ML20138F321

Radiological Environ Monitoring Program Rept No 29,Jan-Dec 1996

ML20138F321
Person / Time
Site:	Pilgrim
Issue date:	12/31/1996
From:	Fountain D, Olivier L, Sejkora K BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
29, BECO-2.97.049, NUDOCS 9705050352
Download: ML20138F321 (99)

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Technical Specification 6.9.C.2 h "

Boston Edison Pilgnm Nuclear Power Staton Rocky Hill Road

• Plymouth, Massachusetts 02360 L. J. Olivier Vice President Nuclear Operations April 29, 1997 are station oirector BECo Ltr. 2.97.049 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 License No. DPR-35 Docket No. 50-293 In accordance with the Pilgrim Nuclear Power Station Technical Specification 6.9.C.2, Boston Edison Company submits the Annual Radiological Environmental Monitoring Program Report for 1996 (Report #29).

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RLC/dmc/9449 Attachment cc: Mr. Hubert Miller Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Alan B. Wang One White Flint North - Mail Stop 1482 11555 Rockville Pike Rockville, MD 20852

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Senior Resident Inspector gj 9705050352 961231 PDR ADOCK 05000293 llElllI.

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PILGRIM NUCLEAR POWER STATION Radiological Environmental Monitoring Program Report No. 29 l

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& Boston Edison PILGRIM NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT NO. 29 JANUARY 01 THROUGH DECEMBER 31,1996 Prepared by: 4 #4h,pgr_

K.J. / C/

SeniorSejkor(ironmental Env Radiochemist Reviewed by[O) O. A V!av 9 7 D.W. Fountain Chemistry Department Manager i Approved by: @ RW S.R. Landahl Radiation Protection Manager Page 1 l

Pilgrim Nucleet Power Station Radiological Enwamental Monitoring Program Report January-December 1996 TABLE OF CONTENTS SECTION SECTION TITLE PAGE EXECUTIVE

SUMMARY

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1.0 INTRODUCTION

7 1.1 Radiation and Radioactivity 7 1.2 Sources of Radiation 8 1.3 Nuclear Reactor Operations 9 1.4 Radioactive Effluent Control 14 i 1.5 Radiological Impact on Humans 17 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 22

= 2.1 Pre-Operational Monitoring Results 22 2.2 Environmental Monitoring Locations 23 2.3 Interpretation of Radioactivity Analyses Results 24 2.4 Ambient Radiation Measurements 26 2.5 Air Particulate Filter Radioactivity Analyses 28 2.6 Charcoal Cartridge Radioactivity Analyses 28 2.7 Milk Radioactivity Analyses 28 I 2.8 Forage Radioactivity Analyses 29 2.9 Vegetable / Vegetation Radioactivity Analyses 29 2.10 Cranberry Radioactivity Analyses 30 2.11 Soil Radioactivity Analyses 30 2.12 Surface Water Radioactivity Analyses 31 1 2.13 Irish Moss Radioactivity Analyses 31 2.14 Shellfish Radioactivity Analyses 31 2.15 Lobster Radioactivity Analyses 31 2.16 Fish Radioactivity Analyses 32 2.17 I 3.0 Sediment Radioactivity Analyses

SUMMARY

OF RADIOLOGICAL IMPACT ON HUMANS 32 72

4.0 REFERENCES

74 APPENDIX A Special Studies 75 APPENDIX B Effluent Release Information 76 APPENDIX C Land Use Census 89 APPENDIX D Environmental Monitoring Program Discrepancies 90 APPENDIX E Quality Assurance Program Results 93 Page 2

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I Pilgrim Nuclear Power Station Radiological Environmental Monitoring Program Report January-December 1996 LIST OF TABLES TABLE TABLE TITLE PAGE 1.2-1 Radiation Sources and Corresponding Doses 8 1.3 1 PNPS Operating Capacity Factor During 1996 9 2.2-1 Routine Radiological Environmental Sampling Locations 34 2.4-1 Off-site Environmental TLD Results 36 2.4-2 On-site Environrnental TLD Results 38 2.4-3 Average TLD Exposures By Distance Zone During 1996 39 2.4-4 Beach Survey Exposure Rate Measurements 40 I 2.5-1 2.6-1 Air Particulate Filter Radioactivity Analyses Charcoal Cartridge Radioactivity Analyses 41 42 2.7-1 Milk Radioactivity Analyses 43 2.8-1 Forage Radioactivity Analyses 44 2.9-1 VegetableNegetation Radioactivity Analyses 45 2.10-1 Cranberry Radioactivity Analyses 46 2.11-1 Soil Radioactivny 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 5'2 '

2.17-1 Sediment Radioactivity Analyses I

53 l 2.17 2 Sediment Plutonium Analyses 54 i 3.0-1 Radiation Doses From 1996 Pilgrim Station Operations 73 1

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! Radiological Environmental Monitoring Program Report January-December 1996 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 l

! 1.5-1 Radiation Exposure Pathways 19 l

, 2.2-1 Environmental TLD Locations Within the PNPS Protected Area 55 2.2-2 TLD and Air Sampling Locations: Within 1 Kilometer 57 2.2-3 TLD and Air Sampling Locations: 1 to 5 Kilometers 59

2.2-4 TLD and Air Sampling Locations

5 to 25 Kilometers *

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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 Airbome Gross Beta Radioactivity Levels: Property Line 69 2.5-3 Airbome Cross Beta Radioactivity Levels: Off-Site 70 2.7-1 Levels of Strontium-90 in Milk Samples 71 l

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l EXECUTIVE

SUMMARY

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION

, RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT JANUARY 01 THROUGH DECEMBER 31,1996 INTRODUCTION This report summarizes the results of the Boston Edison Company's Radiological I Environmental Monitoring Program (REMP) conducted in the vicinity of Pilgrim Nuclear Power Station (PNPS) during the period from January 1 to December 31,1996. This document has been prepared in accordance with the requirements of PNPS Technical Specifications section 6.9.C.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.

I SAMPLING AND ANALYSIS I 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.

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During 1996, there were 1,401 samples collected from the atmospheric, aquatic and terrestrial environments. In addition,432 exposure measurements were obtained using environmental themioluminescent dosimeters (TLDs) and six exposure rate measurements were performed using a high pressure ion chamber. All of the various samples and TLDs were collected by Boston Edison Company and Massachusetts Division of Marine Fisheries personnel.

A few minor problems were encountered during 1996 in the collection of environmental samples in accordance with the PNPS Technical Specifications. Eight out of 440 TLDs were missing from their posted locations during the quarterly retrieval process. Equipment failures and power outages resulted in missing six out of the required 583 airbome particulate filters, I and six of the 583 charcoal filters. One air particulate filter was lost at the analyticallab prior to processing. Due to seasonal unavailability of Group I (bottom distribution) and Group 11 (near-i bottom distribution) fishes in the vicinity of the discharge canal, these samples were missed during the first quarter of 1996. A full description of the discrepancies encountered with the environmental monitoring program is presented in Appendix D of this report. l l

I There were 1,579 analyses performed on the environmental media samples. All analyses were performed by the Yankee Atomic Electric Company Environmental Laboratory in Westborough, Mass. All samples were analyzed as required by the PNPS Technical l Specifications.

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l LAND USE CENSUS The annual land use census in the vicinity of Pilgrim Station was conducted as required by lg Technical Specifications between October 10 and 31,1996. A total of 33 gardens having an l5 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 33 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 1996, all samples (except charcoal cartridges) collected as part of the REMP at Pilgrim iE Station continued to contain detectable amounts of naturatiy-occurring and man-made

,3 radioactive materials. The only sample collected in 1996 which showed detectable activity potentially attributable to PNPS operations was blue mussel shells collected from the discharge canal outfall. Since this medium is non-edible, the low level of cobalt-60 detected in

, this sample does not represent a normal exposure pathway, and no dose assessment was performed. Off-site ambient radiation measurements using environmental TLDs and a high pressure ion chamber ranged between 45 and 97 mR/ year. This range of ambient radiation

.E levels is consistent with natural background radiation levels for Massachusetts as determined 5 by the Environmental Protection Agency (EPA).

RADIOLOGIQAL IMPACT TO THE GENERAL PUBLIC 1

During 1996, radiation doses to the general public as a result of Pilgrim Station's operation i

.I continued to be well below the federal limits and much less than the dose due to other man-made and naturally-occurring sources of 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 1996 was about 2.7 mrem for the year. This conservative estimate is well below the EPA's annual dose limit to I 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 1996 Radiological Environmental Monitoring Program for Pilgrim Station resulted in the

.I 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 evaluatin 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 which are normally present due to natural and man-made background radiation.

! Based on this information, there is no evidence of any 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 1996 performed by Boston Edison 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 6.9.C.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 31,1996.

The Radiological Environmental Monitoring Program consists of taking radiation I 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 BECo's radiological staff and have been I reported semiannually or annually to the Nuclear Regulatory Commission and others since 1972.

i 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 i understanding the radiological impact on the environment and humans from the operation of l 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. l Radioactive material exists naturally and has always been a part of our environment. The l 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 which 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 I 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 Correspondina 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 pproximate Total 300 Approximate Total 60 Cosmic radiation from the sun and outer space penetrates the earth's atmosphere and l continuously bombards us with rays and charged particles. Some of this cosmic radiation I 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, i

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

1 l levels of radon / thoron gases in these areas. In total, these various sources of naturally-l occurring radiation and radioactivity contribute to a total dose of about 300 mrem per year l

l In addition to natural radiation, we are normally exposed to radiation from a number of man-l made sources. The single largest doses from man-made sources result from therapeutic and I

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

'elevisions and smoke detectors, contribute about 10 mrem /yr. Much smaller doses result from l 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

'g electricity to supply the entire city of Boston, Massachusetts. Pilgrim Station is a boiling water g 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 1996. Monthly capacity factors are given in Table 1.3-1.

