ML021360494

Submittal of Radiological Environmental Monitoring Program Report for 2001 (Report 34)

ML021360494
Person / Time
Site:	Pilgrim
Issue date:	05/09/2002
From:	Riggs W Entergy Nuclear Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
2.02.036
Download: ML021360494 (102)

Text

SEn tergy Entergy Nuclear Generation Co.

Pilgrim Station 600 Rocky Hill Road Plymouth, MA 02360 William J. Riggs Director, Nuclear Assessment May 9, 2002 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 2001 (Report #34)

LETTER NUMBER:

2.02.036

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 2001 (Report #34).

Sincerely, PMK/dd

Attachment:

Radiological Environmental Monitoring Program Report for 2001 (Report #34) 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 202036

PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 Radiological Environmental Monitoring Program Report January 1 through December 31, 2001 "Entergy

Prepared by:.

Reviewed by:

Reviewed by:

Approved by:.

K.J. SejkoFa-a7" L

/

Coordinator: HP/Chemistry Support Manager, Technical Services Page 1 PILGRIM NUCLEAR POWER STATION Facility Operating License DPR-35 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT JANUARY 01 THROUGH DECEMBER 31, 2001 I

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Pilgrim Nuclear Power Station Radiological Environmental Monitoring Program Report January-December 2001 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 Vegetablefegetation 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 Quality Assurance Program Results Corrected 2000 Sediment Analyses Results Page 2 PAGE 5

7 7

8 9

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

Pilgrim Nuclear Power Station Radiological Environmental Monitoring Program Report January-December 2001 LIST OF TABLES TABLE TABLE TITLE PAGE 1.2-1 Radiation Sources and Corresponding Doses 8

1.3-1 PNPS Operating Capacity Factor During 2001 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 2001 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 Vegetable/Vegetation 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 2001 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 2001 87 E.1 Intralaboratory And Interlaboratory Results - 2001 94 F.1 Historical Plutonium-238 Sample Results 97 Page 3

Pilgrim Nuclear Power Station Radiological Environmental Monitoring Program Report January-December 2001 LIST OF FIGURES FIGURE FIGURE TITLE PAGE 1.3-1 Radioactive Fission Product Formation 11 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 Page 4

EXECUTIVE

SUMMARY

ENTERGY NUCLEAR PILGRIM NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT JANUARY 01 THROUGH DECEMBER 31, 2001 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, 2001. 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.

In July 1999, ownership and control of Pilgrim Station was transferred from Boston Edison Company to Entergy Nuclear Generation Company. Although the operating license of the plant was transferred with the ownership, no changes were made in the operation of the plant which would affect the environmental monitoring program or releases of radioactivity to the environment, as summarized in this report.

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 2001, there were 1,383 samples collected from the atmospheric, aquatic and terrestrial environments.

In addition, 427 exposure measurements were obtained using environmental thermoluminescent dosimeters (TLDs), and six exposure rate measurements were performed using a high-pressure ion chamber.

A small number of inadvertent issues were encountered during 2001 in the collection of environmental samples in accordance with the PNPS Offsite Dose Calculation Manual (ODCM).

Thirteen out of 440 TLDs were unaccounted for during the quarterly retrieval process.

However, the 427 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, 571 of 572 air particulate and charcoal cartridges were collected and analyzed as required. A full description of any discrepancies encountered with the environmental monitoring program is presented in Appendix D of this report.

There were 1,568 analyses performed on the environmental media samples. Analyses were performed by the Duke Engineering and Services Environmental Laboratory in Westborough, Massachusetts. Samples were analyzed as required by the PNPS ODCM.

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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, 2001.

A total of 31 vegetable gardens having an area of more than 500 square feet were identified within five kilometers (three miles) of PNPS.

No new milk or meat animals were located during the census. Of the 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 2001, 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. Only one sample of non-edible mussel shell collected in 2001 showed any detectable activity attributable to PNPS operations.

Offsite ambient radiation measurements using environmental TLDs and a high-pressure ion chamber ranged between 42 and 102 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 2001, 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 2001 was about 3.5 mrem for the year. This conservative estimate is well below the EPA's annual dose limit to any member of the general public and is a fraction of a percent of the typical dose received from natural and man-made radiation.

CONCLUSIONS The 2001 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 2001 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, 2001.

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

Source (millirem/year)

Cosmic/cosmogenic 30 Medical/Dental 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 turn. These radioactive byproducts from cosmic ray bombardment are referred to as cosmogenic radionuclides. Isotopes such as beryllium-7 and carbon-14 are formed in this way. Exposure to cosmic and cosmogenic sources of radioactivity results in about 30 mrem of radiation dose per year.

Additionally, natural radioactivity is in our body and in the food we eat (about 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) 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 2001, but was in a refueling outages during the period of 20-Apr through 24-May.

The resulting monthly capacity factors are presented in Table 1.3-1.

TABLE 1.3-1 PNPS OPERATING CAPACITY FACTOR DURING 2001 (Based on 670 megawatts electric)

Month Percent Capacity January 98.2%

February 99.3%

March 98.2%

April 65.9%

May 30.1%

June 94.4%

July 98.4%

August 82.4%

September 98.3%

October 98.8%

November 98.9%

December 85.9%

Annual Average 87.4%

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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 turns a turbine, which turns a generator, producing electricity. In both cases, the steam passes through a condenser where it changes back into water and recirculates back through the system. The cooling water source for Pilgrim Station is the Cape Cod Bay.

The key difference between Pilgrim's nuclear power and conventional power is the source of heat used to boil the water. Conventional plants burn 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-137 (Cs-137).

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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.

-.Radiation Neutrons Radiation 0

0 0.

Uranium Fission Products Figure 1.3-1 Radioactive Fission Product Formation Page 11 Neutrn Uranium

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

So, activation products are nothing more than ordinary naturally-occurring atoms that are made unstable or radioactive by neutron bombardment. These activation products circulate along with the reactor coolant water and will deposit on the internal surfaces of pipes and equipment.

The radioactive activation products on the pipes and equipment emit radiation.

Examples of some activation products are manganese-54 (Mn-54), iron-59 (Fe-59), cobalt-60 (Co-60), and zinc-65 (Zn-65).

mE..-'

o-60 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

SIMPLIFIED DIAGRAM OF A BOILING WATER REACTOR

4. PRIMARY CONTAINMENT

1. FUEL PELLETS 2

/

REACTOR BUILDING

3. REACTOR VESSEL FUEL CLADDING

5. SECONDARY CONTAINMENT A

DRYWELL Figure 1.3-3 Barriers To Confine Radioactive Materials Page 13

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 federal release limits, the tank is drained to the liquid effluent discharge header.

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

This detector is connected to a radiation level meter and a strip chart recorder in the Control Room.

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

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

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

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

The types and quantities of radioactive liquid and gaseous effluents released from Pilgrim Station during 2001 were reported to the Nuclear Regulatory Commission annually. The 2001 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.

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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 affect 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:

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

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

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

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

"* external radiation from an airborne plume of radioactivity;

"* internal radiation from inhalation of airborne radioactivity;

"* external radiation from deposition of radioactive effluents on soil;

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

"* internal radiation from consumption of vegetation containing radioactivity 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 amount 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.

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EXAMPLES OF PILGRIM STATION'S RADIATION EXPOSURE PATHWAYS 7.........

• ýý.....................

ý........'ý

...................I.......

LIQUID EFFLUENTS

3. DIRECT RADIATION

4. DIRECT RADIATION

,_ (SOIL DEPOSITION)

(AIR SUBMERSION)

1. SHORELINE DIRECT RADIATION (FISHING, PICNICJNG)

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

INGESTION

5. CONSUMPTION (VEGETATION)

DEPOSITION

6. CONSUMPTION (MILK AND MEAT)

DEPOSITION

3. CONSUMPTION (FISH, SHELLFISH)

INGESTION Figure 1.5-1 Radiation Exposure Pathways Page 19

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

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

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

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

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

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

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

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

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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 2001 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 2001 is discussed in Section 2 of this report.

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

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

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

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

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

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

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

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

"* Milk Radioactive Cesium-137 Concentrations: 9.3 - 32 pCi/liter;

"* 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 pCi/kg.

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

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

"* monitoring the transfer and long-term buildup of specific radionuclides in the environment to revise the monitoring program and environmental models in response to changing conditions; checking the condition of the station's operation, the adequacy of operation in relation to the adequacy of containment, and the effectiveness of effluent treatment so as to provide a mechanism of determining unusual or unforeseen conditions and, where appropriate, to trigger special environmental monitoring studies; 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 2001 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. Duke Engineering and Services Radiological Engineering Group and Environmental Laboratory personnel 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 Duke Engineering and Services Environmental Laboratory personnel.

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 Duke Engineering and Services, 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 Page 23

for the current year.

Depending upon the circumstances, a special study may also be completed (see Appendix A for 2001 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 2001 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) program.

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.

The blind duplicates, split samples and spiked samples are analyzed by PNPS, Duke Engineering and Services Environmental Laboratory, and the other four sponsor companies.

The 2001 results of this QA program are summarized in Appendix E. These results indicate that the analyses and measurements performed during 2001 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 2001. 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 tables were generated by the Duke Engineering and Services ERMAP computer program (Reference 17). 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 pCi/liter 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 Duke Engineering and Services 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 571 routine samples (11 stations/wk

• 52 weeks, minus 1 missing result). None of the samples exceeded ten times the average concentration at the control location.

The lower limit of detection (LLD) required by the ODCM is 0.01 pCi/m 3.

For samples collected from the ten indicator stations, 518 out of 519 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 0.018 +/- 0.007 (1.8 +/- 0.7 E-2) pCi/mi3. Individual values ranged from -0.00026 to 0.0444 (-2.6 - 443.6 E-4) pCi/m 3.

The monitoring station which yielded the highest mean concentration was station number 21 (East Weymouth Control), which yielded a mean concentration of 0.020 +/- 0.007 pCi/m 3, based on 52 observations.

Individual values ranged from 0.0073 to 0.040 pCi/m 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 0.020 +/- 0.007 pCi/m.

Individual samples at the control location ranged from 0.0073 to 0.040 pCi/m 3.

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Referring to the third entry in the table, analyses for potassium-40 (K-40) 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. There is no LLD value listed for K 40 in the PNPS ODCM.

At the indicator stations, individual concentrations of K-40 ranged from -0.0055 to 0.012 pCi/m 3, for a mean concentration of 0.0025 +/- 0.0041 pCi/m 3.

However, none of the forty samples analyzed showed detectable amounts of potassium-40 at the three-sigma level. It is important to note that the mean value presented is calculated from forty observations, all of which yielded no detectable activity.

The station that yielded the highest mean concentration of K-40 was station 10. Again, the mean value of 0.0046 +/- 0.0078 pCi/m 3 is based on four observations, none of which yielded any detectable activity.

Therefore, no potassium-40 was detected in any of the samples collected from the sampling stations.

The previous paragraphs illustrate an important point about applying the three-sigma criterion to determine if radioactivity is detected.

While such a screening criterion can be applied to a single measurement, it is inappropriate to apply it to a mean value calculated from multiple measurements. In the case of K-40 in air particulate filters, none of the 40 individual samples was "positive" at the 3-sigma, level. If the individual results are similar, even though they are "non-positive", the resulting standard deviation is artificially low, and does not reflect the total uncertainty associated with all of the measurements.

This makes the 3-sigma criterion inappropriate for application to a mean and standard error calculation from several measurements.

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 2001, 417 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 42 to 540 mR/yr.

The average exposure rate at control locations greater than 15 km from Pilgrim Station (i.e., Zone 4) was 61.3 +/- 8.3 mR/yr. When the 3-sigma confidence interval is calculated based on these Page 26

control measurements, 99% of all measurements of background ambient exposure would be expected to be between 36 and 86 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.

None of the TLDs located within or immediately adjacent to the PNPS protected area exhibited a significant (>20%) increase in exposure since 2000. 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 2000.

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 2.4 mrem/yr above their average ambient background dose of 61 mrem/yr.

One TLD, located in the basement of the Plymouth Memorial Hall, indicated an annual exposure of 102 mR. The exposure at this location is due to the close proximity of stone building material, which contains higher levels of naturally-occurring radioactivity, as well a from 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 90.9 +/- 78.3 mR/yr to 63.2 +/- 6.7 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 66.9 +/- 3.7 mR/yr, which compares quite well with the average control location exposure of 61.3 +/- 8.3 mR/yr.

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 18) 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.

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In conclusion, measurements of ambient radiation exposure around Pilgrim Station do not indicate any significant increase in exposure levels.

Although some increases in ambient radiation exposure level were apparent on Entergy property very close to Pilgrim Station, there were no measurable increases at areas beyond Entergy's control.

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

Out of 572 filters (11 locations

• 52 weeks), 571 samples were collected and analyzed during 2001. 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. This occurrence did not adversely affect the monitoring results.

The results of the analyses performed on these 571 filter samples are summarized in Table 2.5-1. Trend plots for the gross beta radioactivity levels at the near station, property line, and offsite airborne monitoring locations are shown in Figures 2.5-1, 2.5-2 and 2.5-3, respectively.

Gross beta radioactivity was detected in 570 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.

No airborne radioactivity attributable to Pilgrim Station was detected in any of the samples collected during 2001.

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

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

Out of 572 cartridges (11 locations

• 52 weeks), 571 samples were collected and analyzed during 2001.

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 2001, required LLDs were met on all 571 filters collected during 2001.

The results of the analyses performed on these 571 charcoal cartridges are summarized in Table 2.6-1.

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

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2.7 Milk Radioactivity Analyses 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, low-level analysis for radioiodine, and strontium-89 and -90.

All 38 samples scheduled for collection during the year were obtained and analyzed.

No problems were encountered in sampling milk during 2001.

The results of the analyses performed on the 38 milk samples are summarized in Table 2.7-1.

Naturally-occurring potassium-40 was detected in all 38 samples. No radioactive iodine was detected in any of the samples. Strontium-90 was detected in 13 of the 19 samples from Plymouth County Farm, and in 4 of the 19 samples collected from the control location in Whitman.

Cesium-1 37 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, 3.3 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 3.0 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 pCi/liter.

When the average preoperational Sr-90 concentration of 9 pCi/liter is corrected for radioactive decay that occurred between 1972 and 2001, the expected concentration would be about 4-5 pCi/liter. The concentrations of 2 to 3 pCi/liter observed in 2001 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 Fora-ge Radioactivity Analyses Samples of animal forage (hay) are collected from the Plymouth County Farm and from the control location in Whitman. Samples of corn to be used for silage at Plymouth County Farm were also collected from the Whipple Farm (2.9 km SW). Samples are collected annually and analyzed by gamma spectroscopy.

All samples of forage were collected and analyzed as required during 2001.

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 2001, and the sample collected at the control location at Whitman Farm indicated detectable cesium-137.

Such Cs-137 concentrations (49 pCi/kg) are indicative of fallout from past nuclear weapons testing. No radionuclides attributable to Pilgrim Station operations were detected in any of the samples.

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2.9 VeqetableNeqetation Radioactivity Analyses Samples of vegetables are routinely collected from the Plymouth County Farm and from the control location in Bridgewater. 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 census are discussed in Appendix C. Samples were also collected from four locations corresponding to the highest atmospheric deposition factors from the two PNPS release points.

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

All samples of vegetables/vegetation were collected and analyzed as required during 2001.

Results of the gamma analyses of these samples are summarized in Table 2.9-1.

Naturally occurring beryllium-7, potassium-40, and thorium-232 were identified in most of the samples collected. Cesium-137 was also detected in one of the samples collected.

