected from the control location at Whitman Farm was 2.5 pCi/liter. The Sr-90 detected in the samples resulted from radioactivity in the environment that was deposited from nuclear weapons testing conducted in the 1950s, 60s, and 70s. Strontium-90 was routinely detected in the preoperational sampling program conducted prior to Pilgrim Startup in 1972, at concentrations ranging from 5 to 18 pCVliter.

When the average preoperational Sr-90 concentration of 9 pCi/liter is corrected for radioactive decay that occurred between 1972 and 2002, the expected concentration would be about 4-5 pCi/liter. The concentrations of 2 to 3 pCi/liter observed in 2002 samples are well below the expected Sr-90 concentrations resulting from weapons testing. It is clear that the Sr-90 observed did not arise from Pilgrim Station operations.

2.8 Forace Radioactivity Analyses Samples of animal forage (hay) are collected from the Plymouth County Farm and from the control location in Whitman.

Saiples are collected annually and analyzed by gamma spectroscopy.

All samples of forage were collected and analyzed as required during 2002. Results of the gamma analyses of forage samples are summarized in Table 2.8-1.

Naturally-occurring beryllium-7 and potassium-40 were detected in forage samples collected during 2002, and the sample collected at the control location at Whitman Farm indicated detectable cesium-137.

Such Cs-137 concentrations (276 pC/kg) are indicative of fallout from past nuclear weapons testing. No radionuclides attributable to Pilgrim Station operations were detected in any of the samples.

Cesium-137 is a product of nuclear weapons testing, and was routinely detected in the preoperational monitoring program at levels of 150 to 290 pCVkg.

When corrected for radioactive decay, the expected concentration in samples of naturally-growing vegetation collected during 2002 would be between 75 and 146 pCiVkg.

The average Cs-137 concentration of 49 pCi/kg observed in the samples collected is indicative of radioactivity arising from weapons fallout, and not Pilgrim Station operations.

2.9 VeaetableNeaetation Radioactivity Analyses Samples of vegetables had historically been collected from the Plymouth County Farm and from the control location in Bridgewater.

However, some problems were encountered in collection of crop samples during 2002. Crops were not grown at the Plymouth County Farm (CF) during 2002.

Due to a loss of state funding at the Bridgewater Correctional Facility, garden samples were not available from this source. An alternate sampling location (Hanson Farm) was identified in the general vicinity in Bridgewater, and was used as a source of control vegetable samples. In addition, samples of vegetables or leafy vegetation were collected at or near a number of gardens identified during the Annual Land Use Census.

Results of this Page 29

census are discussed in Appendix C.

Samples of vegetables are collected annually and analyzed by gamma spectroscopy.

Twelve samples of vegetables/vegetation were collected and analyzed as required during 2002.

Results of the gamma analyses of these samples are summarized in Table 2.9-1. Naturally-occurring beryllium-7 and potassium-40 were identified in most of the samples collected.

Contrary to past years, and to the results of forage samples collected at Whitman Farm, cesium-1 37 was not detected in any of the samples collected.

2.10 Cranberry Radioactivity Analyses Samples of cranberries are routinely collected from two bogs in the Plymouth area and from the control location in Halifax. Samples of cranberries are collected annually and analyzed by gamma spectroscopy.

During 2002, the bog at Manomet Point was not harvested, so no sample was collected from this location. This discrepancy is noted in Appendix D.

Three samples of cranberries were collected and analyzed during 2002. Results of the gamma analyses of cranberry samples are summarized in Table 2.10-1. No radionuclides attributable to Pilgrim Station operations were detected in any of the samples.

2.11 Soil Radioactivity Analyses A survey of radioactivity in soil is conducted once every three years at the 10 air sampling stations in the Plymouth area and the control location in East Weymouth. These locations serve as fixed survey locations at which repeated measurements can be made to determine any buildup of radioactivity.from deposition of airbome radionuclides.

At each of these locations, in situ (in-field) measurements were made with a portable gamma spectroscopy unit and a high-pressure ion chamber.

The portable gamma spectrometer is used to identify radionuclides present across a large area beneath the detector, whereas the high-pressure ion chamber is used to detect exposure levels arising from naturally-occurring and deposited radionuclides in the soil. Samples of soil are also collected at these 11 locations and taken to the laboratory for more detailed gamma spectroscopy analysis.

The soil survey was last performed as required in 2000. Results of the gamma analyses of these samples are summarized in the annual report for 2000.

2.12 Surface Water Radioactivity Analyses Samples of surface water are routinely collected from the discharge canal, Bartlett Pond in Manomet and from the control location at Powder Point Bridge in Duxbury. The discharge canal is sampled continuously by a composite sampler. Grab samples are collected weekly from the Bartlett Pond and Powder Point Bridge locations.

Samples of surface water are composited every four weeks and analyzed by gamma spectroscopy and low-level iodine analysis. These monthly composites are further composited on a quarterly basis and tritium analysis is performed on this quarterly sample.

A total of 36 samples (3 locations

• 12 sampling periods) of surface water were collected and analyzed as required during 2002. Results of the analyses of water samples are summarized in Table 2.12-1. Naturally-occurring potassium-40 was detected in samples composed primarily of seawater. No radioactivity attributable to Pilgrim Station operations was detected in any of the samples collected during 2002.

Page 30

2.13 Irish Moss Radioactivity Analyses Samples of Irish moss are collected from the discharge canal outfall and two other locations in the Plymouth area (Manomet Point, Ellisville), and from a control location in Marshfield (Green Harbor). All samples are collected on a quarterly basis, and processed in the laboratory for gamma spectroscopy analysis. Due to persistent inclement weather during the first quarter of 2002, the sample could not be collected at Ellisville. This discrepancy in discussed in more detail in Appendix D.

Sixteen samples of Irish moss scheduled for collection during 2002 were obtained and analyzed. Results of the gamma analyses of these samples are summarized in Table 2.13-1.

Naturally-occurring beryllium-7, potassium-40, and actinium/thorium-228 were detected in a number of the samples. No radioactivity attributable to Pilgrim Station operations was detected in any of the samples collected during 2002.

2.14 Shellfish Radioactivity Analyses Samples of blue mussels, soft-shell clams and quahogs are collected from the discharge canal outfall and two other locations in the Plymouth area (Manomet Point, Plymouth Harbor), and from control locations in Duxbury and Marshfield.

All samples are collected on a quarterly basis, and processed in the laboratory for gamma spectroscopy analysis.

In addition to analyzing the edible portion (meat) from each of the samples, the shells from samples collected from the discharge canal outfall and from all control location samples are also analyzed.

There was a delay in shipping and receipt of fourth quarter shellfish samples to the J.A.

Fitzpatrick Environmental Laboratory. Due to this delay, and the loss of some sample mass' when the frozen samples thawed while en route, aggressive detection limits of 5 pCiVkg could:

not be met on some of the samples. Although extended (>60 hours) analyses were performed, the achieved LLDs were in the range of 7 to 10 pCikg. Such low-level screening still provides for adequate assessment of potential impact of PNPS operations. Other details regarding this event can be found in Appendix D.

All 48 samples of shellfish meat and shells scheduled for collection during 2002 were obtained and analyzed. Results of the gamma analyses of these samples are summarized in Table 2.14-1. Naturally-occurring beryllium-7, potassium-40, and actinium/thorium-228 were detected in a number of the samples. Low-levels of cesium-137 were detected during the fourth quarter in samples of mussels collected in the vicinity of the PNPS discharge canal, soft-shelled clams from Plymouth Harbor, and both soft-shelled clams and quahogs collected from the control location in Duxbury. Although the levels observed are most likely due to fallout from weapons testing, an assessment of potential dose impact was performed.

This assessment is documented in Appendix A. Based on this assessment, the maximum total body dose resulting from ingestion of shellfish containing low-levels of Cs-137 was 0.005 mrem.

2.15 Lobster Radioactivity Analyses Samples of lobsters are routinely collected from the outfall area of the discharge canal and from the control location in Duxbury. Samples are collected monthly from the discharge canal outfall from June through September and annually from the control location. All lobster samples are analyzed by gamma spectroscopy.

All five samples of lobsters were collected and analyzed as required during 2002. Results of the gamma analyses of lobster samples are summarized in Table 2.15-1. The only radionuclide detected in any of the samples was naturally-occurring potassium-40.

No radionuclides attributable to Pilgrim Station operations were detected in any of the samples.

Page 31

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

Group I - Bottom Oriented: Winter Flounder, Yellowtail Flounder Group II - Near-Bottom Distribution: Tautog, Cunner, Pollock, Atlantic Cod, Hake Group IlIl - Anadromous: Alewife, Smelt, Striped Bass Group IV - Coastal Migratory: Bluefish, Herring, Menhaden, Mackerel Two subsamples of each category of fish are typically collected during each collection period.

Group I and 11 fishes are sampled on a quarterly basis from the outfall area of the discharge canal, and on an annual basis from a control location. Group IlIl and IV fishes are sampled annually from the discharge canal outfall and control location. All samples of fish are analyzed by gamma spectroscopy.

Due to declining fish stock and the migration of fish to deeper water during colder seasons, samples of Groups I and 11 fishes could not be collected during the first and fourth quarters of the year. Although repeated and concerted efforts were made to collect the fish in the vicinity of the Discharge Canal Outfall, no samples could be obtained.

In addition, only a single subsample of winter flounder (Group I) could be collected during the third quarter, due to the limited number;and size of fish captured. Additional details regarding these discrepancies can be found in Appendix D.

Nineteen samples of fish were collected during 2002. Results of the gamma analyses of fish samples collected are summarized in Table 2.16-1. The only radionuclides detected in any of the samples were naturally-occurring potassium-40 and actiniumlthorium-228.

No radionuclides attributable to Pilgrim Station operations were detected in any of the samples.

2.17 Sediment Radioactivity Analyses Samples of sediment are routinely collected from the outfall area of the discharge canal and from three other locations in the Plymouth area (Manomet Point, Plymouth Harbor and Plymouth Beach), and from control locations in Duxbury and Marshfield. Samples are collected twice per year and are analyzed by gamma spectroscopy. Sediment cores are subdivided into depth increments for analysis of radionuclide distribution by depth. During the first half of the year, samples are divided into 2 cm increments, whereas samples for the second half of the year are divided into 5 cm increments. In addition to the gamma analyses, plutonium analyses are performed on the surface layer samples collected during the first half of the year from the discharge canal outfall, Plymouth Harbor, Manomet Point and Duxbury.

Plutonium analyses are also performed on a mid-depth section from the discharge canal sample and Duxbury sample.

Two sets of samples of sediment collected during the first half of the year were not analyzed as required. Although records indicate that the samples were collected and delivered to the analytical laboratory in June, analyses were not performed and the samples could not be located.

Eight depth-incremental sub-samples from Plymouth Harbor, as well as the eight depth-incremental sub-samples from Duxbury Bay were delivered to the lab on 27-Jun-2002 Page 32

along with 38 samples from the other sampling locations. It is surmised that the samples were assumed to be backup samples from the other locations, not requiring analysis. Two of the samples from the control location in Duxbury were to be analyzed for plutonium, to establish a baseline for comparison to the indicator locations closer to the plant. Plutonium analyses from indicator locations (Discharge Canal Outfall and Manomet Point) indicated no detectable plutonium. Additional discussion regarding this discrepancy can be found in Appendix D.

Forty samples of sediment were collected during 2002. Gamma analyses were performed on these samples. Results of the gamma analyses of sediment samples are summarized in Table 2.17-1. Results of the plutonium analyses are presented in Table 2.17-2. Naturally-occurring potassium-40 and actinium/thorium-228 were detected in a number of the samples. No cobalt-60 was detected in any of the 24 indicator samples.

Cesium-137 was detected in 5 of 31 indicator station samples and in 4 of 9 control station samples. No plutonium was detected in the three indicator station samples analyzed Cesium-137 levels in indicator samples ranged from non-detectable to a maximum concentration of 20 pCikg. Concentrations in samples collected from the control locations beyond the influence of Pilgrim Station ranged from non-detectable to a maximum concentration of 17 pCikg. The comparability of the results from indicator and control stations indicates that the source of this activity is not Pilgrim Station. The levels detected are also comparable to concentrations observed in the past few years and are indicative of Cs-137 resulting from nuclear weapons testing.

Page 33

Table 2.2-1 Routine Radiological Environmental Samplina Locations Pilgrim Nuclear Power Station, Plymouth. MA Description No Code Distance Direction Air Particulate Filters, Charcoal Cartridges, Soil Medical Building 00 WS 0.2 km SSE East Rocky Hill Road 01 ER 0.9 km SE West Rocky Hill Road 03 WR 0.8 km WNW Property Line 06 PL 0.5 km NNW Pedestrian Bridge 07 PB 0.2 km N

Overlook Area 08 OA 0.1 km W

East Breakwater 09 EB 0.5 km ESE Cleft Rock 10 CR 1.3 km SSW Plymouth Center 15 PC 6.7 km W

Manomet Substation 17 MS 3.6 km SSE East Weymouth Control 21 EW 40 km NW Milk Plymouth County Farm 11 CF 5.6 km W

Whitman Farm Control 21 WF 34'km WNW Forage Plymouth County Farm 11 CF 5.6 km W

Whitman Farm Control 12 WF 34 km WNW Whipple Farm 43 WH 2.9 km SW Vegetation Plymouth County Farm 11 CF 5.6 km W

Bridgewater Farm Control 27 BF 31 km W

Cranberries Manomet Point Bog 13 MR 3.9 km SE Bartlett Road Bog 14 BR 4.3 km SSE Pine Street Bog Control 23 PS 26 km WNW Page 34

Table 2.2-1 (continued)

Routine Radiological Environmental Samlinc Locations Pilgrim Nuclear Power Station. Plymouth. MA No Code Distance Direction Surface Water Discharge Canal Bartlett Pond Powder Point Control Irish Moss Discharge Canal Outfall Manomet Point Ellisville Brant Rock Control Shellfish Discharge Canal Ouffall Plymouth Harbor Duxbury Bay Control Manomet Point Green Harbor Control 11 DIS 12 Ply-H 13 Dux-Bay 15 MP 24 GH Lobster Discharge Canal Ouffall Plymouth Harbor Duxbury Bay Control Fishes Discharge Canal Outfall Priest Cove Control Jones River Control Vineyard Sound Control Buzzard's Bay Control Cape Cod Bay Control Sediment Discharge Canal Outfall Plymouth Harbor Duxbury Bay Control Plymouth Beach Manomet Point Green Harbor Control 11 DIS 15 Ply-H.

13 Dux-Bay 11 DIS 29 PC 30 JR 92 MV 90 BB 98 CC-Bay 11 DIS 12 Ply-H 13 Dux-Bay 14 PLB 15 MP 24 GH Page 35 Description 11 DIS 17 BP 23 PP 0.2 km 2.7 km 13 km 0.7 km 4.0 km 12 km 18 km 11 DIS 15 MP 22 EL 34 BR N

SE NNW NNE ESE SSE NNW 0.7 km 4.1 km 13 km 4.0 km 16 km 0.5 km 6.4 km 11 km 0.5 km 48 km 13 km 64 km 40 km 24 km 0.8 km 4.1 km 14 km 4.0 km 3.3 km 16 km NNE W

NNW ESE NNW N

WNW NNW N

SW WNW SSW SSW ESE NE W

NNW WNW ESE NNW

Table 2.4-1 Offsite Environmental TLD Results TLD Station TLD Location*

Exposure Rate - mR/quarter (Value +/- Std.Dev.)

i~2002 Annual-ID Description Distance/Directon Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure I