TABLE 1.3-1 PNPS OPERATING CAPACITY FACTOR DURING 1996 I (Based on 670 MWe) l Month Percent Capacity January 92.1 February 99.4 March 99.3 I April May 75.9 98.2 June 94.3 July 95.3 August 92.3 September 51.4 October 94.0 November 94.9 December 97.7

, Average 90.4 l

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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 fuelis depleted or spent. This process is called a chain reaction.

.I 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 I products and radioactive activation products.

Radioactive fission products, as illustrated in Figure 1.3-1 (Reference 5), originate from the l 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 i

the fuel cladding. These fission products circulate along with the reactor coolant water and will j 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 l (Cs-137). )

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Nuclear Fission

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

Radiation and fission products are by-products of the process, uranium [

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1 Radioactive activation products (see Figure 1.3-2), on the other hand, originate from two sources. The first is by neutron bombardment of the hydrogen, oxygen and other gas (helium, l 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, I activation products are nothing more than ordinary naturally-occurring atoms that are made unstable or radioactive by neutron bombardment. These activation products circulate along with the reactor coolant water and will deposit on the intemal surfaces of pipes and equipment.

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

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Neutron Stable Radioactive Cobalt Nucleus Cobalt Nucleus I

I Figure 1.3-2 Radioactive Activation Product Formation I 1 1

I 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 l (Reference 5), are:

1) fuel pellets;

2) fuel cladding;

3) reactor vessel and piping;

4) primary containment (drywell and torus); and,

5) secondary containment (reactor building).

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SIMPLIFIED DIAGRAM OF A BOILING WATER REACTOR l

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I REACTOR BUILDING DRMELL Figure 1.3-3 Barriers To Confine Radioactive Materials Page 13

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l The ceramic uranium fuel pellets provide the first barrier. Most of the radioactive fission i products are either physically trapped or chemically bound between the uranium atoms, where l they will remain. However, a few fission products which are volatile or gaseous may diffuse {

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

1 The third barrier consists of the reactor pressure vessel, steel piping and equipment that .

confines 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 I 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.

1 The fourth barrier is the primary containment. This consists of the drywell and the torus. The I drywell is a steel lined enclosure that is shaped like an inverted light bulb. The drywell's steel pressure vessel is enclosed by an approximately five foot thick concrete wall. The torus is a donut-shaped pressure suppression chamber. The steel walls of the torus are nine feet in l

diameter with the donut itself having an outside diameter of about 130 feet. Small amounts of I 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 which may escape from the primary containment. This reactor building is equipped with a filtered ventilation systern that is used when needed to reduce the radioactivity that escapes from the primary containment.

Most of the radioactive fission and activation products are confined by the five barriers.

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 I 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, l and monitored by a variety of systems and procedures which include. j e reactor water cleanup system; liquid radwaste treatment system;

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. sampling and analysis of the liquid radwaste tanks; and, e 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 ihat 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 I 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 neutrailizing 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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I The preceding discussion illustrates that many controls exist to reduce the radioactive liquid I effluents released to the Cape Cod Bay to as far below the release limits as is reasonably achievable.

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

. reactor building ventilation system;

. reactor building vent effluent radioactivity monitor; I

. sampling and analysis of reactor building vent effluents;

. standby gas treatment system;

. main stack effluent radioactivity monitor and sampling;  ;

e sampling and analysis of main stack effluents; e augmented off-gas system; )

. steam jet air ejector (SJAE) monitor; and, e off-gas radiation monitor.

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

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 which 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 l I 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 i

total amount of tritium and radioactive gaseous and particulate effluents released.

If air containing elevated amounts of noble gases is routed rmst the reactor building vent's I effluent radioactivity monitor, an alarm will alert the Control R un operators that release limits are being approached. The Coritrol Room operators, accc* og 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 which further reduces concentration levels of gaseous releases to the environment to as far I below the release limits as is reasonably achievable.

The approximately 330 foot tall main stack has a special probe inside it which 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 E 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.

I 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 g -

I l remove radioactive particulates. The recombiner collects free hydrogen and oxygen gas and recombines them into water. This helps reduce the gaseous releases of short-lived isotopes of 1 oxygen which 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 g low as is reasonably achievable. The effluents are always monitored, sampled and analyzed l

3 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 I automatically shut to stop the release, or Control Room operators will implement procedures to ensure that federal regulatory limits are always met. l

1.5 Radioloaical Impact on Humans l

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 i 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 1996 were reported to the Nuclear Regulatory Commission semiannually. The 1996 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 Technical Specifications operational objectives.

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 (wate ed meteorological (atmospheric) characteristics in the area. Information on the water flow, /ind speed, wind direction, and atmospheric mixing characteristics are used to estimate how radioactivity will distribute and disperse in the ocean and the atmosphere.

I Page 17

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

The radiation exposure pathway to humans is the path radioactivity takes from its release point at Pilgrim Station to its 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:

1) extemal radiation from liquid effluents that deposit and accumulate on the

shoreline;

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

3) intemal 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:

1) external radiation from an airborne plume of radioactivity;

2) intemal radiation from inhalation of airborne radioactivity;

3) extemal radiation from deposition of radioactive effluents on soil;

4) intemal radiation from consumption of vegetation containing radioactivity absorbed from the soil due to ground deposition of radioactive effluents; and,

5) internal radiation ' rom consumption of milk and meat containing radioact..ay deposited on forag s which is eaten by cattle and other livestock.

In addition, ambient (direct) rarbibn emitted from contained sources of radioactivity at PNPS

'I contribute 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 I measurements of radiation and radioactivity in the environment. When PNPS-related activity is detected in samples which 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

.g is naturally present in the environment. Therefore, radiation doses are calculated using g 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 Boston Edison Co.

personnel. These computer codes use the guidelines and methodology set forth by the NRC Page 18

I in Regulatory Guide 1.109 (Reference 6). The dose calculations are documented and described in detail in the Pilgrim Nuclear Power Station's Off-site Dose Calculation Manual (Reference 7) which has been reviewed by the NRC.

Monthly dose calculations are performed by Boston Edison Co. personnel. Semiannual dose calculations are performed for Boston Edison Co. by Yankee Atomic Electric Co., using their advanced "YODA" computer program. 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.

I

'I II

!I I

g e... se

EXAMPLES OF PILGRIM STATION'S RADIATION EXPOSURE PATHWAYS X

j GA'SEOUSL I, SEFFLOENTS

""" j. ...:. i jgt  :

p l uouio im.. m y ,j EFFLUENTS f . j I /

, A B. ~

3. DIRECT RADIATION

( TATION) 2. AIR INHALATION

4. DIRECT RADIATION I (SOIL DEPOSITION) 1. DIRECT RADIATION i _

1. SHORELINE DIRECT RADIATION N v (AIR SUBMERSION)

(FISHING, PICNICJNG)

5. CONSUMPTION 1 (VEGETATION) j DEPOSITION I 2. DIRECT RADIATION (IMMERSION IN OCEAN, D

BOATING, SWIMMING)

[ G e GGGb Awarre eie I 6. CONSUMPTION (MILK AND MEAT)

DEPOSITION

3. CONSUMPTION (FISH, SHELLFISH) A jg .L - vINGESTION

. l.,.?hX N'*:*:@?W

.. k . '.' . .

Figure 1.5-1 Radiation Exposure Pathways Page 20

l 1

After dose calculations are performed, the results are compared to the federal dose limits for

I the public. The two federal agencies that are charged wnh the responsibility of protecting the i

public from radiation and radioactivity are the Nuclear Regulatory Commission (NRC) and The j Environmental Protection Agency (EPA).

,I i i

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

I .

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

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

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

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

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

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

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, I

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

The summary of the 1996 radiologicalisopact 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 1996 is discussed in Section 2 of this report.

g -

l I

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

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

2) 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 1 years, from August 1968 to June 1972. Examples of background radiation and radioactivity j levels measured during this time period are as follows: I

. Airbome Radioactivity Particulate Concentration (gross beta): 0.02 - 1.11 pCi/m';

I

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

. Seawater Radioactivity Concentrations (gross beta): 12 - 31 pCi/! iter;

. 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-137 Concentra1ons: 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 Co. 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:

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

2) 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;

3) checking the condition of the station's operation, the adequacy of operation in I 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

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

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

The Nuclear Regulatory Commission requires that Boston Edison Company provide monitoring I of the plant environs for radioactivity that will be released as a result of normal operatiorm, including anticipated operational occurrences, and from postulated accidents. The NRC has established guidelines (Reference 14) which specify an acceptable monitoring program. The Boston Edison Company's 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 I 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.

I 2.2 Environmental Monitorina 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 which 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 1996 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 Technical Specifications, Sections 7.0/8.0.

The land-based (terrestrial) samples and monitoring devices are collected by Boston Edison personnel from the Electrical Engineering and Station Operation Department's Environmental

' I Laboratory. The aquatic samples are collected by the Division of Marine Fisheries - Pilgrim Station Project personnel. The direct radiation measurements and soil radioactivity measurements are conducted by Yankee Atomic Electric Company, Radiological Engineering Group and Environmental Laboratory personnel, respectively. The radioactivity analysis of samples and the processing of the environmental TLDs is performed by Yankee's 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 Technical Specifications.

Upon receipt of the analysis results from Yankee Atomic Electric Co., the Boston Edison staff reviews the rasults. If the radioactivity concentrations are above the reporting levels, the NRC Page 23

I

.g must be notified within 30 days. For radioactivity which is detected that is attributable to

g Pilgrim Station's operation, calculations are performed to determine the cumulative dose contribution for the current year. Depending upon the circumstances, a special study may also be completed (see Appendix A for 1996 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 1996 Garden and Milk Animal Census are reported )

in Appendix C. i I The accuracy of the data obtained through Boston Edison Company's Radiological Environmental Monitoring Program is ensured through a comprehensive Quality Assurance (QA) program. BECo's QA program has been established to ensure confidence in the l

measurements and results of the radiological monitoring program through:

. Regular surveillances of the sampling and monitoring program; e An annual audit of the analytical laboratory by the sponsor companies;

. Participation in the United States Environmental Protection Agency and other cross- l check programs; a

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 Boston Edison Company's Quality Assurance Department.