The highest level of cesium-137 (112 pCi/kg) was detected in a sample of naturally-growing vegetation, a mixture of grass, herbaceous plants, and leaves from bushes and trees, which was collected 1.5 km (0.9 mi) south-southwest of the PNPS Reactor Building. As was the case for all samples of naturally-growing vegetation, these samples were collected and analyzed "as is", without processing the material to remove soil and dust on the surface of the plants. As documented in the previous REMP reports, Cs-137 was detected in nearly all of the soil surveys conducted in previous years, indicating that Cs-137 is widespread in soil throughout New England. In addition to Cs-137, the vegetation samples in question also contained detectable thorium-232 decay-chain nuclides, indicating appreciable levels of soil and dust were incorporated with the vegetation comprising the sample.

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

When corrected for radioactive decay, the expected concentration in samples of naturally-growing vegetation collected during 2001 would be between 75 and 146 pCi/kg.

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.

2.10 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 2001, the bog at Manomet Point was not harvested, so no sample was collected from this location. This discrepancy is noted in Appendix D.

Two samples of cranberries were collected and analyzed as required during 2001.

Results of the gamma analyses of cranberry samples are summarized in Table 2.10-1.

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 30

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 airborne 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 2001. 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 2001.

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 2001, 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 2001 were obtained and analyzed. Results of the gamma analyses of these samples are summarized in Table 2.13-1.

Naturally-occurring beryllium-7 and potassium-40 were detected in a number of the samples.

No radioactivity attributable to Pilgrim Station operations was detected in any of the samples collected during 2001.

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 Page 31

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.

All 48 samples of shellfish meat and shells scheduled for collection during 2001 were obtained and analyzed, as well as five additional samples. Results of the gamma analyses of these samples are summarized in Table 2.14-1.

Naturally-occurring beryllium-7, potassium-40, and thorium-232 were detected in a number of the samples. Low-levels of cobalt-60 (2.5 pCi/kg) were detected in one sample of mussel shells collected in the vicinity of the PNPS discharge canal at the beginning of the third quarter. However, there was no detectable Co-60 in the corresponding edible portions of this sample.

Since there was no detectable plant-related activity in edible portions, no human ingestion pathway exists for this type of marine biota.

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 2001. 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.

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 III - 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 II 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 III and IV fishes are sampled annually from the discharge canal outfall and control location. All samples of fish are analyzed by gamma spectroscopy.

Eighteen samples of fish were collected during 2001.

Results of the gamma analyses of fish samples collected are summarized in Table 2.16-1. 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 32

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.

All 56 samples of sediment were collected as required during 2001. All of the required 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 beryllium-7, potassium-40, and thorium-232 were detected in a number of the samples.

No cobalt-60 was detected in any of the 39 indicator samples.

Cesium-1 37 was detected in 11 of 39 indicator station samples and in 3 of 17 control station samples. Plutonium-239/240 was also detected in two of four indicator station samples, and both of the control station samples.

Cesium-137 levels in indicator samples ranged from non-detectable to a maximum concentration of 34 pCi/kg.

Concentrations in samples collected from the control locations beyond the influence of Pilgrim Station ranged from non-detectable to a maximum concentration of 11 pCi/kg. 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.

The concentration of plutonium isotopes the samples collected from the control locations beyond the influence of Pilgrim Station ranged from 4.4 to 5.0 pCi/kg. Plutonium in indicator samples ranged from non-detectable to 7.2 pCi/kg. The levels detected are comparable to concentrations observed in the past few years and are indicative of plutonium deposited in the environment from nuclear weapons testing.

As part of the comparison of sediment analyses results to previous years, questions were raised about the abnormally high plutonium-238 concentrations observed in samples collected during 2000. Follow-up investigations conducted by the analytical laboratory that performed the 2000 analyses concluded that the results were invalid due to cross-contamination from laboratory glassware. This laboratory also analyzes-samples for Department of Energy clean up projects. Due to the expense of the specialized glassware, it is re-used. Updated tables from the 2000 Annual Radiological Environmental Monitoring Program Report are included in Appendix F.

Page 33

Table 2.2-1 Routine Radiological Environmental Sampling 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 Sampling Locations Pilgrim Nuclear Power Station, Plymouth, MA Description No Code Distance Direction Surface Water Discharge Canal 11 DIS 0.2 km N

Bartlett Pond 17 BP 2.7 km SE Powder Point Control 23 PP 13 km NNW Irish Moss Discharge Canal Outfall 11 DIS 0.7 km NNE Manomet Point 15 MP 4.0 km ESE Ellisville 22 EL 12 km SSE Brant Rock Control 34 BR 18 km NNW Shellfish Discharge Canal Outfall 11 DIS 0.7 km NNE Plymouth Harbor 12 Ply-H 4.1 km W

Duxbury Bay Control 13 Dux-Bay 13 km NNW Manomet Point 15 MP 4.0 km ESE Green Harbor Control 24 GH 16 km NNW Lobster Discharge Canal Outfall 11 DIS 0.5 km N

Plymouth Harbor 15 Ply-H 6.4 km WNW Duxbury Bay Control 13 Dux-Bay 11 km NNW Fishes Discharge Canal Outfall 11 DIS 0.5 km N

Priest Cove Control 29 PC 48 km SW Jones River Control 30 JR 13 km WNW Vineyard Sound Control 92 MV 64 km SSW Buzzard's Bay Control 90 BB 40 km SSW Cape Cod Bay Control 98 CC-Bay 24 km ESE Sediment Discharge Canal Outfall 11 DIS 0.8 km NE Plymouth Harbor 12 Ply-H 4.1 km W

Duxbury Bay Control 13 Dux-Bay 14 km NNW Plymouth Beach 14 PLB 4.0 km WNW Manomet Point 15 MP 3.3 km ESE Green Harbor Control 24 GH 16 km NNW Page 35

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

Exposure ate - mR/nuarter Value +Std.Dev.)

2001 Annual*

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

I I_

mR/year Zone 1TLDs: 0-3km 0-3 km 23.1+/-+23.6 21.5+/-13.1 22.9+/-19.9 23.4+/-21.2 90.9+/-78.3 BLW BOAT LAUNCH WEST 0.11 krn E 62.7 +/-5.0 48.1 +/-3.9 54.1 +/-3.3 53.7+/-3.3 218.6+/-25.4 OA OVERLOOK AREA 0.15 km W 155.9+/-8.3 95.5+/-3.3 139.2+/-8.5 149.6+/-12.8 540.1 +/-110.3 TC HEALTH CLUB 0.15 km WSW 50.4+/-1.9 34.4+/-1.4 44.6+/-1.7 48.3+/-1.7 177.6+/-28.6 BLE BOAT LAUNCH EAST 0.16 km ESE Missing 33.0 +/-1.3 37.2+/- 1.6 37.9 +/-1.8 144.1 +/- 11.3 PB PEDESTRIAN BRIDGE 0.21 km N 36.3 +/- 1.2 34.0+/- 2.3 36.0 +/-2.2 38.0 +/-2.3 144.4 +/-7.8 P01 SHOREFRONT SECURITY 0.22 km NNW 37.3+/-1.9 28.0+/- 1.4 34.1 +/-2.1 33.5 +/-3.0 132.8+/-16.1 WS MEDICAL BUILDING 0.23 km SSE 34.9 +/- 1.1 29.1 +/- 1.5 31.5:+/- 1.7 33.4 +/-1.5 128.9 +/-10.5 CT PARKING LOT 0.31 km SE 20.8 +/- 0.9 20.3+/- 1.5 19.7 +/- 0.9 22.2 +/-1.4 83.0 +/-4.9 PA SHOREFRONT PARKING 0.35 km NNW 19.9 +/- 0.7 20.3 +/- 0.8 21.0:+/- 1.2 21.2+/- 1.2 82.3 +/-3.2 A STATION A 0.37 km WSW 20.5 +/- 0.7 19.7 +/- 0.7 21.2 +/- 0.9 21.3 +/-1.3 82.6 +/-3.5 F STATION F 0.43 km NW 18.0+/-0.6 19.2+/-1.2 19.6+/-0.8 19.6+/-0.7 76.5+/-3.5 B STATION B 0.44 krn S 23.8 +/- 0.9 23.3+/- 1.2 24.1 +/- 1.0 24.2 +/-1.0 95.4 +/- 2.7 EB EAST BREAKWATER 0.44 km ESE 18.7+/-0.5 19.9+/-0.8 17.8+/-1.1 18.2+/-1.0 74.7 +/- 4.0 PMT PNPS MET TOWER 0.44 km WNW 17.0 +/- 0.5 18.0+/-1.0 18.3+/-1.1 17.5+/-1.1 70.9+/-3.0 H STATION H 0.47 km SW 20.8+/-1.1 20.3+/-0.9 21.4+/-1.2 21.3+/-0.8 83.9+/-2.9 I STATION I 0.48 km WNW 17.6 +/- 0.8 18.9 +/- 0.7 Missing 18.6 +/- 1.0 73.5 +/- 3.5 L STATION L 0.50 km ESE 16.7+/-0.6 18.5+/-0.9 19.7+/-1.1 19.8+/-0.7 74.7+/-6.0 G STATION G 0.53 km W 15.9+/-0.7 16.6+/-0.7 16.9+/- 1.0 17.7+/-1.0 67.1 +/-3.3 D STATION D 0.54 km NNW 17.6+/-0.6 18.7+/- 1.0 19.3 +/- 1.0 18.7+/-0.9 74.2+/-3.3 PL PROPERTYLINE 0.54 km NW 16.6 +/- 0.7 17.8:+/- 0.6 17.6 +/- 0.7 17.9 +/- 1.1 69.8 +/- 2.7 C STATION C 0.57kmn ESE 15.7+/-0.6 16.9+/-1.1 17.1 +/-0.8 17.6+/-1.0 67.2+/-3.7 HB HALL'S BOG 0.63 krn SE 15.6 +/-0.7 16.9 +/-0.7 16.7 +/-0.8 17.6+/- 0.6 66.9 +/-3.7 GH GREENWOOD HOUSE 0.65 km ESE 16.6+/-0.6 17.3+/-0.7 17.3+/-0.9 17.9+/-1.0 69.1 +/-2.6 WRW ROCKY HILL ROAD 0.83km WNW 18.2+/-0.6 20.5+/- 1.0 19.1 +/-1.2 21.0+/-0.8 78.8 +/-5.4 ERE ROCKY HILL ROAD 0.89 km SE 13.0+/- 0.6 15.1 +/- 0.7 13.8 +/- 1.3 14.6 +/- 0.9 56.5 +/- 4.1 MT MICROWAVE TOWER 1.03 km SSW 15.5 +/- 0.9 17.8 +/- 0.9 17.2 +/- 0.8 17.0 +/- 0.9 67.5 +/- 4.2 CR CLEFT ROCK 1.27 km SSW Missing 17.6 +/- 0.6 16.6 +/- 1.0 16.4 +/- 0.8 67.5 +/- 3.2 BD BAYSHORE/GATE RD 1.34 km WNW 15.8 +/- 0.8 17.2 +/- 0.8 16.5 +/- 0.6 16.8 +/- 1.0 66.3 +/- 2.9 MR MANOMET ROAD 1.38km S 13.7+/-0.6 15.7+/-0.6 15.4+/-1.5 14.8+/-0.8 59.7+/-3.9 DR DIRT ROAD 1.48 km SW 13.1 +/-0.5 14.8 +/-0.7 14.3 +/-0.7 14.4+/-0.9 56.5 +/-3.3 EM EMERSON ROAD 1.53 krn SSE 15.0 +/- 0.5 16.2+/-0.9 15.4+/- 1.0 16.2+/-0.6 62.8 +/-2.9 EP EMERSON/PRISCILLA 1.55 km SE Missing 16.9 +/- 0.8 17.2 +/-1.1 15.7:+/- 0.8 66.3 +/- 3.8 AR EDISON ACCESS ROAD 1.59 km SSE 17.0+/-0.7 15.5+/-0.9 14.7+/-0.9 14.6+/-0.7 61.8 +/-4.7 BS BAYSHORE 1.76 km W Missing 19.2 +/- 0.8 17.1 +/- 1.3 17.7 +/- 0.9 72.0 +/- 5.0 E STATION E 1.86 km S 15.8+/-0.5 17.2+/-0.9 16.3+/- 1.1 16.2+/-1.5 65.5+/-3.2 JG JOHN GAULEY 1.99 km W 15.6 +/- 0.6 17.5 +/-1.3 16.5 +/- 0.8 17.5 +/- 0.9 67.2 +/- 4.1 J STATION J 2.04 km SSE 14.1 +/-0.6 15.8+/-0.7 15.4+/-1.1 15.4+/-0.8 60.7+/-3.4 RC PLYMOUTH YMCA 2.09 km WSW 14.4 +/- 0.6 16.5 +/- 0.6 15.7 +/- 0.8 15.4 +/- 0.7 62.0 +/- 3.7 WH WHITEHORSE ROAD 2.09 km SSE 15.2 +/-0.6 16.2 +/-0.9 16.0 +/- 1.1 15.9 +/-0.8 63.2 +/-2.5 K STATION K 2.17km S 14.5+/-0.5 15.9+/-0.8 15.4+/-0.8 15.3+/-1.0 61.1 +/-2.9 TT TAYLOR/THOMAS 2.26 km SE 14.7 +/- 0.6 16.7 +/- 0.6 14.8 +/-1.0 16.0 +/-1.2 62.2 +/- 4.2 YV YANKEE VILLAGE 2.28 km WSW 15.1 +/- 0.7 16.7 +/- 0.9 16.2 +/- 0.9 15.9 +/- 0.7 63.9 +/- 3.2 GN GOODWIN PROPERTY 2.38 km SW 10.9+/-0.5 12.8+/-0.8 11.5+/-0.8 12.1 +/-0.6 47.3+/-3.6 RW RIGHT OF WAY 2.83km S 14.0+/-0.6 15.3+/-1.0 14.1 +/-1.0 15.3+/-0.9 58.8 +/-3.4 TP TAYLOR/PEARL 2.98 km SE 13.7 +/- 0.5 15.0 +/- 0.8 14.2 +/- 0.7 15.0 +/- 0.9 58.0 +/- 3.0

• 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 36

Table 2.4-1 (continued)