~~mR/year Zone I TLDs: 0-3 km 0-3 km 23.4 +/- 22.6 21.7 23.2 23.4 +/- 22.8 22.0 24.1 90.6 +/- 92.1 BLW BOAT LAUNCH WEST 0.11 km E 60.3 +/-3.4 55.1 +/- 5.7 60.4 +/-3.9 58.8 5.8 234.6 +/- 13.8 OA OVERLOOK AREA 0.15 km W 155.0 7.4 159.3 +/- 11.1 158.3 8.2 164.2 9.1 636.8 +/-23.7 TC HEALTH CLUB 0.15 km WSW 49.3 +/- 2.3 47.0 +/- 1.7 50.5 +/- 1.4 47.7 +/- 2.2 194.5 +/- 7.3 BLE BOAT LAUNCH EAST 0.16 km ESE 42.0 +/- 2.6 37.4 +/- 2.5 39.6 +/- 2.6 39.7 +/- 2.8 158.6 f 9.2 PB PEDESTRIAN BRIDGE 0.21 km N 36.7 +/- 1.6 32.4 +/- 2.0 33.7 1.8 33.2 +/- 1.7 136.0 8.2 P01 SHOREFRONT SECURITY 0.22 km NNW 34.3+/- 1.9 33.7 +/-2.0 36.3 1.9 34.1 +/- 2.4 138.4 +/- 6.2 WS MEDICAL BUILDING 0.23 km SSE 35.7 +/- 3.0 34.0+/- 1.4 35.7 1.7 33.8 +/- 2.1 139.2 +/- 6.0 CT PARKING LOT 0.31 km SE 20.9 +/- 1.0 19.4 +/- 1.2 21.2 1.0 21.5 +/- 1.3 83.1 +/- 4.4 PA SHOREFRONT PARKING 0.35 km NNW 20.6 +/- 1.7 18.8 0.8 21.4 0.8 19.6+/- 1.0 80.4 +/- 5.2 A STATION A 0.37 km WSW 20.8 +/- 0.9 19.5 +/- 0.9 22.1 1.2 19.6 +/- 1.5 81.9 5.4 F STATION F 0.43 km NW 18.8 +/- 0.8 17.7 +/- 0.9 19.3 f 1.0 16.9 +/- 0.9 72.7 +/- 4.7 EB EAST BREAKWATER 0.44 km ESE 18.9 +/- 1.2 15.3 +/- 0.5 16.3 +/- 0.7 15.2 +/- 0.8 65.8 +/- 7.2 B STATION B 0.44 km S 23.1 +/-2.2 22.0 +/- 1.1 23.4 1.0 21.4 +/- 1.3 89.8 4.7 PMT PNPS MET TOWER 0.44 km WNW 17.9+/- 0.9 16.7 +/- 0.7 18,5 f 0.8 15.8 +/- 0.9 68.9 5.1 H STATION H 0.47 km SW 20.8 +/- 1.0 20.3 +/- 0.9 21.9 +/- 0.9 19.3 +/- 1.2 82.3 +/- 4.8 I STATION I 0.48 km WNW 18.1 +/- 1.0 16.7 +/- 0.9 17.7 +/- 1.0 16.4 +/- 1.1 69.0 +/- 3.7 L STATION L 0.50 km ESE 19.0 +/- 1.2 17.4 +/- 0.9 18.2 +/- 1.0 17.2 +/- 0.9 71.9 +/- 3.9 G STATION G 0.53 km W 16.8 +/- 0.9 14.9 +/- 0.8 16.7+/- 0.8 14.2 +/- 1.0 62.6 5.4 D STATION D 0.54 km NNW 17.9 +/- 1.2 16.5 +/- 0.9 18.6 +/- 0.9 16.1 +/- 1.1 69.1 +/- 5.2 PL PROPERTY LINE 0.54 km NW 17.2 +/- 0.9 15.1 +/- 1.2 17.4 +/- 0.6 14.8 +/- 0.9 64.4 +/- 5.8 C STATION C 0.57 km ESE 16.7 +/- 1.1 14.1 +/- 0.8 21.6 +/- 2.6 13.7 +/- 0.8 66.1 14.9 HB HALL'S BOG 0.63 km SE 16.0 +/- 1.0 14.0 +/- 0.8 16.3 +/- 0.6 13.9 +/- 0.8 60.2 +/- 5.4 GH GREENWOOD HOUSE 0.65 km ESE 17.1 +/- 1.0 15.1 +/- 1.0 17.6 +/- 0.7 15.3 +/- 0.8 65.1 +/- 5.3 WR W ROCKY HILL ROAD 0.83 km WNW 19.3 +/- 1.7 17.2 +/- 1.0 19.3 +/- 0.7 16.4 +/- 0.9 72.2 +/- 6.3 ER E ROCKY HILLROAD 0.89km SE 13.2+/- 1.5 12.1 +/- 0.7 14.0 +/-0.6 11.0+/-0.8 50.4 5.6 MT MICROWAVE TOWER 1.03 km SSW 17.1 +/- 1.1 14.9 +/- 1.0 16.5 +/- 0.8 14.2 +/- 1.0 62.7 +/- 5.9 CR CLEFT ROCK 1.27 km SSW 15.6 +/- 0.9 14.1 +/-0.6 15.1 +/- 0.7 13.6 +/-1.0 58.5 +/-4.0 BD BAYSHOREIGATE RD 1.34 km WNW 16.8 +/- 1.2 15.2 +/- 0.6 16.0 +/- 0.7 15.0 +/- 1.0 63.1 +/- 3.7 MR MANOMET ROAD 1.38 km S 14.4 +/- 1.1 13.0 +/- 0.7 14.5 +/- 0.9 12.4 +/- 0.7 54.2 t 4.4 DR DIRT ROAD 1.48 km SW 13.7 +/-0.9 12.3 +/- 0.6 14.2 +/- 0.7 11.9 +/- 0.9 52.2+/- 4.8 EM EMERSON ROAD 1.53 km SSE 14.8 +/- 0.6 Missing 14.6 +/- 0.7 15.7 +/- 1.1 60.1 +/- 3.0 EP EMERSON/PRISCILLA 1.55 km SE 14.8 +/- 0.8 13.3 +/- 0.9 14.6 +/- 0.6 Missing 56.9 +/- 3.8 AR EDISON ACCESS ROAD 1.59 km SSE 14.8 +/- 0.8 12.3 +/- 0.6 14.3 +/- 0.6 12.2 +/- 0.7 53.7 +/- 5.6 BS BAYSHORE 1.76 km W 17.2 +/- 1.0 16.3 +/- 0.9 15.9 +/- 0.8 15.1 +/- 0.9 64.5 +/- 3.9 E STATION E 1.86 km S 15.9 +/- 1.1 14.4 +/- 0.6 16.1 +/- 0.6 13.7+/- 0.9 60.2+/- 4.9 JG JOHN GAULEY 1.99 km W 16.1 +/- 0.9 14.7 +/- 0.6 16.1 +/- 1.0 14.4 +/- 0.9 61.3 +/-t 4.1 J STATION J 2.04 km SSE 15.1 +/- 1.1 13.0 +/- 1.0 15.6 +/- 0.6 12.9 +/- 0.8 56.6 +/- 5.9 RC PLYMOUTH YMCA 2.09 km SSE 14.7 +/- 0.6 13.2 +/- 0.7 15.1 +/- 0.8 15.0 +/- 1.3 58.0 +/- 3.9 WH WHITEHORSE ROAD 2.09 km WSW 14.8 +/- 1.0 13.8 +/- 1.1 15.3 +/- 0.6 12.8 +/- 0.9 56.8 +/- 4.9 K STATION K 2.17 km S 14.9 +/- 0.8 13.0 +/- 0.6 15.0 +/- 1.0 12.9 +/- 0.7 55.8 +/- 4.9 TT TAYLOR/THOMAS 2.26 km SE Missing 12.5 +/- 0.5 13.5 +/- 0.6 15.4 +/- 0.9 55.1 +/- 6.1 YV YANKEE VILLAGE 2.28 km WSW 15.9 +/- 1.3 13.9 +/- 0.9 15.4 +/- 0.9 13.7 +/- 0.7 59.0 +/- 4.7 GN GOODWIN PROPERTY 2.38 km SW 11.5 +/- 0.9 10.7 +/- 0.6 11.9 +/- 0.5 10.0 +/- 0.6 44.1 +/- 3.6 RW RIGHT OF WAY 2.83 km S 13.3 +/- 0.6 12.0 +/- 0.7 13.5 +/- 0.6 12.3 +/- 1.0 51.2 +/- 3.4 TP TAYLOR/PEARL 2.98 km SE 13.2 +/- 0.5 11.6 +/- 0.5 13.9 +/- 0.9 14.9 +/- 1.1 53.6 +/- 5.7 Page 36

• 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.

Table 2.4-1 (continued)

Offsite Environmental TLD Results TLD Station TLD Location' Exposure Rate - mR/

arter Value +/-

d.Dev.

2002 Annual-ID Description Distance/Direction Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure mR/year Zone2TLDs: 3-8km 3-8km 13.0+/- 1.9 11.7 +/-2.0 13.3 +/-2.0 13.6+/- 1.8 51.6 +/- 8.1 VR VALLEY ROAD 3.26 km SSW 11.9 A 0.6 11.0 +/- 0.7 12.8 +/- 0.8 13.3 +/- 0.8 49.0 +/- 4.3 ME MANOMET ELEM 3.29 km SE 13.8 +/- 0.7 12.4 +/- 0.6 14.6 0.7 14.8 +/- 1.1 55.6 +/- 4.7 WC WARREN/CLIFFORD 3.31 km W 13.9 0.9 12.2 +/- 0.6 13.2 +/- 0.5 12.1 +/- 0.8 51.5 +/- 3.7 BB RT.3A/BARTLETT RD 3.33 km SSE 14.4 +/- 0.8 12.5 +/- 0.8 14.6 +/- 0.7 12.5 +/- 0.8 54.0 +/- 4.8 MP MANOMET POINT 3.57 km SE 14.2 +/- 0.7 12.6 +/- 0.6 13.9 +/- 0.6 15.3 +/- 1.4 56.0 +/- 4.7 MS MANOMET SUBSTATION 3.60 km SSE 16.9 +/- 1.1 15.4 +/- 0.6 17.8 +/- 0.8 14.5 +/- 0.9 64.7 +/- 6.1 BW BEACHWOOD ROAD 3.93 km SE 13.7 +/- 0.5 12.8 +/- 0.5 14.2 +/- 0.6 15.2 +/- 1.0 55.9 +/- 4.3 PT PINES ESTATE 4.44 km SSW 12.2 +/- 0.9 11.1 +/- 0.9 12.8 +/- 0.8 13.7 +/- 0.8 49.7 +/- 4.6 EA EARL ROAD 4.60 km SSE 12.9 +/- 0.5 11.8 +/- 0.7 13.6 +/- 0.8 11.5 +/- 0.7 49.9 +/- 4.2 SP S PLYMOUTH SUBST 4.62 km W 14.2 +/- 1.3 13.4 +/- 0.6 14.3 +/- 0.9 15.4 +/- 1.0 57.4 +/- 3.9 RP ROUTE 3 OVERPASS 4.81 km SW 13.6 +/- 0.8 11.9 +/- 0.9 13.1 +/- 0.9 14.6 +/- 0.9 53.2 +/- 4.9 RM RUSSELL MILLS RD 4.85 km WSW 12.6 +/- 0.9 11.8 +/- 0.7 13.0 +/- 0.5 13.9 +/- 0.8 51.4 +/- 3.8 HD HILLDALE ROAD 5.18 km W 14.8 +/- 1.2 13.4 +/- 0.7 14.4 +/- 0.7 13.2 +/- 0.8 55.9 +/- 3.5 MB MANOMET BEACH 5.43 km SSE 13.4 +/- 0.7 12.1 +/- 0.6 13.6 +/- 0.5 14.5+/- 1.0 53.6 +/- 4.2 BR BEAVERDAM ROAD 5.52 km S 13.1 +/- 0.9 12.2 +/- 0.5 13.6 +/- 0.6 14.5 +/- 0.9 53.4 +/- 4.1 PC PLYMOUTH CENTER 6.69 km W 10.2 +/- 0.8 8.4 +/-0.6 10.2 +/- 0.9 10.6 +/- 0.9 39.4 +/- 4.3 LD LONG POND/DREW RD 6.97 km WSW 13.1 +/- 0.5 11.6 0.7 13.0 +/- 0.5 11.1 +/- 0.7 48.8 +/- 4.2 HR HYANNIS ROAD 7.33 km SSE 13.0 +/- 0.8 11.7 0.6 14.4 +/- 1.0 12.9 +/- 0.8 52.1 +/- 4.6 SN SAOUISH NECK 7.58 km NNW 11.0 0.6 9.3 0.8 10.7 +/-0.7 10.9 +/-0.7 41.9 +/- 3.5 MH MEMORIAL HALL 7.58 km WNW 7.4 +/- 0.6 5.8 +/- 0.5 7.4 +/- 0.4 17.6 +/- 0.9 38.2 +/- 21.8 CP COLLEGE POND 7.59 km SW 13.0 0.7 11.5 0.5 14.3 1.1 12.4 +/- 0.8 51.1 +/- 5.0 Zone 3 TLDs: 8-15 km 8-15 km 13.3 +/- 17 11.9 1.6 14.5 1.4 12.6 +/- 1.2 52.2 +/- 6.8 DW DEEP WATER POND 8.59 km W 15.3 +/- 0.8 14.0 0.7 17.1 +/-0.9 14.8 +/- 0.9 61.1 +/- 5.6 LP LONG POND ROAD 8.88 km SSW 11.3 +/- 0.6 10.1 +/-0.4 13.3 0.8 11.1 +/- 1.0 45.8 +/- 5.5 NP NORTH PLYMOUTH 9.38 km WNW 16.8 +/- 1.3 15.3 +/- 0.5 16.0 +/- 0.9 14.5 +/- 0.9 62.6 +/- 4.3 SS STANDISH SHORES 10.39 km NW 12.7 +/- 0.9 11.3 +/-0.8 12.9 +/- 0.6 12.8 +/- 0.8 49.7 +/- 3.3 EL ELLISVILLE ROAD 11.52 km SSE 13.7 +/- 0.6 12.1 +/-0.6 14.8 +/-0.8 12.4 +/-0.9 53.0 +/- 5.0 UC UP COLLEGE POND RD 11.78 km SW 11.7 +/- 0.7 10.3+/- 0.5 13.4 +/- 1.0 11.5 +/- 0.8 46.9 +/- 5.3 SH SACRED HEART 12.92 km W 12.7 +/- 0.8 11.5 +/- 0.7 14.6 +/- 0.5 12.2 +/- 0.7 50.9 +/- 5.5 KC KING CAESAR ROAD 13.11 km NNW 13.8 0.9 12.3 +/-0.9 Missing 12.7 +/-0.7 51.7 3.5 BE BOURNE ROAD 13.37 km S 12.1 +/- 0.6 11.0+/-f 0.5 13.9 0.8 11.9 0.8 48.9 +/- 5.2 SA SHERMAN AIRPORT 13.43 km WSW 12.8 +/- 0.6 11.5 +/- 0.5 14.3 +/- 0.7 12.3 +/- 0.7 50.9 +/- 4.9 Zone 4 TLDs: >15 km

>15 km 14.3 2.1 13.1 +/-2.0 15.3 2.1 13.8 +/-1.8 56.6 +/- 8.2 CS CEDARVILLE SUBST 15.93 km S 14.7 +/- 0.9 12.7 +/- 0.6 16.2 +/- 1.0 13.5 +/- 1.3 57.0 +/- 6.4 KS KINGSTON SUBST 16.15 km WNW 12.5 +/- 0.7 11.7 +/-0.6 14.3 +/- 1.1 12.4 +/-0.8 50.9 +/- 4.9 LR LANDING ROAD 16.46 km NNW 13.2 +/- 0.6 11.9 +/-0.6 13.7 +/- 0.6 13.2 +/-0.8 52.0 +/-3.4 CW CHURCHIWEST 16.56 km NW 12.1 +/- 0.8 11.5 +/-1.2 12.8 +/- 0.6 12.2 +/-0.7 48.6 +/- 2.8 MM MAIN/MEADOW 17.02 km WSW 13.5 +/- 0.7 12.6 +/- 1.0 15.3 +/- 1.3 12.9 +/- 1.0 54.3 +/- 5.2 DMF DIV MARINE FISH 20.97 km SSE 17.9 +/- 0.8 16.8 +/- 0.9 19.0 +/- 1.0 16.8 +/- 1.1 70.5 +/- 4.6 EW EWEYMOUTH SUBST 39.69 km NW 16.1 +/-0.7 14.9 +/-0.7 16.1 +/- 0.7 15.8 +/-0.9 62.9 2.8 Page 37

• 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.

Table 2.4-2 Onsite Environmental TLD Results TLD Station TLD Location*

Exposure Rate - mR/quarter (Value +/- Std.Dev.)

2002 Annuar ID Description Distance/Direction Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure

_mR/vear Onsite TLDs P21 O&M/RXB. BREEZEWAY 50 m SE 25.1 1.2 23.6 +/- 1.1 26.3 +/- 1.1 23.2 +/- 1.5 98.2 +/- 6.3 P24 EXEC.BUILDING 57mW 73.8 +/-3.2 73.2 +/- 3.4 75.4 +/-2.2 79.2 +/- 4.7 301.5 +/- 12.8 P04 FENCE-R SCREENHOUSE 66 m N 110.2 +/- 4.5 103.6 f 3.8 105.2 +/- 8.0 104.9 +/- 10.7 423.9 +/- 18.7 P20 O&M - 2ND W WALL 67 m SE 73.5 +/-4.6 73.3 +/-8.2 75.6 +/-7.4 71.1 +/- 6.1 293.5 +/- 15.3 P25 EXEC.BUILDING LAWN 76 m WNW 119.8 +/- 12.0 111.7 +/- 7.2 113.3 +/- 6.3 126.0 +/- 8.2 470.7 +/- 31.4 P05 FENCE-WATER TANK 81 m NNE 37.9 +/- 3.0 35.4 +/-3.0 36.7 +/- 2.1 34.0 +/-2.9 144.0 +/-8.6 P06 FENCE-OIL STORAGE 85 m NE 62.8 +/- 3.2 58.5 +/- 2.7 62.4 +/- 5.5 57.6 +/- 3.5 241.2 +/- 13.1 P19 O&M -2ND SW CORNER 86 m S 87.7 +/- 5.9 62.9 +/- 3.3 109.2 +/- 5.9 103.5 +/- 6.1 363.3 +/- 83.7 P18 O&M - 1ST SW CORNER 90 m S 70.2 +/- 2.4 75.8 +/- 8.2 70.4 +/- 6.6 70.0 +/- 5.3 286.4 +/- 16.5 P08 COMPRESSED GAS STOR 92 m E 62.7 +/- 4.0 60.7 +/- 3.0 64.2 +/- 6.3 61.5 +/- 3.9 249.0 +/- 10.8 P03 FENCE-L SCREENHOUSE 100 m NW 94.9 +/- 3.2 94.6 +/- 3.4 90.8 +/-3.7 98.6 +/- 8.5 378.9 +/- 16.4 P17 FENCE-EXEC.BUILDING 107 m W 184.8 +/-6.0 184.4 +/- 10.1 183.7 +/-20.4 194.9 +/- 12.8 747.8 +/-34.2 P07 FENCE-INTAKE BAY 121 m ENE 49.4 +/- 4.3 44.5 +/- 4.8 43.2 +/- 2.5 45.2 +/- 5.6 182.3 +/- 13.9 P23 O&M - 2ND S WALL 121 m SSE 48.3 1.7 50.5 +/- 2.9 50.5 +/- 1.6 48.6 +/- 2.4 198.0 +/-6.5 P26 FENCE-WAREHOUSE 134 m ESE 54.9 +/-2.9 54.1 +/-4.6 55.8 +/- 5.3 56.9 +/-5.1 221.7 10.3 P02 FENCE-SHOREFRONT 135 m NW 64.2 +/- 2.5 66.1 +/- 5.1 65.6 +/- 5.1 62.5 +/- 3.0 258.4 +/- 10.5 P09 FENCE-W BOAT RAMP 136 m E 49.5 +/- 3.5 47.0 +/- 5.0 49.3 +/- 2.9 49.2 +/- 3.4 195.1 +/- 8.9 P22 O&M -2ND N WALL 137 m SE 40.2 +/- 1.3 42.9 +/- 3.5 41.9 +/- 2.2 39.6 +/- 2.9 164.7 +/- 8.1 P16 FENCE-W SWITCHYARD 172 m SW 145.7 +/- 6.0 161.9 +/- 10.1 149.6 +/- 12.5 161.2 +/-9.6 618.3 +/- 38.2 P 11 FENCE-TCF GATE 183 m ESE 75.9 +/-4.5 61.5 +/- 3.7 69.0 +/- 3.2 67.6 +/-3.2 274.0 +/-24.8 P27 FENCE-TCF/BOAT RAMP 185 m ESE 59.2 +/- 2.8 46.9 +/- 2.5 71.8 +/- 5.2 119.1 +/- 4.9 296.9 +/- 126.6 P12 FENCE-ACCESS GATE 202 m SE 38.2 +/- 1.9 35.1 +/- 1.5 37.8 +/- 1.3 38.1 +/- 2.7 149.3 +/- 7.1 P15 FENCE-E SWITCHYARD 220 m S 50.7 +/- 4.6 50.4 +/- 3.7 49.8 +/- 2.7 50.8 +/- 2.8 201.7 +/- 7.4 PIO FENCE-TCF/INTAKE BAY 223 m E 52.4 +/- 3.3 47.3 +/- 3.3 39.9 +/- 2.7 40.4 +/- 2.7 180.0 +/- 24.5 P13 FENCE-MEDICAL BLDG.

224 m SSE 35.3 +/-2.1 34.3 +/- 2.1 35.9 +/- 2.3 34.3 +/- 1.6 139.9 +/- 5.2 P14 FENCE-BUTLER BLDG 228 m S 41.4 +/-2.5 37.8 +/- 2.0 37.9 +/- 2.5 32.6 +/- 1.4 149.7 +/- 15.2 P28 FENCE-TCF/PRKNG LOT 259 m ESE 52.1 +/- 2.3 65.2 +/- 2.0 52.2 +/-2.6 47.4 +/- 2.6 216.9 +/- 31.0

• 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 38

Table 2.4-3 Average TLD Exposures By Distance Zone During 2002 Average Exposure +/- Standard Deviation: mR/ eriod Exposure Zone 1*

Zone 2 Zone 3 Zone 4 Period 0-3 km 3-8 km 8-15 km

>15 km Jan-Mar 23.4 22.6 13.0+/- 1.9 13.3 1.7 14.3 + 2.1 Apr-Jun 21.7 +/- 23.2 11.i + 2.0 11.9 1.6 13.1 +/- 2.0 Jul-Sep 23.4 +/- 22.8 13.3 +/- 2.0 14.5 +/- 1.4 15.3 +/- 2.1 Oct-Dec 22.0 +/- 24.1 13.6 + 1.8 12.6 +/- 1.2 13.8 + 1.8 Jan-Dec 90.6 + 92.1**

51.6 + 8.1 52.2 + 6.8 56.6 + 8.2

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

• • When corrected for TLDs located within the site boundary, the Zone 1 annual average is calculated to be 57.7 + 7.0 mR/yr.