I The blind duplicates, split samples and spiked samples are analyzed by Boston Edison Company, Yankee Atomic Electric Company's Environmental Laboratory, and the other four sponsor companies. The 1996 results of this QA program are summarized in Appendix E.

These results indicate that the analyses and measurements performed during 1996 exhibited I acceptable precision and accuracy.

2.3 Interpretation of Radioactivity Analyses Results The following pages summarize the analytical results of the environmental samples collected I during 1996. Data for each environmental medium are included in a separate section. A discussion of the sampling program and results is followed by a table which summarizes the year's data for each type of medium. The tables were generated by the Yankee Atomic Electric Company's ERMAP computer program (Reference 17). The unit of measurement for

'I 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 which 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 which have detection capability requirements specified in the PNPS Technical Specifications.

Page 24

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

For each sampling medium, each radionuclide is preser. ed with a set of statistical parameters.  !

This set of statistical parameters includes separate ars fyses for (1) the indicator stations, (2) !

, the station having the highest annual mean concerv . tion, and (3) the control stations. For each of these three groups of data, the Yankee Atomic ERMAP computer program calculates:

. The mean value of a] 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 l 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 i 0.8 pCi/ liter would be considered positive" (detectable Sr-90), whereas another sample with a ,

concentration of 2.1 i 0.9 pCi/ liter would be considered " negative", indicating no detectable i strontium-90. The latter sample may actually contain strontium-90, but the levels counted during its analysis were not significantly different than background levels.

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 40). Gross beta (GR-B) analyses were performed I on 576 routine samples (11 stations /wk

• 53 weeks, minus 7 missing samples). None of the samples exceeded ten times the average concentration at the control location. The lower limit of detection (LLD) required by Technical Specifications is 0.01 pCi/m .

l

'I For samples collected from the ten indicator stations, 522 out of 523 samples indicated detectable activity at the three-sigma (standard deviation) level. The mean concentration of gross beta activity in these 523 indicator station samples was 0.016 i 0.005 (1.6 i 0.5 E-2) pCi/m . Individual values ranged from 0.0036 to 0.0312 (3.6 - 31.2 E-3) pCi/m .

The monitoring station which yielded the highest mean concentration was station number 21 (East Weymouth), which yielded a mean concentration of 0.018 i 0.005 pCi/m , based on 53 I observations. Individual values ranged from 0.0078 to 0.0291 pCi/m All 53 samples showed detectable activity at the three-sigma level.

At the control location, all 53 out of 53 samples yielded detectable gross beta activity, for an average concentration of 0.018 i 0.005 pCi/m Individual samples at the control location ranged from 0.0078 to 0.0291 pCi/m .

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). No samples exceeded ten times the mean control station concentration. There is no LLD value listed for K-40 in the PNPS Technical Specifications.

Page 25

At the indicator stations, individual concentrations of K-40 ranged from -0.0065 to 0.0091 pCi/m', for a mean concentration of 0.00057 i 0.00041 pCi/m3 , 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.

g The station which yielded the highest mean concentration of K-40 was station 17. Again, the

.g mean value of 0.0061 i 0.0026 pCi/m 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 illustrates 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 sinale 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 j 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. I 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 l time periods, environmental TLDs are typically posted for periods of one to three months. i Such TLD monitoring yields averaae 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. Forty of these locations are listed as required monitoring locations in the PNPS Technical Specifications. In addition, 27 of the 110 TLDs are located on-site, within the PNPS protected / restricted area.

I Out of the 440 TLDs (110 locations

• 4 quarters) posted during 1996,432 were retrieved and processed. Those TLDs missing from their monitoring locations were lost to storm damage and vandalism, and their absence is discussed in Appendix D. The results for environmental TLDs located off-site, beyond the PNPS protected / restricted area fence, are presented in Table 2.4-1. Results from on-site TLDs posted within the restricted area presented in Table 2.4-2. In addition to TLD results for individual locations, results from off-site 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).

I Annual exposure rates measured at off-site locations ranged from 42 to 583 mR/yr. The averaae exposure rate at control locations greater than 15 km from Pilgrim Station (i.e., Zone

4) was 58.7 6.6 mR/yr. When the 3-sigma confidence interval is calculated based on these I control measurements,99% of all measurements of backaround ambient exposure would be expected to be between 39 and 79 mR/yr.

Page 26

1

m Inspection of on-site TLD results listed in Table 2.4-2 indicates that all of those TLDs located lg 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 on-site. The radionuclide nitrogen-16 contained in steam flowing through the turbine accounts for most of the exposure on-site. Although this radioactivity la contained within the turbine and is not released to the atmosphere, the " sky shine" which occtics from the turbine increases the ambient radiation levels in areas near the turbine building. Such TLD

locations which experienced appreciable increases since 1995 due to turbine sky shine are P02, P03, P12, P13, P14, P15, P16, P17, P18, P19, P22, P23, P24, and P25. Some increases in exposure also occur from the transit and temporary storage of radioactive wastes I on-site. TLD locations P03 and P10 are near the radwaste trucklcck and experienced exposure increases due to staging and transit of radwaste on-site. TLD location P28 is located adjacent to the low level waste storage facility, and experienced exposure increases since

g 1995 from accumulations in radwaste being stored there. It must be emphasized that all of the

!E locations mentioned are within the protected / restricted area and are not accessible by members of the general public.

A small number of off-site TLD locations in close proximity to the protected / restricted area indicated ambient radiation exposure above expected background levels. All of these locations are on Boston Edison controlled property, and experienced exposure increases since 1995 due to turbine sky shine (e.g., locations OA, TC, P01, WS, CT, and A) and/or transit and

, storage of radwaste on-site (e.g., location BLE). A hypothetical maximum exposed member of the public accessing these near-site areas on Boston Edison controlled property for limited periods of time would receive a maximum dose of 2.4 mrem /yr above their average ambient background dose of 59 mrem /yr.

l 1

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 Boston Edison 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 93.2 i 86.1 mR/yr to 60.2 i 7.2 mR/yr. Additionally, exposure rates measured at areas beyond Boston Edison control did not indicate any increase in ambient exposure from Pilgrim Station operation. For example, the annual exposure rate at the nearest off-site resident (location HB,0.6 km SE) was 60.0 t 3.3 mR/yr, which compares quite well with the average controllocation exposure of 58.7 6.6 mR/yr.

I A second technique for mt. - uring 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.

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

Page 27

I 2.5 Air Particulate Filter Radioactivity Analyses

Airbome particulate radioactivity is sampled by drawing a stream of air through a glass fiber filter which has a very high efficiency for collecting airbome 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. Boston Edison uses this l

technique to monitor 10 locations in the Plymouth area, along with the control location in East l Weymouth.

1 Out of 583 filters (11 locations

• 53 weeks),576 samples were collected and analyzed during

1996. 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. One sample was also lost at the laboratory prior to analysis. These discrepancies are noted in Appendix D. Despite the problems listed above, the required LLDs were met on 574 of the 576 filters collected during 1996.

The results of the analyses performed on these 576 filter samples are summarized in Table 2.5-1. Trend plots for the gross beta radioactivity levels at the near station, property line, and off-site airborne monitoring locations are shown in Figures 2.5-1,2.5-2 and 2.5-3, respectively.

Gross beta radioactivity was detected in 575 of the filter samples collected, including 53 of the 53 control location samples. This gross beta activity arises from naturally-occurring

.I radionuclides such as radon decay daughter products. Beryllium-7 was the only gamma i

l emitting nuclide detected, and it was observed in all 44 of the quarterly composites analyzed. l lg No radionuclides attributable to Pilgrim Station operations were detected in any of the airbome i E p rticuiate samples collected. l 2.6 Charcoal Cartridae Radioactivity Analyses Airbome radioactive iodine is sampled by drawing a stream of air through a charcoal cartridge I after it has passed through the high efficiency glass fiber filter. As is the cace with the air particulate filters, these samplers are operat3d continuously, and the resulting cartridges are collected weekly for analysis. Weekly cartricge samples are analyzed for radioactive iodine.

The same eleven locations monitored for airbome particulate radioactivity are also sampled for airbome radiciodine.

Out of 583 cartridges (11 locations

• 53 weeks), 577 samples were collected and analyzed

.I during 1996. As a result of low volumes due to power loss or pump failure, required LLDs were not met on one of the 577 filters collected. These discrepancies are noted in Appendix D.

The results of the analyses performed on these 577 charcoal cartridges are summarized in Table 2.6-1. No airbome radioactive iodine was detected in any of the charcoal cartridges collected.

2.7 Milk Radioactivity Analyses Samples of unprocessed milk are collected from the Plymouth County Farm and from the controllucation 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 radiciodine, and strontium-89 and -90.

Page 28

All 40 samples scheduled for collection during the year were obtained and analyzed. No problems were encountered in sampling milk during 1996.

I The results of the analyses performed on the 40 milk samples are summarized in Table 2.7-1.

Naturally-occurring potassium-40 was detected in all 40 samples. No radioactive iodine was detected in any of the samples. Strontium-90 was detected in 14 of the 20 samples from Plymouth County Farm, and in 7 of the 20 samples collected from the control location in Whitman. Cesium-137 was not detected in any of the samples collected during the year.

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

The highest concentration of Sr-90,3.3 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 Whitman Farm was 2.8 pCi/ liter. The Sr-90 ce.tected in the samples resulted from radioactivity in the environment which was deposited from nuclear weapons testing conducted in the 1950s and 60s. 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 which occurred between 1972 and 1996, the expected concentration would be about 5 pCi/ liter. The concentrations of 3 to 4 pCi/ liter observed in 1996 samples are well below the expected Sr-90 concentrations resulting from weapons testing. It is cleer that the Sr-90 observed did not arise from Pilgrim Station operations.