Offsite Environmental TLD Results TLD Station TLD Location*

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

2001 Annual ID Description Distance/Direction Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure mR/year Zone 2 TLDs: 3-8km 3-8km 13.9+/-2.9 15.3+/-3.1 14.6+/-2.9 14.6+/-1.5 58.4+/-10.6 VR VALLEY ROAD 3.26 km SSW 12.6 +/-0.6 14.3 +/-0.9 13.2 +/-0.8 13.6 +/-1.1 53.8 +/-3.3 ME MANOMET ELEM 3.29 km SE 14.5+/-0.5 Missing 15.5+/-1.1 16.0+/-1.3 61.2+/-3.8 WC WARREN/CLIFFORD 3.31 km W 13.2 +/- 0.5 14.9 +/- 0.6 14.0 +/- 0.7 13.9 +/- 0.7 55.9 +/- 3.1 BB RT.3A/BARTLETT RD 3.33 km SSE 13.7 +/- 0.5 Missing 14.4 +/- 0.7 14.7 +/- 0.9 57.0 +/- 2.7 MP MANOMET POINT 3.57 km SE 14.4 +/-0.5 15.2 +/- 0.8 14.7 +/- 1.0 15.5+/- 1.1 59.8 +/- 2.6 MS MANOMET SUBSTATION 3.60 km SSE 17.1 +/- 0.5 18.0 +/- 0.9 17.3 +/- 0.8 18.0 +/-1.0 70.3 +/- 2.5 BW BEACHWOOD ROAD 3.93 krn SE 14.3 +/-0.6 15.4+/-0.9 15.2 +/-0.9 16.0 +/-1.0 60.8 +/-3.4 PT PINES ESTATE 4.44 km SSW 12.7+/-0.6 14.0+/-0.6 13.4+/-1.1 14.1 +/-1.0 54.2+/-3.1 EA EARL ROAD 4.60 km SSE 12.5+/-0.5 14.3+/-0.7 13.5+/-0.9 13.9+/-1.1 54.2+/-3.5 SP S PLYMOUTH SUBST 4.62 km W 14.3+/-0.6 16.0+/-0.6 15.2+/-0.8 15.7+/-1.0 61.1 +/-3.4 RP ROUTE 3 OVERPASS 4.81 km SW 13.3 +/- 0.5 14.6 +/- 0.6 14.4 +/- 0.9 14.9 +/- 0.7 57.3 +/- 3.2 RM RUSSELL MILLS RD 4.85 km WSW Missing 14.6 +/- 0.6 13.8 +/- 0.9 14.9 +/- 0.8 57.8 +/- 2.8 HD HILLDALE ROAD 5.18 km W 14.3+/-0.7 15.3+/-0.7 15.3+/-0.9 15.3+/-0.9 60.3+/-2.6 MB MANOMET BEACH 5.43 krn SSE 13.9 +/- 0.6 14.6 +/- 0.5 14.2 +/- 1.2 14.5 +/- 0.8 57.2 +/- 2.1 BR BEAVERDAM ROAD 5.52 krn S Missing 15.5 +/- 0.9 14.2+/- 1.0 15.0 +/- 0.7 59.7 +/- 3.3 PC PLYMOUTH CENTER 6.69 krn W 10.2 +/- 0.5 11.1 +/- 0.6 10.2 +/- 0.7 10.8 +/- 0.4 42.2 +/- 2.1 LD LONG POND/DREW RD 6.97 km WSW 12.2 +/- 0.5 14.1 +/- 0.8 13.8 +/-0.6 13.8 +/- 0.8 53.8 +/- 3.7 HR HYANNIS ROAD 7.33 km SSE 13.2 +/- 0.5 14.8 +/- 0.8 14.0 +/- 0.7 14.6 +/- 0.8 56.5 +/-3.3 MH MEMORIAL HALL 7.58 km WNW 24.1 +/- 0.9 26.8 +/- 0.9 25.3 +/- 1.6 Missing 101.7 +/- 6.0 SN SAQUISH NECK 7.58 km NNW 11.2 +/- 0.6 12.5 +/- 0.9 11.3 +/- 0.7 12.0 +/- 0.6 47.0 +/-2.9 CP COLLEGE POND 7.59 km SW 12.7 +/- 0.4 14.6 +/- 0.8 13.9 +/- 0.7 14.3 +/- 0.8 55.5 +/-3.5 Zone 3 TLDs: 8-15 km 8-15 km 13.4+/-1.4 14.9+/-1.3 14.2+/-1.6 14.8+/-1.5 57.4+/-6.1 DW DEEP WATER POND 8.59 km W 15.0 +/- 0.5 17.1 +/-1.5 17.2+/-2.8 17.6+/-0.7 66.9 +/-5.7 LP LONG POND ROAD 8.88 km SSW 12.6 +/- 0.7 14.2 +/- 0.7 12.7 +/-0.5 13.3 +/- 0.6 52.8 +/- 3.2 NP NORTH PLYMOUTH 9.38 km WNW 16.1 +/-0.6 17.3+/- 0.9 16.8 +/-0.9 16.9+/-0.7 67.2 +/-2.5 SS STANDISH SHORES 10.39 km NW 12.9 +/- 0.4 13.9:+/- 0.5 13.1 +/- 0.8 13.7 +/- 0.8 53.6 +/- 2.3 EL ELLISVILLE ROAD 11.52 km SSE 13.2 +/- 0.5 15.4 +/- 0.9 14.2 +/- 0.9 14.9:+/- 0.8 57.7 +/-4.2 UC UP COLLEGE POND RD 11.78 km SW 11.6+/-0.5 13.6+/-0.8 13.1 +/-1.5 13.1 +/-0.7 51.4+/-3.9 SH SACRED HEART 12.92 km W Missing 14.7 +/- 0.8 13.9 +/- 0.7 15.1 +/- 1.8 58.2 +/- 3.8 KC KING CAESAR ROAD 13.11 km NNW 13.6+/-0.6 15.1 +/-0.8 14.2+/-0.6 15.1 +/-0.7 58.0+/-3.2 BE BOURNE ROAD 13.37 km S 12.1 +/- 0.6 14.0 +/-0.8 13.2 +/- 0.7 13.7 +/-0.8 53.0 +/- 3.6 SA SHERMAN AIRPORT 13.43 km WSW 13.3 +/- 0.6 14.1 +/- 0.5 13.9 +/- 0.9 14.6 +/-0.6 55.9 +/- 2.5 Zone4TLDs: >15 km

>15 km 14.1 +/-1.7 16.1 +/-2.1 15.2 +/-2.3 15.9+/-_2.1 61.3+/- 8.3 CS CEDARVILLE SUBST 15.93 km S 14.4 +/-0.6 15.9+/-0.6 15.4 +/-0.7 16.4+/-0.7 62.1 +/-3.7 KS KINGSTON SUBST 16.15 km WNW 13.3+/-0.6 14.5+/-0.5 13.1 +/-1.0 14.8+/- 1.0 55.7+/-3.6 LR LANDING ROAD 16.46 km NNW 13.1 +/-0.5 15.2+/-11.1 14.2+/-0.7 14.5+/-0.8 57.0 +/-3.9 CW CHURCH/WEST 16.56 km NW 11.9+/- 0.7 13.7 +/-0.5 13.1 +/-0.8 13.5+/- 0.5 52.2 +/-3.4 MM MAIN/MEADOW 17.02 krn WSW 13.4 +/- 0.6 15.4 +/- 0.9 Missing 15.2 +/- 0.9 58.8 +/- 4.8 DMF DIV MARINE FISH 20.97 km SSE 16.8+/-0.7 19.7+/-1.1 19.1 +/-1.2 19.4+/-1.1 75.0+/-5.6 EW E WEYMOUTH SUBST 139.69 km NW 15.5 +/- 0.6 18.2 +/-0.6 16.6:+/- 1.1 17.4 +/- 0.8 67.7 +/- 4.9 Distance and direction are measured from centerline of Reactor Building to the monitoring location.

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

Page 37

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

Exposure Rate - mR/quarter (Value

• Std.Dev.)

2001 Annual ID Description Distance/Direction Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure mR/year Onsite TLDs P21 O&M/RXB. BREEZEWAY 50 m SE 33.2+/- 1.3 26.7+/- 1.8 26.9:+/- 1.4 26.0+/- 0.8 112.8:+/- 13.7 P24 EXEC.BUILDING 57 m W 59.8 +/- 2.3 49.7 +/- 2.0 71.9 +/- 4.9 71.3 +/- 3.3 252.7 +/- 42.9 P04 FENCE-R SCREENHOUSE 66 m N 110.6:+/- 7.4 100.9 +/-5.1 114.7 +/-7.6 110.8 +/-5.2 436.9 +/- 26.8 P20 O&M - 2ND W WALL 67 m SE 72.3 + 2.4 47.2 +/- 2.0 65.4 +/- 3.5 67.7 +/- 4.3 252.5 +/- 44.5 P25 EXEC.BUILDING LAWN 76 m WNW 127.6 +/- 6.8 124.1 +/- 5.0 109.5 +/- 8.2 111.9 +/- 11.9 473.0 +/- 39.5 P05 FENCE-WATER TANK 81 m NNE 48.2 +/- 3.7 33.2 +/- 1.3 35.3 +/- 1.5 36.3 +/- 2.4 153.1 +/- 27.4 P06 FENCE-OIL STORAGE 85 m NE 96.7 +/- 6.5 56.8 +/- 2.4 63.5 +/- 3.7 57.5 +/- 1.8 274.4 +/- 76.4 P19 O&M - 2ND SW CORNER 86 m S 105.1 +/-5.8 65.4 +/- 3.9 96.7 +/- 4.0 96.9 +/- 5.4 364.0 +/- 70.8 P18 O&M - 1ST SW CORNER 90 m S 69.6 +/-6.5 50.0 +/- 4.3 59.0 +/- 2.5 59.4 +/- 4.6 238.2 +/- 33.4 P08 COMPRESSED GAS STOR 92 m E Missing 44.8 +/- 1.5 56.0 +/- 4.9 61.8 +/- 5.7 216.8 +/- 36.0 P03 FENCE-L SCREENHOUSE 100 m NW 96.9 +/- 3.4 72.3 +/- 5.4 89.4 +/- 3.2 90.0 +/- 4.0 348.5 +/- 42.6 P17 FENCE-EXEC.BUILDING 107 m W 188.4 +/- 8.3 113.0 +/- 3.6 152.3 +/- 6.3 162.0 +/- 7.4 615.7 +/- 125.7 P07 FENCE-INTAKE BAY 121 m ENE 68.6 +/- 2.4 36.7 +/- 2.3 46.0 +/- 2.8 41.2 +/- 2.0 192.5 +/- 57.0 P230&M-2ND SWALL 121 m SSE 48.6+/-1.8 34.3+/-1.7 42.6+/-2.3 45.8+/-1.2 171.3+/-24.9 P26 FENCE-WAREHOUSE 134 m ESE 57.6 +/- 2.6 42.3 +/- 2.1 51.5 +/- 3.6 53.2 +/- 3.9 204.6 +/- 26.5 P02 FENCE-SHOREFRONT 135 m NW 65.3 +/- 3.0 45.2 +/- 2.0 57.9 +/- 2.3 59.8 +/-2.1 228.2 +/-34.2 P09 FENCE-W BOAT RAMP 136m E 49.9+/-1.9 37.0+/-2.2 44.5+/-3.1 44.9+/-1.5 176.4+/-21.9 P22 O&M - 2ND N WALL 137m SE 41.6+/-3.1 30.8+/-1.2 37.5+/-2.6 38.5+/-1.3 148.3+/-18.8 P16 FENCE-W SWITCHYARD 172 m SW 146.9 +/- 4.8 94.2 +/- 5.6 136.5 +/- 9.5 140.7 +/- 8.7 518.3 +/- 96.9 P11 FENCE-TCF GATE 183 rn ESE 54.8 +/-2.9 61.3 +/- 2.1 62.7 +/-3.6 56.8 +/- 2.0 235.6 +/- 15.9 P27 FENCE-TCF/BOAT RAMP 185 m ESE 46.4 +/- 2.9 44.4 +/- 3.8 53.5 +/- 2.7 52.0 +/- 4.0 196.3 +/- 18.6 P12 FENCE-ACCESS GATE 202 rn SE 40.7 +/- 2.0 29.2 +/- 0.9 35.3 +/- 2.0 39.3 +/- 2.6 144.5 +/- 20.9 P15 FENCE-E SWITCHYARD 220 m S 51.5 +/- 3.1 36.0 +/- 2.1 47.3 +/-2.0 49.3 +/- 3.7 184.1 +/- 28.1 P10 FENCE-TCF/INTAKE BAY 223 m E 48.0 +/- 2.2 48.9 +/-3.0 53.0 +/- 1.6 55.9 +/-4.0 205.7 +/- 15.8 P13 FENCE-MEDICAL BLDG.

224 m SSE 36.8 +/- 2.2 28.7 +/- 1.3 34.1 +/- 1.3 36.6 +/- 4.7 136.3 +/- 16.0 P14 FENCE-BUTLER BLDG 228m S 54.6+/-2.1 32.1 +/-1.3 36.6+/-2.1 38.1 +/-1.9 161.5+/-39.6 P28 FENCE-TCF/PRKNG LOT 259 m ESE 102.5 +/- 6.8 115.6 +/- 5.1 46.3 +/- 2.5 41.5 +/- 1.5 305.9 +/- 152.4 Distance and direction are measured from centerline of Reactor Building to the monitoring location.

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

Page 38

Table 2.4-3 Average TLD Exposures By Distance Zone During 2001 Average Exposure +/- Standard Deviation: mR/period Exposure Zone 1*

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

>15 km Jan-Mar 23.1 +/- 23.6 13.9 +/- 2.9 13.4 +/- 1.4 14.1 +/- 1.7 Apr-Jun 21.5 +/- 13.1 15.3 +/- 3.1 14.9 +/- 1.3 16.1 +2.1 Jul-Sep 22.9 +/- 19.9 14.6 +/- 2.9 14.2 +/- 1.6 15.2 +/- 2.3 Oct-Dec 23.4 +/-21.2 14.6 +/- 1.5 14.8 +/- 1.5 15.9 +/- 2.1 Jan-Dec 90.9 +/- 78.3**

58.4 +/- 10.6 57.4 +/- 6.1 61.3 +/- 8.3 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 63.2 +/- 6.7 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 J

R/hr mR/yr Beach Terrain White Horse Beach (Near Hilltop Ave) 7.5 +/- 0.4 65 3.3 Sandy. Few granite boulders 2.62 km SE within thirty feet.

Priscilla Beach (In Back of Full Sail Bar) 9.5 +/- 0.8 83 6.8 Sandy with small amounts of 1.89 km SE gravel.

Plymouth Beach (Outer Beach) 6.5 +/- 0.4 57 +/- 3.1 Sandy.

7.21 km WNW Plymouth Beach (Inner Beach) 6.5 +/- 0.3 57 +/- 2.9 Sandy.

6.07 km WNW Plymouth Beach (Behind Bert's Restaurant) 13.9 0.7 122 +/- 6.2 Sandy with gravel. Breakwater 3.66 km W and seawall nearby.

Duxbury Beach (Control) 7.5 +/- 0.4 65 +/- 3.3 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 Station, Plymouth, MA (January - December 2001)

MEDIUM: Air Particulates (AP)

UNITS: DCi/cubic meter Indicator Stations Mean Required Range LLD (No. Detected*l Station With Highest Mean Sta. Mean Range (No. Detected")

Control Stations Mean Range (No. Detected**1 GR-B (571)

(0)

Be-7 (44)

(0)

K-40 (44)

(0)

Mn-54 (44)

(0)

Co-60 (44)

(0)

Cs-134 (44)

(0)

Cs-137 (44)

(0) 0.01 (1.8 +/-O.7)E-2

(-2.6 - 443.6)E -4 (518/519)

( 7.6:+/- 2.1)E -2

( 2.8 - 11.6)E -2 (40/40)

( 2.5

• 4.1)E -3

(-5.5 - 12.4)E -3 (0/40)

( 2.5 +/- 27.5)E -5

(-5.7 - 5.5)E -4 (0/40)

(-4.3 +/- 289.0)E -6

(-5.5 - 6.5)E -4 (0/40) 0.01

( -6.6 +/- 25267.8)E -8

( -5.2 - 5.0)E -4 (0/40) 0.01

(-5.3 +/- 26.1)E -5

(-6.2 - 6.2)E -4 (0/40) 21

( 2.0

• 0.7)E -2

( 7.3 - 40.0)E -3 (52/ 52) 09

( 8.5 +/- 2.0)E -2

( 6.3 - 10.2)E -2 (4/4) 10

( 4.6 +/-7.8)E-3

( -5.5 - 12.4)E -3 (0/4) 15

( 2.2 +/-2.6)E-4

( 3.1 - 54.8)E -5 (0(4) 03

( 1.1

• 2.9)E -4

( -1.7 - 4.4)E -4 (0/4) 15

( 2.2 +/- 1.7)E -4

( 1.0 - 3.7)E -4 (0/4) 21

( 2.0 +/- 2.6)E -4

( -4.2 - 49.3)E -5 (0/4)

( 2.0 t 0.7)E -2

( 7.3 - 40.0)E -3 (52/52)

( 8.3

• 1.7)E -2

( 6.3 - 10.0)E -2 (4/4)

( 1.9:+/- 4.8)E -3

(-2.7 - 6.4)E -3 (0/4)

(-1.0 +/- 2.6)E -4

(-2.9 - 2.2)E -4 (0/4)

(-1.4 +/- 4.0)E -4

(-6.4 - 1.5)E -4 (0/4)

(-8.1 t 31.3)E -5

(-3.6 - 2.5)E -4 (0/4)

( 2.0 +/- 2.6)E -4

(-4.2 - 49.3)E -5 (0/4)

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

• • The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.