Page 39

Table 2.4-4 Beach Survey Exposure Rate Measurements Ambient Radiation Survey Results Page 40 Exposure Rate +/- 1 std. dev.

Location pR/hr mR/yr Beach Terrain White Horse Beach (Near Hilltop Ave) 8.3 +/- 0.4 73 3.5 Sandy. Few granite boulders 2.62 km SE within thirty feet.

Priscilla Beach (In Back of Full Sail Bar) 10.2 +/- 0.5 89 + 4.4 Sandy with small amounts of 1.89 km SE gravel.

Plymouth Beach (Outer Beach) 6.8 +/- 0.3 60 +/- 2.6 Sandy.

7.21 km WNW Plymouth Beach (Inner Beach) 6.3 +/- 0.3 55 +/- 2.6 Sandy.

6.07 km WNW Plymouth Beach (Behind Bert's Restaurant) 12.8 +/- 0.6 112 +/- 5.3 Sandy with gravel. Breakwater 3.66 km W and seawall nearby.

Duxbury Beach (Control) 7.4 +/- 0.4 65 +/- 3.5 Sandy with coarse gravel and 10.94 km NNW exposed cobble.

Table 2.5-1 Air Particulate Filter Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Staton, Plymouth, MA (January - December2002)

No. Analyses Required Radionuclide Non-routine*

LLD GR-B 572 0

Be-7 0.01 44 0

44 0

K-40 Cs-1 34 44 0

Cs-I 37 44 0

.01

.01 Indicator Stations Mean +/- Std.Dev.

Range Fracton>LLD 1.7E-2 t 5.4E-3 3.6E 3.4E-2 520 /520 7.8E-2 : 2.1 E-2 3.7E 1.1E-1 40 /40 3.2E-2 +/- 1.3E-2 1.6E 5.8E-2 10 /40

<LLD

<LLD 0/40

<LLD

<LLD 0 I 40 Staton with Highest Mean Staton: Mean +/- Std.Dev.

Range Fraction>LLD EW: 1.8E-2+/- 4.9E-3 7.2E 3.5E-2 52/52 EW: 9.3E-2 +/- 3.1 E-2 6.6E 1.2E-1 4/4 PB: 5.8E-2 +/- 9.OE-3 5.8E 5.8E-2 1/4

<LLD

<LLD 0/4 Control Stations Mean +/- Std.Dev.

Range Fracton>LLD 1.8E-2 +/- 4.9E-3 72E 3.5E-2 52/52 9.3E-2 f3.1E-2 6.6E 1.2E-1 4/4 4.3E-2 +/- 8.0E-3 4.3E-2 -4.3E-2 1 /4

<LLD

<LLD 0/4

<LLD

<LLD 0/4

<LLD

<LLD 0/4

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

Page 41 U-P.M.;

IMaslaetrl urUWIo Pu/u ImeLe IMAcnil ms r_a<<teI I ItIITC.

rr/.o_rAr

Table 2.6-1 Charcoal Cartridge Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Staton, Plymouth, MA (January - December2002)

MEDIUM: Charcoal Cartridae (CF)

UNITS:

Ci/cubic meter No. Analyses Required Radionuclide Non-routine*

LLD Indicator Stations Mean +/- Std.Dev.

Range Fraction>LLD Stabon with Highest Mean Staton: Mean +/- Std.Dev.

Range Fracfion>LLD Control Stations Mean +/- Std.Dev.

Range Fraction>LLD 1-131 572 0.07

<LLD

<LLD

<LLD 0

<LLD

<LLD

<LLD 0/520 0/52 0/52

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

Page 42

Table 2.7-1 Milk Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December2002)

MEUPnlM:

Milk TM)

UINITS:

nCi/kri No. Analyses Required Radionuclide Non-routinea LLD Indicator Stations Mean t Std.Dev.

Range Fmction>LLD Station with Highest Mean Station: Mean f Std.Dev.

Range Fracbon>LLD Control Stations Mean t Std.Dev.

Range Fraction>LLD 1.4E3 +/- 5.7E1 1.3E3-1.5E3 13 /13

<LLD

<LLD 0/9 1

15 15 15 2.6E0 +/- 1.OEO 1.6E0 - 4.4E0 6/9

<LLD

<LLD 0/13

<LLD

<LLD 0/13

<LLD

<LLD 0/13

<LLD

<LLD 0 /13 CF. 1.4E3 +/- 5.7E1 1.3E3 - 1.5E3 13 13

<LLD

<LLD 0/9 CF: 2.6E0 +/- 1.OEO 1.6E0 - 4.4E0 6/9

<LLD

<LLD 0 13 1.4E3 +/- 9.5E1 1.0E3 - 1.6E3 24 /24

<LLD

<LLD 0/15 2.OEO 4.6E-1 1.7E0 - 2.5EO 4/15

<LLD

<LLD 0 /24

<LLD

<LLD 0 /13

<LLD

<LLD 0 /13

<LLD

<LLD 0/13

<LLD

<LLD 0/24

<LLD

<LLD 0/24

<LLD

<LLD 0/24

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

Page 43 K-40 37 0

Sr-89 24 0

Sr-90 24 0

1-131 37 0

Cs-1 34 Cs-i 37 Ba-1 40 37 0

37 0

37 0

Table 2.8-1 Forage Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Staton, Plymouth, MA (January - December2002)

MEDIUM: Foracie (TC)

UNITS:

nCi/k wet No. Analyses Required Radionuclide Non-routine LLD Be-7 2

0 K-40 2

0 1-131 2

0 Cs-134 Cs-1 37 2

0 2

0 AcTh-228 130 130 2

0 Indicator Stations Mean +/- Std.Dev.

Range Fraction>LLD

<LLD

<LLD 011 8.0E+3 +/- 2.9E+2 8.0E+3 - 8.OE+3 1/i

<LLD

<LLD 01

<LLD

<LLD 01

<LLD

<LLD 0/I

<LLD

<LLD 01 Station with Highest Mean Station: Mean +/- Std.Dev.

Range Fraction>LLD WF: 1.6E+3 +/- 2.OE+2 1.6E+3 -1.6E+3 11 CF: 8.OE+3 +/- 2.9E+2 8.0E+3-8.0E+3 1/1

<LLD

<LLD 0/1

<LLD

<LLD 0/I WF: 2.8E+2 +/-2.3E+1 2.8E+2-2.8E+2 I/I Control Stations Mean +/- Std.Dev.

Range Fraction>LLD 1.6E+3+/-t 2.OE+2 1.6E+3-1.6E+3 i11 4.3E+3 t 2.5E+2 4.3E+3 - 4.3E+3 i/l

<LLD

<LLD 0/I

<LLD

<LLD 0/I 2.8E+2 +/- 2.3E+1 2.8E+2 - 2.8E+2 I/1

<LLD

<LLD 0/I

<LLD

<LLD 0/1

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

Page 44

Table 2.9-1 VegetableNegetation Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December2002)

MEDIUM: Veaetation (TF_

UNITS:

Ci/kq wet No. Analyses Required Radionuclide Non-routine*

LLD Indicator Stations Mean +/- Std.Dev.

Range Fraction>LLD Station with Highest Mean Station: Mean +/- Std.Dev.

Range Fraction>LLD Control Stations Mean f Std.Dev.

Range Fraction>LLD 60 60 60 1.1E3 +/-2.7E2 5.9E2-1.4E3 6/10 3.6E3 t 1.4E3 1.3E3 - 6.1E3 10/10

<LLD

<LLD 0/ 17

<LLD

<LLD 0/10

<LLD

<LLD 0 /10

<LLD

<LLD 0/10 WH: 1.4E3 +/-1.8E2 1.4E3 - 1.4E3 1/2 GWD: 5.1E3+/-3.0E2 5.1E3 - 5.1E3 1 /1

<LLD

<LLD 0/2

<LLD

<LLD 0/2

<LLD

<LLD 0/2

<LLD

<LLD 0/2 0.OEO +/- 0.OEO 0.OEO - 0.OEO 0/2 2.4E3 +/- 7.8E2 1.9E3 - 2.9E3 2/2

<LLD

<LLD 0/2

<LLD

<LLD 0/2

<LLD

<LLD 0/2

<LLD

<LLD 0/2

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

Page 45 Be-7 12 0

K-40 12 0

1-131 19 0

Cs-1 34 Cs-137 AcTh-228 12 0

12 0

12 0

Table 2.10-1 Cranberry Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January -December2002)

No. Analyses Required Radionuclide Non-routine LLD Be-7 3

0 K-40 3

0 1-131 Indicator Stations Mean : Std.Dev.

Range Fraction>LLD

<LLD

<LLD 012

<LLD

<LLD 0/2 3

0 Cs-1 34 3

0 Cs-1 37 AcTh-228 3

0

<LLD

<LLD 0/2 60

<LLD

<LLD 0/2 60 3

0

<LLD

<LLD 0/2

<LLD

<LLD 0/2 Stabon with Highest Mean Staton: Mean +/- Std.Dev.

Range Fraction>LLD

<LLD

<LLD 01

<LLD

<LLD 01I

<LLD

<LLD 01 Control Stations Mean t Std.Dev.

Range Fraction>LLD

<LLD

<LLD 011

<LLD

<LLD 01I

<LLD

<LLD O I

<LLD

<LLD 011

<LLD

<LLD 011

<LLD

<LLD Oil

<LLD

<LLD 011

<LLD

<LLD 011

<LLD

<LLD 1

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

Page 46 RACMilIR11-Irnnrn PO I INI1TO-nile n

Table 2.11 -1 Soil Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December2002)

MEDIUM: Soil (TS)

UNITS:

Ci/kp wet Routine soil surveys and analyses are required only once every three years. This survey was last performed as scheduled in 2000, and is not due to be performed until the year 2003.

Page 47

Table 2.12-1 Surface Water Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December2002)

MEDIUM: Surface Water (WS)

UNITS:

Ci/<

No. Analyses Required Radionuclide Non-routine' LLD H-3 12 0

3000 Indicator Stations Mean +/- Std.Dev.

Range Fraction>LLD

<LLD

<LLD 0/8 Stabon with Highest Mean Stabon: Mean f Std.Dev.

Range Fraction>LLD Control Stations Mean +/- Std.Dev.

Range Fraction>LLD

<LLD

<LLD 0/4

<LLD

<LLD 0/4 DIS: 3.5E2 +/- 1.1E2 2.2E2 -5.8E2 12/12

<LLD

<LLD 0/12

<LLD

<LLD 0/12

<LLD

<LLD 0/12

<LLD

<LLD 0 / 12

<LLD

<LLD 0 /12

<LLD

<LLD 0/12

<LLD

<LLD 0/12

<LLD

<LLD 0/12

<LLD

<LLD 0/12

<LLD

<LLD 0/12 K-40 36 0

3.4E2 +/- 9.8E1 2.3E2 - 5.1E2 12/12

<LLD

<LLD 0/12 Mn-54 Fe-59 Co-58 Co-60 Zn-65 Zr-95 1-131 36 0

36 0

36 0

36 0

36 0

36 0

36 0

<LLD

<LLD 0/12

<LLD

<LLD 0/12 15 30 15 15 30 15 15 18 15 3.3E2+/- 1.AE2 2.0E2 - 5.8E2 15/24

<LLD

<LLD 0/24

<LLD

<LLD 0/24

<LLD

<LLD 0/24

<LLD

<LLD 0/24

<LLD

<LLD 0124

<LLD

<LLD 0/24

<LLD

<LLD 0/24

<LLD

<LLD 0/24

<LLD

<LLD 0 /24

<LLD

<LLD 0 /24

<LLD

<LLD 0112

<LLD

<LLD 0/12

<LLD

<LLD 0 12 Cs-1 34 Cs-137 Ba-1 40 36 0

36 0

36 0

<LLD

<LLD 0/12

<LLD

<LLD 0/12

<LLD

<LLD 0/12

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

<LLD

<LLD 0/12 Page 48 I

Table 2.13-1 Irish Moss Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Staton, Plymouth, MA (January - December2002)

MElIM: lrish Moss (Al)

UNITS: nrilk wet No. Analyses Required Radionuclide Non-routinea LLD Indicator Stations Mean +/- Std.Dev.

Range Fraction>LLD Staion with Highest Mean Staton: Mean +/- Std.Dev.

Range Fraction>LLD Control Stations Mean +/- Std.Dev.

Range Fraction>LLD 2.8E2 +/- 6.5E1 1.8E2 - 3.5E2 5/12 130 260 130 6.9E3 +/- 1.7E3 4.4E3 - 9.6E3 12 /12

<LLD

<LLD 0/12

<LLD

<LLD 0/12

<LLD

<LLD 0/12 130

<LLD

<LLD 0/12 260 130 130

<LLD

<LLD 0/12

<LLD

<LLD 0 /12

<LLD

<LLD 0/12 1.0E2 f 3.3E1 7.1E1 - 1.4E2 3/12 EL: 3.3E2 +/- 5.2EI 3.1 E2 - 3.5E2 2/4 DIS: 8.5E3 +/- 1.2E3 6.8E3 - 9.6E3 4/4

<LLD

<LLD 014

<LLD

<LLD 0/4

<LLD

<LLD 0/4

<LLD

<LLD 0/4

<LLD

<LLD 0/4

<LLD

<LLD 0/4

<LLD

<LLD 0/4 EL: 1.4E2 +/- 1.7E1 1.4E2 - 1.4E2 1/4 Page 49 Be-7 16 0

K-40 16 0

Mn-54 16 0

<LLD

<LLD 0/12 Fe-69 16 0

6.0E3 3.3E3 1.2E3 - 8.7E3 4/4 Co-58 16 0

<LLD

<LLD 0/4 Co-60 16 0

<LLD

<LLD 0/4 Zn-65 16 0

<LLD

<LLD 0/4 Cs-1 34 Cs-1 37

<LLD

<LLD 0/4 16 0

16 0

<LLD

<LLD 0/4 AcTh-228 16 0

<LLD

<LLD 0/4

<LLD

<LLD 0/4 A Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.

9.5E1 +/- 1.8E1 9.5E1 - 9.5E1 1/4

Table 2.14-1 Shellfish Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Stabon, Plymouth, MA (January - December2002)

MEDIUM: Shellfish (SF)

UNITS: DCi/ka wet No. Analyses Required Radionuclide Non-routine LLD Indicator Stations Mean t Std.Dev.

Range Fraction>LLD Stab'on with Highest Mean Stabon: Mean +/- Std.Dev.

Range Fraction>LLD Control Stations Mean t Std.Dev.

Range Fraction>LLD PLYH: 8.0E1 +/-t5.2E1 5.1E1 -1.4E2 3/12 MP: 2.2E3 +/- 1.8E3 9.8E2 - 4.8E3 4/4

<LLD

<LLD 0/12

<LLD

<LLD 0/12

<LLD

<LLD 0/12

<LLD

<LLD 0/12

<LLD

<LLD 0 /12

<LLD

<LLD 0/12

<LLD

<LLD 0 /12 PLYH: 7.3E0+/-:2.1E0 7.3E0 - 7.3E0 1 /12

<LLD

<LLD 0112 PLYH: 1.3E2+/- 1.7E1 1.3E2-1.3E2 1 12 Be-7 48 0

K.40 48 0

Mn-54 Fe-59 Co-58 Co-60 48 0

48 0

48 0

130 260 130 48 0

Zn-65 48 0

6.2E1 3.021 4.121 - 1.4E2 9124 1.7E3 +/- 1.2E3 1.8E2 - 4.8E3 22/24

<LLD

<LLD 0/24

<LLD

<LLD 0 /24

<LLD

<LLD 0/24

<LLD

<LLD 0 /24

<LLD

<LLD 0/24

<LLD

<LLD 0/24

<LLD

<LLD 0/24 4.8E0 +/- 2.3E0 3.4E0 - 7.3E0 3/24

<LLD

<LLD 0/24 4.6E1 +/- 4.7E1 1.1 E1 - 1.3E2 5 /24 Zr-95 48 0

7.1E1 +/- 3.3E1 4.7E1 - 1.3E2 5/24 1.2E3 +/- 9.5E2 7.8E1 - 4.1 E3 21/24

<LLD

<LLD 0/24

<LLD

<LLD 0 /24

<LLD

<LLD 0/24

<LLD

<LLD 0/24

<LLD

<LLD 0/24

<LLD

<LLD 0/24

<LLD

<LLD 0 /24 1.6E0 +/- 1.2E0 8.7E-1 -2.3E0 2/24

<LLD

<LLD 0 /24 5.2E1 2.5E1 1.8E1 - 9.021 7 /24 5

5 5

5 Is 48 0

48 0

48 0

Cs-134 Cs-1 37 Ce-144 AcTh-228 48 0

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

Page 50

Table 2.15-1 Lobster Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Staton, Plymouth, MA (January - December2002)

MEDIUM: American Lobster (HA)

UNITS: DCi/kp wet No. Analyses Required Radionuclide Non-routine*

LLD Be-7 5

0 Indicator Stations Mean +/- Std.Dev.

Range Fraction>LLD

<LLD

<LLD 0/5 Station with Highest Mean Staton: Mean t Std.Dev.

Range Fraction>LLD Control Stations Mean t Std.Dev.

Range Fraction>LLD

<LLD

<LLD 0/5

<LLD

<LLD 0/5 CC-Canal: 2.2E3 +/- 3.0E2 2.2E3 - 2.2E3 1/I

<LLD

<LLD 0/5

<LLD

<LLD 0 /5

<LLD

<LLD 0/5

<LLD

<LLD o05

<LLD

<LLD 0/5

<LLD

<LLD 0/5

<LLD

<LLD 0/5

<LLD

<LLD 0/5 K-40 5

0 Mn-54 5

0 Fe-59 130 260 5

0 Co-58 5

130 0

2.2E3 +/- 3.0E2 2.2E3 - 2.2E3 1 /1

<LLD

<LLD 0/5

<LLD

<LLD 0/5 2.2E3 3.2E2 2.0E3 -2.6E3 4/4

<LLD

<LLD 0/5

<LLD

<LLD 0/5

<LLD

<LLD 0/5

<LLD

<LLD 0/5

<LLD

<LLD 0/5

<LLD

<LLD 0/5

<LLD

<LLD 0/5

<LLD

<LLD 0/5

<LLD

<LLD ol5 5

0 5

0 5

0 0

Co-60 Zn-65 Cs-134 Cs-1 37 AcTh-228 130 260 130 130

<LLD

<LLD 0/5

<LLD

<LLD 0/5 5

0

<LLD

<LLD 0/5

<LLD

<LLD 0/5

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

<LLD

<LLD 0/5 Page 51

Table 2.16-1 Fish Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Stabon, Plymouth, MA (January - December2002)

MEDIUM: Fish (FH)

UNITS: voCi/ka wet No. Analyses Required Radionuclide Non-routine*

LLD Be-7 19 0

Indicator Stations Mean +/- Std.Dev.

Range Fraction>LLD

<LLD

<LLD 0 /11 Station with Highest Mean Station: Mean f Std.Dev.

Range Fraction>LLD Control Stations Mean +/- Std.Dev.