2.8 Foraae Radioactivity Analyses Samples of animal forage (hay) are collected from the Plymouth County Farm and from the controllocation 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 1996. Results of the gamma analyses of forage samples are summarized in Table 2.8-1. The only radionuclides

=

detected in any of the samples were naturally-occurring beryllium-7, and potassium-40. No radionuclides attributable to Pilgrim Station operations were detected in any of the sary!es.

2.9 Veaetable/Veaetation Radioactivity Analyses Samples of vegetables are routinely collected from the Plymouth County Farm and from the contro! location at Bridgewater Farm. Due to temporary unavailability of samples at the control location in Bridgewater during 1996, substitute control samples were collected at a farm stand in Waltham (72 km NW). 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 three 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 1996.

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 nearly all of the samples collected. Cesium-137 was also detected in three of the samples collected.

The highest level of cesium-137 (180 pCi/kg) was detected in a sample of naturally-growing vegetation, a mixture of grass, herbaceous plants, and leaves from bushes and trees, which I was collected 0.5 km (0.3 mi) southwest of the PNPS Reactor Building. As was the case for all Page 29

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 1994 REMP report, Cs-137 was detected in nearly all of the soil surveys conducted during 1994, indicating that Cs-137 is widespread in soil throughout New England.

I 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. It should be noted that the three I vegetable samples collected at the control location, which showed no detectable Cs-137 or Th-232, were relatively " clean" samples of vegetables, ready for human consumption. These samples did not contain large amounts of soil or dust which may have yielded detectable levels of both Cs-137 and Th-232.

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 I radioactive decay, the expected concentration in samples of naturally-growing vegetation collected during 1996 would be between 90 and 170 pCi/kg. Clearly, the average Cs-137 concentration of 31 pCi/kg observed in the samples collected are 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 controllocation in Halifax. Samples of cranberries are collected annually and analyzed by gamma spectroscopy.

All three samples of cranberries were collected and analyzed as required during 1996. Results of the gamma analyses of cranberry samples are summarized in Table 2.10-1. The only I 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.

2,11 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, samples of topsoil are collected for gamma spectroscopy analysis in the laboratory.

Soil cores are also collected if possible for gamma analyses as a function of depth. In addition, in-field measurements are made at each location 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.

The soil survey was performed as required in 1994. A total of 35 samples of topsoil and depth-divided soil cores were collected and analyzed. The results of the laboratory analyses of these soil samples are summarized in Table 2.11-1. Naturally-occurring beryllium-7, potassium-40, and thorium-232 were detected in a number of the samples. Cobalt-60 was detected in samples collected from three locations on Boston Edison property. Cesium-137 was detected in 26 of the 35 samples, including those collected from the control location. A detailed discussion of these results can be found in the 1994 REMP report.

i 1

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 canalis 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 g analysis. These monthly composites are further composited on a quarterly basis and tritium

E 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 1996. Results of the analyses of water samples are summarized in Table 2.12-1. 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.

2.13 Irish Moss Radioactivity Analyses Samples of Irish moss are collected from the discharge canal outfall and two other locations in l 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.

I All 16 samples of Irish moss scheduled for collection during 1996 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 radionuclides attributable to Pilgrim Station operations were detected in any of the samples.

2.14 Shellfish Radioactivity Analyses Samples of blue mussels, soft-shell clams and quahogs are collected from the discharge canal outfall and two other locations in the Plymouth area (Manomet Point, Plymouth Harbor), and from control locations in Duxbury and Marshfield. All samples are collected on a quarterly basis, and processed in the laboratory for gamma spectroscopy analysis. In addition to analyzing the edible portion (meat) from each of the samples, the shells from samples collected from the discharge canal outfall and from all control location samples are also analyzed.

All 48 samples of shellfish meet and shells scheduled for collection during 1996 were obtained

. and analyzed. Results of the gamma analyses cf 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 Co-60 were detected in blue mussel shells collected from the discharge canal outfall during the first quarter of 1996. Since the shells are not I edible, such low-level contamination does not represent a normal exposure pathway, and no dose assessment was performed. The edible portions of mussel meat collected during the same period did not contain any detectable activity.

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 I samples are analyzed by gamma spectroscopy.

Page 31

All five samples of lobsters were collected and analyzed as required during 1996. 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 controllocations 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 11 - Near-Bottom Distribution: Tautog, Cunner, Pollock, Atlantic Cod, Hake Group til- 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 ll fishes are sampled on a quarterly basis from the outfall area of the discharge ,

I canal, and on an ann :al basis from a :ontrol location. Group Ill and IV fishes are sampled annually from the discharge canal outfall and control location. All samples of fish are analyzed by gamma spectroscopy.

I Twenty-four samples of fish were collected during 1996. Group I and Group li species of fish were unavailable in the vicinity of the discharge canal during the first quarter of the year. This unavailability is believed to be due to low water temperatures and rough seas. These 1 discrepancies are noted in Appendix D. I Results of the gamma analyses of fish samples collected are summarized in Table 2.16-1.

I 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.

l l

I 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 I 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, I 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 and analyzed as required during 1996. Results of the gamma analyses of sediment samples are summarized in Table 2.17-1. Results of the I plutonium analyses are presented in Table 2.17-2. Naturally-occurring beryllium-7, Page 32

potassium-40 and thorium-232 wera detected in a number of the samples. No cobalt-60 was detected in any of the 39 indicator samples. Cesium-137 was detected in 9 of 39 indicator station samples and in 10 of 17 control station samples. Plutonium-239/240 was detected in one of the four indicator station samples and in both of the control station samples.

Cesium-137 levels in indicator samples ranged from non-detectable to a maximum concentration of 25 pCi/kg. Concentrations in samples collected from the control locations beyond the influence of Pilgrim Station also ranged from non-detectable to a maximum concentration of 52 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.

Plutonium-239/240 levels in indicator samples ranged from non-detectable to a maximum concentration of 9.4 pCi/kg. Concentrations in samples collected from the control locations beyond the influence of Pilgrim Station ranged from 6.3 pCi/kg to a maximum concentration of 11.9 pCi/kg. The fact that the results from in6cator locations are lower than those from the 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 plutonium deposited in the environment from nuclear weapons testing.

I l l

l I

I I

I I

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Page 33

Table 2.2-1 Routine Radioloaical Environmental Samplina Locations Pilarim Nuclear Power Station. Plymouth. MA I Description No Code Distance Direction 1

'I Air Particulate Filters. Charcoal Cartridaes. Soil Medical Building East Rocky Hill Road 00 01 WS ER 0.2 km 0.9 km SSE 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 I Manomet Substation 17 MS 3.6 km SSE East Weymouth Control 21 EW 40 km NW Milk l Plymouth County Farm 11 CF 5.6 km W Whitman Farm Control 21 WF 34 km WNW Foraae Plymouth County Farm 11 CF 5.6 km W I Whitman Farm Control 12 WF 34 km WNW Whipple Farm 43 WH 2.9 km SW Veaetation Plymouth County Farm 11 CF 5.6 km W Bridgewater Farm Control 27 BF 31 km W

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

.I I

I ""' '

Table 2.2-1 (continued)

Routine Radioloaical Environmental Samplina Locations Pilarim Nuclear Power Station. Plymouth. MA Description No Code Distance Direction Surface Water Discharge Canal 11 DlS 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 0.5 km N I Manomet Point Ellisville Brant Rock Control 15 22 MP EL 3.9 km 13 km ESE SSE 34 BR 16 km NNW Shellfish Discharge Canal Outfall 11 DlS 0.5 km N Plymouth Harbor 12 Ply-H 4.5 km W Duxbury Bay Control 13 Dux-Bay 13 km NNW Manomet Point 15 MP 3.9 km ESE Green Harbor Control 24 GH 16 km NNW Lobster i Discharge Canal Outfall 11 DlS 0.5 km N I Plymouth Harbor Duxbury Bay Control 15 13 Ply-H Dux-Bay 6.4 km 11 km WNW 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 I Cape Cod Bay Control Sediment 98 CC-Bay 24 km ESE Discharge Canal Outfall 11 DIS 0.5 km N  ;

Plymouth Harbor 12 Ply-H 4.8 km W  !

Duxbury Bay Control 13 Dux-Bay 14 km NNW Plymouth Beach 14 PLB 4.0 km W  !

Manomet Point 15 MP 3.9 km ESE l Green Harbor Control 24 GH 16 km NNW i

I I

Page 35

Table 2.4-1 Off-Site Environmental TLD Results I TLD Station TLD Location

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

1996 Annual" I ID Description Zone 1 TLDs: 0-3 km Distance / Direction Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure mR/ year BLW BOAT LAUNCH WEST 0.11 km E 62.621.8 58 e 2 2.1 57.0 t 3 8 62 1 36 240.3 t 12.3 OA OVERLOOK AREA 015km W 140.6240 140.1 t 5.0 134.1 t 4 8 168.128.0 582.9 2 61.8 TC HEALTH CLUB 0.15 km WSW 44.1 i 1.5 42.7 t 1.4 42421.8 54 3 t 4.1 183 6

• 23 3 BLE BOAT LAUNCH EAST 0.16 km ESE 54.1 t 2 4 56.2 35 53123.4 567248 220.1 i 10.0 PB PEDESTRIAN BRIDGE O 21 km N 34 5 i 1.1 32.2 i 1.1 32.8