Page 41 Radionuclides (No. Analyses)

(Non-Routine*)

I I

I I

I I

J(N o.

I

Radionuclides (No. Analyses)

(Non-Routinel 1-131 (571)

(0)

Required LLD 0.07 Table 2.6-1 Charcoal Cartridge Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2001)

MEDIUM: Charcoal Cartrid-ge (CF)

UNITS:

pCi/cubic meter Indicator Stations Station With Highest Mean Mean Sta. Mean Range Range (No. Detected*)

(No. Detected-)

( 2.4

• 85.7)E -4 06

( 2.3 -t 7.4)E -3

( -2.9 - 2.2)E -2

( -1.2-1.6)E -2 (0/519)

(0/52)

Control Stations Mean Range (No. Detected-)

( -1.6 +/- 9.1)E -3

(-2.2 - 1.9)E -2 (0/52)

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

The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.

Page 42

Table 2.7-1 Milk Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2001)

Indicator Stations Mean Required Range LLD (No. Detected***

Station With Highest Mean Sta. Mean Range (No. fl.tAnt*d*%

Control Stations Mean Range

( 1.4+/-0.1)E3

( 1.2 - 1.5)E 3 (19/19)

(-5.1 +/- 29.2)E -1

(-7.9 - 5.1)E 0 (0/19)

( 1.7:+/- 0.8)E 0

( 0.0 - 3.3)E 0 (13/19)

( 1.2 +/- 1.4)E -1

(-1.5 - 3.7)E -1 (0/19) 15

( 1.5+/- 1.6)E 0

(-1.7 - 4.3)E 0 (0/19) 15

( 2.6 +/- 15.0)E -1

(-2.2 - 2.6)E 0 (0/19) 15

(-2.4 +/- 21.6)E -1

(-3.2 - 4.0)E 0 (0/19) 11

( 1.4+/- 0.1)E 3

( 1.2 - 1.5)E 3 (19/19) 11

(-5.1 t 29.2)E -1

( -7.9 - 5.1)E 0 (0/19) 11

( 1.7.t0.8)E0

( 0.0- 3.3)E 0 (13/19) 11 (1.2 +/- 1.4)E -1

(-1.5 - 3.7)E -1 (0/ 19) 11 (1.5 +/- 1.6)E 0

(-1.7 - 4.3)E 0 (0/19) 11

( 2.6 +/- 15.0)E -1

(-2.2 - 2.6)E 0 (0/19) 11

(-2.4:+/- 21.6)E -1

(-3.2 - 4.0)E 0 (0/19)

( 1.3 +/- 0.1)E 3

( 1.2 - 1.4)E 3 (19/19)

(-6.5. 30.9)E -1

( -5.0 - 4.9)E 0 (0/19)

( 1.1., 0.7)E 0

(-3.1 - 302.1)E -2 (4/19)

( 6.5 +/- 14.5)E -2

(-1.1 - 5.4)E -1 (0/19)

( 9.1 t 2166.6)E -3

(-4.5 - 3.1)E 0 (0/19)

(-1.5 t 19.3)E -1

(-3.7 - 3.4)E 0 (0/19)

(-4.8 +/- 22.3)E -1

(-4.3 - 4.3)E 0 (0/19)

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

The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.

Page 43 Radionuclides (No. Analyses)

(Non-Routine*l K-40 (38)

(0)

Sr-89 (38)

(0)

Sr-90 (38)

(0) 1-131 (38)

(0)

Cs-1 34 (38)

(0)

Cs-137 (38)

(0)

Ba-140 (38)

(0)

NAMr'll"KA

KAHL, KA "Killro fl; ft, U

I U

U (Non-Routine*)

(No Detected**l (No Detected")

A.4=1"111 lb.4-AA;IL- /'l"kA\\

Table 2.8-1 Forage Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2001)

MEDIUM: Forage (TC)

UNITS: pCi/kq wet Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Sta. Mean Mean (No. Analyses)

Required Range Range Range (Non-Routine)

LLD (No. Detected*)

(No. Detected-)

(No. Detected*)

Be-7 (2)

( 1.6+/-0.2)E3 11

( 1.6 +/-0.2)E3

( 1.1 +/-0.1)E3 (0)

(1/ 1)

(1/1)

(1/ 1)

K-40 (2)

( 9.9 t 0.4)E 3 11

( 9.9:+/- 0.4)E 3

( 9.6 -, 0.3)E 3 (0)

(1/1 (1/ 1)

(1/ 1) 1-131 (2)

( 5.1 +/- 4.4)E 1 21

( 1.9+/-0.9)E2

( 1.9 0.9)E 2 (0)

(0/1)

(0/1)

(0/1)

Cs-134 (2) 130

(-6.3+/-13.5)E0 21

( 3.8+/-10.3)E0

( 3.8+/-10.3)E0 (0)

(0/1)

(0/1)

(0/1)

Cs-137 (2) 130

( 3.5 +/- 1.7)E 1 21

( 4.9 +/- 1.3)E 1

( 4.9 +/- 1.3)E 1 (0)

(0/1)

(1/ 1)

(1/ 1)

Th-232 (2)

( 1.0 +/-0.6)E 2 21

( 1.4+/- 0.6)E 2

( 1.4+/- O.6)E2 (0)

(0/1)

(0/1)

(0/1)

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

• • The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.

Page 44

Table 2.9-1 VegetableNegetation Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2001)

MEDIUM: Vegetation (TF)

UNITS: pCi/kq wet Indicator Stations Station With Highest Mean Mean Sta. Mean Required Range Range LLD (No. Detected*)

(No. Detected*)

( 1.5+/-1.2)E3 06

( 3.9+/-0.1)E3

(-6.4 - 387.8)E 1 (9/12)

(1/1)

( 3.6+/-1.9)E3 32

( 7.0+/-0.3)E3

( 6.3 - 69.7)E 2 (12/12)

(1/ 1) 60

( -2.0 +/- 28.2)E 0 35

( 1.2 I1.O)E 1

( -7.9 - 5.3)E 1

( 6.8 - 17.9)E 0 (0/22)

(0/2) 60

( 5.0 +/- 7.9)E 0 32

( 1.8* 0.7)E 1

(-7.5 - 17.6)E 0 (0/12)

(0/1) 60

( 8.5 +/- 33.5)E 0 99

( 4.9 +/- 8.9)E 1

(-1.4 - 11.2)E 1

( -1.3 - 11.2)E 1 (1/12)

(1/2)

( 1.0+/-1.0)E2 06

( 2.6+/-0.5)E2

(-6.1 - 26.0)E 1 (7/12)

(1/1)

Control Stations Mean Range (No. Detected*)

( 4.8 +/- 7.9)E 2

( -2.2 - 1395.0)E 0 (1/3)

( 3.5 +/- 1.8)E 3

( 2.2 - 5.6)E 3 (3/3)

(-2.1

• 4.0)E 1

(-5.8 - 1.9)E 1 (0/4)

( 1.7 -,- 4.7)E 0

( 5.3 - 27.0)E -1 (0/3)

( 1.0+/-1.2)E1

(-2.1 - 17.6)E 0 (0/3)

( 2.9 +/- 4.5)E 1

(-6.4 - 74.4)E 0 (1/3)

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

• • The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.

Page 45 Radionuclides (No. Analyses)

(Non-Routine*)

Be-7 (15)

(0)

K-40 (15)

(0) 1-131 (26)

(0)

Cs-134 (15)

(0)

Cs-137 (15)

(0)

Th-232 (15)

(0)

Table 2.10-1 Cranberry Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2001)

MEDIUM: Cranberries (CB)

UNITS: DCi/kg wet Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Sta. Mean Mean (No. Analyses)

Required Range Range Range (Non-Routine*)

LLD (No. Detected*"

(No. Detected")

(No. Detected**"

Be-7 (2)

( 1.0 +/-1.4)E 2 23

( 1.0 +/- 1.1)E 2

( 1.0 +/- 1.1)E 2 (0)

(0/1)

(0/1)

(0/1)

K-40 (2)

( 5.5 +/-2.6)E 2 23

( 6.2:+/- 1.8)E 2

( 6.2:+/- 1.8)E 2 (0)

(Of/1)

(1/1 (1/ 1) 1-131 (2)

( 6.7+/-21.2)E1 14

( 6.7+/-21.2)E1

(-6.0+/-4.4)E1 (0)

(0/1)

(0/1)

(0/1)

Cs-134 (2) 60

( 1.6+/-1.4)E1 14

( 1.6+/-1.4)E1

( 9.6+/-10.6)E0 (0)

(0/1)

(0/1)

(0/1)

Cs-137 (2) 60

(-6.4+/-11.5)E0 14

(-6.4+/-11.5)E0

(-9.6+/-9.8)E0 (0)

(o/1)

(o/1)

(o/1)

Th-232 (2)

(-2.9 +/- 5.6)E 1 14

( -2.9 +/- 5.6)E 1

( -3.6 +/- 3.4)E 1 (0)

(o/1)

(o/1)

(o/1)

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

• • The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.

Page 46

Table 2.11-1 Soil Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2001)

MEDIUM: Soil (TS)

UNITS:

pCi/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 - December 2001)

MEDIUM: Surface Water (WS)

UNITS: pCi/kq Indicator Stations Mean Required Range LLD (No. Detected**l Station With Highest Mean Sta. Mean Range Control Stations Mean Range H-3 (12)

(0)

K-40 (36)

(0)

Mn-54 (36)

(0)

Co-58 (36)

(0)

Fe-59 (36)

(0)

Co-60 (36)

(0)

Zn-65 (36)

(0)

Zr-95 (36)

(0) 1-131 (36)

(0)

Cs-1 34 (36)

(0)

Cs-1 37 (36)

(0)

Ba-1 40 (36)

(0) 23

(

23

(

3.8 +/- 5.4)E 2 1.1 -11.4)E 2 (0/4) 2.9 +/- 0.3)E 2 2.5 - 3.7)E 2 (12/12) 3000

( 1.9 t 28.5)E 1

( -2.9-5.2)E 2 (0/8)

( 1.4 t 1.5)E 2

(-4.0 - 37.1)E 1 (12/24) 15

(-5.9+/-t 13.4)E -1

(-2.6 - 2.3)E 0 (0/24) 15

( 2.4 +/- 150.2)E -2

(-2.7 - 3.0)E 0 (0/24) 30

( 1.4 t 4.1)E 0

(-4.4 - 9.7)E 0 (0/24) 15

(-5.3 +/- 14.2)E -1

(-3.4 - 3.5)E 0 (0/24) 30

(-2.5 +/- 5.2)E 0

(-1.6 - 0.8)E 1 (0/24) 15 (1.1

+/- 19.3)E -1

(-3.2 - 2.9)E 0 (0/24) 1 (8.1 +/- 19.3)E -2

(-2.5 - 6.1)E -1 (0/24) 15 (1.5 = 15.8)E -1

(-2.3 - 2.3)E 0 (0/24) 18

(-4.1 +/- 12.0)E -1

(-2.4 - 1.3)E 0 (0/24) 15

( 3.3 +/- 28.7)E -1

(-5.4 - 6.3)E 0 (0/24)

( (

(

3.8 t 5.4)E 2 1.1 - 11.4)E 2 (0/4) 2.9 t 0.3)E 2 2.5 - 3.7)E 2 (12/12)

(-5.0 +/-:20.5)E -1

(-3.4 - 3.3)E 0 (0/12)

(-3.1 & 1O.O)E -1

(-1.5 - 1.1)E 0 (0/12)

(-2.3 & 3.5)E 0

(-6.8 - 3.3)E 0 (0/12) 5.8& 15.1)E-1

(-1.3 - 3.8)E 0 (0/12)

(-2.5 +/- 3.6)E 0

(-8.6-2.2)E 0 (0/12) 9.1 & 25.9)E -1

(-3.3 - 4.7)E 0 (0/12) 4.8 +/- 19.4)E -2

(-3.6 - 2.8)E -1 (0/12)

(-2.6 & 77.8)E -2

(-1.7 - 0.9)E 0 (0/12)

(-3.9 t 157.2)E -2

(-2.6 - 2.0)E 0 (0/12)

(-4.6 t 20.8)E -1

(-4.5 - 3.4)E 0 (0/12)

Page 48 Radionuclides (No. Analyses)

(Non-Routine*)

11

(-3.9+/- 13.5)E -1

( -2.4 - 2.3)E 0 (0/12) 17

( 7.8+/- 145.8)E -2

(-2.0 - 2.4)E 0 (0/12) 11

( 1.5 +/- 4.4)E 0

( -4.4 - 9.7)E 0 (0/12) 23

( 5.8 +/- 15.1)E -1

(-1.3 - 3.8)E 0 (0/12) 11

(-2.5 +/- 2.9)E 0

(-7.8 - 1.3)E 0 (0/12) 23

( 9.1 +/- 25.9)E -1

(-3.3 - 4.7)E 0 (0/12) 11

( 9.6 +/- 23.3)E -2

(-2.5 - 6.1)E -1 (0/12) 17

( 6.8 +/- 13.6)E -1

(-2.3 - 2.3)E 0 (0/12) 23

(-3.9 +/- 157.2)E -2

(-2.6 - 2.0)E 0 (0/12) 17 (1.7+/-2.6)E0

(-3.0 - 6.3)E 0 (0/12)

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

• • The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.

LLD (No. Detected-)

(No Detected**l

[No Detected")

Table 2.13-1 Irish Moss Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2001)

MEDIUM: Irish Moss (AL)

UNITS: pCi/kq wet Indicator Stations Mean Required Range LLD (Nn ntnctp~d**

Station With Highest Mean Sta. Mean Range Control Stations Mean Range (No. Detected*)

( 1.4 +/- 1.2)E 2

(-5.5 - 33.7)E 1 (1/12)

( 5.7 +/-1.1)E3

( 4.4 - 7.7)E 3 (12/12)

(-4.5 +/- 8.8)E 1

(-1.7 - 1.1)E 2 (0112)

( -7.1 +/- 98.9)E -1

( -2.3 - 1.3)E 1 (0/12)

( -3.2 +/- 14.0)E 0

( -2.8 - 1.6)E 1 (0/12)

( 1.8 +/- 3.9)E 1

(-4.7 - 10.7)E 1 (0/12) 4.5 +/- 87.0)E -1

(-1.4 - 1.2)E 1 (0/12)

(-1.4 +/- 3.9)E 1

(-5.7 - 9.3)E 1 (0/12)

( -7.4 +/- 78.5)E -1

( -1.0 - 1.3)E 1 (0/12)

( 3.1 +/- 165.3)E -1

(-1.7 - 4.6)E 1 (0/12) 2.0 +/- 3.9)E 1

(-5.6 - 8.2)E 1 (0/12) 22

( 2.5 +/- 0.7)E 2

( 2.3 - 2.9)E 2 (1/3) 11

( 6.4+/-1.0)E3 5.3 - 7.7)E 3 (5/5) 11

(-2.6 +/- 11.5)E 1

(-1.7 - 1.1)E 2 (0/5) 22

( 6.7 +/-49.5)E-1

(-1.5 - 2.6)E 0 (0/3) 11

(-1.5 +/- 6.9)E 0

(-1.0 - 0.6)E 1 (0/5) 15

( 2.2 +/- 2.6)E 1 6.0 - 47.1)E 0 (014) 22

( 2.2 +/- 5.2)E 0

(-7.5 - 55.9)E -1 (0/3) 22

( 7.9 +/- 78.6)E 0

( -4.9 - 9.3)E 1 (0/3) 22

( 3.0

• 12.6)E 0

( -1.0 - 1.3)E 1 (0/3) 15

( 1.1 +/- 2.4)E 1

(-6.0 - 45.8)E 0 (0/4) 11

( 2.86+/- 2.6)E 1

(-4.2 - 49.0)E 0 (0/5) 7.5 +/- 9.8)E 1 (1.4 - 21.1)E 1 (0/4)

(6.1 +/- 3.1)E 3 2.9 - 10.2)E 3 (4/4)

(-3.5 +/- 10.4)E 1

(-1.3 - 0.9)E 2 (0/4)

(-5.5 +/- 8.2)E 0

(-1.2 - 0.1)E 1 (0/4)

(-2.3 +/- 11.9)E 0

(-1.4 - 1.2)E 1 (0/4)

(1.4+/-1.9)E1 9.3 - 218.0)E -1 (014) 2.2 +/- 6.3)E 0

(-2.4 - 6.4)E 0 (0/4)

(-1.2 +/-22.1)E 1

(-2.7 - 1.2)E 1 (0/4)

(-2.9 +/- 11.7)E 0

(-1.9 - 0.7)E 1 (0/4)

(-3.6 +/- 10.2)E 0

(-1.4 - 0.8)E 1 (0/4)

( 1.6;+/- 3.8)E 1

( -1.7 - 5.9)E 1 (0/4)

Page 49 Radionuclides (No. Analyses)

(NonmRoutine*l Be-7 (16)

(0)

K-40 (16)

(0)

Cr-61 (16)

(0)

Mn-54 (16)

(0)

Co-S8 (16)

(0)

Fe-59 (16)

(0)

Co-60 (16)

(0)

Zn-65 (16)

(0)

Cs-1 34 (16)

(0)

Cs-137 (16)

(0)

Th-232 (16)

(0)

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

• • The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.