Range Fraction>LLD

<LLD

<LLD 0 /11

<LLD

<LLD 018 DIS: 3.4E3 f 5.0E2 2.4E3 - 4.2E3 11(11

<LLD

<LLD 0/11

<LLD

<LLD 0/11

<LLD

<LLD 0/11

<LLD

<LLD 0/11

<LLD

<LLD 0 /11

<LLD

<LLD 0/11

<LLD

<LLD 0I11

<LLD

<LLD 0 /11 K-40 19 0

Mn-54 19 0

Fe-59 19 0

2.9E3 t 1.4E3 1.1 E3 - 4.8E3 8/8 Co-58 19 0

<LLD

<LLD 0/8 Co-60 19 0

130 260 130 130 260 130 130

<LLD

<LLD 0/8 3.4E3 +/- 5.0E2 2.4E3 - 4.2E3 11/11

<LLD

<LLD 0/11

<LLD

<LLD 0 /11

<LLD

<LLD 0/11

<LLD

<LLD 0/11

<LLD

<LLD 0/11

<LLD

<LLD 0 /11

<LLD

<LLD 0/11 Zn-65 19 0

<LLD

<LLD 0/8 Cs-134 Cs-137

<LLD

<LLD 0/8 19 0

19 0

<LLD

<LLD 0/8 AcTh-228 19 0

<LLD

<LLD 018

<LLD

<LLD 0/11

<LLD

<LLD 0/8

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

3.9E1 +/- 1.8E1 3.9E1 -3.9E1 1 8 Page 52

Table 2.17-1 Sediment Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December2002)

MEDIUM: Sediment (SE)

UNITS: DCi/ka drv No. Analyses Required Radionuclide Non-routine^

LLD Be-7 40 40 0

Indicator Stations Mean f Std.Dev.

Range Fraction>LLD

<LLD

<LLD 0/24 Station with Highest Mean Station: Mean +/-t Std.Dev.

Range Fraction>LLD Control Stations Mean +/- Std.Dev.

Range Fraction>LLD

<LLD

<LLD 0/12

<LLD

<LLD 0/24 DIS: 1.2E4 +/-8.4E2 9.9E3 - 1.3E4 4/4

<LLD

<LLD 0/12

<LLD

<LLD 0/12

<LLD

<LLD 0/12

<LLD

<LLD 0/12

<LLD

<LLD 0/12 PLH: 1.9E1 +/-t2.6E0 1.9E1 - 2.OE1 3/3

<LLD

<LLD 0/12 PLB: 3.3E2+/-t5.lE1 2.7E2 - 3.6E2 3/3

<LLD

<LLD 0/3

<LLD

<LLD 0/3 K-40 40 0

Co-58 40 0

Co-6O 40 0

Zn-65 40 0

Zr-95 40 0

Cs-1 34 Cs-1 37 Ce-144 50 50 50 50 50 50 150 25 25 1.1E4 1.3E3 8.8E3 - 1.3E4 31/31

<LLD

<LLD 0/24

<LLD

<LLD 0/24

<LLD

<LLD 0/24

<LLD

<LLD 0/24

<LLD

<LLD 0/24 1.7E1 3.4E0 1.3E1 -2.OE1 5/31

<LLD

<LLD 0 /24 2.6E2 +/- 6.5El 1.6E2 -3.6E2 19/19

<LLD

<LLD 0/3

<LLD

<LLD 0/3 40 0

40 0

40 0

1.1E4 +/- 1.4E3 9.6E3 - 1.4E4 9/9

<LLD

<LLD 0/24

<LLD

<LLD 0 /24

<LLD

<LLD 0/24

<LLD

<LLD 0/24

<LLD

<LLD 0/24 1.OE1 5.8E0 5.4E0 - 1.7E1 4/9

<LLD

<LLD 0 /24 3.2E2 t 1.6E1 3.1 E2 - 3.4E2 3/3 Missing Missing Missing Missing Missing Missing AcTh-228 Pu-238 Pu-239 22 0

3 0

3 0

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

Page 53 Be-7

Table 2.17-2 Sediment Plutonium Analyses Environmental Radiological Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2002)

• NDA indicates no detectable activity.

Page 54 pCVkg (dry) +/- 1 S.D.

Location Core Depth (cm)

Plutonium-238 Plutonium-2391240 Discharge Canal Outfall 0 - 5 NDA NDA Discharge Canal Outfall 5 - 10 NDA NDA Plymouth Harbor 14-16 Missing Missing Manomet Point 0 - 2 NDA NDA Duxbury Bay - Control 0 - 2 Missing Missing Duxbury Bay - Control 12 - 14 Missing Missing

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

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

Page 55 TLD Station Location*

Description

[Code Distance/Direction TLDs Within Protected Area O&M/RXB. BREEZEWAY P21 50 m SE EXEC.BUILDING P24 57 m W FENCE-R SCREENHOUSE P04 66 m N O&M-2NDW WALL P20 67 m SE EXEC.BUILDING LAWN P25 76 m WNW FENCE-WATER TANK P05 81 m NNE FENCE-OIL STORAGE P06 85 m NE O&M -2ND SW CORNER P19 86 m S O&M - 1ST SW CORNER P18 90 m S COMPRESSED GAS STOR P08 92 m E FENCE-L SCREENHOUSE P03 100 m NW FENCE-EXEC.BUILDING P17 107 m W O&M - 2ND S WALL P23 121 m ENE FENCE-INTAKE BAY P07 121 m SSE FENCE-WAREHOUSE P26 134 m ESE FENCE-SHOREFRONT P02 135 m NW FENCE-W BOAT RAMP P09 136 m E O&M - 2ND N WALL P22 137 m SE FENCE-WSWITCHYARD P16 172 m SW FENCE-TCF GATE P11 183 m ESE FENCE-TCF/BOAT RAMP P27 185 m ESE FENCE-ACCESS GATE P12 202 m SE FENCE-E SWITCHYARD P15 220 m S FENCE-TCF/INTAKE BAY P10 223 m E FENCE-MEDICAL BLDG.

P13 224 m SSE FENCE-BUTLER BLDG P14 228 m S FENCE-TCF/PRKNG LOT P28 259 m ESE

Figure 2.2-1 (continued)

Environmental TLD Locations Within the PNPS Protected Area

-l Intake Channel Page 56 I

1*B M

1)-ft Met Tower

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

Air/Soil Sampling Station l

Location*

Description Code Distance/Direction Description Code Distance/Direction Zone 1 TLDs: 0-3 km BOAT LAUNCH WEST BLW 0.11 km E OVERLOOKAREA OA 0.15 km W OVERLOOK AREA OA 0.15 km W PEDESTRIAN BRIDGE PB 0.21 km N HEALTH CLUB TC 0.15 km WSW MEDICAL BUILDING WS 0.23 km SSE BOAT LAUNCH EAST BLE 0.16 km ESE EAST BREAKWATER EB 0.44 km ESE PEDESTRIAN BRIDGE PB 0.21 km N

PROPERTY LINE PL 0.54 km NNW SHOREFRONT SECURITY P01 0.22 km NNW W ROCKY HILL ROAD WR 0.83 km WNW MEDICAL BUILDING WS 0.23 km SSE E ROCKY HILL ROAD ER 0.89 km SE PARKING LOT CT 0.31 km SE SHOREFRONT PARKING PA 0.35 km NNW STATION A A

0.37 km WSW STATION F F

0.43 km NW STATION B B

0.44 km S EAST BREAKWATER EB 0.44 km ESE PNPS MET TOWER PMT 0.44 km WNW STATION H H

0.47 km SW STATION I I

0.48 km WNW STATION L L

0.50 km ESE STATION G G

0.53 km W STATION D D

0.54 km NW PROPERTY LINE PL 0.54 km NNW STATION C C

0.57 km ESE HALUS BOG HB 0.63 km SE GREENWOOD HOUSE GH 0.65 km ESE W ROCKY HILL ROAD WR 0.83 km WNW E ROCKY HILL ROAD ER 0.89 km SE Page 57

Figure 2.2-2 (continued)

TLD and Air/Soil Sampling Locations: Within 1 Kilometer Page 58

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

Air/Soil Sampling Station Location*

Descripbon Code Distance/Direction Description Code Distance/Direction Zone 1 TLDs: 0-3 km MICROWAVE TOWER MT 1.03 km SSW CLEFT ROCK CR 1.27 km SSW CLEFT ROCK CR 1.27 km SSW MANOMET SUBSTATION MS 3.60 km SSE BAYSHORE/GATE RD BD 1.34 km WNW MANOMETROAD MR 1.38 km S DIRT ROAD DR 1.48 km SW EMERSON ROAD EM 1.53 km SSE EMERSON/PRISCILLA EP 1.55 km SE EDISON ACCESS ROAD AR 1.59 km SSE BAYSHORE BS 1.76 km W STATION E E

1.86 km S JOHN GAULEY JG 1.99 km W STATIONJ J

2.04 km SSE WHITEHORSE ROAD WH 2.09 km SSE PLYMOUTH YMCA RC 2.09 km WSW STATION K K

2.17 km S TAYLOR/THOMAS TT 2.26 km SE YANKEE VILLAGE YV 2.28 km WSW GOODWIN PROPERTY GN 2.38 km SW RIGHT OF WAY RW 2.83 km S TAYLOR/PEARL TP 2.98 km SE Zone 2 TLDs: 3-8 km VALLEY ROAD VR 3.26 km SSW MANOMETELEM ME.

3.29 km SE WARREN/CLIFFORD WC

'3.31 km W RT.3AIBARTLETT RD BB 3.33 km SSE MANOMET POINT MP 3.57 km SE MANOMET SUBSTATION MS 3.60 km SSE BEACHWOOD ROAD BW 3.93 km SE PINES ESTATE PT 4.44 km SSW EARLROAD EA 4.60 km SSE S PLYMOUTH SUBST SP 4.62 km W ROUTE 3 OVERPASS RP 4.81 km SW RUSSELL MILLS RD RM 4.85 km WSW

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

Page 59

Figure 2.2-3 (continued)

TLD and Air/Soil Sampling Locations: 1 to 5 Kilometers Pr4 -.

Page 60

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

Air/Soil Sampling Station Location*

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

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

Page 61

Figure 2.2-4 (continued)

TLD and Air/Soil Sampling Locations: 5 to 25 Kilometers Page 62

Figure 2.2-5 Terrestrial and Aquatic Sampling Locations Description Code Distance/Direction* l Descripton Code Distance/Direction MILK Plymouth County Farm Whitman Farm Control FORAGE Whipple Farm Plymouth County Farm Whitman Farm Control VEGETABLESNEGETATION Site Boundary C E

Site Boundary B E

Rocky Hill Road F

Site Boundary D E

Site Boundary A E

Clay Hill Road C

Brook Road E

Beaverdam Road E

Plymouth County Farm C

Div. Marine Fisheries I

Bridgewater Farm Control E

Norton Control CRANBERRIES Manomet Point Bog Bartlett Road Bog E

Pine Street Bog Control F

5.6 km W 34 km WNW 2.9 km SW 5.6 km W 34 km WNW 0.5 km SW 0.5 km ESE 0.9 km SE 1.1 km SSW 1.5 km SSW 1.6 km W 2.9 km SSE 3.4 km S 5.6 km W 21 km SSE 31 km.W 50 km;W W-3.9 km SE 4.3 km SSE 26 km WNW SURFACE WATER Discharge Canal Bartlett Pond Powder Point Control IRISH MOSS Discharge Canal Outfall Manomet Point Ellisville Brant Rock Control SHELLFISH Discharge Canal Outfall Plymouth Harbor Manomet Point Duxbury Bay Control Powder Point Control Green Harbor Control LOBSTER Discharge Canal Outfall Plymouth Beach Plymouth Harbor Duxbury Bay Control FISHES Discharge Canal Ouffall Plymouth Beach Jones River Control Cape Cod Bay Control N River-Hanover Control Cataumet Control Provincetown Control Buzzards Bay Control Priest Cove Control Nantucket Sound Control Atlantic Ocean Control Vineyard Sound Control SEDIMENT Discharge Canal Outfall Plymouth Beach Manomet Point Plymouth Harbor Duxbury Bay Control Green Harbor Control DIS BP PP DIS MP EL BK DIS PLY-H MP DUX-BAY PP GH DIS PLB PLY-H DUX-BAY DIS PLB JR CC-BAY NR CA PT BB PC NS AO MV DIS PLB MP PLY-H DUX-BAY GH 0.2 km N 2.7 km SE 13 km NNW 0.7 km 4.0 km 12 km 18 km NNE ESE SSE NNW 0.7 km NNE 4.1 km W 4.0 km ESE 13 km 13 km 16 km 0.5 km 4.0 km 6.4 km 11 km 0.5 km 4.0 km 13 km 24 km 24 km 32 km 32 km 40 km 48 km 48 km 48 km 64 km 0.8 km 4.0 km 3.3 km 4.1 km 14 km 16 km NNW NNW NNW N

W WNW NNW N

W WNW ESE NNW SSW NE SSW SW SSE E

SSW NE W

ESE W

NNW NNW

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

Page 63 CF WF WH CF WF 3C 3B RH 3d 3A CH 3K 3D CF

)MF 3F NC AR BT PS

Figure 2.2-5 (continued)

Terrestrial and Aquatic Sampling Locations

\\

4 BoMETEs

\\e OFLH-N4ORTH WEST 34EflO ERS WEST,NORTIWEST Ku~

WET.ORlWS P

I X3LKLOMETERS WE%

I e:4 1LOMEERS E,

SOUTHWEST 41LOMETERS 64 MJ SoOTHSOUTHWEST SOUJH f

I SYMBOL KEY SHELLFISH (M BLUEMUSSEL)

(S SOFr-SHELL)

(H HARD-SHELL)

Q IRISH MOSS

=

LOBSTER FISHES SURFACE WATER

[

SEDIMENT O CRANBERRY f

VEGETATION D1 MELK 0

ZMLES 2

SCALE NORTHEPSr AS KOMESERS WHIrEHORSE BEACH M

24 LMERS E

SbUTHSAST I KILMETERS SOUTHSOTHEAST 41 KLOMETERS SOUTH,SUTHEAST Page 64

Figure 2.2-6 Environmental Sampling And Measurement Control Locations

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

Page 65 Description Code Distance/Direction*

Description Code Distance/Direction*

TLD SURFACE WATER Cedarville Substation CS 16 km S Powder Point Control PP 13 km NNW Kingston Substation KS 16 km WNW Landing Road LR 16 km NNW IRISH MOSS Church & West Street CW 17 km NW Brant Rock Control BK 18 km NNW Main & Meadow Street MM 17 km WSW Div. Marine Fisheries DMF 21 km SSE SHELLFISH East Weymouth EW 40 km NW Duxbury Bay Control DUX-BAY 13 km NNW Substation Powder Point Control PP 13 km NNW AIR SAMPLER Green Harbor Control GH 16 km NNW East Weymouth EW 40 km NW Substation LOBSTER MILK Duxbury Bay Control DUX-BAY 11 km NNW Whitman Farm Control WF 34 km WNW FISHES FORAGE Jones River Control JR 13 km WNW Whitman Farm Control WF 34 km WNW Cape Cod Bay Control CC-BAY 24 km ESE N River-Hanover Control NR 24 km NNW VEGETABLESNEGETATION Cataumet Control CA 32 km SSW Div. Marine Fish. Control DMF 21 km SSE Provincetown Control iPT 32 km NE Bidgewater Farm Control BF 31 km W Buzzards Bay Control

.'BB 40 km SSW Norton Control NC 50 km W Priest Cove Control PC, 48 km SW Nantucket Sound Control NS 48 km SSE Atlantic Ocean Control AO 48 km E CRANBERRIES Vineyard Sound Control MV 64 km SSW Pine Street Bog Control PS 26 km WNW SEDIMENT SOIL Duxbury Bay Control DUX-BAY 14 km NNW East Weymouth EW 40 km NW Green Harbor Control GH 16 km NNW Substation

Fgure 2.2-6 (continued)

Environmental Sampling And Measurement Control Locations AwAdusErTsBAY CAPE COD BAY g(BAY

) CANAL NANTUCKET SOUND

@ZS Page 66 SYMBOL KEY SHEEL (M BLlUE MUSSEL)

(S SOFT-SHEL CLAM)

(H HARD-SHEM CLA)

O DMOSS D

LOBSTER Cx Fisass

\\7 SURFACE WATER 3 CRNRRY 0

VEGETATIONNORA.G O TID ElADRSAMPLFE o

MILES 10 SCALE EL

Historical Beach Survey Exposure Rate Measurements 77 79 81 83 85 87 89 91 93 95 97 99 01 Year

+-Whitehorse Beach at Hilltop Avenue

-a-Priscilla Beach at Full Sail Bar Plymouth Beach - Outer

-o Plymouth Beach - Inner x

Plymouth Beach at Berts

-*-- Duxbury Beach Control Figure 2.4-1 Historical Beach Survey Exposure Rate Measurements Page 67 14 12 10 0

G) 0 G

0a)

-6

.)

E

Airborne Gross-Beta Radioactivity Levels Near-Station Monitors 0.OE+00 1 I

I a

I I

Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month - 2001 AP-00 Warehouse AP-07 Pedestrian Bridge AP-08 Overlook Area

-~-AP-09 East Breakwater as AP-21 East Weyrnouth Control Figure 2.5-1 Airborne Gross-Beta Radioactivity Levels: Near Station Monitors Page 68 5.OE-02 4.0E-02 0 3.0 E-02 E

U

-0 C-)

o 2.0E-02

.)

a0-1.OE-02

Airborne Gross-Beta Radioactivity Levels Property Line Monitors O.OE+00 I

I Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month - 2001

-_-AP-01 E. Rocky Hill Road

-- AP-06 Property Line AP-03 W. Rocky Hill Road

-/- AP-21 East Weymouth Control Figure 2.5-2 Airborne Gross-Beta Radioactivity Levels: Property Line Monitors Page 69 5.oE-02 4.OE-02 C

3.OE-02 E

CY a

-C, C.)

2.OE-02 1.OE-02

Airborne Gross-Beta Radioactivity Levels Offsite Monitors 0.OE+00 1 I

I Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month - 2001 AP-10 Cleft Rock

-a-AP-15 Plymouth Center

--- AP-17 Manomet Substation AP-21 East Weymouth Control Figure 2.5-3 Airbome Gross-Beta Radioactivity Levels: Offsite Monitors Page 70 5.OE-02 a) a) 3.OE-02 E

0

.a

-0

° 2.0E-02 r

Levels of Strontium-90 in Milk Samples Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month - 2001 Plymouth County Farm Whitman Farm Figure 2.7-1 Levels of Strontium-90 in Milk Samples Page 71 5-4.

.)

00

.2 2-

-I

-n Jan I

I E

r

3.0

SUMMARY

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

calculations based on measurements of plant effluents; and calculations based on measurements of environmental samples.

The first method utilizes data from the radioactive effluents (measured at the point of release) together with conservative models that calculate the dispersion and transport of radioactivity through the environment to humans (Reference 7). The second method is based on actual measurements of radioactivity in the environmental samples and on dose conversion factors recommended by the Nuclear Regulatory Commission. The measured types and quantities of radioactive liquid and gaseous effluents released from Pilgrim Station during 2002 were reported to the Nuclear Regulatory Commission, copies of which are provided in Appendix B.

The measured levels of radioactivity in the environmental samples that required dose calculations are listed in Appendix A.

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

shoreline extemal radiation during fishing and recreation at the Pilgrim Station Shorefront; external radiation from the ocean during boating and swimming; and ingestion of fish and shellfish.

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

extemal radiation from cloud shine and submersion in gaseous effluents; inhalation of airborne radioactivity; extemal 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 and Waste Disposal Report" for the period of January 1 through December 31, 2002.

Page 72

Table 3.0-1 Radiation Doses from 2002 Pilgrim Station Operations

• Gaseous effluent exposure pathway includes combined dose from particulates, odines and tritium in addition to noble gases.

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

Two federal agencies establish dose limits to protect the public from radiation and radioactivity.