• 1.2 36.2 i 1.6 135 8 i 7.7 P01 SHOREFRONT SECURITY 0 22 km NNW 33.3 i 1.1 31,9 t 1.4 32.3 t 1.2 36.5 t 1.7 133.9 i 8.8 WS MEDICAL BUILDING 0.23 km SSE 32.5 t 1.4 32.0 t 2 0 32.5 i 1 8 36.2 i 1.8 133.2 i 8 6 CT PARKING LOT 0 31 km SE 261 t 0 7 27.4221 29 8 t 1.9 29 2 t 18 112.4 t 7.5 PA SHOREFRONT PARKING 0.35 km NNW 194206 19 ? t 0.8 196208 21.211.0 80 0 36 A STATION A 0.37 km WSW 22.311.0 18.9 i 0.8 19.5 t 1.0 21.4 t 1.3 82.1 i 6 7 F STATION F 0 43 km NW 17.8 t 0.7 16 4 t 1.1 184207 17.9 t 0 9 70.6 i 3.8 B STATION B 0 44 km S 22 4 i 1.5 19 8 t 0.9 21.0 t 0 9 21.7 t 1.0 84 9 t 4 9 EB EAST BREAKWATER 0 44 km ESE 210 t 0 9 21.7 t 0 9 22.2 i 1.0 21521.2 86.5 t 2 8 PMT PNPS MET TOWER 0 44 km WNW 15 4 t 0.9 16.1206 16.5 t 0.7 17.1 08 650233 H STATION H 0.47 km SW 23 8 t 1.0 20 8 i O 8 22 0 t 0 7 22.8 t 1.1 89 4

• 5.4 i STATION I 0.48 km WNW 16.9 t 0 6 164i08 17.5 t 0.7 17.1

• 0.9 68.022.3 I L STATlON L G STATION G D STATION D PL PROPERTY LINE 0 50 km ESE 0.53 km W 0 54 km NW 0.54 km NNW 18 0 t 0.6 169i08 21.0 t 0 9 163106 17.9 t 0.7 15.8 i 0 8 20 2 t 1.0 16 0 t 0.7 19 0 t 0.7 16 2 t 0 6 21.5 i 0.8 168i06 20.7 t 2.7 16721.0 21.221.2 17.9 i 0 9 75 6 59 65 6

• 2.7 84 0 t 3 0 66923.7 C STATION C 0.57 km ESE 15 6 i 0.7 15 4 t 0 6 17.0 t 0.7 17.621.1 65.7

• 4 6 HB HALL'S BOG 0 63 km SE 14 6 i 0.5 141 t 0.7 15.7 0.6 15.6 i 0.9 60.0 t 3 3 GH GREENWOOD HOUSE 0.65 km ESE 19220.9 17.210.7 18.120.7 18421.0 72.9 i 3.7 WR W ROCKY HILL ROAD 0 83 km WNW 18 0 t 0 8 18 4 t 18 18.7 t 0 9 19 4 t 1.0 74523.4 I ER E ROCKY HILL ROAD MT MICROWAVE TOWER CR CLEFT ROCK BD BAYSHORE/ GATE RD 0.89 km SE 1.03 km SSW 1.27 km SSW 1.34 km WNW 13.1 t 1.0 17.9 t 0.7 13 9 t 0.5 15.2206 13.020.6 15.5 t 0 9 14 0 t 0.7 15.5 t 1.0 14 0 i 1.4 Missing 148i07 17410.6 14.1 i 1 0 17.011.0 15.011.0 15 0 t 0 8 541 t 3.1 67.3254 57.622.7 63 2 t 4 7 MR MANOMET ROAD 1.38 km S 14 5 t 0.7 12.2 i 0 8 146i06 13 5 t 0 8 548247 DR DIRT ROAD 1.48 km SW 15 0 t 0 9 12.7 i 0 5 15 2 t 0 6 14.1 i 0.7 57.0 t 4.7 EM EMERSON ROAD 1.53 km SSE 16.3 t 1.2 13 2 05 14 9 t 0 8 14.3 t 0 8 58 6 55 EP EMERSON /PRISCILLA 1.55 km SE 16 9 t 0 6 13 6 t 0.7 153i08 14 9 t 0.9 60.6 i 5 6 AR EDISON ACCESS ROAD 1.59 km SSE 14 5 t 0.7 14 5 t 0.7 139i06 12820.7 55 7 i 3.5 BS BAYSHORE 1.76 km W 16 7 i 0.7 16320.7 17.9108 16.3 i 0.8 67.3

• 3 3 E STATION E 1.86 km S 17 2 i O 9 14420.5 168i05 159i08 64 3 i 5.2 JG JOHN GAULEY 1.99 km W 15.4 t 0.7 15.7 t 0.6 17.220.7 15 9

• 1.3 643i36 J STATION J 2.04 km SSE 14 9 t 0.7 Missing 15.0105 13.7209 58.2 i 3.2 WH WHITEHORSE ROAD 2 09 km SSE 149i08 12 9 t 0 6 144206 13 8 t 0 8 56.1 t 3 6 RC PLYMOUTH YMCA 2.09 km WSW 18 4 t 1.2 143207 16.7209 154209 64.7 t 7.3 K STATION K 2.17 km S 154106 148107 139206 13.6 t 0 7 57.7135 TT TAYLOR / THOMAS 2.26 km SE 14 8 t 0 6 13 6 06 15221.0 15.221.2 58.8 t 3.5 YV YANKEE VILLAGE 2 28 km WSW 16 6 t 0.7 14320.7 15 8 t 0 9 15 8

• 1.2 62.6 i 4 3 GN GOODWIN PROPERTY 2.38 km SW 128106 101i06 128106 120209 47.7 t 5.2 RW RIGHT OF WAY 2 83 km S 12.4 i 0.8 Missing 12.6 i 0.4 12.8 t 0 9 50 3 i 1.9 TP TAYLOR / PEARL 2 98 km SE 131 t 0 6 126207 14 3 t 2.0 14 7 t 0 9 54 7

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

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

I Page 36

I Table 2.4-1 (continued)

Off-Site Environmental TLD Results I TLD Station TLD Location

• Exposure Rate - mR/ quarter,(Value i Std.Dev )

1996 Annual **

ID Description Distance / Direction Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure mR/ year Zone 2 TLDs 3-8 km VR VALLEY ROAD 3.26 km SSW 13.220.7 12 5 t 0 6 14.1 t 10 13.321.1 53 0 t 3.1 ME MANOMET ELEM 3 29 km SE 139i07 142208 13.5 t 0 8 13.5 i 0.8 55.1 2.1 WC WARREN /CLIFFORD 3 31 km W 14 7 t 0.5 130208 15 0 i 0.9 14.1 t 12 56.7

• 4 0 BB RT.3A/ BARTLETT RD 3 33 km SSE 15 0 t 0 6 156i10 14 9 t 1.0 14321.1 59 7 t 2.8 MP MANOMET POINT 3.57 km SE 137206 12 4 t 0 7 13620.7 13 2 t 0 8 529*28

)

I MS MANOMET SUBSTATION BW BEACHWOOD ROAD PT PINES ESTATE 3 60 km SSE 3 93 km SE 4 44 km SSW 16.3207 146208 14 5 t 0 6 17.1 t 0 6 15 0 t 0.6 12.7 t 0 7 17.4 t 0.7 13720.5 13 5 t 0.5 17.7 t 1.1 154209 12.9 t 10 68.4229 58723.2 536i36 EA EARL ROAD 4 60 km SSE 136i05 Missing 11.9204 Missing 50.9 i 4 8 I SP S PLYMOUTH SUBST RP ROUTE 3 OVERPASS RM RUSSELL MILLS RD 4 62 km W 4 81 km SW 4 85 km WSW 16.0 t 0 5 14 8 t 0 6 14.2 i O 5 144206 136i07 12.7 i 0 6 15.6 06 142i06 13.5 t 0 8 15.5 1.0 14 0 t 0.7 12.720.8 61.4 3.1 56712.3 53123.2 HD HILLDALE ROAD 5.18 km W 16.3 i 0 9 13 7 t 0 9 15 8

• 0.7 15.1 t 0 9 609i48 )

MB MANOMET BEACH 5 43 km SSE 144206 14.1205 12.8 i 0 4 14 2 t 0 9 55 4 t 31 j BR BEAVERDAM ROAD 5 52 km S 13.7 i O 6 12.2

• 0 6 13.3 t 0 6 12.7 i 0.8 51.8 i 3 0 l PC PLYMOUTH CENTER 6 69 km W 11.0 t 0 4 10 0 t 0 9 10 0 t 0.7 11.0 t 0 9 42 0 t 2.7 LD LONG POND / DREW RD 6 97 km WSW 13 5 i 0.7 12.7205 145i 0.8 13 8 t 1.3 54523.4 I HR HYANNIS ROAD MH MEMORIAL HALL SN SAQUISH NECK 7.33 km SSE 7.58 km WNW 7.58 km NNW 143i07 Missing 10 7 i O 4 14 7 i 0.7 22 6 t 1.1 11.4206 13 8 t 0 6 246i09 12.0 t 1.0 13.7 t 1.0 25.7 22 12222.2 56 4 2.3 97.1 i 7 0 463237 CP COLLEGE POND 7 59 km SW 14 5 t 0 6 13 2 0.5 14 0 t 0 6 13 2 i 0.7 54922.8 Zone 3 TLDs: 8-15 km DW DEEP WATER POND 8 59 km W 17.1 t 0 5 16.7206 17.4 i 0 9 15 8 t 1.1 66.9 i 3 2 LP LONG POND ROAD 8.88 km SSW 13 3 t 0.5 12.1 t 0 6 13 0 t 0.7 11.9208 50.4230 I NP NORTH PLYMOUTH SS STANDISH SHORES EL ELLISVILLE ROAD

,,9 38 km WNW

' 10 39 km NW 11.52 km SSE 16220.7 130106 14 0 t 0 6 158206 11810.4 149209 17.521.3 13.1 i 0 5 140108 17.1 i 1.3 13.5 t 0 8 14 2 i 1.1 666i38 51.5 t 3.1 57.1 t 2 4 UC UP COLLEGE POND RD 11.78 km SW 133i06 Missing 13 4 t 0.7 Missing 53.521.8 I SH SACRED HEART KC KING CAESAR ROAD BE BOURNE ROAD SA SHERMAN AIRPORT 12 92 km W 1311 km NNW 13 37 km S 14 7 i O 5 13.7 t 0 4 138206 14 0 t 0 6 13.7 i 0 6 13 1 08 152*10 14 0 t 10 13621.1 13.7 i 1 0 14 0 t 1.0 12 9 t 10 57.6 i 3 i 55 3 t 18 53 3 t 2 5 13 43 km WSW 148i07 12.8 i 0.5 141105 134i10 55.0239 Zone 4 TLDs >15 km CS CEDARVILLE SUBST 15 93 km S 15 4 t 0.7 15 8 t 0 7 143206 15.7 i 1.0 61.3 t 3 2 KS KINGSTON SUBST 1615 km WNW 146205 12.8208 142i07 13.8 t 0 9 55.5 t 3 4 LR LANDING ROAD 16 46 km NNW 13 3 i O 5 13.3 t 0 5 141*09 131208 53 8 t 2.3 CW CHURCH / WEST 16 56 km NW 12.3205 11.7 06 12.9 i 0.7 12.2 t 10 49.1225 MM MAIN / MEADOW 17.02 km WSW 15 3 t 0 7 14.3 t 0 7 15 5i1.0 14.1 t 0.9 59 2 t 3 3 '

DMF DIV MARINE FISH 20 97 km SSE 15 8 1.0 17.3 0.7 16 7 t 1.2 16 6 i 1.1 66423.1 EW E WEYMOUTH SUBST l

39 69 km NW 153206 16.0 i 0 7 166206 18 0 t 1.7 65 8 t 5 0 j 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, .