(Non-Routine*1 (No Detected-)

LLD INo Detected-)

Table 2.14-1 Shellfish Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2001)

MEDIUM: Shellfish (SF)

UNITS: pCi/kq wet Indicator Stations Mean Required Range LLD (No D*tpet~d***

Station With Highest Mean Sta. Mean Range (No. Detected-)

Control Stations Mean Range (No. Detected**1 Be-7 (53)

(0)

K-40 (53)

(0)

Cr-51 (53)

(0)

Mn-54 (53)

(0)

Co-58 (53)

(0)

Fe-59 (53)

(0)

Co-so (53)

(0)

Zn-65 (53)

(0)

Zr-95 (53)

(0)

Cs-134 (53)

(0)

Cs-1 37 (53)

(0)

Ce-144 (53)

(0)

Th-232 (53)

(0)

( 2.4 t 4.0)E I

(-8.9 - 12.5)E 1 (3/29)

( 1.0 O.8)E 3

(-2.6 - 238.6)E 1 (25/29)

(-1.5 +/- 4.5)E 1

(-1.7 - 0.9)E 2 (0/29) 130

(-3.0 +/- 6.7)E 0

(-1.7 - 1.5)E 1 (0/29) 130

( -3.3 +/- 6.5)E 0

( -2.4 - 0.3)E 1 (0/29) 260

( 5.3 +/- 17.0)E 0

(-1.3 - 7.1)E 1 (0/29) 5

( 1.9 +/-4.6)EO

( -8.1 - 14.8)E 0 (1/29) 5

( -1.2 +/- 2.3)E 1

( -8.2 - 0.6)E 1 (0/29) 5

( 1.5 +/-10.7)EO

(-1.6 - 4.1)E 1 (0/29) 5 (3.1 +/-7.1)E 0

(-4.3 - 25.5)E 0 (0/29) 5

(-4.5 +/- 73.6)E -1

(-2.8 - 2.0)E 1 (0/29) 15

(-8.2 +/- 24.2)E 0

(-7.3 - 3.0)E 1 (0/29)

( 2.8 +/- 3.7)E 1

(-5.4 - 1 0.5)E 1 (11/29) 15

( 4.3+/-1.8)E1

( 2.6 - 6.7)E 1 (2/6) 15

( 1.2+/-0.9)E3

( 1.3 - 23.9)E 2 (6/6) 11

(-1.8:+/- 12.6)E 0

(-1.6 - 1.9)E 1 (0/10) 13

(-2.5 +/- 1350.4)E -2

(-4.0 - 1.5)E 1 (0/16) 24

( 2.9 & 13.8)E -1

(-1.1 - 2.4)E 0 (0/8) 12

( 1.2+/-2.4)E 1

( -1.3 - 7.1)E 1 (0/13) 12

( 2.8 +/- 6.8)E 0

(-8.1 - 14.8)E 0 (0/13) 11

( -1.1 +/- 2.6)E 0

( -6.0 - 1.4)E 0 (0/10) 13

( 2.3 +/- 15.4)E 0

(-2.4 - 2.4)E 1 (0/16) 13

( 7.4 +/- 9.7)E 0

(-4.4 - 24.8)E 0 (0/16) 11

( 3.7 +/- 108.9)E -2

( -1.6 - 2.0)E 0 (0/10) 13

( 1.3 +/- 3.8)E 1

( -4.8 - 8.4)E 1 (0/16) 13

( 7.0 +/- 7.6)E 1

( -4.2 - 23.8)E 1 (6/16)

Page 50 Radionuclides (No. Analyses)

(Non-Routine*l

(-6.7 +/- 863.7)E -1

(-2.0 - 1.6)E 2 (4/24)

( 8.3 +/- 7.6)E 2

( 3.5 - 251.8)E 1 (16/24)

(-8.5 - 92.8)E 0

(-2.1 - 2.4)E 2 (0/24)

(-1.3 +/- 108.8)E -1

(-4.0 - 1.5)E 1 (0/24)

(-1.8 +/- 7.5)E 0

(-2.5 - 1.0)E 1 (0/24)

( 3.9 +/- 19.6)E 0

(-3.6 - 5.3)E 1 (0/24)

(-1.8 +/- 4.4)E 0

(-1.4 - 0.3)E 1 (0/24)

(-1.4 +/- 2.7)E 1

(-7.5 - 3.8)E 1 (0/24)

( 1.7 +/- 12.3)E 0

(-2.4 - 2.4)E 1 (0/24)

( 5.4 8.3)E 0

(-4.4 - 24.8)E 0 (0/24)

(-3.3 = 64.8)E -1

(-1.1 - 2.0)E 1 (0/24)

( 7.9 & 31.5)E 0

(-4.8 - 8.4)E 1 (0/24)

( 5.7:+/- 6.4)E 1

(-4.2 - 23.8)E 1 (11/24)

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

The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.

i(No.

Detected-)

(Non-Routine*1 LLD (No Detected**'

Table 2.15-1 Lobster Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2001)

MEDIUM: American Lobster (HA)

UNITS: pCi/kq wet Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Sta. Mean Mean (No. Analyses)

Required Range Range Range (Non-Routine*)

LLD (No. Detected")

(No. Detected-)

(No. Detected-)

Be-7 (5)

(-2.3+/-10.2)E 1 80

( 6.3+/-9.1)E1

( 6.3+/-9.1)E 1 (0)

( -8.1 - 11.8)E 1 (0/4)

(0/1)

(0/1)

K-40 (5)

( 2.3 +/-20.3)E 3 11

( 2.3 +/- 0.3)E 3

( 1.6 +/- 0.3)E 3 (0)

( 2.0 - 2.5)E 3

( 2.0 - 2.5)E 3 (414)

(4/4)

(1/i1)

Mn-54 (5) 130

(-3.6 +/- 6.8)E 0 80

( -7.7 +/- 94.3)E -1

(-7.7 +/- 94.3)E -1 (0)

(-9.3 - 2.9)E 0 (0/4)

(0/1)

(0/1)

Co-58 (5) 130

( 4.7 +/- 14.3)E0 11

( 4.7+/-14.3)E 0

(-6.2+/-9.2)E0 (0)

(-6.6 - 21.8)E 0

( -6.6 - 21.8)E 0 (0/4)

(0/4)

(0/1)

Fe-59 (5) 260

( 5.2:+/- 55.9)E 0 80

( 2.2 +/- 3.1)E 1

( 2.2:+/- 3.1)E 1 (0)

( -4.6 -8.0)E 1 (0/4)

(0/1)

(0/1)

Co-60 (5) 130

( -9.5 +/- 53.0)E -1 11

( -9.5 +/- 53.0)E -1

(-1.6+/-t 1.4)E 1 (0)

(-4.4 - 3.2)E 0

(-4.4 - 3.2)E 0 (0/4)

(0/4)

(0/1)

Zn-65 (5) 260

(-2.1 +/- 2.9)E 1 11

( -2.1 +/- 2.9)E 1

(-4.7 +/- 2.8)E 1 (0)

(-5.9 - 0.1)E 1

(-5.9 - 0.1)E 1 (0/4)

(0/4)

(0/1)

Cs-134 (5) 130

(-5.1 +/-5.6)E0 80

( 4.8+/-9.3)E0

( 4.8+/-9.3)E0 (0)

(-8.7 - -2.3)E 0 (0/4)

(0/1)

(0/1)

Cs-137 (5) 130

(-6.1 +/-6.6)E0 11

(-6.1 +/-6.6)E0

(-9.6+/-9.7)E0 (0)

(-1.3 --O.3)E 1

( -1.3 - -0.3)E 1 (0/4)

(0/4)

(0/1)

Th-232 (5)

(-5.0 +/- 3.6)E 1 11

( -5.0 +/- 3.6)E 1

(-8.7 +/- 3.9)E 1 (0)

(-7.8 -- 1.6)E 1

(-7.8 - -1.6)E 1 (0/4)

(0/4)

(0/1)

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

• • The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.

Page 51

Table 2.16-1 Fish Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2001)

MEDIUM: Fish (FH)

UNITS: pCi/kg wet Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Sta. Mean Mean (No. Analyses)

Required Range Range Range (Non-Routine*)

LLD (No. Detected*)

(No. Detected*-

(No. Detected*)

Be-7 (18)

(-2.1 +/- 11.2)E 1 87

( 7.6 +/- 10.1)E 1

( 1.8 +/- 9.8)E 1 (0)

(-2.3 - 1.6)E 2

(-9.7 - 16.6)E 1 (0/10)

(0/1)

(0/8)

K-40 (18)

( 3.56+/- 0.2)E 3 40

( 4.0 +/- 0.4)E 3

( 3.3 +/- 0.6)E 3 (0)

( 3.3 - 3.9)E 3

( 3.8 -4.2)E 3

( 2.6 - 4.2)E 3 (10/10)

(2/2)

(8/8)

Mn-54 (18) 130

( 6.9 +/- 6628.7)E -3 85

( 1.3:+/- 1.4)E 1

( 4.3 +/- 141.0)E -1 (0)

(-9.6 - 9.7)E 0

( 5.5 - 21.4)E 0

( -1.6 - 2.1)E 1 (0/10)

(0/2)

(0/8)

Co-58 (18) 130

(-1.2 +/- 1.2)E 1 85

( 8.4:+/- 11.2)E 0

( 1.4, -11.8)E 0 (0)

(-3.4- 0.6)E 1

( 2.5 - 14.3)E 0

( -1.6 - 1.8)E 1 (0/10)

(0/2)

(0/8)

Fe-59 (18) 260

( 1.5+/-4.7)E1 87

( 8.8+/-4.4)E1

( 9.2+/-69.1)E0 (0)

(-3.3 - 9.1)E 1

( -7.6 - 8.8)E 1 (0/10)

(011)

(0/8)

Co-60 (18) 130

(-3.7+/-10.6)E0 40

( 9.2+/-17.6)E0

( 4.3+/-12.9)E0 (0)

(-1.7 - 1.0)E 1

( -1.9 - 20.3)E 0

(-5.7 - 27.2)E 0 (0/10)

(0/2)

(0/8)

Zn-65 (18) 260

( -1.8 +/- 4.5)E 1 87

( -6.8 +/- 27.9)E 0

( -3.3 +/- 3.1)E 1 (0)

( -1.1 - 0.7)E 2

( -7.7 - 1.4)E 1 (0/10)

(0/1)

(0/8)

Cs-134 (18) 130

(-8.0+/-95.6)E-1 13

( 1.0+/-2.4)E1

( 1.4-r16.6)E0 (0)

(-1.7 - 1.2)E 1

( -1.3 - 3.2)E 1

(-2.1 - 3.2)E 1 (0/10)

(0/3)

(0/8)

Cs-137 (18) 130

( 4.1 +/-131.1)E-1 85

( 5.3+/-24.3)E0

( 2.1 +/-15.2)E0 (0)

(-3.1 - 1.3)E 1

( -1.1 - 2.1)E 1

( -1.2 - 2.7)E 1 (0/10)

(0/2)

(0/8)

Th-232 (18)

( 3.4 +/- 40.4)E 0 13

( 3.3 +/- 5.1)E 1

( -5.8 +/- 640.7)E -1 (0)

(-6.1 - 5.5)E 1

( 1.4-78.1)E 0

(-1.2- 0.8)E 2 (0/10)

(0/3)

(0(8)

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

• • The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.

Page 52

Table 2.17-1 Sediment Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2001)

MEDIUM: Sediment (SE)

UNITS: pCi/kq dry Indicator Stations Mean Required Range LLD tNn~ fltr*tentd**

Station With Highest Mean Sta. Mean Range (No. Detected*)

Control Stations Mean Range (No. Detected**

Be-7 (56)

(0)

K-40 (56)

(0)

Co-58 (56)

(0)

Co-60 (56)

(0)

Zn-65 (56)

(0)

Zr-95 (56)

(0)

Cs-1 34 (56)

(0)

Cs-137 (56)

(0)

Ce-1 44 (56)

(0)

Th-232 (56)

(0)

Pu-238 (6)

(0)

Pu-239 (6)

(0)

C 5.2 +/- 66.9)E 0

( -1.2-3.2)E 2 (0/39)

( 9.5 +/- 2.9)E 3

( 6.0 - 19.4)E 3 (39/39) 50

( -5.3 +/- 5.7)E 0

( -1.9 - 0.4)E 1 (0/39) 50

( 1.5 +/- 2.9)E 0

(-4.3 - 8.8)E 0 (0/39) 50

( 1.9 +/- 1.5)E 1

(-1.2 - 4.2)E 1 (0/39) 50

( 8.2 +/- 11.6)E 0

(-2.7 - 3.1)E 1 (0/39) 50

( 5.6 +/- 11.1)E 0

(-1.7 - 3.2)E 1 (0/39) 50

( 6.2 +/- 9.8)E 0

(-3.9 - 33.8)E 0 (11/39) 150

( -2.5 +/- 22.3)E 0

( -6.8 - 2.6)E 1 (0/39)

( 3.1 +/- 1.4)E 2

( 1.3 - 8.1)E 2 (39/39) 25

( 1.3 +/- 1.1)E 0

( 5.9 - 29.0)E -1 (0/4) 25

( 3.5 +/- 2.9)E 0 (1.1

-7.2)E 0 (2/4)

(1/1) 13

( 2.7 +/- 5.2)E 1

(-4.1 - 14.3)E 1 (1/11) 11 (1.3 +/-0.3)E4

( 1.0 - 1.9)E 4 (11/11) 15

(-2.6 +/- 4.6)E 0

(-1.2 - 0.4)E 1 (0/11) 12 (1.9 +/-2.9)EO

(-1.7 - 8.8)E 0 (0/11) 12

( 2.2 1.7)E 1

(-1.2 - 4.0)E 1 (0/11) 13

( 1.3 +/- 1.3)E 1

(-2.1 - 36.6)E 0 (0/11) 15 (7.1 +/- 8.8)E 0

(-6.1 -221.1)E -1 (0/11) 12

( 1.9 +/-0.8)E 1

( 7.4 - 33.8)E 0 (10/11) 12 (5.1

=16.5)E 0

(-2.0 - 2.6)E 1 (0/11) 12

( 4.6 +/-1.4)E2

( 2.9 - 8.1)E 2 (11/11) 13

( 1.8 +/- 1.8)E 0

( 6.5 - 30.0)E -1 (0/2) 12

( 7.2 +/-20.8)E 0 Page 53 Radionuclides (No. Analyses)

(Non-Routinel*

( 2.1 t 6.2)E 1

(-7.4-16.3)E 1 (2/17)

( 9.9 t 1.2)E 3

( 7.9 - 11.8)E 3 (17/17)

(-6.7 +/- 6.3)E 0

(-2.1 - 0.2)E 1 (0/17)

(-1.1 +/- 28.5)E -1

(-4.2 - 5.1)E 0 (0/17)

( 5.9:+/- 18.1)E 0

(-2.9 - 3.6)E 1 (0/17) 1.1 +/- 1.1)E 1

(-2.1 - 36.6)E 0 (0/17)

( 6.3 +/- 65.6)E -1

(-8.4 - 21.1)E 0 (0/17)

( 4.7 +/- 4.2)E 0

(-6.7 - 10.9)E 0 (3117)

(-3.7 +/- 27.5)E 0

(-7.1 - 3.8)E 1 (0/17)

( 3.9:+/- 1.1)E 2

( 2.3 - 5.5)E 2 (17/17)

( 1.8:+/- 1.8)E 0

( 6.5 - 30.0)E -1 (0/2)

( 4.7 +/- 0.9)E 0

( 4.4 - 5.0)E 0 (212)

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

The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.