The Nuclear Regulatory Commission (NRC) specifies a whole body dose limit of 100 mrem/yr to be received by the maximum exposed member of the general public. This limit is set forth in Section 1301, Part 20, Title 10, of the U.S. Code of Federal Regulations (1 OCFR20).

By comparison, the Environmental Protection Agency (EPA) limits the annual whole body dose to 25 mrem/yr, which is specified in Section 10, Part 190, Title 40, of the Code of Federal Regulations (40CFR190).

Another useful "gauge" of radiation exposure is provided by the amount of dose a typical individual receives each year from natural and man-made (e.g., diagnostic X-rays) sources of radiation. The typical American receives 300 to 400 mrem/yr from such sources.

As can be seen from the doses resulting from Pilgrim Station Operations during 2002, all values are well within the federal limits specified by the NRC and EPA.

In addition, the calculated doses from PNPS operation represent only a fraction of a percent of doses from natural and man-made radiation.

A second method of dose estimation involves calculations based on radioactivity detected in environmental media. During 2002, the only environmental media which contained radioactivity potentially attributable to Pilgrim Station operation was shellfish, which contained low levels of cesium-137. Although the Cs-137 detected is most likely due to fallout from weapons testing, an assessment was performed to determine the maximum dose received from ingestion of such shellfish. Details of this assessment are presented in Appendix A. The maximum calculated total body dose from this ingestion pathway was calculated as 0.005 mrem, with a corresponding maximum organ dose of 0.007 mrem.

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

Page 73 Maximum Individual Dose From Exposure Pathway - mrem/yr Gaseous Liquid Ambient T

Receptor Effluents*

Effluents Radiation**

Total Total Body 2.7 0.000042 2.7 5.4 Thyroid 3.0 0.0000060 2.7 5.7 Max. Organ 3.0 0.00022 2.7 5.7

4.0 REFERENCES

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

2)

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

3)

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

4)

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

5)

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

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

7)

Pilgrim Nuclear Power Station Offsite Dose Calculation Manual, Revision 8, August 1998.

8)

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

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

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

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

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

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

14) United States Nuclear Regulatory Commission, NUREG-0473, "Standard Radiological Effluent Technical Specifications for Boiling Water Reactors," Revision 3, September 1982.

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

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

17) T. Messier, Framatome/DE&S, "2002 Annual Beach Ion-Chamber Survey" REG 03-005, February 5, 2003.

Page 74

APPENDIX A SPECIAL STUDIES Shellfish Radioactivity The only environmental media which contained radioactivity potentially attributable to Pilgrim Station operations was shellfish.

The only nuclide detected was cesium-137 (Cs-137), at concentrations ranging from non-detectable to a maximum concentration of 7.4 pCi/kg, which was detected in a sample of soft-shelled clams collected from Plymouth Harbor.

In actuality, the activity detected in this and other samples is most likely attributable to Cs-1 37 in the environment from weapons testing in the 1950s through 1970s. Cesium-137 is widely distributed in environmental media, and has been routinely seen in the past in other indicator and control samples, including shellfish. Levels of Cs-137 detected in sediment collected at control locations were similar to those collected from indicator locations. When coupled with the fact that liquid discharges from Pilgrim Station during 2002 were significantly reduced compared to previous years, any detectable Cs-137 observed in environmental media is most certainly due to weapons testing.

To assess the potential dose impact from such Cs-137, standard equations found in Regulatory Guide 1.109 and the Pilgrim Station Offsite Dose Calculation Manual were used. The approach used calculates the total intake of Cs-1 37 based on ingestion/consumption rates, and multiplies that value by a dose conversion factor to derive the resulting dose. The following table outlines the approach taken and the resulting dose to the maximally-exposed organ in each of three age groups:

Maximum Total BodV Dose Ingestion Age Intake Concentration Total Intake Dose Factor Total Dose Class kg/vr pCi/kg pCi mrem/pCi mrem Adult 9

7.3 65.7 7.14E-5 4.69E-3 Teen 6

7.3 43.8 5.19E-5 2.27E-3 Child 3

7.3 21.9 4.62E-5 1.01 E-3 Maximum Orqan Dose Ingestion Age Intake Concentration Total Intake Dose Factor Total Dose Class kg/yr pCi/kg pCi mrem/pCi mrem Adult 9

7.3 65.7 1.09E-4 7.2E-3

~ ~(liv e r)_

Teen 6

7.3 43.8 1.49E-4 6.5E-3 Child_____

3________

7.3___________

21.9_________

(bie) 7.2E-3____(ie Child 3

7.3 21.9 3.27E-4 7.2E-3

_ _ _ _ _(b o n e )

As can be seen in the above table, the maximum whole body dose received from ingestion of shellfish containing low-levels of Cs-137 would be 0.005 mrem, while the maximum organ dose would be 0.007 mrem. This can be compared to the 30-40 mrem/yr received from the ingestion of other radioactivity (e.g.,

potassium-40, uranium, thorium, etc.) naturally present in food.

Page 75

APPENDIX B Effluent Release Information TABLE TITLE PAGE B.1 Supplemental Information 77 B.2-A Gaseous Effluents Summation of All Releases 79 B.2-B Gaseous Effluents - Elevated Releases 81 B.2-C Gaseous Effluents - Ground Level Releases 83 B.3-A Liquid Effluents Summation of All Releases 85 B.3-B Liquid Effluents 87 Page 76

Table 2.1 Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Supplemental Information January-June 2002 FACILITY: PILGRIM NUCLEAR POWER STATION

a. Fission and activation gases:

b,c. lodines, particulates with half-life:

>8 days, tritium

d. Liquid effluents:

2. EFFLUENT CONCENTRATION LIMITS 500 mrem/yr total body and 3000 mrem/yr for skin at site boundary 1500 mren/yr to any organ at site boundary 0.06 mrem/month for whole body and 0.2 mrem/month for any organ (without radwaste treatment)

a. Fission and activation gases:

b. lodines:

c. Particulates with half-life > 8 days:

d. Liquid effluents:

3. AVERAGE ENERGY 10CFR20 Appendix B Table II 10CFR20 Appendix B Table II 10CFR20 Appendix B Table II 2E-04 gCiVmL for entrained noble gases; 1 OCFR20 Appendix B Table II values for all other radionuclides Not Applicable

4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY

a. Fission and activation gases:

b. lodines:

c. Particulates:

d. Liquid effluents:

5. BATCH RELEASES

a. Liquid Effluents

1. Total number of releases:

2. Total time period (minutes):

3. Maximum time period (minutes):

4. Average time period (minutes):

5. Minimum time period (minutes):

6. Average stream flow (Liters/min):

during periods of release of effluents into a flowing stream

b. Gaseous Effluents

6. ABNORMAL RELEASES High purity germanium gamma spectroscopy for all gamma emitters; radiochemistry analysis for H-3, Fe-55 (liquid effluents),

Sr-89, and Sr-90 0

-%U-2.98E+02 i 1.70E+02 Page 77

1. REGULATORY LIMITS UCENSE: DPR-35

a. Liquid Effluents

b. Gaseous Effluents

Table 2.1 (continued)

Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Supplemental Information July-December 2002 FACILITY: PILGRIM NUCLEAR POWER STATION LICENSE: DPR-35

1. REGULATORY LIMITS

a. Fission and activation gases:

b,c. lodines, particulates with half-life:

>8 days, tritium

d. Liquid effluents:

2. EFFLUENT CONCENTRATION LIMITS 500 mrem/yr total body and 3000 mrem/yr for skin at site boundary 1500 mrem/yr to any organ at site boundary 0.06 mrem/month for whole body and 0.2 mrem/month for any organ (without radwaste treatment)

a. Fission and activation gases:

b. lodines:

c. Particulates with half-life > 8 days:

d. Liquid effluents:

3. AVERAGE ENERGY 10CFR20 Appendix B Table II 10CFR20 Appendix B Table II 10CFR20 Appendix B Table II 2E-04 +/-CimL for entrained noble gases; 10CFR20 Appendix B Table II values for all other radionuclides Not Applicable

4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY

a. Fission and activation gases:

b. lodines:

c. Particulates:

d. Liquid effluents:

High purity germanium gamma spectroscopy for all gamma emitters; radiochemistry analysis for H-3, Fe-55 (liquid effluents),

Sr-89, and Sr-90

5. BATCH RELEASES

a. Liquid Effluents

1. Total number of releases:

2. Total time period (minutes):

3. Maximum time period (minutes):

4. Average time period (minutes):

5. Minimum time period (minutes):

6. Average stream flow (Liters/min):

during periods of release of effluents into a flowing stream

b. Gaseous Effluents

6. ABNORMAL RELEASES None None.....

None None

':"R None None.,.,.,

None None..

None None Page 78

a. Liquid Effluents

b. Gaseous Effluents

.I i.

Table 2.2-A Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Summation of All Releases January-June 2002 Period:

Period:

Estimated I Jan-Mar 2002 Apr-Jun 2002 Total Error A. FISSION AND ACTIVATION GASES Total Release: Ci 5.77E+00 3.24E+01 J

+/-22%

Average Release Rate During Period: g,CVsec 7.31 E-01 4.10E+00 Percent of Effluent Control Limit B. IODINES Total lodine-131 Release: Ci 4.28E-04 l4.67E-04

+/-

+20%

Average Release Rate During Period:

CVsec 5.43E-05 5.92E-05 Percent of Effluent Control Limit C. PARTICULATES Total Release: Ci 2.28E-04 1.12E-04 21%

Average Release Rate During Period: IxCVsec 2.89E-05 1.42E-05 Percent of Effluent Control Limit Gross Alpha Radioactivity: Ci NDA NDA D. TRITIUM Total Release: Ci j

1.59E+02 l

1.25E+02

+/-

_20%

Averacie Release Rate During Period: uCVsec 2.02E+01 1.59E+01 Percent of Effluent Control Limit I

t Notes for Table 2.2-A:

• Percent of Effluent Control Limit values based on dose assessments are provided in Section 7 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 gCVcc.

Page 79

Table 2.2-A (continued)

Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Summation of All Releases July-December 2002 Period:

I Period:

I Estimated I Jul-Sep 2002 Oct-Dec 2002 Total Error A. FISSION AND ACTIVATION GASES Total Release: Ci 1.91E+01 5.22E+00

+/-

_22%

Average Release Rate During Period:

iCVsec 2.42E+00 6.62E-01 Percent of Effluent Control Limit J

B. IODINES Total Iodine-131 Release: Ci 8.57E-04 l06.89E-04 l

0%

Average Release Rate During Period:

CVsec 1.09E-04 8.73E-05 l

Percent of Effluent Control Limit C. PARTICULATES Total Release: Ci 3.70E-04 7.20E-04

+/-21%

Average Release Rate During Period:

CVsec 4.69E-05 9.12E-05 Percent of Effluent Control Limit Gross Alpha Radioactivity: Ci NDA NDA D. TRITIUM i

Total Release: Ci l

1.57E+02 l

2.49E+02

+/-

+20%

Averaae Release Rate Durina Period: uCVsec 1.99E+01 3.16E+01 "I

Percent of Effluent Control Limit i

I Notes for Table 2.2-A:

• Percent of Effluent Control Limit values based on dose assessments are provided in Section 7 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 Ci/cc.

Page 80

Table 2.2-B Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Elevated Release January-June 2002 Continuous Mode Batch Mode Nuclide Released Jan-Mar 2002 l

Apr-Jun 2002 Jan-Mar 2002 Apr-Jun 2002

1. FISSION AND ACTIVATION GASES - Ci Ar-41 NDA NDA N/A N/A Kr-85m NDA NDA N/A N/A Kr-87 NDA NDA N/A N/A Kr-88 NDA NDA N/A N/A Xe-1 33 NDA NDA N/A N/A Xe-1 33m NDA NDA N/A N/A Xe-1 35 NDA 2.53E+01 N/A N/A Xe-135m NDA NDA N/A N/A Total for period NDA 2.53E+01 N/A N/A

2. IODINES - Ci 1-131 1.90E-04 1.79E-04 N/A N/A 1-133 1.16E-03 9.04E-04 N/A N/A Total for period 1.35E-03 1.08E-03 N/A N/A

3. PARTICULATES - Ci Mn-54 NDA NDA N/A N/A Co-60 6.03E-06 NDA N/A N/A Sr-89 1.18E-05 1.69E-05 N/A N/A Sr-90 NDA NDA N/A N/A Cs-1 37 1.37E-06 NDA N/A N/A Ba/La-1 40 1.69E-05 2.68E-05 N/A N/A Total for period 3.61 E-05 4.37E-05 N/A N/A

4. TRITIUM-Ci H-3 l

3.03E+00 4.15E+0 N/A N/A Notes for Table 2.2-B:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

Fission Gases: 1 E-04 gCVcc lodines:

1 E-1 2 tiCVcc Particulates:

1 E-1 1 iCVcc Page 81

Table 2.2-B (continued)

Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Elevated Release July-December 2002 I

Continuous Mode Batch Mode NuclideReleased Jul-Sep 2002 l Oct-Dec 2002 0Jul-Sep202 l Oct-Dec 2002

1. FISSION AND ACTIVATION GASES - Ci Ar-41 NDA NDA N/A N/A Kr-85m NDA NDA N/A N/A Kr-87 NDA NDA N/A N/A Kr-88 NDA NDA N/A N/A Xe-133 NDA NDA N/A N/A Xe-133m NDA NDA N/A N/A Xe-135 1.42E+01 NDA N/A N/A Xe-135m NDA NDA N/A N/A Total for period 1.42E+01 NDA N/A N/A

2. IODINES - Ci 1-131 1.97E-04 1.30E-04 N/A N/A 1-133 1.08E-03 7.44E-04 N/A N/A Total for period 1.28E-03 i

8.74E-04 N/A N/A

3. PARTICULATES - Ci NDA NDA Mn-54 NDA NDA N/A N/A Co-60 NDA NDA N/A N/A Sr-89 1.70E-05 7.32E-06 N/A N/A Sr-90 NDA NDA N/A N/A Cs-137 NDA NDA N/A N/A Ba/La-1 40 9.27E-05 NDA N/A N/A Total for period 1.1 OE-04 7.32E-06 N/A N/A

4. TRITIUM-Ci H-3 I

4.90E+00 6.02E+00 N/A N/A Notes for Table 2.2-B:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

Fission Gases: 1 E-04 tCVcc lodines:

1 E-1 2 giCVcc Particulates:

1 E-1 1 [tCVcc Page 82

Table 2.2-C Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Ground Level Release January-June 2002 I

Continuous Mode Batch Mode Nuclide Released I Jan-Mar 2002 l Apr-Jun 2002 l Jan-Mar 2002 l Apr-Jun 2002 I

1. FISSION AND ACTIVATION GASES - Ci Ar-41 NDA NDA N/A N/A Kr-85m NDA NDA N/A N/A Kr-87 NDA NDA N/A N/A Kr-88 NDA NDA N/A N/A Xe-133 NDA NDA N/A N/A Xe-1 33m NDA NDA N/A N/A Xe-1 35 5.77E+00 7.02E+00 N/A N/A Xe-135m NDA NDA N/A N/A Total for period 5.77E+00 7.02E+00 N/A N/A

2. IODINES - Ci 1-131 2.38E-04 2.88E-04 N/A N/A 1-133 2.53E-03 2.78E-03 N/A N/A Total for period 2.77E-03 3.07E-03 N/A N/A

- :n3. PARTICULATES-Ci Mn-54 NDA NDA N/A N/A Co-60 NDA NDA N/A N/A Sr-89 1.11 E-04 6.85E-05 N/A N/A Sr-90 NDA NDA N/A N/A Cs-137 3.19E-05 NDA N/A N/A Ba/La-1 40 4.90E-05 NDA N/A N/A Total for period 1.92E-04 6.85E-05 N/A N/A

4. TRITIUM - Ci H-3 I

1.56E+02 1.21 E+02 N/A N/A Notes for Table 2.2-C:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

Fission Gases: 1 E-04 iCVcc lodines:

1 E-1 2 tCVcc Particulates:

1 E-11 IjCVcc Page 83

Table 2.2-C (continued)

Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Ground Level Release July-December 2002 Continuous Mode Batch Mode Nuclide Released Jul-Sep 2002 l Oct-Dec 2002 Jul-Sep 2002 l Oct-Dec 2002

1. FISSION AND ACTIVATION GASES - Ci Ar-41 NDA NDA N/A N/A Kr-85m NDA NDA N/A N/A Kr-87 NDA NDA N/A N/A Kr-88 NDA NDA N/A N/A Xe-133 NDA NDA N/A N/A Xe-133m NDA NDA N/A N/A Xe-135 4.89E+00 5.22E+00 N/A N/A Xe-135m NDA NDA N/A N/A Total for period 4.89E+00 5.22E+00 N/A N/A

2. IODINES - Ci 1-131 6.59E-04 5.58E-04 N/A N/A I-133 5.20E-03 5.14E-03 N/A N/A Total for period 5.86E-03 5.70E-03 N/A N/A

3. PARTICULATES - Ci Mn-54 1.90E-06 NDA N/A N/A Co-60 NDA NDA N/A N/A Sr-89 1.OOE-04 9.73E-05 N/A N/A Sr-90 NDA NDA N/A N/A Cs-1 37 NDA NDA N/A N/A Ba/La-140 1.58E-04 6.15E-04 N/A N/A Total for period 2.60E-04 7.12E-04 N/A N/A

4. TRITIUM - Ci H-3 1.52E+02 2.43E+02 N/A N/A Notes for Table 2.2-C:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

Fission Gases: 1 E-04 ICVcc lodines:

1 E-1 2 liCVcc Particulates:

1 E-1 CICVcc Page 84

Table 2.3-A Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents - Summation of All Releases January-June 2002 Period:

l Period:

I Estimated I Jan-Mar 2002 Apr-Jun 2002 Total Error A. FISSION AND ACTIVATION PRODUCTS Total Release (not including H-3, noble gas, or alpha): Ci 1.OOE-03 l

N/A

+/-

+/-12%

Average Diluted Concentration During Period:

iCVmL 2.86E-09 N/A Percent of Effluent Concentration Limit*

5.24E-02%

N/A B. TRITIUM Total Release: Ci 2.93E-01 J

N/A

+/-

+/-9.4%

Average Diluted Concentration During Period:

CVmL 8.39E-07 7

N/A Percent of Effluent Concentration Limit*

8.39E-02%

l N/A C. DISSOLVED AND ENTRAINED GASES Total Release: Ci NDA N/A 16%

Average Diluted Concentration During Period:

CVmL NDA N/A Percent of Effluent Concentration Limit*

NDA N/A D. GROSS ALPHA RADIOACTIVITY Total Release: Ci NDA N/A

+/-34%

E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION Waste Volume: Liters I

4.56E+04 N/A

+/-5.7%

F. VOLUME OF DILUTION WATER USED DURING PERIOD Dilution Volume: Liters 1.52E+1 N/A

+/-1 0%

Notes for Table 2.3-A:

• Additional percent of Effluent Control Limit values based on dose assessments are provided in Section 7 of this report.

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

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

Page 85

Table 2.3-A (continued)

Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents - Summation of All Releases July-December 2002 Period:

Period:

Estimated I Jul-Sep 2002 lOct-Dec 2002 Total Error A. FISSION AND ACTIVATION PRODUCTS Total Release (not including H-3, noble gas, oralpha): Ci N/A N/A

+/-12%

Average Diluted Concentration During Period:

CVmL N/A N/A Percent of Effluent Concentration Limit*

N/A N/A B. TRITIUM Total Release: Ci N/A N/A

+/-9.4%

Average Diluted Concentration During Period:

tCVmL N/A N/A Percent of Effluent Concentration Limit*

N/A N/A C. DISSOLVED AND ENTRAINED GASES Total Release: Ci N/A N/A

+/-16%

Average Diluted Concentration During Period:

CVmL N/A N/A Percent of Effluent Concentration Limit*

N/A N/A D. GROSS ALPHA RADIOACTIVITY Total Release: Ci N/A N/A

+/-34%

E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION.