1 Page 37

Table 2.4-2 I On-Site Environmental TLD Results I TLD Station TLD Location

• Exposure Rate - mR/ quarter,(Value i Std.Dev.),_.

1996 Annuat**

ID Description Distance / Direction Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure mR/ year Onsde TLDs P21 O&M/RXB. BREEZEWAY 50 m SE 44 3 i 1.0 38.5 t 2 0 37.3 t 2.1 32.2 t 1.8 152.4 1 20.2 I P24 EXEC BUILDING PO4 FENCE-R SCREENHOUSE P20 O&M - 2ND W WALL 57 m W 66 m N 67 m SE 47.3 i 3 3 105 0 t 6 9 899i38 43112.2 83.8244 79815.2 56.9 i 5.3 83.7 i 4.0 77.1234 64 8 t 6 2 942270 87.6 t 5.0 212.12399 366.7 i 42.2 334 4 t 26 0 P25 EXEC BUILDING LAWN 76 m WNW 123924.7 111.4 t 5 6 137.6 i 5.1 130.5 t 9.1 503.5 t 46.3 I P05 FENCE-WATER TANK P06 FENCE-OIL STORAGE P190&M - 2ND SW CORNER 81 m NNE 85 m NE 86 m S 43 2 i 2.8 112 0 t 3.8 97.8 i 4 9 36.922.1 66 9 i 5 i 90.8 i 4 0 36.1 t 2.5 71.4130 89 6 t 4 0 38.6 i 3 6 57.0 t 4 4 1106i98 154 8

• 13.8 307.3 i 97.1 38871405 P180&M - 1ST SW CORNER 90 m S 865i85 74.7 t 8 8 71.2 t 7.4 932i131 325 7 i 45 4 PO8 COMPRESSED GAS STOR 92 m E 703242 61.9249 58 4 i 3.3 64.2 t 5.1 254 8 t 21.9 P03 FENCE-L SCREENHOUSE 100 m NW 1128249 99 4 i 5.7 100 8 t 4 6 103 9 t 6 8 41682266 P17 FENCE-EXEC BUILDING 107 m W 176 8 t 7.5 157.529.4 137327.0 195 8*18 2 667.4 t 1031 P23 O&M - 2ND S WALL 121 m ENE 52821.5 50 5 t 2.8 46 8 t 1.6 589239 2091 t 21.0 I P07 FENCE-INTAKE BAY P26 FENCE-WAREHOUSE P02 FENCE-SHOREFRONT 121 m SSE 134 m ESE 135 m NW 56 6 t 16 58.1231 66.1 t 3 2 44.1 t 2.7 53 2 t 4 7 57.3 t 3 2 48.5 t 2.1 57.0 t 7.4 60 9 i 6.1 66 8 t 5 5 59.0 i 5 4 71.0 t 5 2 2161240.5 227.3 i 14 9 255.4

• 25 6 P09 FENCE-W BOAT RAMP 136 m E 50 5 t 3 4 44622.6 44.7 t 2.0 52.2 40 192.0 2 16.9 P22 OaM - 2ND N W ALL 137 m SE 46.5 t 2.8 444i40 40821.9 47.5 t 2.7 179.2 t 13 3 P16 FENCE-W SWITCHYARD 172 m SW 136 4 t 6 4 124029.7 127.3 t 4 3 146.5 t 11.5 534 2 t 43 9 P11 FENCE-TCF GATE 183 m ESE 50 0 t 3.7 55.7 i 3 9 50.4 t 2.8 56.1245 212.3 i 15.2 P27 FENCE-TCF/ BOAT RAMP 185 m ESE 51.3132 60.4242 54.7 i 2.6 597i47 226.12189 P12 FENCE-ACCESS GATE 202 m SE 37.4 i 2 0 36 0 t 3 0 32.4 i 1.9 38.9 t 1.9 144 7 t 12.1 P15 FENCE-E SWITCHYARD 220 m S 475124 43812.7 44 0 t 2.3 51.5 t 4 6 186 8

• 15 9 P10 FENCE-TCF/ INTAKE BAY 223 m E 44 4 t 2.1 452223 46 0 2.5 469237 182.5

• 6 9 P13 FENCE-MEDICAL BLDG 224 m SSE 35.7 t 1.7 32.7 t 1.7 32.7 t 1.6 38 9 t 2.5 140 0 i 12.4 P14 FENCE-BUTLER BLOG 228 m S 35 3 t 2 4 31.9214 31.8 t 18 37.6232 136.5 i 12.2 P28 FENCE-TCF/PRKNG LOT 259 m ESE 91.8 i 4 3 117.32109 130.5 t 9.5 112 6 i10 5 452.2 t 66 8 Distance and direction are measured from centerline of Reactor Building to the monitoring location.

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

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Table 2.4-3 Average TLD Exposures By Distance Zone During 1996 I Exposure Period Average Exposure i Standard Deviation: mR/ period Zone 1*

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

>15 km Jan-Mar 23.2 i 20.7 14.1 i 1.4 14.4 i 1.3 14.6 i 1.3 Apr-Jun 22.5 i 21.2 13.9 i 2.6 13.9 i 1.7 14.5 i 2.0 Jul-Sep 23.1 i 19.7 14.4 i 2.8 14.5 i 1.7 14.9 + 1.5 Oct-Dec 24.3 i 24.8 14.4 i 3.0 14.0 i 1.6 14.8 i 2.1 Jan-Dec 93.2 t 86.1** 56.8 i 9.9 56.9 i 6.0 58.7 t 6.6

• 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 l be 60.2 i 7.2 mR/yr.

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Page 39

Table 2.4-4 Beach Survey Exposure Rate Measurements Ambient Radiation Survey Results I Lecation White Horse Beach Exposurs Rate 1 sta.dev.

R/hr mR/yr Beach Terrain (Near Hilltop Ave) 8.8 i 0.1 7710.9 Sandy Few granite boulders 2.62 km SE within thirty,_ feet.

Priscilla Beach (In Back of Full Sail Bar) 9.2 i 0.1 81 i 0.9 Sandy with small amounts of I 1.90 km SE Plymouth Beach

g. ravel.

(Outer Beach) 6.4 i 0.1 5610.9 Sandy, a 7.24 km WNW Plymouth Beach i

(Inner Beach) 6.5 i 0.1 5710.9 Sandy.

6.01 km WNW

, Plymouth Beach (Behind Bert's Restaurant) 9.7 1 0.1 85 0.9 Sandy with gravel. Breakwater 3.62 km W and seawall nearby.

Duxbury Beach (Control) 8.110.1 71 i 0.9 Sandy with coarse gravel and 11.02 km NNW exposed cobble.

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Table 2.5-1 l Air Particulate Filter Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 1996))

MEDIUM: Air Particulates UNITS: oCl/ cubic meter Indicator Stations Station With Highqs.LM J an Q.gntrol Stations Radionuclide Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (Non-Routine *) LLD (No. Detected") (No. Detected") (No. Detected")

GR-B (576) 0.01 ( 1.6 2 0.5)E -2 21 ( 1.810.5)E -2 ( 1.8 i 0.5)E -2 (0) ( 3.6 - 31.2)E -3 ( 7.8 - 29.1)E -3 ( 7.8 - 29.1)E -3 (522/523) (53/53) (53/53) i Be-7 (44) ( 9.3 i 1.5)E -2 21 ( 1.12 0.1)E -1 ( 1.1 t 0.1)E -1 (0) ( 6.8 - 12.1)E -2 ( 1.0 - 1.1)E -1 ( 1.0 - 1.1)E -1 (40/40) (4/ 4) (4/ 4)

K-40 (44) ( 5.7

• 41.7)E -4 07 ( 6.12 2.6)E -3 ( 2.7 7.0)E -3 (0) ( -6.5 - 9.1)E -3 ( 3.9 - 7.6)E -3 (-2.2 - 12.2)E -3 (0/ 40) (0/ 4) (0/ 4)

Cs-134 (44) 0.01 ( -5.9 23.7)E -5 06 ( 1.121.9)E -4 (-5.9 t 26.2)E -5 1 (0) ( -5.0 - 4 2)E -4 ( -4.7 - 29.5)E -5 ( -3.7 - 1.6)E -4 l (0/ 40) (0/ 4) (0/ 4) l Cs-137 (44) 0.01 ( -4.2 216.7)E -6 08 ( 1.5

• 3.5)E -4 (-9.5 216.1)E -5 (0) ( -4.6 - 5.8)E -4 ( -1.8 - 5.8)E -4 ( -2.0 - 0.9)E -4 (0/ 40) (0/ 4) (0/ 4)

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in Technical Specification Table 7.1-1.