(No. Detected-)

(Non-Routine*)

LLD lNo Detected**'

Table 2.17-2 Sediment Plutonium Analyses Environmental Radiological Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2001) pCi/kg (dry) +/- 1 S.D.

Location Core Depth (cm)

Plutonium-238 Plutonium-239/240 Discharge Canal Outfall 0 - 5 NDA 4.4 + 1.4 Discharge Canal Outfall 5 - 10 NDA NDA Plymouth Harbor 14 - 16 NDA 7.17 +/- 0.82 Manomet Point 0 - 2 NDA NDA Duxbury Bay - Control 0 - 2 NDA 4.4 +/- 1.3 Duxbury Bay - Control 12 - 14 NDA 5.02 +/- 0.75

• NDA indicates no detectable activity.

Page 54

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

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

Page 55

Figure 2.2-1 (continued)

Environmental TLD Locations Within the PNPS Protected Area IUU meters Page 56

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

Air/Soil Sampling Station Location*

Description Code Distance/Direction Description Code Distance/Direction Zone 1 TLDs: 0-3 km BOAT LAUNCH WEST BLW 0.11 km E

OVERLOOK AREA OA 0.15 km W

OVERLOOK AREA OA 0.15 km W PEDESTRIAN BRIDGE PB 0.21 km N

HEALTH CLUB TC 0.15 km WSW MEDICAL BUILDING WS 0.23 km SSE BOAT LAUNCH EAST BLE 0.16 km ESE EAST BREAKWATER EB 0.44 km ESE PEDESTRIAN BRIDGE PB 0.21 km N

PROPERTY LINE PL 0.54 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 HALL'S BOG HB 0.63 km SE GREENWOOD HOUSE GH 0.65 km ESE W ROCKY HILL ROAD WR 0.83 krn 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*

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

1.86 km S JOHN GAULEY JG 1.99 km W STATION J J

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

2.17 km S TAYLOR/THOMAS TT 2.26 km SE YANKEE VILLAGE YV 2.28 km WSW GOODWIN PROPERTY GN 2.38 km SW RIGHT OF WAY RW 2.83 km S TAYLOR/PEARL TP 2.98 km SE Zone 2 TLDs: 3-8 krn VALLEY ROAD VR 3.26 km SSW MANOMET ELEM ME 3.29 km SE WARREN/CLIFFORD WC 3.31 km W RT.3A/BARTLETT RD BB 3.33 km SSE MANOMET POINT MP 3.57 km SE MANOMET SUBSTATION MS 3.60 km SSE BEACHWOOD ROAD BW 3.93 km SE PINES ESTATE PT 4.44 km SSW EARL ROAD EA 4.60 km SSE S PLYMOUTH SUBST SP 4.62 km W ROUTE 3 OVERPASS RP 4.81 km SW RUSSELL MILLS RD RM 4.85 km WSW

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

Page 59

Figure 2.2-3 (continued)

TLD and Air/Soil Sampling Locations: 1 to 5 Kilometers Page 60 V-rý

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 MANOMET BEACH 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 CHURCH/WEST CW 16.56 km NW MAIN/MEADOW MM 17.02 km WSW DIV MARINE FISH DMF 20.97 km SSE

_1 1_1 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 K'

Page 62 BR

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

MILK Plymouth County Farm Whitman Farm Control FORAGE Whipple Farm Plymouth County Farm Whitman Farm Control VEGETABLESNEGETATION Site Boundary C Site Boundary B Rocky Hill Road Site Boundary D Site Boundary A Clay Hill Road Brook Road Beaverdam Road Plymouth County Farm Div. Marine Fisheries Bridgewater Farm Control Norton Control CRANBERRIES Manomet Point Bog Bartlett Road Bog Pine Street Bog Control 5.6 km W 34 km WNW 2.9 km 5.6 km 34 km CF WF WH CF WF BC BB RH Bd BA CH BK 3D OF

)MF 3F NIC km km km km km km km km km km km km 3.9 km 4.3 km 26 km SW W

WNW SW ESE SE SSW SSW W

SSE S

W SSE W

W SE SSE 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 Outfall 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 kr 2.7 kr 13 km 0.7 km 4.0 km 12 km 18 km 0.7 4.1 4.0 13 13 16 km km km km km km 0.5 0.5 0.9 1.1 1.5 1.6 2.9 3.4 5.6 21 31 50 n

N n SE NNW NNE ESE SSE NNW NNE W

ESE 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 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 MR BT PS

Figure 2.2-5 (continued)

Terrestrial and Aquatic Sampling Locations

\\~24KILOMETERS NORTH-NORTHWEST 34 KILOMETERS WEST.NORTHWEST 31 KILOMETERS WEST 50 KILOMETERS WEST 49 KILOMETERS SOUTHWEST 4D IGLOMETERS 64 KIU SOUTH-SOlUTWEST SOUTI 4

KILOMIETRS SOUTH-SOUTHEAST I

I Page 64

Figure 2.2-6 Environmental Sampling And Measurement Control Locations TLD Cedarville Substation Kingston Substation Landing Road Church & West Street Main & Meadow Street Div. Marine Fisheries East Weymouth Substation AIR SAMPLER East Weymouth Substation MILK Whitman Farm Control FORAGE Whitman Farm Control VEGETABLESNEGETATION Div. Marine Fish. Control Bridgewater Farm Control Norton Control CRANBERRIES Pine Street Bog Control SOIL East Weymouth Substation CS KS LR CW MM DMF EW 16 16 16 17 17 21 40 EW WF WF km km km km km km km S

WNW NNW NW WSW SSE NW 40 km NW 34 km WNW 34 km WNW DMF BF NC 21 31 50 PS EW km SSE km W km W 26 km WNW 40 km NW SURFACE WATER Powder Point Control IRISH MOSS Brant Rock Control SHELLFISH Duxbury Bay Control Powder Point Control Green Harbor Control LOBSTER Duxbury Bay Control FISHES 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 Duxbury Bay Control Green Harbor Control PP 13 km NNW BK 18 km NNW DUX-BAY 13 km NNW PP GH 13 km NNW 16 km NNW DUX-BAY 11 km NNW JR CC-BAY NR CA PT BB PC NS AO MV 13 km 24 km 24 km 32 km 32 km 40 km 48 km 48 km 48 km 64 km WNW ESE NNW SSW NE SSW SW SSE E

SSW DUX-BAY 14 km NNW GH 16 km NNW

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

Page 65 Description Code Distance/Direction* I Description Code Distance/Direction*

Figure 2.2-6 (continued)

Environmental Sampling And Measurement Control Locations MASSACHU BAY ii

<Cc CAPECOD BAY

<gýBAY

'CANAL Page 66 SYMBOL KEY

(*

LLFISH (M BLUE MUSSEL)

(S SoFr-SHELL CLAM, (H HARD-SHELL CLAM,)

C)

IRISH MOSS LOBSTER USURFACE WATER o CRANBERRY SVEGETATION/FORAGE O TLD El AIR SAMPLER 0

MILES 10 SCALE

Historical Beach Survey Exposure Rate Measurements 14 12 10, 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 m Plymouth Beach - Inner w Plymouth Beach at Berts Duxbury Beach Control Figure 2.4-1 Historical Beach Survey Exposure Rate Measurements Page 67 8

6 0

(D

0) a: e E

4 2

0

Airborne Gross-Beta Radioactivity Levels Near-Station Monitors 5.0E-02 4.OE-02 "a 3.OE-02 E

.0

(/n

=

o 2.OE-02 1.OE-02 O.OE+00 J

Mar Apr May Jun Jul Aug Month - 2001 Sep Oct Nov Dec AP-00 Warehouse

- AP-07 Pedestrian Bridge AP-08 Overlook Area AP-09 East Breakwater AP-21 East Weymouth Control Figure 2.5-1 Airborne Gross-Beta Radioactivity Levels: Near Station Monitors Page 68 Feb an f4

Airborne Gross-Beta Radioactivity Levels Property Line Monitors 5.OE-02 4.OE-02 a) 3.0E-02 E

0 o 2.0E-02 1.0E-02 Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month - 2001 AP-01 E. Rocky Hill Road w AP-03 W. Rocky Hill Road AP-06 Property Line x

AP-21 East Weymouth Control Figure 2.5-2 Airborne Gross-Beta Radioactivity Levels: Property Line Monitors Page 69 p

I I

O.OE+00 JJan

Airborne Gross-Beta Radioactivity Levels Offsite Monitors 5.OE-02 4.OE-02

( 3.OE-02 E

0 2.OE-02 1.OE-02

/

0.OE+00 Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month - 2001 AP-10 Cleft Rock

-uAP-15 Plymouth Center

-- -AP-17 Manomet Substation AP-21 East Weymouth Control Figure 2.5-3 Airborne Gross-Beta Radioactivity Levels: Offsite Monitors Page 70

Levels of Strontium-90 in Milk Samples Feb Mar Apr May Jun Jul Month - 2001 Aug Sep Oct Nov

• Plymouth County Farm Whitman Farm Figure 2.7-1 Levels of Strontium-90 in Milk Samples Page 71 5

4.

3 2

01 0

0 C.,

Jan Dec

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 2001 were reported to the Nuclear Regulatory Commission, copies of which are provided in Appendix B.

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

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

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

"* external radiation from the ocean during boating and swimming; and

"* ingestion of fish and shellfish.

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

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

"* inhalation of airborne radioactivity;

"* external radiation from soil deposition;

"* consumption of vegetables; and

"* consumption of milk and meat.

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

The dose assessment data presented were taken from the "Radioactive Effluent and Waste Disposal Report" for the period of January 1 through December 31, 2001.

Page 72

Table 3.0-1 Radiation Doses from 2001 Pilgrim Station Operations Maximum Individual Dose From Exposure Pathway - mrem/yr Gaseous Liquid Ambient Receptor Effluents*

Effluents Radiation**

Total Total Body 1.3 0.00068 2.2 3.5 Thyroid 1.5 0.00019 2.2 3.7 Max. Organ 1.5 0.0017 2.2 3.7

• Gaseous effluent exposure pathway includes combined dose from particulates, iodines 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 (10CFR20).

By comparison, the Environmental Protection Agency (EPA) limits the annual whole body dose to 25 mrem/yr, which is specified in Section 10, Part 190, Title 40, of the Code of Federal Regulations (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 2001, 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 2001, no plant-related radioactivity was detected in any of the environmental samples collected in the vicinity of Pilgrim Station that would serve as food pathways.

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

4.0 REFERENCES

1)

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

2)

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

3)

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

4)

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

5)

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

6)

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

7)

Pilgrim Nuclear Power Station Offsite Dose Calculation Manual, Revision 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) E. Vossahlik, Yankee Atomic Electric Company, Computer Program "ERMAP," Version 3.1

- January 9, 1979.

18) E. Keefer, Duke Engineering and Services, "Summary of the Results of the 2001 PNPS Beach Survey," REG 01-101, December 3, 2001.

Page 74

APPENDIX A SPECIAL STUDIES No radioactivity attributable to Pilgrim Station operations was detected in environmental samples collected during 2001. Therefore, no special dose calculation studies were performed for year 2001.

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 2001 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

a. Fission and activation gases:

b. lodines:

c. Particulates with half-life > 8 days:

d. Liquid effluents:

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

4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY

a.

b.

C.

d.

Fission and activation gases:

lodines:

Particulates:

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

a. Liquid Effluents

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

Sr-89, and Sr-90 Jan-Mar 2001 Apr-Jun 2001 12 21 3.69E+02 1.45E+03 5.OOE+01 2.20E+02 3.08E+01 6.90E+01 2.50E+01 2.30E+01 1.18E+06 6.93E+05 None None None None None None Page 77

1. REGULATORY LIMITS LICENSE: DPR-35

Table 2.1 (continued)

Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Supplemental Information July-December 2001 FACILITY: PILGRIM NUCLEAR POWER STATION

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

a. Fission and activation gases:

b. lodines:

c. Particulates with half-life > 8 days:

d. Liquid effluents:

3. AVERAGE ENERGY 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) 10CFR20 Appendix B Table II 1 OCFR20 Appendix B Table II 10CFR20 Appendix B Table II 2E-04 gCi/mL 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:

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

a. Liquid Effluents

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

Sr-89, and Sr-90 Jul-Sep 2001 Oct-Dec 2001 16 9

8.01 E+02 2.61 E+02 2.OOE+02 3.50E+01 5.01 E+01 2.90E+01 2.50E+01 2.1OE+01 1.17E+06 1.17E+06 None None None 1

None None Page 78 LICENSE: DPR-35

Table 2.2-A Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Summation of All Releases January-June 2001 Period:

Period:

I Estimated Jan-Mar 2001 Apr-Jun 2001 Total Error A. FISSION AND ACTIVATION GASES Total Release: Ci 7.78E+01 4.50E+01

+/-22%

Average Release Rate During Period:

,Ci/sec 9.86E+00 5.71 E+00 Percent of Effluent Control Limit B. IODINES Total Iodine-131 Release: Ci 2.92E-04 4.38E-04

+/-20%

Average Release Rate During Period: 4Ci/sec 3.70E-05 5.56E-05 Percent of Effluent Control Limit C. PARTICULATES Total Release: Ci 4.39E-04 7.69E-04

+/-_21%

Average Release Rate During Period: lCi/sec 5.56E-05 9.75E-05 Percent of Effluent Control Limit Gross Alpha Radioactivity: Ci NDA NDA D. TRITIUM Total Release: Ci 6.30E+01 5.29E+01

+/-20%

Average Release Rate During Period: lCi/sec Percent of Effluent Control Limit 7.98E+00 6.70E+00 Notes for Table 2.2-A:

• Percent of Effluent Control Limit values based on dose report.

assessments are provided in Section 7 of this

1. NDA stands for No Detectable Activity.

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

Page 79

Table 2.2-A (continued)

Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Summation of All Releases July-December 2001 Period:

I Period:

Estimated Jul-Sep 2001 1 Oct-Dec 2001 Total Error A. FISSION AND ACTIVATION GASES Total Release: Ci 3.45E+01 9.80E+00

+/-_22%

Average Release Rate During Period: gCi/sec 4.37E+00 1.24E+00 Percent of Effluent Control Limit B. IODINES Total Iodine-131 Release: Ci 4.77E-04 7.16E-04

+/-20%

Average Release Rate During Period: 4Ci/sec 6.04E-05 9.08E-05 Percent of Effluent Control Limit C. PARTICULATES Total Release: Ci 5.62E-04 1.35E-04

+/-21%

Average Release Rate During Period: iiCi/sec 7.12E-05 1.71 E-05 Percent of Effluent Control Limit Gross Alpha Radioactivity: Ci NDA NDA D. TRITIUM Total Release: Ci 7.03E+01 7.43E+01

+/-20%

Average Release Rate During Period: jiCi/sec Percent of Effluent Control Limit 8.91 E+00 9.41 E+00 -1 Notes for Table 2.2-A:

• Percent of Effluent Control Limit values based on do,,

report.