I Waste Volume: Liters I

N/A N/A

+/-5.7%

F. VOLUME OF DILUTION WATER USED DURING PERIOD Dilution Volume: Liters I

N/A N/A

+/-10%

Notes for Table 2.3-A:

• Additional percent of Effluent Control Limit values based on dose assessments are provided in Section 7 of this report.

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

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

Page 86

Table 2.3-B Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents January-June 2002 Iuclid Released I Continuous Mode J

Batch Mode lNuclide Released Jan-Mar 2002 I

Apr-Jun 202 lJan-Mar 202 lApr-Jun 202l

1. FISSION AND ACTIVATION PRODUCTS - Ci Cr-51 N/A N/A NDA N/A Mn-54 N/A N/A 6.60E-05 N/A Fe-55 N/A N/A 7.06E-04 N/A Fe-59 N/A N/A NDA N/A Co-58 N/A N/A NDA N/A Co-60 N/A N/A 8.21 E-05 N/A Zn-65 N/A N/A 2.26E-06 N/A Sr-89 N/A N/A NDA N/A Sr-90 N/A N/A 2.33E-06 N/A Zr/Nb-95 N/A N/A NDA N/A Ag-1 Om N/A N/A NDA N/A Sb-124 N/A N/A NDA N/A Cs-137 N/A N/A 1.42E-04 N/A Total for period N/A N/A 1.OOE-03 N/A

2. DISSOLVED AND ENTRAINED GASES - Ci Xe-133 N/A N/A J

NDA N/A Xe-135 N/A N/A NDA N/A Total for period N/A N/A NDA N/A Notes for Table 2.3-B:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

Strontium:

5E-08 ICimL lodines:

1 E-06 jICVmL Noble Gases:

1 E-05 jiCVmL All Others:

5E-07 gCVmL Page 87

Table 2.3-B (continued)

Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents July-December 2002 r

l

~~~~Continuous Mode lBatch Mode Nuclide Released l Jul-Sep 2002 l

Oct-Dec 2002 Jul-Sep202 Oct-Dec 2002

1. FISSION AND ACTIVATION PRODUCTS - Ci Cr-51 N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A Fe-55 N/A N/A N/A N/A Fe-59 N/A N/A N/A N/A Co-58 N/A N/A N/A N/A Co-60 N/A N/A N/A N/A Zn-65 N/A N/A N/A N/A Sr-89 N/A N/A N/A N/A Sr-90 N/A N/A N/A N/A Zr/Nb-95 N/A N/A N/A N/A Ag-1 Om N/A N/A N/A N/A Sb-124 N/A N/A N/A N/A Cs-137 N/A N/A N/A N/A Total for period N/A N/A N/A N/A

2. DISSOLVED AND ENTRAINED GASES - Ci Xe-133 N/A N/A N/A N/A Xe-135 N/A N/A N/A N/A Total for period N/A N/A N/A N/A Notes for Table 2.3-B:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

Strontium:

5E-08 ICVmL lodines:

1 E-06 ICVmL Noble Gases:

1 E-05 gCVmL All Others:

5E-07 gCVmL Page 88

APPENDIX C LAND USE CENSUS RESULTS The annual land use census for gardens and milk and meat animals in the vicinity of Pilgrim Station was performed between September 23 and October 31, 2002.

The census was conducted by driving along each improved road/street in the Plymouth area within 5 kilometers (3 miles) of Pilgrim Station to survey for visible gardens with an area of greater than 500 square feet. In compass sectors where no gardens were identified within 5 km (SSW, WNW, NW, and NNW sectors), the survey was extended to 8 km (5 mi). A total of 31 gardens were identified in the vicinity of Pilgrim Station.

In addition, the Town of Plymouth Animal Inspector was contacted for information regarding milk and meat animals.

Atmospheric deposition (D/Q) values at the locations of the identified gardens were compared to those for the existing sampling program locations.

These comparisons enabled PNPS personnel to ascertain the best locations for monitoring for releases of airborne radionuclides.

Gardens yielding higher D/Q values than those currently in the sampling program were also sampled as part of the radiological environmental monitoring program.

Based on assessment of the gardens identified during the 2002 land use census, samples of garden-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 compass sectors.

These locations, and their distance and direction relative to the PNPS Reactor Building, are as follows:

Rocky Hill Road 0.9 km SE Brook Road

'2.9 km SSE Beaverdam Road 3.4 km S Bay Colony Drive 3.1 km WSW ClayHill Road 1.6 km W In addition to these special sampling locations identified and sampled in conjunction with the 2002 land use census, samples were also collected at or near the Plymouth County Farm (5.6 km W), Whipple Farm (2.9 km SW), and from a control location in Bridgewater (31 km W).

No new milk or meat animals were identified during the land use census. In addition, the Town of Plymouth Animal Inspector stated that their office is not aware of any animals at locations other than the Plimoth Plantation and the Plymouth County Farm. Samples of milk and forage have historically been collected from the Plymouth County Farm and were part of the 2002 sampling program.

Page 89

APPENDIX D ENVIRONMENTAL MONITORING PROGRAM DISCREPANCIES There were a number of instances during 2002 in which inadvertent issues were encountered in the collection of environmental samples. All of these issues were minor in nature and did not have an adverse effect on the results or integrity of the monitoring program. Details of these various problems are given below.

In 2002, four thermoluminescent dosimeters (TLDs) were not recovered from their assigned locations during the quarterly retrieval process.

During the first quarter retrieval, the TLD located at Taylor & Thomas (TT) was presumably lost to storm damage. Vandalism was assumed to be the cause of losses of the TLDs at Emerson Road (EM) during the second quarter, King Caesar Road (KC) during third quarter, and Emerson & Priscilla (EP) during the fourth quarter.

Despite these losses, the 436 TLDs that were collected (99%) allowed for adequate assessment of the ambient radiation levels in the vicinity of Pilgrim Station.

During the fourth quarter of 2001, major renovation was taking place at Memorial Hall (MH),

and the TLD posted at that location was relocated to the exterior of the building during the first three quarters of the year 2002. It was relocated within the building during the fourth quarter.

Although all four TLDs were recovered, the fourth quarter result was significantly higher than the other quarters due to buildup of radon in the building.

Within the air sampling program, there were a few instances in which continuous sampling was interrupted at the eleven airborne sampling locations during 2002. Most of these interruptions were due to short-term power losses and were sporadic and of limited duration (less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> out of the weekly sampling period). Such events did not have any significant impact on the scope and purpose of the sampling program, and all lower limits of detection (LLDs) were met for both particulates and iodine-131 on the filters.

When the sample was collected from the East Rocky Hill Road (ER) location during the week of 08-14 May 2002, the exterior power cutoff/circuit breaker was found turned off. There was also minor damage to the sampling station due to vandalism. Although PNPS Security investigated the event, no further actions were taken. Despite the lower than normal volumes, the required LLDs were met on the particulate and charcoal samples collected. No further problems were encountered at this location during 2002.

A power surge resulting in a blown fuse contributed to partial sampling at West Rocky Hill Road (WR) during the week of 18-23 December 2002, resulting in a 61-hour run time out of the 120-hour sampling period. Despite the lower than normal volumes, the required LLDs were met on the particulate and charcoal samples collected.

Despite the lower-than-normal sampling volumes in the various instances involving power interruptions and equipment failures, required LLDs were met on 572 of the 572 particulate filters and 572 of the 572 iodine cartridges collected during 2002. None of the sample analyses associated with limited pump run times indicated any questionable or anomalous results. When viewed collectively during the entire year of 2002, the following sampling recoveries were achieved in the airbome sampling program:

Page 90

WS 99.9%

PB 99.5%

PC 100.0%

ER 98.7%

OA 100.0%

MS 100.0%

WR 99.1%

EB 99.8%

EW 100.0%

PL 100.0%

CR 100.0%

In July 2002, the Plymouth County Farm ceased operation of its dairy and garden facilities.

This was historically the only dairy facility near Pilgrim Station, and had been sampled continuously since Pilgrim Station began operation in 1972. Although attempts were made to obtain samples from an alternate indicator location, a suitable substitute could not be found.

Thus, milk collection and crop collection at Plymouth County Farm was discontinued in July, but control samples of milk continued to be collected and analyzed in the event an indicator milk location could be secured.

An alternate location had to-be found for sampling control vegetable samples in the Bridgewater area. In past years, samples had been collected at the Bridgewater County Farm, associated with the Bridgewater Correctional Facility. Due to loss of state funding for garden projects during 2002, no garden was grown.

An alternate location was found at the Hanson Farm in Bridgewater, located in the same compass sector, and at approximately the same distance as the Bridgewater County Farm. As expected for control samples, vegetables collected at this location only contained naturally-occurring radioactivity (K-40).

Some problems were encountered in collection of crop samples during 2002. Crops were not grown at the Plymouth' County Farm (CF) during 2002. However, samples of naturally-growing vegetation (grass, leaves from trees and bushes, etc.) were collected near some gardens' identified during the annual land use census. Due to the unavailability of crops grown in these' gardens, these substitute samples were collected as near as practicable to the gardens of interest. No radionuclides attributed to PNPS operations were detected in any of the samples.

Additional details regarding the land use census can be found in Appendix C of this report.

The cranberry bog at Manomet Point (MP) was not in production during 2002, so a sample could not be obtained from this location. Samples were collected as required from the other indicator bog located along Bartlett Road (BT).

Again, the extensive sampling of leafy vegetation would provide a better indication of deposition radionuclides, so the loss of this sample does not adversely affect overall monitoring efforts.

The delivery of samples of shellfish collected during fourth quarter of 2002 was delayed due to scheduling of personnel around end-of-year holidays and vacations. In addition, samples were delayed during the express mail shipment, and the frozen samples thawed prior to receipt at the analytical laboratory. Some of the plastic containers developed holes during the handling and shipping, and portions of shellfish liquid were lost.

Due to the radioactive decay between sample collection and analysis, and the loss of some sample mass (liquid) in transit, some of the very low-level limits of detection could not be met on several of the samples.

Pilgrim Station's detection requirement of 5 pCi/kg is a factor of 30-times lower than the 150 pCi/kg standard used by the rest of the nuclear industry. Prolonged (>60-hour) analyses were performed on the samples, and the achieved detection sensitivity was between 7 and 10 pCVkg, and was only slightly above the PNPS requirement.

Lobster samples are normally collected on a monthly basis between June and September. Due to inclement weather in August 2002, the collection of the August sample was delayed into the Page 91 Location Recoverv Location RecoverV Location Recoverv

first week of September. Thus, four samples were collected as required, and the slight delay in collection of the August sample did not adversely affect the sampling program.

Samples of Group I (bottom-distribution) and Group 11 (near-bottom distribution) fishes were not collected in the vicinity of the discharge outfall during the first and fourth calendar quarters of 2002. Such fish species move to deeper water during colder months, and were not available.

Repeated and concerted efforts were made, but failed to produce fish samples during the first and fourth quarters.

Two sets of samples of sediment collected during the first half of the year were not analyzed as required. Although paperwork records indicate that the samples were collected and delivered to the analytical laboratory in June, analyses were not performed and the samples could not be located.

Eight depth-incremental sub-samples from Plymouth Harbor, as well as the eight depth-incremental sub-samples from Duxbury Bay were delivered to the lab on 27-Jun-2003 along with 38 samples from the other sampling locations. It is surmised that the samples were not clearly labeled and were assumed to be backup samples from the other locations.

Historically, backup samples for several locations have been submitted, but not analyzed unless follow-up analyses were required to further define radionuclide concentrations. Two of the samples from the control location in Duxbury were scheduled to be analyzed for plutonium, to establish a baseline for comparison to the indicator locations closer to the plant. Plutonium analyses from indicator locations indicated no detectable plutonium.

In summary, the various problems encountered in collecting and analyzing environmental samples during 2002 were relatively minor when viewed in the context of the entire monitoring

.program. None of the discrepancies resulted in an adverse impact on the overall monitoring program.

Page 92

APPENDIX E FRAMATOME ANP QUALITY ASSURANCE PROGRAM RESULTS E.1 Introduction The accuracy of the data obtained through the PNPS Radiological Environmental Monitoring Program (REMP) is ensured through a comprehensive Quality Assurance Program.

This appendix addresses those aspects of quality assurance that deal with the accuracy and precision of the analytical sample results and the environmental TLD measurement results that are obtained by PNPS from the Framatome ANP Environmental Laboratory.

Much of the information contained herein has been summarized from the Framatome ANP "Semi-Annual Quality Assurance Status Report: January - June 2002," and "Semi-Annual Quality Assurance Status Report: July - December 2002."

As stated earlier in the report, Pilgrim Station began using Entergy's J.A. Fitzpatrick Environmental Laboratory beginning in July 2002 for sample analysis of REMP samples. Since this laboratory also has an intercomparison program, details of those results are also summarized in Appendix F.

E.2 Framatome Laboratory Analyses Quality control programs were performed by the Framatome ANP Environmental Lab during 2002 to demonstrate the validity of laboratory analyses in the media types of air filter, charcoal (iodine) cartridges, milk, soil/sediment, vegetation, and water.

These quality control assessments are performed within the following intercomparison programs:,

Framatome ANP intralaboratory quality control program to assure the validity and reliability of the data. This program includes quality control of laboratory-equipment, use of reference standards for calibration, and analysis of blank and spiked samples. The records of the quality control program are reviewed by the responsible cognizant individual, and corrective measures are taken, as appropriate.

Framatome ANP participation in a crosscheck program with Analytics, Inc. for environmental air filter, water, and milk samples.

Framatome ANP participation in a crosscheck program with the National Institute of Standards and Technology (NIST), formerly the National Bureau of Standards. This comparison program evaluates the E-Lab's performance relative to standard measurement techniques certified by the NIST.

In addition to the intercomparison programs mentioned previously, a blind duplicate program is maintained in which paired samples from the five sponsor companies, including Pilgrim Station, are prepared from homogeneous media and sent to the laboratory for analysis. The results from this blind duplicate program are used to check for precision in laboratory analyses in environmental media typically collected and analyzed for the sponsor companies.

The results of these studies are discussed below.

E.3 Framatome ANP Intralaboratory and Independent Interlaboratory Results Results of the Quality Assurance Program are reported in two separate categories based upon Framatome ANP acceptance criteria. The first criterion concems accuracy, which is defined as the deviation of any one result from the assumed known value. The second criterion concems precision, which deals with the ability of the measurement to be faithfully replicated by a comparison of an individual result to the mean of all results for a given sample set.

Page 93

The Quality Assurance Program implemented at the analytical laboratory indicated good precision and accuracy in reported values. Table E.1 shows the cumulative results of accuracy and precision for laboratory analyses in 2002 for Framatome ANP intralaboratory analyses, as well as Analytics and NIST interlaboratory crosscheck analyses. A total of 870 analyses were performed for accuracy cross-comparisons, while 474 crosscheck analyses were performed to assess precision. For accuracy, 71.1% and 90.7% of the results were within 5 and 10 percent of the known values, respectively, with 99.2% of all results falling within the laboratory criterion of 15 percent. For precision, 86.7% and 96.0% of the results were within 5 and 10 percent of the mean, respectively, with 99.4% of all results meeting the laboratory criterion of 15 percent.

TABLE E.1 FRAMATOME ANP INTRALABORATORY AND INTERLABORATORY RESULTS - 2002

• This category also contains those samples having a verified zero concentration which were analyzed and found not to contain detectable levels of the nuclide of interest.

The results of the numerous intercomparisons performed during 2002 validate the quality of the analyses performed by Framatome ANP.

Even though some of the analyses may not be directly applicable to samples and analyses encountered in a REMP program, the high degree of compliance reflects the overall quality of laboratory controls in place at Framatome ANP.

E.4 Framatome ANP Blind Duplicate Program A total of 28 paired samples were submitted for analysis during 2002. The database used for the duplicate analysis consisted of paired measurements of 25 gamma-emitting nuclides, H-3, Sr-89, Sr-90, low-level 1-131, and gross beta. The sample media included milk, groundwater, sea/river water, food crops, marine algae, and mussel meat.

A dual-level criterion for agreement has been established.

If the paired measurements fall within +/- 15% of their average value, then agreement between the measurements has been met.

If the value falls outside of the +/- 15% criteria, then a two standard deviation range (95 percent Page 94 Fraction of Measurements Total Number of within deviation range Category Measurements

+/-5%

+/- 10%

+/- 15%*

Framatome ANP INTRALABORATORY ANALYSES Accuracy 510 80.0%

93.7%

99.2%

Precision 114 85.1%

91.2%

97.4%

ANALYTICS INTERLABORATORY ANALYSES Accuracy 339 59.3%

85.5%

99.1%

Precision 339 86.4%

97.3%

100.0%

NIST INTERLABORATORY ANALYSES Accuracy 21 l

47.6%

100.0%

100.0%

Precision 21 100.0%

100.0%

100.0%

TOTAL COMBINED ANALYSES Accuracy 870 l

71.1%

90.7%

99.2%

Precision 474 1

86.7%

96.0%

99.4%

confidence level) is established for each of the analyses. If the confidence intervals for the two analyses overlap, agreement is obtained.

From the 28 paired samples, 690 paired duplicate measurements were analyzed during 2002.

Out of these measurements, 684 (99.1%) fell within the established criteria discussed above.

No trend was evident with respect to repeated failings of measurements for the listed radionuclides and media.

Four of the 'failures' involved gamma spectroscopy pairings for nuclides in which there was no detectable radioactivity in either of the paired measurements.

E.5 Framatome ANP Environmental TLD Measurements Quality control testing was performed during 2002 to demonstrate the performance of the routine environmental TLD processing by Framatome ANP.

The quality of the dosimetric results is evaluated relative to independent third party testing and intemal performance testing.

These tests were performed independent of the processing of environmental TLDs at Framatome ANP.

In all of these tests, dosimeters were irradiated to known doses and submitted to Framatome ANP for processing as unknowns.

The quality control programs provide a statistical measure of accuracy, precision and consistency of the processing against a reliable standard, which in turn points out any trends or changes in performance.

Framatome ANP began performance testing of the Panasonic environmental TLDs in July 1987. The testing included internal performance testing and testing by an independent third party.

A +/- 30% accuracy acceptance standard under field conditions is recommended by ANSI 545-1975, "American National Standard Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry (Environmental Applications)." The Laboratory Quality Control Audit Committee (LQCAC) adopted acceptance criteria for accuracy and precision to be used in 2002 on November 13, 1987.

Recognizing the inherent variability associated with each dosimeter type, control limits for accuracy and precision of +/- 3 sigma plus 5% (for bias) were set by the LQCAC. The actual magnitude of the 3 sigma plus 5% control limits depends on the historical perfomance of each type of dosimeter, with each response being indicative of random and systematic uncertainties, combined with any deviation attributable to TLD operation.

The results of the TLD quality control programs are reported in the categories of accuracy and precision. Accuracy was calculated by comparing each discrete reported dose to the known or delivered dose. The deviation of individual results relative to the mean reported dose is used as a measure of precision.

The quality control program implemented for dosimetry processing indicated good precision and accuracy in the reported values.

In 2002, there were 90 quality control tests.

All 42 environmental TLDs tested during January - June 2002 were within the control limits for both accuracy and precision.

The comparisons yielded a mean accuracy of +0.86%.

The comparisons exhibited a precision value with an overall standard deviation of 1.34%. The 48 TLDs tested in July - December 2002 showed a mean accuracy of +1.95%. TLDs measured during the second semiannual period exhibited a precision value with a standard deviation of 1.35%, well within the acceptance criteria. In total, all 84 environmental TLDs tested during 2002 were within the control limits for both accuracy (+/- 20.1%) and precision (+/- 12.8%).

Page 95

E.6 Conclusions Laboratory analysis results for the independent Interlaboratory Comparison programs (i.e.,

EPA, Analytics, DOE, and NIST), the Framatome ANP intralaboratory quality control program, and the sponsor companies blind duplicate program met the laboratory criterion of less than 15% deviation in more than 96% of all cases.

The environmental TLD measurements for intralaboratory and independent third party comparisons resulted in both mean accuracy and precision within 2% deviation.

Therefore, the quality assurance programs for the PNPS Radiological Environmental Monitoring Program indicated that the analyses and measurements performed by the Framatome ANP Environmental Laboratory during 2002 exhibited acceptable accuracy and precision.

Page 96

APPENDIX F J.A. FITZPATRICK INTERLABORATORY COMPARISON PROGRAM F.1 Program Description Radiological Effluent Technical Specification (RETS) and Radiological Effluent Controls (RECS) require that each licensee participate in an Interlaboratory Comparison Program.

The Interlaboratory Comparison Program shall include sample media for which samples are routinely collected and for which comparison samples are commercially available.

Participation in an Interlaboratory Comparison Program ensures that independent checks on the precision and accuracy of the measurement of radioactive material in the environmental samples are performed as part of the Quality Assurance Program for environmental monitoring. To fulfill the Technical Specification requirement for an Interlaboratory Comparison Program, the JAF Environmental Laboratory has engaged the services of two independent laboratories to provide quality assurance comparison samples. The two laboratories are Analytics, Incorporated in Atlanta, Georgia and the U.S. Department of Energy's Environmental Measurements Laboratory (EML) in New York City.

Analytics supplies requested sample media as blind sample spikes, which contain certified levels of radioactivity unknown to the analysis laboratory. These samples are prepared and analyzed using standard laboratory procedures. The results are submitted to Analytics, which issues a statistical summary report.

The JAFNPP Environmental Laboratory uses predetermined acceptance criteria methodology for evaluating the laboratory's performance for Analytic's sample results.

In addition to the Analytics Program, the JAF Environmental Laboratory participated in the Environmental Measurements Laboratory (EML) Quality Assessment Program (QAP).

EML supplies sample media as blind sample spikes to approximately 127 laboratories worldwide.

These samples, containing a spiked amount of low-level activity, are analyzed using standard laboratory procedures. The results are submitted to the Environmental Measurements Laboratory for statistical evaluation. Reports are provided to each participating laboratory, which provide an evaluation of the laboratory's performance.

During 2002, tritium analyses for the JAF Environmental Laboratory were performed by Framatome, ANP.

Page 97

F.2 Proaram Schedule TABLE F.1 2002 QA Program Schedule Water Gross Beta 0

2 2

Water Tritium 1

2 3

Water 1-131 2

0 2

Water Mixed Gamma 2

2 4

Air Gross Beta 2

2 4

Air 1-131 2

0 2

Air Mixed Gamma 2

2 4

Milk 1-131 2

0 2

Milk Mixed Gamma 2

0 2

Soil Mixed Gamma 1

0 1

'/ no;tirs I

4 A

t1 17

[101 27 F.3 Acceptance Criteria Each sample result is evaluated to determine the accuracy and precision of the laboratory's analysis result. The evaluation method for the QA sample results is dependent on the supplier of the sample. The sample evaluation methods are discussed below.

F.3.1 Analytics Sample Results Samples provided by Analytics are evaluated using what is specified as the NRC method. This method is based on the calculation of the ratio of results reported by the participating laboratory (QC result) to the Vendor Laboratory Known Value (reference result).

An Environmental Laboratory analytical result is evaluated using the following calculation:

The value for the error resolution is calculated.

The error resolution =

Reference Result Reference Results Error Using the appropriate row under the Error Resolution column in Table F.2 below, a corresponding Ratio of Agreement interval is given.

The value for the ratio is then calculated.

Ratio of Agreement =

QC Result Reference Result If the value falls within the agreement interval, the result is acceptable.

Page 98 l

v I

TABLE F.2 Ratio of Agreement EROMRESOLUTON RA IO OFAREEMENT:

<3 0.4 to 2.5 3.1 to 7.5 0.5 to 2.0 7.6 to 15.5 0.6 to 1.66 15.6 to 50.5 0.75 to 1.33 50.6 to 200 0.8 to 1.25

>200 0.85 to 1.18 Again, this acceptance test is generally referred to as the "NRC" method. The acceptance criteria is contained in JAFNPP procedure DVP-04.01 and was taken from the Criteria of Comparing Analytical Results (USNRC) and Bevington, P.R., Data Reduction and Error Analysis for the Physical Sciences, McGraw-Hill, New York, (1969). The NRC method generally results in an acceptance range of approximately +25% of the Known Value when applied to sample results from the Analytics Inc. Interlaboratory Comparison Program.