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

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I Table 2.6-1 l

Charcoal Cartridge Radioactivity Analyses Radiological Environmental Program Summary i

Pilgrim Nuclear Power Station, Plymouth, MA 1 (January - December 1996)

MEDIUM: CharcoalCartridae UNITS: oCi/ cubic meter m Indicator Stations Station With Hiahest Mean Control Stations Rad onuclide Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (Non-Routine *) LLD (No Detected **) (No. Detected") (No. Detected")

1-131 (577) 0.07 (-2.4 2 88.8)E -4 01 ( 1.8 2 8.9)E -3 ( -3.0 2 8.2)E -3 (0) ( -6.3 - 2.3)E -2 ( -1.5 - 2.3)E -2 ( -2.2 - 1.3)E -2 (0/ 524) (0/ 53) (0/ 53) l

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in Technical Specification Table 7.1 1.

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

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Table 2.7-1 Milk Radioactivity Analyses Radiological Environmental Program Summary I Pilgnm Nuclear Power Station, Plymouth, MA (January - December 1996)

MEDIUM: Milk UNITS: DCi/ka I Radionuclide Indicator Stations Mean Station With Hiohest Mean Sta. Mean Control Stations Mean (No. Analyses) Required Range Range Range (Non-Routine *) LLD (No Detected") (No. Detected") (No Detected")

K-40 (40) ( 1.5 2 0.1)E 3 11 ( 1.5 0.1)E 3 ( 1.5 2 0.1)E 3 (0) ( 1.3 1.6)E 3 ( i.3 - 1.6)E 3 ( 1.4 - 1.6)E 3 I Sr-89 (40)

(0)

(20/20)

( 1.6119.2)E -1

(-3.4 - 3.8)E O 11 (20/20)

( 1.6 19.2)E -1

( -3.4 - 3.8)E O (20/20)

(-6.0 2 29.8)E -1

(-6.1 - 2.7)E O (0/ 20) (0/ 20) (0/ 20)

Sr-90 (40) ( 1.710.9)E O 11 ( 1.7 2 0.9)E O (1.1 0.8)E O (0) ( -3.9 - 33.4)E -1 ( -3.9 - 33.4)E -1 ( -7.7 - 27.8)E -1 (14/20) (14/20) (7/ 20) )

1-131 (40) 1 ( 6.9 210.0)E -2 11 ( 6.9110.0)E -2 ( 6.5 2 77.2)E -3 (0) ( -5.5 - 38.1)E -2 (-5.5 38.1)E -2 (-1.1 - 2.5)E -1 <

(0/ 20) (0/ 20) (0/ 20) l 1

Cs-134 (40) 15 (-6 8 215.3)E -1 21 (-3.8

• 127.2)E -2 (-3.8

• 127.2)E -2 (0) (-3.9 - 1.8)E O ( -2.9 - 2.3)E O (-2.9 - 2.3)E O (0/ 20) (0/ 20) (0/ 20)

Cs-137 (40) 15 ( 1.111.7)E O 11 ( 1.121.7)E O ( 7.3 i 16.8)E -1 (0) ( -2.3 - 4.0)E O (-2.3 - 4.0)E O (-2.1 - 3.8)E O (0/ 20) (0/ 20) (0/ 20)

I Ba-140 (40)

(0) 15 (-4.4 219.6)E 1

(-5.1 - 3.1)E O (0/ 20) 21 ( 8.2 t 23.3)E -1

(-3.1 - 5.6)E O (0/ 20)

( 8.2 23.3)E -1

(-3.1 - 5.6)E O (0/ 20)

I

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels :n Technical Specification Table 7.1-1.

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

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Table 2.8-1 Forage Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA

I (January - December 1996)

MEDIUM: Forace UNITS: oCi/ka wet IDdjiggtgr Stations Station With Hichest Mean Control Statigna Radionuclide Mean Sta. Mean Mean  ;

(No. Analyses) Required Range Range Range 1 (Non-Routine *) LLD (No. Detected") (No. Detected") (No. Detected") l l

Be-7 (3) ( 1.210.8)E 3 21 ( 1.8 i 0.2)E 3 ( 1.8 2 0.2)E 3 (0) ( 5.9 17.8)E 2 .

I K-40 (3)

(0)

(2/ 2)

( 6.2 2 4.3)E 3

( 3.1 - 9.2)E 3 11 (1/1)

( 9.2 2 0.4)E 3 (1/1)

( 3.4 2 0.3)E 3 (2/ 2) (1/1) (1/1) 1-131 (3) (-1.6 21.5)E 1 21 l

( 3.9 2 3.1)E 1 ( 3.9 2 3.1)E 1 (0) (-2.2 --1.1)E 1 (0/ 2) (0/1) (0/1)

Cs-134 (3) 130 (-9 6 212.0)E O 21 ( 5.0 i 13.6)E O ( 5.0i 13.6)E O (0) (-1.7 --0.2)E 1 (0/ 2) (0/1) (0/1)

Cs-137 (3) 130 ( 1.2 2 9.6)E O 21 ( 4.4 1.8)E 1 ( 4.4 21.8)E 1 (0) ( -3.7 - 6.1)E O (0/ 2) (0/1) (0/1)

I Th-232 (3)

(0)

(-1.7 t 4.3)E 1

(-4.1 - 0.6)E 1 (0/ 2) 21 ( 8.12 7.3)E 1 (0/1)

( 8.1 t 7.3)E 1 (0/1)

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in Technical Specification Table 7.1 1.

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

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l Table 2.9-1 Vegetable / Vegetation Radioactivity Analyses Radiological Environmental Prograrn Summary I Pilgnm Nuclear Power Station, Plymouth, MA (January - December 1996)

MEDIUM: Ve2gtation UNITS: oCl/ka wet I Radionuclide Indicator Stations Mean S.tption With Hiahest Mean Sta. Mean Control Stations Mean l

i (No. Analyses) Required Range Range Range I (Non-Routine *) LLD (No. Detected") (No. Detected") (No. Detected")

Be-7 (17) ( 1.3 21.7)E 3 32 ( 5.9i 01)E 3 ( 6.8 t 8.5)E 2 (0) ( -8.3 - 586.7)E 1 ( 1.7 - 177.9)E 1 (8/12) (1/1) (2/ 5) j K-40 (17) ( 1.8

• 0.8)E 3 30 ( 2.5 t 1.8)E 3 ( 1.6 2 0.4)E 3 '

(0) ( 5 8 37.6)E 2 ( 1.2- 3.8)E 3 ( 1.2- 2.1)E 3 i (11/12) (2/ 2) (5/ 5) j I-131 (17) (-7.3 214 4)E O 30 ( 6.7 2 21.4)E O (-7.0 214 9)E O (0) (-2.9 - 2.0)E 1 ( -6 9 - 20.3)E O ( -2.2 - 0.7)E 1 (0/12) (0/ 2) (0/ 5)

Cs-134 (17) 60 ( 7.9 2 85.5)E -1 32 ( 1.4 21.3)E 1 ( 3.8 2 7.6)E O (0) (-1.2 - 1.4)E 1 ( -4.0 - 13.2)E O (0/12) (0/1) (0/ 5)

Cs-137 (17) 60 ( 3.115.7)E 1 02 ( 1.8 t 0.1)E 2 ( 3.8 t 6.7)E O (0) (-1.4 - 18.3)E 1 (-3.3 - 9.1)E O (3/12) (1/1) (0/ 5)

Th-232 (17) ( 6.9 2 5.3)E 1 01 ( 1.6 2 0.3)E 2 ( 3.2 i 4.6)E 1 (0) ( -1.7 - 16 0)E 1 (-6.1 - 103.6)E O (4/12) (1/1) (1/ 5)

• Non-Routine refers to those radionuclides that exceec,ed the Reporting Levels in Technical Specification Table 7.1-1.

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

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1 1

Table 2.10-1 l Cranberry Radioactivity Analyses Radiological Environmental Program Summary l

I Pilgnm Nuclear Power Station, Plymouth, MA l (January - December 1996)

MEDIUM: Cranberries UNITS: oCi/ka wel Lndicator Stations Station Wrth Hichest Mgm Control Stations Radionuclide Mean Sta. Mean Mean (No. Analyses) Required Range Range Range l (Non-Routine") LLD (No Detected") (No. Detected") (No. Detected")

Be-7 (3) ( 8.6 i 5.7)E 1 14 ( 1.12 0.7)E 2 ( 7.7 t 12.0)E 1 1 (0) ( 6.1 - 11.1)E 1 l O/ 2) (0/1) (0/1)

K-40 (3) ( 5.1 i 1.5)E 2 23 ( 9.3 i 3.1)E 2 ( 9.3 t 3.1)E 2 (0) ( 4 4 - 5.8)E 2 l (2/ 2) (0/1) (0/1) 6-131 (3) ( 1.2 2 20.8)E O 14 (1.4 1.7)E 1 (-5.9

• 5 6)E 1 (0) (-1.2 - 1.4)E 1 (0/ 2) (0/1) (0/1)

Cs-134 (3) 60 ( 4.0 212.8)E O 14 ( 1.2

• 0.9)E 1 ( 1.0

• 1.2)E 1 )

(0) ( -4.2 - 12.3)E O '

(0/ 2) (0/1) (0/1) l

'I Cs-137 (3)

(0) 60 ( 3.3 2 5.5)E O

( 2.1 - 4.5)E O (0/ 2) 14 (4.5 7.9)E O (0/1)

( 1.2

• 15.0)E O (0/1)

,I Th-232 (3)

(0)

( 1.1 t 2.7)E 1

( 0.0 - 21.6)E O 23 ( 1.5 t 0.7)E 2 ( 1.5 t 0.7)E 2 (0/ 2) (0/1) (0/1)

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in Technical Specircation Table 7.1-1.