1. NDA stands for No Detectable Activity.

2. LLD for airborne gross alpha activity listed as NDA is

e assessments are provided in Section 7 of this 1 E-1 1 jaCi/cc.

Page 80 I

I I

I

Table 2.2-B Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Elevated Release January-June 2001 ci e

I Continuous Mode Batch Mode Nuclide Released Jan-Mar 2001 I Apr-Jun 2001 Jan-Mar 2001 I Apr-Jun 2001

1. FISSION AND ACTIVATION GASES - Ci Ar-41 3.50E+00 2.60E+00 N/A N/A Kr-85m 1.40E+01 2.OOE+01 N/A N/A Kr-87 1.86E+00 2.50E-01 N/A N/A Kr-88 2.21 E+01 5.01 E+00 N/A N/A Xe-133 1.65E+01 9.28E+00 N/A N/A Xe-133m 1.38E-01 4.90E-01 N/A N/A Xe-135 3.19E-01 7.40E-01 N/A N/A Xe-1 35m NDA NDA N/A N/A Total for period 5.84E+01 3.83E+01 N/A N/A

2. IODINES - Ci I1-131 1.55E-04 2.42E-04 N/A N/A 1-133 7.82E-04 9.58E-04 N/A N/A Total for period 9.37E-04 1.20E-03 N/A N/A

3. PARTICULATES - Ci Mn-54 2.70E-07 1.08E-05 N/A N/A Co-60 1.99E-06 3.90E-06 N/A N/A Sr-89 1.90E-05 4.45E-05 N/A N/A Sr-90 NDA NDA N/A N/A Cs-137 4.29E-07 4.16E-06 N/A N/A Ba/La-1 40 1.03E-04 2.72 E-04 N/A N/A Total for period 1.25E-04 3.35E-04 N/A N/A

4. TRITIUM - Ci H-3 I

4.37E+00 3.73E+00 N/A I

N/A Notes for Table 2.2-B:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

Fission Gases: 1E-04 gCi/cc lodines:

1E-12 pCi/cc Particulates:

1 E-1 1 gCi/cc Page 81

Table 2.2-B (continued)

Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Elevated Release July-December 2001 Continuous Mode Batch Mode Nuclide Released Jul-Sep 2001 1 Oct-Dec 2001 Jul-Sep 2001 Oct-Dec 2001

1. FISSION AND ACTIVATION GASES - Ci Ar-41 4.74E+00 NDA N/A N/A Kr-85m 8.63E+00 NDA N/A N/A Kr-87 NDA NDA N/A N/A Kr-88 7.78E-01 NDA N/A N/A Xe-1 33 1.24E+01 NDA N/A N/A Xe-133m NDA NDA N/A N/A Xe-135 1.29E+00 NDA N/A N/A Xe-135m NDA NDA N/A N/A Total for period 2.78E+01 NDA N/A N/A

2. IODINES - Ci 1-131 2.98E-04 2.56E-04 N/A N/A 1-133 1.37E-03 1.37E-03 N/A N/A Total for period 1.67E-03 1.63E-03 N/A N/A

3. PARTICULATES - Ci Mn-54 3.73E-06 6.73E-06 N/A N/A Co-60 3.93E-06 2.78E-06 N/A N/A Sr-89 3.14E-05 1.97E-05 N/A N/A Sr-90 NDA 8.14E-07 N/A N/A Cs-137 5.21 E-06 NDA N/A N/A Ba/La-1 40 2.12E-04 NDA N/A N/A Total for period 2.56E-04 3.OOE-05 N/A N/A

4. TRITIUM - Ci H-3 I

4.30E+00 3.78E+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 gCi/cc lodines:

1 E-12 ptCi/cc Particulates:

1E-11 gCi/cc Page 82

Table 2.2-C Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Ground Level Release January-June 2001 I

Continuous Mode Batch Mode Nuclide Released Jan-Mar 2001 I

Apr-Jun 2001 Jan-Mar2001 I Apr-Jun 2001

1. FISSION AND ACTIVATION GASES - Ci Ar-41 NDA NDA N/A N/A Kr-85m 9.27E-01 NDA N/A N/A Kr-87 2.91 E+00 7.40E-01 N/A N/A Kr-88 NDA NDA N/A N/A Xe-1 33 NDA NDA N/A N/A Xe-133m NDA NDA N/A N/A Xe-135 8.38E+00 2.53E+00 N/A N/A Xe-135m 7.12E+00 3.44E+00 N/A N/A Total for period 1.93E+01 6.71 E+00 N/A N/A

2. IODINES - Ci 1-131 1.37E-04 1.96E-04 N/A N/A 1-133 1.09E-03 1.32E-03 N/A N/A Total for period 1.23E-03 1.52E-03 N/A N/A

3. PARTICULATES - Ci Mn-54 NDA 3.27E-05 N/A N/A Co-60 1.05E-05 4.22E-05 N/A N/A Sr-89 1.48E-04 2.99E-04 N/A N/A Sr-90 NDA 2.41 E-06 N/A N/A Cs-137 1.74E-06 1.32E-05 N/A N/A Ba/La-1 40 1.54E-04 4.42E-05 N/A N/A Total for period 3.14E-04 4.34E-04 N/A N/A

4. TRITIUM - Ci IH-3 I

5.86E+01 I

4.91 E+01 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 gCi/cc lodines:

1 E-12 pCi/cc Particulates:

1 E-1 1 pCi/cc Page 83

Table 2.2-C (continued)

Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Ground Level Release July-December 2001 Continuous Mode Batch Mode Nuclide Released Jul-Sep 2001 1 Oct-Dec 2001 Jul-Sep 2001 Oct-Dec 2001

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 1.68E+00 N/A N/A Xe-133m NDA NDA N/A N/A Xe-1 35 6.66E+00 8.12E+00 N/A N/A Xe-135m NDA NDA N/A N/A Total for period 6.66E+00 9.80E+00 N/A N/A

2. IODINES - Ci 1-131 1.79E-04 4.60E-04 N/A N/A 1-133 1.36E-03 4.31 E-03 N/A N/A Total for period 1.54E-03 4.77E-03 N/A N/A

3. PARTICULATES - Ci Mn-54 4.83E-06 NDA N/A N/A Co-60 9.53E-06 NDA N/A N/A Sr-89 1.05E-04 1.05E-04 N/A N/A Sr-90 NDA NDA N/A N/A Cs-137 5.11 E-05 NDA N/A N/A Ba/La-140 1.35E-04 NDA N/A N/A Total for period 3.06E-04 1.05E-04 N/A N/A

4. TRITIUM - Ci H-3 I

6.60E+01 7.05E+01 N/A I

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: 1E-04 pCi/cc lodines:

1 E-1 2 gCi/cc Particulates:

1 E-11 jICi/cc Page 84

Table 2.3-A Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents - Summation of All Releases January-June 2001 Period:

Period:

Estimated Jan-Mar 2001 1 Apr-Jun 2001 Total Error A. FISSION AND ACTIVATION PRODUCTS Total Release (not including H-3, noble gas, or alpha): Ci 1.82E-03 4.98E-03

+/-12%

Average Diluted Concentration During Period: jxCi/mL 4.18E-09 4.97E-09 Percent of Effluent Concentration Limit*

3.80E-01 %

1.61 E-01 %

B. TRITIUM Total Release: Ci 2.17E-01 1.94E+01

+/-9.4%

Average Diluted Concentration During Period: W.Ci/mL 4.98E-07 1.94E-05 Percent of Effluent Concentration Limit*

4.98E-02%

1.94E+00%

C. DISSOLVED AND ENTRAINED GASES Total Release: Ci NDA NDA

+/-16%

Average Diluted Concentration During Period: riC/mL NDA NDA Percent of Effluent Concentration Limit*

NDA NDA D. GROSS ALPHA RADIOACTIVITY Total Release: Ci NDA NDA

+/-34%

E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION Waste Volume: Liters 1

2.11E+04 4.12E+05

+/-5.7%

F. VOLUME OF DILUTION WATER USED DURING PERIOD Dilution Volume: Liters 1.53E+11 1.17E+11

+/-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. NDA stands for No Detectable Activity.

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

3. 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 2001 Period:

I Period:

Estimated Jul-Sep 2001 1 Oct-Dec 2001 Total Error A. FISSION AND ACTIVATION PRODUCTS Total Release (not including H-3, noble gas, or alpha): Ci 2.OOE-03 1.45E-03

+/-12%

Average Diluted Concentration During Period: pCi/mL 2.13E-09 4.73E-09 Percent of Effluent Concentration Limit*

1.05E-01%

1.18E-01%

B. TRITIUM Total Release: Ci 7.11E-01 7.45E-03

+/-9.4%

Average Diluted Concentration During Period: gCi/mL 7.56E-07 2.43E-08 Percent of Effluent Concentration Limit*

7.56E-02%

2.43E-03%

C. DISSOLVED AND ENTRAINED GASES Total Release: Ci NDA NDA

+/-16%

Average Diluted Concentration During Period: gCi/mL I

NDA NDA Percent of Effluent Concentration Limit*

NDA NDA D. GROSS ALPHA RADIOACTIVITY Total Release: Ci NDA NDA

+/-34%

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

6.84E+04 1.60E+04

+/-5.7%

F. VOLUME OF DILUTION WATER USED DURING PERIOD Dilution Volume: Liters 1.55E+11 1.56E+11

+/-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. NDA stands for No Detectable Activity.

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

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

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Table 2.3-B Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents January-June 2001 I

Continuous Mode Batch Mode Nuclide Released Jan-Mar 2001 I Apr-Jun 2001 Jan-Mar 2001 Apr-Jun 2001

1. FISSION AND ACTIVATION PRODUCTS - Ci Cr-51 N/A N/A NDA 2.51 E-04 Mn-54 N/A N/A 4.63E-05 6.96E-04 Fe-55 N/A N/A 8.44E-06 1.63E-03 Fe-59 N/A N/A NDA 2.06E-04 Co-58 N/A N/A NDA 2.42E-05 Co-60 N/A N/A 2.03E-04 8.55E-04 Zn-65 N/A N/A 1.30E-06 6.76E-05 Sr-89 N/A N/A NDA 1.39E-05 Sr-90 N/A N/A 2.32E-05 3.99E-05 Zr/Nb-95 N/A N/A NDA 4.34E-06 Ag-110m N/A N/A NDA 1.37E-05 Sb-1 24 N/A N/A NDA 7.23E-06 Cs-137 N/A N/A 1.54E-03 1.17E-03 Total for period N/A N/A 1.82E-03 4.98E-03

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

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

Strontium:

5E-08 gCi/mL lodines:

1 E-06 gCi/mL Noble Gases:

1E-05 pCi/mL All Others:

5E-07 gCi/mL Page 87

Table 2.3-B (continued)

Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents July-December 2001 Continuous Mode Batch Mode Nuclide Released Jul-Sep 2001 1 Oct-Dec 2001 Jul-Sep 2001 Oct-Dec 2001

1. FISSION AND ACTIVATION PRODUCTS - Ci Cr-51 N/A N/A NDA NDA Mn-54 N/A N/A 1.52E-04 1.12E-04 Fe-55 N/A N/A 4.48E-04 9.18E-04 Fe-59 N/A N/A 2.18E-05 4.02E-06 Co-58 N/A N/A 1.83E-06 4.1OE-07 Co-60 N/A N/A 5.97E-04 9.78E-05 Zn-65 N/A N/A 8.97E-06 3.10E-06 Sr-89 N/A N/A 2.24E-06 NDA Sr-90 N/A N/A 1.79E-05 4.14E-06 Zr/Nb-95 N/A N/A NDA NDA Ag-110m N/A N/A 2.36E-05 NDA Sb-124 N/A N/A NDA 3.45E-07 Cs-137 N/A N/A 7.32E-04 3.07E-04 Total for period N/A N/A 2.OOE-03 1.45E-03

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

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

Strontium:

5E-08 laCi/mL lodines:

1E-06 !gCi/mL Noble Gases:

1E-05 gCi/mL All Others:

5E-07 j*Ci/mL 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 October 22 and 31, 2001.

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 2001 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

"* Clay Hill Road 1.6 km W In addition to these special sampling locations identified and sampled in conjunction with the 2001 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).

Samples of naturally-growing vegetation were also collected from the site boundary locations yielding the highest deposition (D/Q) factors for each of the two release points.

These locations, and their distance and direction relative to the PNPS Reactor Building were:

Highest Main Stack D/Q:

1.5 km SSW Highest Reactor Building Vent D/Q:

0.5 km ESE Control sample of naturally-growing vegetation was collected at the DMF shop in Sandwich (21 km SSE).

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 2001 sampling program.

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APPENDIX D ENVIRONMENTAL MONITORING PROGRAM DISCREPANCIES There were a number of instances during 2001 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 affect on the results or integrity of the monitoring program. Details of these various problems are given below.

In 2001, thirteen thermoluminescent dosimeters (TLDs) were not recovered from their assigned locations during the quarterly retrieval process. During the first quarter retrieval, TLDs were lost when utility poles to which they were attached were replaced at Emerson and Priscilla (EP),

Bayshore Drive (BS), and Sacred Heart School (SH). Several TLDs were also lost during this period when trees were cut down in vicinity of new construction projects near Russell Mills Road (RM) and Beaver Dam Road (BR).

TLDs were also lost to storm damage or premature weathering of the TLD holder during this period at Boat Launch East (BLE), Cleft Rock (CR),

and the on-site location near the compressed gas storage facility (P08). TLD losses during the second quarter at Manomet Elementary (ME) and Rte. 3A and Bartlett Road (BB) were also attributed to premature weathering of the TLD holders. During the third quarter retrieval, the TLD at Station I (I) was lost to brush-clearing activities, while the TLD at Main and Meadow (MM) was lost to a utility pole replacement. During the fourth quarter, major renovation was taking place at Memorial Hall (MH), and the TLD posted at that location was removed with construction debris. Despite these losses, the 427 TLDs that were collected (97%) allowed for adequate assessment of the ambient radiation levels in the vicinity of Pilgrim Station.

Within the air sampling program, there were a few instances in which continuous sampling was interrupted at the eleven airborne sampling locations during 2001. 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-1 31 on the filters.

Power surges resulting in blown fuses contributed to partial sampling at Manomet Substation (MS) during the period 01-08 May (137.8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> run time); Medical Building (WS) during the week of 29-May through 05-Jun (91.4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> run time); East Rocky Hill Road (ER) during the week of 17-24 Jul (87.6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> run time); and also at the Pedestrian Bridge (PB) sampler during the period 25-Dec-2001 through 01-Jan-2002 (50.9 hour1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> run time). In the cases of the WS and PB samples, the fuse was found blown, but the sampler operated correctly when the fuse was replaced. In the case of the MS and ER failures, the bearing in the pump seized and caused the fuse to blow, necessitating replacement of the sampler.

Despite the lower than normal volumes, the required LLDs were met on the particulate and charcoal samples collected in all four situations.

Efforts to shift power loads to support the refueling outage in May resulted in interruption to power at the Pedestrian Bridge (PB) and.Overlook Area (OA) air samplers. During the week of 24 Apr through 01 May, power was interrupted at Pedestrian Bridge (92.4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> run time) and Overlook Area (128.9 hour1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> run time).

The outage continued into the following week at Pedestrian Bridge (0.0 hour0 days <br />0 hours <br />0 weeks <br />0 months <br /> run time). Required LLDs were met on samples collected during the earlier week, but no samples were collected or analyzed during from the PB air sampler during the second week.