This method is used as the procedurally required assessment method and requires the generation of a nonconformity report when results are unacceptable.

F.3.2 Environmental Measurements Laboratory (EML)

The laboratory's analytical performance is evaluated by EML based on the historical analytical capabilities for individual analyte/matrix pairs. The statistical criteria for Acceptable Performance, "A", has been chosen by EML to be between the 15th and 85th percentile of the cumulative normalized distribution, which can be viewed as the middle 70% of all historic measurements.

The Acceptable With Waminq criteria, "W", is between the 5th and 15th percentile and between the 85th and 95th percentile.

In other words, the middle 70% of all reported values are acceptable, while the other 5th-15th (10%) and 85th-95th percentiles (10%) are in the waming area. The Not Acceptable criteria, "N", is established at less than the 5th percentile and greater than the 95th percentile, that is, the outer 10% of the historical data. Using five years worth of historical analytical data, the EML, determined performance results using the percentile criteria summarized below:

Result Cumulative Normalized Distribution Acceptable ("A")

15% - 85%

Acceptable with Waming ('W")

5% - 15% or 85% - 95%

Not Acceptable ("N")

<5% or >95%

F.4 Program Results Summary The Interlaboratory Comparison Program numerical results are provided on Table F.7.

F.4.1 Analytics QA Samples Results Seventeen QA blind spike samples were analyzed as part of Analytics' 2002 Interlaboratory Comparison Program. The following sample media were evaluated as part of the comparison program.

Air Charcoal Cartridge,1-131 Air Particulate Filter, Mixed Gamma Emitters/Gross Beta Page 99

Water, 1-131/Mixed Gamma Emitters/Tritium Soil, Mixed Gamma Emitters Milk, l-131 Mixed Gamma Emitters Vegetation, Mixed Gamma Emitters The JAF Environmental Laboratory performed 79 individual analyses on the seventeen QA samples. Of the 79 analyses performed, 77 were in agreement using the NRC acceptance criteria for a 97.5% agreement ratio.

Sample non-conformities are discussed in Section F.4.2.

F.4.2 Analvtics Sample Nonconformities F.4.2.1 Analvtics Sample E-3286-05, Cr-51 in Milk: Nonconformity No. 02-09 A spiked mixed gamma in milk sample supplied by Analytics, Inc., was analyzed in accordance with standard laboratory procedures.

The sample contained a total of nine radionuclides for analysis. Nine of the nine radionuclides present were quantified. Eight of the nine radionuclides were quantified within the acceptable range. The results for Cr-51 were determined to be outside the QA Acceptance Criteria. The milk sample was analyzed on three different detectors with the mean Cr-51 results reported as 176.7 pCVI. The known results for the sample was 227 pCVI as..'

determined by the supplier.

An evaluation of the Cr-51 result was performed. The spectrum and peak search results were examined with no abnormalities identified. Cr-51 decays by electron capture with a 27.7 day half-life and a gamma ray energy of 320 KeV with a yield of 9.8%. No secondary gamma energies are produced in the Cr-51 decay scheme. This low gamma energy yield and short half-life will result in very low net counts for samples containing environmental levels of Cr-51. The average net count rate of the three analyses ranged from a high of 1.9 counts per minute to a low of 0.68 counts per minute. One of the three reported results was 244 pCVI and resulted in an agreement when compared to the known of 227 with a ratio of 1.07. This result had an associated counting error of 13.1%. The remaining two counts had ratios of 0.55 and 0.71 with high associated counting errors of 29.3% and 21.2% respectively.

The combination of the following; low sample activity, very small net count rate, short half-life, low gamma energy, and small gamma yield, resulted in an inaccurate sample result. The wide range of the associated counting errors demonstrates the low confidence level in the reported results. The poor analytical results for this sample are not routine and do not indicate a programmatic deficiency in the analysis of Cr-51 in milk samples or other environmental media.

Confidence in the accurate analysis of Cr-51 can be demonstrated by other Cr-51 analytical results, both in the sample results for the 2002 QA program and historical Cr-51 QA results.

The Cr-51 results for the other Quality Assurance samples analyzed as part of the 2002 Interlaboratory Comparison Program were all acceptable and are summarized below:

Page 100

TABLE F.3 2002 Cr-51 Results 3ample--lD --:

Mediun 4 AF

• -; XE-

-Lab Rati.

E-3051-05 WATER pCVliter 234+/-20 198+/-10 1.18 E-3284-05 WATER pCVliter 324+/-23 304+/-15 1.07 E-3052-05 FILTER pCi/filter 187+/-13 203+/-10 0.92 E-3285-05 FILTER pCVfilter 157+/-13 141 +/-7 1.11 E-3215-05 MILK pCVliter 239+/-19 235+/-12 1.02 E-3218-05 VEGETATION pCVkg 408+23 403+/-20 1.01 E-3216-05nr Cl ni/le IR7M-7r, 91g1 1Q, 1fl 1.07 A review of historical QA data for 2001 was also performed to determine if this is a recurring systematic error or bias. In 2001, eleven QA samples were analyzed which contained Cr-51. The mean ratio for these samples relative to the known (reference) value is 98.5. There were two Cr-51 nonconformities in the 2001 Interlaboratory Comparison Program, and they were determined not to be systematic or programmatic errors. The historic Cr-51 nonconformities were a low percentage of the overall gamma spectroscopy QA program and have been determined to be the result of the low sample activity and low gamma yields for Cr-51 in the spiked samples.

Analytical methods and system calibrations are not the cause of this nonconformity, based on the accurate results achieved for the analysis of the other eight radionuclides present in the sample.

No corrective actions were implemented as a result of this nonconformity.

F.4.2.2 Analytics Samole E-3285-05: Nonconformity No. 02-08. Air Particulate Gamma Emitters The gamma spectral analysis of sample E-3285-05 resulted in the quantification of nine radionuclides.

Results for eight of the identified radionuclides were in agreement with the reference value and one measurement was in disagreement. The Fe-59 results had a calculated ratio of 1.29, which places the results outside the acceptable limit. The sample ratio of 1.29 demonstrates that the Fe-59 sample result is biased high. An evaluation of the Fe-59 result was performed. Fe-59 concentrations were detected in three of the three analyses reported for this sample. The spectrum and peak search results were examined with no abnormalities identified.

Fe-59 decays with a 44.5 day half-life with two gamma ray energies of 1099 KeV and 1291 KeV with yields of 57% and 43% respectively. Fe-59 concentrations were identified at both the 1099 KeV and 1291 KeV peaks in all three analysis with the following results.

TABLE F.4 Nonconformity No. 02-08 Fe-59 Results LJLMAUJ Number redA I

1099 KeV 1291 KeV Mean Concentration 1

69.9 79.3 73.5 2

68.5 61.4 65.4 8

74.7 73.0 73.9 M50ean -pCifilterS 71.0 71.2 70.9 Rao

=1.29 1.30 1.29 Page 101

There were no significant differences for the activity that was measured at either of the two Fe-59 peaks. The number of total counts measured in both of these peaks may be biased high due to coincidence counting as the result of other radionuclides that are present in the sample. The relatively low gamma yield and low activity of 55 pCi/Kg may have also contributed to the inaccuracy of this sample result.

Fe-59 was measured in seven other samples analyzed as part of the 2002 Interlaboratory Comparison Program. All of these samples were in agreement with the reference laboratory with a mean agreement ratio of 1.09. This mean ratio of greater than 1.09 would indicated that these samples were biased high and the bias was the possible result of coincidence counting from other radionuclides in the sample. The amount of bias experienced in most Interlaboratory Comparison Program samples due to coincidence counting has been limited to less than 20 percent and has resulted in sample results which were statistically acceptable when compared to the reference value. Changes to the radionuclide library were made in 2001 to direct the gamma spectroscopy software to calculate the mean concentration value based on both the 1099 KeV and 1291 KeV peaks. In most gamma spectra, this has reduced the effect of the coincidence count on the Fe-59 analytical results as the 1291 KeV peak may be less affected by the coincidence counting in multiple radionuclide samples.

No corrective actions were implemented as a result of this nonconformity.

F.4.3 Environmental Measurements Laboratory (EML)

In 2002, JAF Environmental Laboratory participated in both the EML Quality Assessment Programs, QAP-56 and QAP-57. Sample sets consisted of the following sample media:

Water-Gross Beta/Mixed Gamma Emitters Water' -Tritium Air Particulate Filter-Mixed Gamma Emitters/Gross Beta A total of 10 samples containing 18 individual radionuclides were evaluated for the samples included in QAP-56 and QAP-57.

Using the EML acceptance criteria, 17 of 18 radionuclides analyses (94.4%) were evaluated to be acceptable. Results for the EML Cross Check Program can be viewed on-line at vw.eml.doe gov. A summary of the JAF Environmental Laboratory results is as follows:

TABLE F.5 JAF Environmental Lab Summary

4
Ax s;W Air 10 10 0

Water 8

7 1

Totali t,'-..'

'18 17 1

Percertage

'.'^.

94.4%

5.6%

Page 102

F.4.3.1 EML Samole QAP-56. Cs-1 34 in Water Nonconformity No. 02-02 The QAP-56 gamma in water sample contained three radionuclides for evaluation; Cs-137, Cs-134, and Co-60. Two of the three radionuclides present, Co-60 and Cs-137, were quantified with agreement ratios of 1.02 and 0.99, respectively. The JAF laboratory reported a Cs-134 result of 2.6 + 0.5 Bq/L (70.3 pCiI). The EML known activity was reported as 3.357 Bq/L (90.74 pCiVL). The agreement ratio for the Cs-134 analysis was 0.77, which placed the result outside the acceptable range. The cause of the nonconformity is attributed to several factors. The concentration of Cs-134 in the sample was very small at 3.36 Bq/L and resulted in a one sigma counting error of approximately 20%. By comparison the one sigma counting errors for the Co-60 result was 1.0% and the one sigma counting error for the Cs-137 result was 1.3%. The high associated counting error was the result of the low count rate measured for the Cs-134 peak and resulted in poor counting statistics. The measurement of the Cs-134 concentration in this sample was further complicated by the presence of an interference peak at 609 KeV. The combination of the low concentration and interference from the 609 KeV peak were both contributing factors in the non-conforming result. A review of the EML summary statistics for this sample showed a relatively high failure or nonconformity rate for other laboratores participating in this sample comparison. Their statistics are as follows:

TABLE F.6 EML Summary QAP-56 Cs-134 in Water O

sotope No..b X. ::::.x::: °in

}-Swth --

%nAo:

tn Io::

>. or v

. j I

Reporting A~~gr en Warning Aremn Cs-134 116 60.3 23.3 I

16.40 Cs-137 146 87.0 11.0 2.10 As the table shows for the 116 laboratories reporting results, only 60.3% were in agreement with the known value. 16.4% of the participating laboratories were not in agreement and 23.3% of laboratories reporting results were in the waming range for the reported results. An additional 30 laboratories reported no results for the Cs-1 34 concentration. By comparison, the statistics for the Cs-1 37 concentration showed a failure rate of only 2.1 % and acceptable results for 87% of the results reported for the study.

The Cs-1 34 results reported for the 2002 QAP-57 study, conducted in the second half of the year, were acceptable with an agreement ratio of 1.0. Cs-134 was measured in nine other comparison samples analyzed as part of the 2002 Interlaboratory Comparison Program. The mean ratio for all the reported results was 0.96 and there were no nonconformities. These results demonstrate that there is no programmatic or systematic error inherent to the analysis of Cs-134 in environmental sample media.

No corrective action was implemented as a result of this nonconformity.

Page 103

TABLE F.7 INTERLABORATORY COMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filters (pCifilter)

AIR pCVfilter GROSS BETA 27.5+/-1.3 24.8+/-1.3 25.9+/-1.3 Mean - 26.1 +/-0.8 12/05/02 E-3467-05 AIR pCVfilter GROSS 114.7+/-1.2 127+/-f6 0.90, A BETA 114.3+/-1.2 Mean = 114.0+/-0.7 (1)

Results reported as activity 1 sigma.

(2)

Results reported as activity +/- 3 sigma.

(3)

Ratio = Reported/Analytics (See Section F.3).

(*)

Sample provided by Analytics, Inc.

(A)

Evaluation Results, Acceptable.

Page 104 06/13/02 E-3214-05

TABLE F.7(Continued)

INTERLABORATORY COMPARISON PROGRAM Tritium Analysis of Water (pCi/liter) pCVliter 9880+/-140 10130+/-140 Mean = 10030+/-81 h

I I

(1)

Results reported as activity 1 sigma. Sample Analyzed by Framatome, ANP.

(2)

Results reported as activity + 3 sigma.

(3)

Ratio = Reported/Analytics (See Section F.3).

(*)

Samples provided by Analytics, Inc.

(A)

Evaluation Results, Acceptable.

Page 105

TABLE F.7 (Continued)

INTERLABORATORY COMPARISON PROGRAM Iodine Analysis of Water, Air and Milk VV I cnI-1 pCVliter UO.:.2 1.0 57.6+/-1.8 60.9+/-1.2 Mean = 59.0+/-0.9 06/13/02 E-3217-05 AIR 1-131 80.2+/-7.4 93+/-5 1.06, A pCVcc 104.0+/-8.1 112.0+/-8.5 Mean = 98.7+/-4.6 06/13/02 E-3215-05 MILK I-131t*

75.8+/-1.0 87+/-4 0.90, A pCi/liter 80.4+/-1.2 76.8+/-1.3 Mean = 77.7+/-0.7 09/12/02 E-3287-05 AIR 1-131 84.4+/-7.1 81+/-4 1.01, A pCi/cc 78.8+/-8.8 83.2+/-7.0 Mean = 82.4+/-4.4 09/12/02 E-3284-05 WATER 1-131 **

76.8+/-1.2 79+/-4 0.95, A pCi/liter 72.6+/-1.2 75.3+/-1.1 Mean = 74.9+/-0.7 09/12/02 E-3286-05 MILK 1-131**

69.8+/-1.5 80+/-4 0.90, A pCiliter 73.8+/-1.3 72.1+/-1.5 M ean = 71.9+/-0.8_

Results reported as activity +/- 1 sigma.

Results reported as activity +/- 3 sigma.

Ratio = Reported/Analytics (See Section F.3).

Samples provided by Analytics, Inc.

Result determined by Resin Extraction/Gamma Spectral Analysis.

Evaluation Results, Acceptable.

Page 106 (1)

(2)

(3)

(*)

(**)

(A)

TABLE F.7 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Water (pCi/liter) vvpiI _

pCi/liter 251.0+/-8.3 249.0+/-8.3 Mean = 249.0+/-5.0 Cr-51 222.0+/-35.5 198+/-10 1.18, A 249.0+/-35.6 232.0+/-33.4 Mean = 234.3+/-20.1 Cs-1 34 80.8+/-5.1 91+/-5 0.89, A 82.6+/-4.3 79.1+/-4.3 Mean = 80.8+/-2.6 Cs-137 184.0+/-6.6 197+/-10 0.94, A 183.0+/-f6.4 191.0+/-6.4 Mean = 186.0+3.7 Mn-54 183.0+/-6.8 166+/-8 1.08, A

.172.0+/-f6.4 185.0+/-6.4 Mean = 180.0+/-3.8 Fe-59 91.4+/-7.0 86+/-4 1.13, A 110.0+/-6.7 89.8+/-6.1 Mean = 97.1 3.8 Zn-65 160.0+/-11.1 164+/-8 1.04, A 182.0+/-9.9 167.0+/-10.6 Mean = 169.7+/-f6.1 Co-60 109.0+/-4.3 124.0+/-4.3 110.0+/-4.0 Mean = 114.3+/-2.4 117+/-6 (1)

Results reported as activity +/- 1 sigma.

(2)

Results reported as activity + 3 sigma.

(3)

Ratio = Reported/Analytics (See Section F.3).

(*)

Sample provided by Analytics, Inc.

(A)

Evaluation Results, Acceptable.

Page 107 03/14/02 E-3051 -05 0.97, A

TABLE F.7 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Water (pCVIlter)

VYm I fl pCVliter 40V.Uz.0 221.0+/-7.6 224.0+/-9.7 Mean = 225.0+/-5.1 Cr-51 321.0+/-38.1 304+/-15 1.07, A 264.0_34.9 389.0_46.1 Mean = 324.7+/-23.1 Cs-1 34 172.0+/-6.9 176+/-9 0.97, A 171.0+/-f6.4 167.0+/-7.9 Mean = 170.0+/-4.1 Cs-1 37 150.0+/-6.4 169+/-8 0.98, A 171.0+/-6.2 174.0+/-7.9 Mean = 165.0+/-4.0 Mn-54 208.0+/-7.1 204+/-10 1.07, A 217.0+/-7.2 232.0+/-9.1 Mean = 219.0+ 4.5 Fe-59 120.0+/-7.0 119+/-6 1.07, A 133.0+/-7.1 127.0+/-8.8 Mean = 126.7+/-4.5 Zn-65 271.0+/-13.1 251+/-13 1.04, A 272.0+/-12.8 242.0+/-15.9 Mean = 261.7+8.1 Co-60 191.0+/-5.3 199+/-10 0.95, A 185.0+/-5.3 191.0+/-6.6 Mean = 189.0+/-3.3 Co-58 130.0+/-6.2 139.0+/-6.1 130.0+/-8.0 Mean = 133.0+/-3.9 130+/-7 1.02, A (1)

Results reported as activity +/- 1 sigma.

(2)

Results reported as activity + 3 sigma.

(3)

Ratio = Reported/Analytics (See Section F.3).

(*)

Sample provided by Analytics, Inc.

(A)

Evaluation Results, Acceptable.

Page 108

TABLE F.7 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Air Particulate Filters (pCi/filter)

(1)

Results reported as activity 1 sigma.

(2)

Results reported as activity +/- 3 sigma.

(3)

Ratio = Reported/Analytics (See Section F.3).

(*)

Sample provided by Analytics, Inc.

(A)

Evaluation Results, Acceptable.

Page 109

~R FER ENCE mAT.

N...

R X..ED 03/14/02 E-3052-05 FILTER Ce-141 236.0+/-5.8 248+/-12 0.94, A pCi/filter 226.0+5.6 236.0+/-6.5 Mean = 232.0+/-3.5 Cr-51 186.0+/-22.2 203+/-10 0.92, A 217.0_22.3 158.0_24.2 Mean = 187.0+/-13.2 Cs-1 34 75.7+/-4.7 93+/-5 0.89, A 93.5+/-4.9 80.5+/-5.7 Mean = 83.2+2.9 Cs-1 37 205.0+/-6.4 202+/-10 1.00, A 204.0+/-6.4 193.0+/-7.3 Mean = 200.7+/-3.9 Mn-54 175.0_6.3 170+/-9 1.04, A 178.0+/-6.5 178.0+/-7.6 Mean = 177.0+/-4.0 Fe-59 93.9+/-6.5 88+/-4 1.11, A 98.9+/-6.9 101.0+/-7.9 Mean = 97.9+/-4.1 Zn-65 178.0+/-11.1 168+/-8 1.02, A 169.0+/-11.2 167.0+/-12.9 Mean = 171.3+/-6.8 Co-60 113.0+/-4.3 120+/-6 0.98, A 120.0+/-4.6 121.0+/-5.3 Mean = 118.0+2.7

TABLE F.7 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis of Air Particulate Filters (pCVfilter) 1 U.U+/-Q.L 104.0+/-4.3 109.0+/-4.1 Mean = 107.3+2.4 Cr-51 159.0+21.4 141+/-7 1.11, A 175.0+/-22.5 137.0+/-21.3 Mean = 157.0+/-12.6 Cs-1 34 82.8+/-5.0 82+/-4 1.02, A 82.60+/-5.2 87.50+/-4.9 Mean = 84.3+/-2.9 Cs-137 92.2+/-4.7 79+/-4 1.16, A 91.2+/-5.0 91.2+/-4.6 Mean = 91.5+2.8 Mn-54 114.0+/-5.6 95+/-5 1.20, A 116.0+/-5.8 112.0+/-5.4 Mean = 114.0+/-3.2 Fe-59 73.5+/-f6.0 55+/-3 1.29, D 65.4+/-6.5 NC-02-08 73.9+/-5.9 Mean = 70.9+/-3.5 Zn-65 140.0+/-10.2 117+/-6 1.24, A 143.0+/-10.8 153.0+/-10.4 Mean = 145.3+/-6.0 Co-60 91.2+/-4.1 92+/-5 1.04, A 98.0+/-4.3 99.4+/-4.2 Mean = 96.2+2.4 Co-58 76.0+/-4.7 72.0+/-4.9 65.7+/-4.4 Mean = 71.2+9.7 60+/-3 I

I I

1.18, A Results reported as activity 1 sigma.

Results reported as activity + 3 sigma.

Ratio = Reported/Analytics (See Section F.3).

Sample provided by Analytics, Inc.

Evaluation Results, Acceptable.

Evaluation Results, Disagreement.

Nonconformity Report Number.

Page 110 pC Vfilter (1)

(2)

(3)

(*)

(A)

(D)

(NC)

TABLE F.7 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Milk (pCiAiter) pCiiter 92.2+/-7.2 93.5_5.9 82.7+/-6.7 Mean = 89.5+/-3.8 Cr-51 230.0+/-33.5 235+/-12 1.02, A 206.0+/-30.6 282.0+/-32.8 Mean = 239.3+18.7 Cs-134 111.0+/-5.4 120+/-6 0.94, A 112.0+/-5.3 115.0+/-5.1 Mean = 112.7+3.0 Cs-1 37 93.9+/-5.1 91+/-5 0.99, A 88.0+/-4.8 87.5+/-5.1 Mean = 89.8+2.9 Mn-54 98.8+/-5.3 95+/-5 1.03, A 93.1+/-5.1 103.0+/-5.3 Mean = 98.3+3.0 Fe-59 83.3+/-6.4 81+/-4 1.06, A 88.8+/-6.4 84.4+/-6.7 Mean = 85.5+3.8 Zn-65 187.0+/-11.7 180+/-9 0.99, A 157.0+/-10.4 192.0+/-11.7 Mean = 178.7+/-6.5 Co-60 115.0+/-4.4 125+/-6 0.97, A 124.0+/-4.4 124.0+/-4.4 Mean = 121.0+/-2.5 Co-58 92.4+/-5.6 99.4+/-5.3 93.8+/-5.1 Mean = 95.2+/-3.1 100+/-5 i

i I

I 0.95, A (1)

Results reported as activity +/- 1 sigma.

(2)

Results reported as activity +/- 3 sigma.

(3)

Ratio = Reported/Analytics (See Section F.3).

(*)

Sample provided by Analytics, Inc.

(A)

Evaluation Results, Acceptable.

Page 111

TABLE F.7 (Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Milk (pCi/liter) 153.0+/-8.6 162.0+/-7.0 Mean = 158.0+/-4.3 Cr-51 244.0+32.0 227+/-11 0.78, D 125.0+36.6 NC 161.0+/-34.1 09 Mean = 176.7+/-1 9.8 Cs-134 120.0+/-5.7 132+/-7 0.89, A 118.0+/-7.0 115.0+/-5.6 Mean = 117.7+/-3.5 Cs-137 111.0+/-5.5 127+/-6 0.95, A 129.0+/-6.9 124.0+/-5.6 Mean = 121.3+/-3.5 Mn-54 159.0_6.2 152+/-8 1.00, A 146.0+/-7.6 151.0_6.0 Mean = 152.0+/-3.8 Fe-59 93.7_6.5 89+/-4 1.08,A 102.0+/-8.4 91.8+/-6.4 Mean = 95.8+/-4.1 Zn-65 192.0+/-11.4 187+/-9 1.01, A 179.0+/-14.9 192.0+/-11.2 Mean = 187.7+/-7.3 Co-60 143.0+/-4.8 149+/-7 0.97, A 145.0+/-6.0 147.0+/-4.7 Mean = 145.0+/-3.0 Co-58 98.1+/-5.2 99.4+/-7.0 104.0+/-5.4 Mean = 100.5+/-3.4 97+/-5 1.04, A S -

Results reported as activity +/- 1 sigma.

Results reported as activity +/- 3 sigma.

Ratio = Reported/Analytics (See Section F.3).

Sample provided by Analytics, Inc.

Evaluation Results, Acceptable.

Evaluation Results, Disagreement.

Nonconformity Report Number.

Page 112 pCUliter (1)

(2)

(3)

')

(A)

(D)

(NC)

TABLE F.7(Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Soil (pCi/gram) 0.114+0.026 0.186+0.024 0.0141+/-0.022 Mean = 0.147+0.014 Cr-51 0.427+0.142 0.318+0.016 1.16, A 0.349+/-0.125 0.334+0.122 Mean = 0.370+/-0.075 Cs-1 34 0.158+0.020 0.163+/-0.008 0.98, A 0.126+0.020 0.192+/-0.020 Mean = 0.159+/-0.012 Cs-1 37 0.240+/-0.019 0.208+/-0.010 1.05, A 0.214+/-0.022 0.204+/-0.020 Mean = 0.219+/-0.012 Mn-54 0.133+/-0.015 0.129+0.006 1.09, A 0.157+/-0.017 0.132+/-0.018 Mean = 0.141 +/-0.010 Fe-59 0.107+0.027 0.109+0.005 1.07, A 0.099+/-0.029 0.145+0.030 Mean = 0.117+/-0.016 Zn-65 0.227+/-0.027 0.243+/-0.012 1.09, A 0.292+/-0.034 0.279+/-0.034 Mean = 0.266+0.019 Co-60 0.156+/-0.012 0.168+/-0.008 0.92, A 0.165+0.014 0.142+/-0.013 Mean = 0.154+/-0.008 Co-58 0.115+/-0.016 0.114+/-0.017 0.125+0.017 Mean =0.118+/-0.010 I

I 0.135+0.007 0.87,A Results reported as activity +/- 1 sigma.

Results reported as activity +/- 3 sigma.

Ratio = Reported/Analytics (See Section F.3).

Sample provided by Analytics, Inc.

Evaluation Results, Acceptable.

Page 113

.JLJ IL.

pCVgram (1)

(2)

(3)

(*)

(A)

TABLE F.7(Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Vegetation (pCi/gram)

U. I I Q'.UVD 0.161+/-0.007 0.176+/-0.008 Mean = 0.171+/-0.004 Cr-51 0.414+/-0.038 0.403+/-0.020 1.01, A 0.424+/-0.040 0.385+0.042 Mean = 0.408+/-0.023 Cs-134 0.227+0.007 0.206+0.010 1.09, A 0.218+0.007 0.229+0.008 Mean = 0.225+0.004 Cs-137 0.162+/-0.006 0.156+0.008 1.06, A 0.154+0.007 0.178+/-0.007 Mean = 0.165+/-0.004 Mn-54 0.186+/-0.007 0.163+/-0.009 1.15, A 0.184+/-0.007 0.193+/-0.001 Mean = 0.188+/-0.004 Fe-59 0.154+/-0.009 0.138+/-0.007 1.09, A 0.141+/-0.009 0.156+0.010 Mean = 0.150+/-0.006 Zn-65 0.327+0.016 0.308+0.015 1.07, A 0.343+/-0.016 0.324+0.017 Mean = 0.331+/-0.009 Co-60 0.233+/-0.006 0.213+/-0.011 1.08, A 0.229+0.006 0.230+/-0.006 Mean = 0.231+/-0.004 Co-58 0.187+/-0.007 0.183+0.007 0.184+/-0.008 Mean = 0.185+/-0.004 0.171+/-0.009 1.08, A (1)

Results reported as activity +/- 1 sigma.

(2)

Results reported as activity +/- 3 sigma.

(3)

Ratio = Reported/Analytics (See Section F.3).

(*)

Sample provided by Analytics, Inc.

(A)

Evaluation Results, Acceptable.

Page 114 pCi/gram

TABLE F.7(Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Water (Bq/liter) 4.0

.U 2.4+/-0.8 3.0_0.6 2.7+/-1.1 2.3+/-1.4 Mean = 2.6+/-0.5 v.I/,

Li NC-02-02 Cs-137 57.1+1.8 56.1+2.93 0.99, A 52.9+/-1.7 57.0+1.7 53.7+1.7 55.5+1.9 Mean = 55.7+/-0.8 1

1 Co-60 352.0+/-3.0 355.9+/-3.1 353.0+/-3.0 352.6+/-3.8 354.5+/-3.6 Mean = 353.8+/-1.5 347.3+/-12.4 1.02, A Results reported as activity +/- 1 sigma.

Ratio = Reported/Environmental Measurements Lab (EML)(See Section F.3).

Sample provided by Environmental Measurements Lab., Dept. of Energy.

Evaluation Results, Acceptable.

Evaluation Results, Disagreement.

Nonconformity Report Number.

Page 115 vv I r Bq/liter (1)

(2)

()

(A)

(D)

(NC)

S

TABLE F.7(Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Water (Bqliter)

(1)

Results reported as activity +/- 1 sigma.

(2)

Ratio = Reported/EML(See Section F.3).

(*)

Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A)

Evaluation Results, Acceptable.

Page 116

,.jA EN IE u 3 REFERENC i

E 0

09/01/02 OAP-57 WATER Cs-134 62.9_2.2 60.2+/-1.86 1.01, A Bq/liter 61.1+/-2.3 59.9+/-2.2 57.7+/-2.7 60.7+/-1.7 62.2+/-2.1 M ean = 60.7+/--0.9 Cs-1 37 81.0+2.5 81.4+/-4.28 0.95, A 77.7+/-2.5 78.1+/-2.4 73.3+/-2.9 77.8+/-1.8

78. 8+/-2.5 Mean = 77.7+/-1.0 Co-60 265.7+/-3.4 268.7+/-9.7 1.00, A 271.6+/-3.6 275.7+/-3.5 258.6+/-4.2 268.3+/-2.5 270.5+/-3.4

_______M ean_= 268.4+/-1.4

TABLE F.7(Continued)

INTERLABORATORY COMPARISON PROGRAM Gamma Analysis Air Particulate Filters (Bq/filter)

I-IL I l Bq/filter ZOAMIu.4 29.5+/-0.4 30.0+/-0.4 29.6+/-0.5 29.2+/-0.4 Mean = 29.3+/-0.2 Mn-54 40.3+/-0.6 38.5+/-0.87 1.04, A 39.6+/-0.6 40.0+/-0.6 40.7+/-0.7 40.0+/-0.6 Mean = 40.0i0.3 1

Cs-1 37 28.2+/-0.5 28.2+/-0.70 0.99, A 28.0+/-0.5 27.5+/-0.5 27.8+/-0.5 27.8+/-0.4 Mean 27.9+/-0.2 09/01/02 QAP-57 FILTER Mn-54 58.1+/-1.0 52.2+/-1.17 1.11, A Bq/fifter 57.7+/-1.1 58.5+/-1.0 58.1+/-1.3 58.5+/-0.9 57.0+/-1.0 Mean = 58.0+/-0.4 Co-60 24.0+/-0.5 23.0+/-0.06 1.00, A 23.5+/-0.6 22.6+/-0.5 23.0+/-0.7 22.4+0.5 22.9+/-0.5 Mean = 23.1+/-0.2 Cs-1 37 33.6+/-0.7 32.5+/-u0.78 1.04, A 34.3+/-0.8 33.8+/-0.7 34.6+/-0.9 32.9+/-+0.7 34.2+/-0.7 M ean = 33.9+/-0.3 (1)

Results reported as activity +/- 1 sigma.

(2)

Ratio = Reported/EML (See Section F.3).

(*)

Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A)

Evaluation Results, Acceptable.

Page 117

TABLE F.7 Continued)

INTERLABORATORY COMPARISON PROGRAM Gross Beta Analysis of Water (Bq/liter)

Bq/liter BETA IuUI I

1125+/-17 1110+/-17 Mean = 1111+/-10 09/01/02 QAP-57 WATER GROSS 782.0+/-19.46 900.0+/-90.0 0.89, A Bq/liter BETA 787.0+/-19.50 823.0+/-19.87 Mean = 797.0+/-11.32 (1)

Results reported as activity +/- 1 sigma.

(2)

Ratio = Reported/EML (See Section F.3).

(*)

Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A)

Evaluation Results, Acceptable.

Page 118

TABLE F.7(Continued)

INTERLABORATORY COMPARISON PROGRAM Tritium Analysis of Water (Bqliter) 4 4 4 4 4 44

.-4 44 44.4:

4

_o 4

4

o.

t.=@44444 4

4 4

4 444 1

44444 0................

4,.,~~~

~~

E...4.

03/01/02 QAP-56 WATER H-3 325+/-5 283.7+/-3.38 1.11, A Bq/liter 310+/-6 313+/-7 Mean =316.0+/-3.4 09/01/02 QAP-57 WATER H-3 249+/-10 227.3+5.61 0.88, A Bq/liter 241+/-10 239+/-10 Mean = 243+/-6 (1)

Results reported as activity 1 sigma.

(2)

Ratio = Reported/EML (See Section F.3).

(*)

Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A)

Evaluation Results, Acceptable.

Page 119

TABLE F.7(Continued)

INTERLABORATORY COMPARISON PROGRAM Gross Beta Analysis of Air (Bq/filter)

Bq/filter 1.4 I t¶JAAJ 1.18+/-0.03 1.21+/-0.03 Mean = 1.20+0.02 09/01/02 QAP-57 AIR GROSS BETA 0.84+/-0.03 0.87+0.087 0.95, A Bq/filter 0.80+/-0.03 0.85+/-f0.03 Mean = 0.83+/-0.02 (1)

Results reported as activity 1 sigma.

(2)

Ratio = Reported/EML (See Section F.3).

(*)

Sample provided by Environmental Measurements Lab., Dept. of Energy.

(A)

Evaluation Results, Acceptable.

Page 120