Page 90

During the week of 29 May through 05 Jun, ants invaded the small shelter housing the air sampler at the East Weymouth (EW). Nest building activity by the ants caused the ground fault circuit interrupt (GFCI) to trip, interrupting power to the sampler. This resulted in run times of 37.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> during the week of 29 May through 05 Jun, and 97.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> during the following week of 05-12 Jun. Steps were taken to exterminate the ants from this location, and place ant bait in remaining sampler housings to prevent further recurrence. Despite the low sample flows, the required LLDs for particulate radioactivity and iodine-131 were met on both of these samples.

During the period 11-18 Dec, the sample hose connecting the vacuum pump to the filter holder became detached from the sample pump at the East Breakwater (EB). The pump had been replaced during the previous week as part of routine maintenance, and it was thought that vibration of the pump might have loosened the connection. This resulted in a situation in which no air was drawn through the filter during the sampling period. The filters were collected and analyzed, and no gross beta activity was detected, verifying that no sampling occurred during the period.

Despite the lower-than-normal sampling volumes in the various instances involving power interruptions and equipment failures, required LLDs were met on 571 of the 571 particulate filters and 571 of the 571 iodine cartridges collected during 2001. 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 2001, the following sampling recoveries were achieved in the airborne sampling program:

Location Recovery Location Recovery Location Recovery WS 98.7%

PB 95.7%

PC 100.0%

ER 98.9%

OA 99.3%

WS 99.7%

WR 100.0%

EB 100.0%

EW 97.7%

PL 100.0%

CR 100.0%

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

2001, 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).

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.

In addition to these substitute samples, samples of naturally-growing vegetation were also collected in the three locations yielding the highest calculated deposition coefficients (D/Q) for airborne releases from PNPS.

Such samples represent "worst case" samples for comparison, as the deposition and resulting ground-level concentrations of radionuclides at these locations would be 2 to 10 times higher than at the gardens identified during the land use census. 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 E of this report.

Page 91

In the sampling of water from the discharge canal, two problems were encountered during 2001.

During the period 06-13 March, the peristaltic pump hose in the water sampler failed, and a grab sample was collected in lieu of the weekly composite sample during this period.

The defective hose was replaced. During the following week of 13-20 Mar, the sampler failed to collect a composite water sample due to the sampling hose being out of the water. The hose had become detached from its anchor in the canal during heavy wave action, and washed up onto the edge of the canal, preventing the collection of a complete sample. A grab sample was also collected in response to this event, and the sample line was secured to a line anchored in the discharge canal on 26-Mar. No problems have occurred since that event.

Samples of Group I (bottom-distribution) and Group II (near-bottom distribution) fishes were not collected in the vicinity of the discharge outfall during the first and fourth calendar quarters of 2001. 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.

Prolonged adverse weather conditions during the latter part of the first quarter prevented collection of the Irish moss sample from Ellisville Harbor (EL). Normal sampling was resumed during second quarter, and the three remaining samples were collected during the year.

Some problems were encountered in collection of crop samples during 2001. Root crops were not grown at the Plymouth County Farm (CF) during 2001, so it was deemed unnecessary to collect a corresponding control sample for this sample type from the control location in Bridgewater.

However, samples of leafy vegetation were collected as required.

The NRC guidance on environmental sampling implies sampling of non-leafy (e.g., root) vegetables to monitor for radioactivity in crops irrigated by water affected by liquid plant effluents.

Since PNPS discharges into Cape Cod Bay, and no such irrigation pathways exist at Pilgrim Station, the absence of a root crop sample from Plymouth County Farm does not compromise the monitoring efforts. Collection and sampling of leafy vegetation, as was performed, provides a better indication of potential deposited radioactivity released from Pilgrim Station in gaseous effluents.

The cranberry bog at Manomet Point (MP) was not in production during 2001, 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.

In summary, the various problems encountered in collecting and analyzing environmental samples during 2001 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 QUALITY ASSURANCE PROGRAM RESULTS 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 Duke Engineering and Services Environmental Laboratory (DESEL).

Much of the information contained herein has been summarized from the DESEL "Semi-Annual Quality Assurance Status Report: January - June 2001," and the DESEL "Semi Annual Quality Assurance Status Report: July - December 2001."

Laboratory Analyses The quality control programs that were performed during 2001 to demonstrate the validity of laboratory analyses by DESEL 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:

DESEL 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.

"* DESEL participation in a crosscheck program with Analytics, Inc. for environmental air filter, water, and milk samples.

DESEL 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.

DESEL Intralaboratory and Independent Interlaboratory Results Results of the Quality Assurance Program are reported in two separate categories based upon DESEL acceptance criteria.

The first criterion concerns accuracy, which is defined as the deviation of any one result from the assumed known value. The second criterion concerns 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.

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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 2001 for DESEL intralaboratory analyses, as well as Analytics and NIST interlaboratory crosscheck analyses.

A total of 600 analyses were performed for accuracy cross-comparisons, while 396 crosscheck analyses were performed to assess precision. For accuracy, 63.8% and 83.0% of the results were within 5 and 10 percent of the known values, respectively, with 96.3% of all results falling within the laboratory criterion of 15 percent. For precision, 83.3% and 94.7% of the results were within 5 and 10 percent of the mean, respectively, with 99.5% of all results meeting the laboratory criterion of 15 percent.

TABLE E.1 INTRALABORATORY AND INTERLABORATORY RESULTS - 2001 Fraction of Measurements Total Number of within deviation range Category Measurements

+/- 5%

+/- 10%

15%*

DESEL INTRALABORATORY ANALYSES Accuracy 290 68.6%

82.4%

97.9%

Precision 86 73.3%

89.5%

100.0%

ANALYTICS INTERLABORATORY ANALYSES Accuracy 304 60.5%

84.2%

95.7%

Precision 304 86.5%

96.1%

99.3%

NIST INTERLABORATORY ANALYSES Accuracy 6

0.0%

50.0%

50.0%

Precision 6

66.7%

100.0%

100.0%

TOTAL COMBINED ANALYSES Accuracy 600 63.8%

83.0%

96.3%

Precision 396 83.3%

94.7%

99.5%

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

which were The results of the numerous intercomparisons performed during 2001 validate the quality of the analyses performed by DESEL.

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

Blind Duplicate Program A total of 31 paired samples were submitted for analysis during 2001. 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 confidence level) is established for each of the analyses. If the confidence intervals for the two analyses overlap, agreement is obtained.

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From the 31 paired samples, 801 paired duplicate measurements were analyzed during 2001.

Out of these measurements, 796 (99.4%) fell within the established criteria discussed above.

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

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

Environmental TLD Measurements Quality control testing was performed during 2001 to demonstrate the performance of the routine environmental TLD processing by DESEL. The quality of the dosimetric results is evaluated relative to independent third party testing and internal performance testing. These tests were performed independent of the processing of environmental TLDs at DESEL. In all of these tests, dosimeters were irradiated to known doses and submitted to DESEL 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.

DESEL 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 2001 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 performance 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 2001, there were 84 quality control tests.

All 36 environmental TLDs tested during January - June 2001 were within the control limits for both accuracy and precision.

The comparisons yielded a mean accuracy of +1.61 %.

The comparisons exhibited a precision value with an overall standard deviation of 0.99%. The 48 TLDs tested in July - December 2001 showed a mean accuracy of +1.22%. TLDs measured during the second semiannual period exhibited a precision value with a standard deviation of 1.52%, well within the acceptance criteria.

In total, all 84 environmental TLDs tested during 2001 were within the control limits for both accuracy (+/- 20.1%) and precision (+/- 12.8%).

Page 95

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

EPA, Analytics, DOE, and NIST), the DESEL 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 Duke Engineering and Services Environmental Laboratory during 2001 exhibited acceptable accuracy and precision.

Page 96

APPENDIX F CORRECTED 2000 SEDIMENT ANALYSES RESULTS As part of the reviews of environmental monitoring data, comparisons are made to results obtained from earlier years.

Upon receipt of the plutonium analyses results for sediment samples in 2001, it was noted that the results for plutonium-238 (Pu-238) collected during 2000 appeared to be abnormally high, especially at the control location in Duxbury. These results are presented in Table F.1 TABLE F.1 Historical Plutonium-238 Sample Results - pCi/kg Location / Sample Depth Discharge Discharge Duxbury Duxbury Manomet Ply Harbor Year 0-2 cm 12-14 cm 0-2 cm 12-14 cm 0-2 cm 0-2 cm 1987 NDA NDA NDA NDA NDA NDA 1988 NDA NDA NDA NDA NDA NDA 1989 NDA NDA NDA NDA NDA NDA 1990 NDA NDA NDA NDA NDA NDA 1991 NDA NDA NDA NDA NDA NDA 1992 NDA NDA NDA NDA NDA NDA 1993 NDA NDA NDA NDA NDA NDA 1994 NDA NDA NDA NDA NDA NDA 1995 NDA NDA NDA NDA NDA NDA 1996 NDA NDA NDA NDA NDA NDA 1997 NDA NDA NDA NDA NDA NDA 1998 NDA NDA Missing NDA NDA NDA 1999 NDA NDA NDA NDA NDA NDA 2000 NDA 9.9 707 506 NDA 1.19 2001 NDA NDA NDA NDA NDA NDA The elevated Pu-238 levels observed in the 2000 samples were initially attributed to the physical nature of the Duxbury samples, which have historically contained detectable Pu-239/240 from fallout from nuclear weapons testing in the 1950s, 60s, and 70s.

After receiving the 2001 results, the results from the previous year were again called into question, and a more detailed historical review of past plutonium results was performed.

As is evident in the above table, plutonium-238 has not historically been detected in sediment samples.

This observation prompted a thorough review of the results and methods at the analytical laboratory that performs the sediment analyses. It was determined that no changes had been made to the analytical procedures, methods, or equipment used since the previous year.

Based on the fact that the laboratory also performs plutonium analyses for soil samples at Department of Energy cleanup sites, laboratory personnel concluded that cross-contamination of the samples was responsible for the anomalous results. Specialized Teflon glassware is utilized in the processing of soil and sediment samples for plutonium analysis.

Due to the expense of this glassware, it is reused from one analysis to the next. Although efforts are made to thoroughly clean the glassware prior to reuse, very low levels of residual activity can remain Page 97

on the surfaces of the containers. The relatively high Pu-238 concentrations encountered in some of the soil samples processed from the DOE sites likely left residual contamination in the glassware.

When that glassware was subsequently used to process the PNPS sediment samples, that residual activity was detected and falsely attributed to the PNPS samples. The laboratory has since taken steps to segregate glassware used to process high-activity samples from that used to process presumably 'clean' samples.

Based on the conclusion of sample cross-contamination, results for 2000 were revised to remove the anomalous values. Since 2000 samples had already been disposed of, reanalysis was not possible to generate new/revised results.

Based on historical Pu-238 results, the results for 2000 were all deemed to be 'Non-Detectable'. Revised tables from the 2000 report, reflecting the updated values, are presented on the following pages.

Page 98

Table 2.17-1 Sediment Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2000)

IVIELfIU

Ih SedUIlmen*t LO*J JII H1.

I-6 I

Pkau uFY Indicator Stations Mean Required Range I I f" 11..-

nI.~,+.J*

Station With Highest Mean Ste. Mean Range Control Stations Mean Range k n-I oultne UULi LINIo. LIttLcb-U I

INU, DJtetULedU I

INo.

LDeetedU1u Be-7 (56)

(0)

K-40 (56)

(0)

Co-58 (56)

(0)

Co-60 (56)

(0)

Zn-65 (56)

(0)

Zr-95 (56)

(0)

Cs-1 34 (56)

(0)

Cs-1 37 (56)

(0)

Ce-144 (56)

(0)

Th-232 (56)

(0)

Pu-238 (6)

(0)

Pu-239 (6)

(0)

( 3.4 +/- 6.0)E 1

(-4.9 - 30.2)E 1 (4/39)

( 9.1 +/- 1.5)E 3

( 6.5-13.3)E 3 (39/39) 50

(-2.8 - 3.2)E 0

(-9.1 -5.5)E 0 (0/39) 50

(-3.2 - 23.8)E -1

(-5.1 -4.1)E 0 (0/39) 50 (1.1 1.2)E 1

(-1.6-4.1)E 1 (0/39) 50

( 5.4 +/- 4.3)E 0

(-4.0 - 15.8)E 0 (0/39) 50

(-5.3 +/- 70.4)E -1

( -1.6 - 1.9)E 1 (0/39) 50

( 4.7 +/- 9.2)E 0

( -5.6 - 30.7)E 0 (8/39) 150

( 5.6 +/- 168.0)E -1

(-3.9-3.1)E 1 (0/39)

( 3.1 +/- 0.9)E 2

( 1.5-5.5)E 2 (39/39) 25 NDA NDA (0/4) 25

( 4.1 +/- 2.4)E 0

( 2.5 - 7.6)E 0 (2/4) 13

( 1.3+3.8)E 2

(-3.1 - 126.5)E 1 (3/11) 13

( 1.3 +/- 0.2)E 4 1.1-1.7)E4 (11/11) 13

(-1.7:+/- 8.3)E 0

(-8.1 - 21.2)2 0 (0/11) 11

( 4.7 +/- 27.0)E -1

(-3.5-4.1)E 0 (0/11) 11

( 1.4 +/- 1.3)E 1

(-4.0 - 41.2)E 0 (0/11) 13

( 1.0+/- 0.8)E 1 2.3 - 25.6)E 0 (0/11) 11

( 1.6 +/- 9.0)E 0

(-1.0 - 1.9)E 1 (0/11) 13 (2.0+/-0.6)E1 1.2 - 2.9)E 1 (10/11) 14

( 7.1 +/- 16.1)E 0

(-1.5 - 3.1)E 1 (0/6) 13

( 4.8 +/- 0.9)E 2

( 3.9 - 7.2)E 2 (11/11) 13 NDA NDA (0/2) 13

( 1.7 +/- 0.4)E 1 1.6-1.9)E1 (2/2)

Page 99 Radionuclides (No. Analyses)

( 9.5 +/- 30.6)E 1

(-5.2 - 126.5)E 1 (3/17) 1.2+/-0.2)E4 8.8 - 16.5)E 3 (17/17)

(-2.7 +/- 6.9)E 0

(-8.9 - 21.2)E 0 (0/17)

(1.2:+/- 34.9)E -1

(-5.3 - 6.5)E 0 (0/17) 8.9 +/- 15.2)E 0

(-1.8 - 3.6)E 1 (0/17) 8.7 +/- 6.7)E 0

(-4.3 - 256.2)E -1 (0/17)

(-5.0:+/- 12.0)E 0

(-3.2 - 1.7)E 1 (0/17)

(1.5 +/- 0.9)E 1

(-1.6 - 29.5)E 0 (10/17)

(-3.2 +/- 26.2)E 0

(-6.2 - 2.7)E 1 (0/17)

( 4.4 +/- 1.0)E 2

( 2.9 - 7.2)2 2 (17/17)

NDA NDA (0/2)

(1.7 +/- 0.4)E 1 (1.6-1.9)E 1 (2/2)

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

• • The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.

l IF.IITO.

.t*111.^

• I--,

Table 2.17-2 Sediment Plutonium Analyses Environmental Radiological Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 2000)

• NDA indicates no detectable activity.

a Updated value.

Page 100 pCi/kg (dry) +/- 1 S.D.

Location Core Depth (cm)

Plutonium-238 Plutonium-239/240 Discharge Canal Outfall 0 - 5 NDA NDA Discharge Canal Outfall 5 - 10 NDAa NDA Plymouth Harbor 14 - 16 NDAa 7.56 +/- 0.76 Manomet Point 0 - 2 NDA 2.45 +/- 0.45 Duxbury Bay - Control 0 - 2 NDAa 15.6 +/- 4.5 Duxbury Bay - Control 12-14 NDAa 19.2 +/- 4.1