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

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Table 2.11-1

~E

'g Soil Radioactivity Analyses 1 Analyses of radioactivity in soil are performed once every three years. The last soil survey was  !

I performed in 1994, and results of these analyses can be found in Pilgrim Station's Radiological Environmental Monitoring Program Report #27, dated April 1996. The next routine soil survey is scheduled to be performed in 1997.

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Table 2.12-1 Surface Water Radioactivity Analyses Radiological Environmental Program Summary Pilgnm Nuclear Power Stata), Plymouth, MA

I (January - December 1996)

MEDIUM: Surface Water UNITS: DCi/ka Indicator Stations Station With Hiahest Mean Control Stations Radionuclide Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (Non-Routine *) LLD (No. Detected") (No. Detected") (No. Detected")

H-3 (12) 3000 (-2.0

• 25.8)E 1 11 ( 3.5132.3)E 1 (-7.6 2 21.9)E 1 (0) (-2.7 - 4.2)E 2 ( .2.5 - 4.2)E 2 (-3 3 - 0.7)E 2 (0/ 4)

I (0/ 8) (0/ 4)

K-40 (36) ( 1.5 21.5)E 2 11 ( 2.910.3)E 2 ( 2.8 t 0.4)E 2 (0) (-2.4 - 34.2)E 1 ( 2.5 - 3.4)E 2 ( 1.9 - 3.3)E 2 (12/ 24) (12/12) (12/12)

Mn-54 (3S) 15 (-3.5 210.7)E -1 11 (-1.6 t 10.6)E -1 (-4 6 10.7)E -1 (0) (-2.3 1.2)E O (-2.1 - 1.2)E O ( -2.7 - 0.7)E O (0/ 24) (0/12) (0/12)

Co-58 (36) 15 (-1,7 t 13.2)E -1 23 ( 8.6 2101.9)E -2 ( 8.6 2101.9)E -2 (0) (-2.7 - 2.2)E O (-1.9 - 1.4)E O (-1.9 - 1.4)E O (0/ 24) (0/12) (0/12)

Fe-59 (36) 30 ( 47 i 30.3)E -1 11 ( 3.3 i 37.6)E -1 (-4.12 22.9)E -1 (0) ( -6 6 - 8.4)E O ( -5.4 - 8.4)E O (-3.7 - 3.1)E O (0/ 24) (0/12) (0/12)

Co-60 (36) 15 ( 1.9114.4)E -1 11 ( 3.2 215.9)E -1 (-B.8 2105 9)E -2 (0) ( -2.2 - 2 8)E O ( -2.2 - 2.8)E O ( -1.9 - 1.6)E O (0/ 24) (0/12) (0/12)

I Zn-65 (36)

(0) 30 (-6 9 2 34 6)E -1

( -8.9 - 5.7)E O (0/ 24) 11 ( 2.8 35.9)E -1

( 41 - 5.7)E O (0/12)

(-1.2 2 3.2)E O

( -5.0 - 4.3)E O (0/12)

I Zr-95 (36) 15 ( 1.012.1)E O 17 (1.4 2 2.1)E O ( 1.7 218.1)E -1 (0) ( -3.2 - 4.7)E O (-3.2 - 3.0)E O ( -3.2 - 3.4)E O (0/ 24) (0/12) (0/12) 1-131 (36) ( 4.9 t 16 0)E -2 11 ( 1.2 21.9)E -1 ( 8.2 211.9)E -2 I

1 (0) ( -1.6 - 5.4)E -1 ( -9.4 - 53.9)E -2 ( -1.4 - 2.4)E -1 (0/ 24) (0/12) (0/12)

/

Cs-134 (36) 15 (-7.2 t 17.2)E -1 17 (-1.5 t 15.0)E -1 ( -5.2 215.0)E -1 (0) ( -5 0 - 2.4)E O ( -2.5 - 2.4)E O (-3.4 - 0.9)E O (0/ 24) (0/12) (0/12)

Cs-137 (36) 18 ( -1.6 i 10.1)E -1 17 (-8.8

• 95.5)E -2 ( -8.9 i 16.9)E -1 I Ba-140 (0)

(36) 15

(-1.8 - 1.4)E O (0/ 24)

( -8.1 125 9)E -1 23

(-1.6 - 1.4)E O (0/12)

( 3.8 2 27.8)E -1

(-3.5 - 2.1)E O (0/12)

( 3.8 2 27.8)E -1 (0) (-5.5 - 4.5)E O (-3.3 7.0)E O (-3.3 - 7.0)E O (0/ 24) (0/12) (0/12)

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in Technical Specification Table 7.1-1.

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

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I-l Table 2.13-1 Irish Moss Radioactivity Analyses t

} Radiological Environmental Program Summary Pilgnm Nuclear Power Station, Plymouth, MA (January - December 1996)

MEDIUM. Irish Moss UNITS: oCi/ka wet Indicator Stations Station With Hichest Mean C.gntr_gl.$.t.al!gna Radionuclide Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (Non-Routine") LLD (No Detected") (No. Detected") (No Detected")

Be-7 (16) ( 1.911.9)E 2 22 (38 2.2)E 2 ( 1.010 5)E 2 (0) (-5.7 - 69.5)E 1 ( 2.2 - 6 9)E 2 ( 7.5 - 13.5)E 1 I K-40 (16)

(0)

(3/12)

( 6.411.3)E 3

( 3 8 - 7.9)E 3 11 (2/ 4)

( 7.4 2 0.5)E 3

( 6.9 - 7.9)E 3 (0/ 4)

( 6.9 2 0.9)E 3

( 5 8 - 7.7)E 3 (12/12) (4/ 4) (4/ 4)

Mn-54 (16) ( 1.6

• 7.1)E O 11 ( 5.3 i 4 5)E O (-3.8 210.6)E O (0) ( -1.4 - 0.9)E 1 ( 2.6 - 8.0)E O ( -1.6 - 0.6)E 1 (0/12) (0/ 4) (0/ 4)

Co-58 (16) ( 2.0 t 9.4)E O 11 ( 5.8111.6)E O (-4.6 210.0)E O (0) (-1.1 - 2.0)E 1 ( -6.0 - 20.1)E O ( -1.7 - 0.2)E 1 (0/12) (0/ 4) (0/ 4)

Fe-50 (16) ( 8.6 2 43 8)E O 15 ( 3.6 2 6.5)E 1 ( 2.12 3.5)E 1 (0) ( -4 5 - 12.7)E 1 ( 2.9 - 1274 0)E -1 (-1.0 - 5.2)E 1 (0/12) (0/ 4) (0/ 4)

Co-60 (16) (-1.2 210.3)E O 11 ( 2.6 t 8 0)E O ( 1.6

• 8.7)E O (0) ( -2.4 - 1.1)E 1 ( -4.7 - 11.1)E O (-8.8 - 5 8)E O (0/12) (0/ 4) (0/ 4)

Zn-65 (16) ( -3.1 25 9)E O 11 ( 1.5 t 1.7)E 1 (-1.2 21.7)E 1 (0) ( -5.0 - 3.2)E 1 ( 2.5 - 32.2)E O ( -2.9 - 0.2)E i (0/12) (0/ 4) (0/ 4)

I Cs-134 (16) ( 1.716 6)E O 15 ( 5.3 2 6.4)E O (-1.3

• 8 9)E O (0) ( -1.2 - 1.2)E 1 (-1.0 - 11.5)E O (-9.3 - 6 4)E O (0/12) (0/ 4) (0/ 4)

Cs-137 (16) ( 7.0 t 11.0)E D 15 ( 9.8 215 9)E O ( 3.4 2 7.4)E O (0) (-6.2 - 30.2)E O ( -6.2 - 30.2)E O ( -6.0 - 8.9)E O (0/12) (0/ 4) (0/ 4)

Th-232 (16) ( 2.812.4)E 1 15 ( 3.12 2.4)E 1 (-2.6 2 2.1)E 1

I (0) ( -1.5 - 6.0)E 1 (0/12)

( 2.2 - 5.7)E 1 (0/ 4)

(-4 4 --1.0)E 1 (0/ 4)

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in Technical Specification Table 7.1-1.

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

I I

Page 49

I Table 2.14-1 Shellfish Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station Plymouth, MA (January - December 1996)

MEDIUM: Shellfish UNITS: oCi/ka wet logicato, Statiqrla Station With Hiahest Mega Control Stations Radionuclide Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (Non-Routine *) LLD (No. Detected") (No. Detected") (No Detected")

Be-7 (48) ( 3.7

• 5.8)E 1 12 ( 4.0 t 8.2)E 1 ( 1.8

• 6 8)E 1 (0) ( -1.2 - 1.5)E 2 ( -1.2 - 1.5)E 2 (-1.8 - 1.8)E 2 (6/ 24) (0/12) (3/ 24)

K-40 (48) ( 9.2 2 4 9)E 2 15 ( 1.3 2 0.2)E 3 ( 8.0 2 6.1)E 2 (0) ( 1.3 - 16 3)E 2 ( 9.9 - 14 2)E 2 ( 3 9 204 2)E 1 l (19/24) (4/ 4) (17/24)

W Mn-54 (48) 130 ( -1.5 61.8)E -1 13 ( 3.219.4)E O ( 2.4 t 7.6)E O (0) ( -2.0 - 1.3)E 1 ( 1.5 - 2.3)E 1 (-1.5 - 2.3)E i (0/ 24) (0/16) (0/ 24)

Co-58 (48) 130 ( 9.7

• 35 9)E -1 12 ( 1.9 2 5.1)E O ( 2.0 71.7)E -1 (0) (-3.1 - 12.2)E O (-3.1 - 12.2)E O (-1.2 - 1.6)E 1 (0/ 24) (0/12) (0/ 24) j Fe 59 (48) 260 (-3.4 t 17.3)E O 11 ( 1.3 2 3.0)E O (-2.7 t 16.4)E O (0) (-5.5 - 2.5)E 1 (-1.4 5.7)E O (-3.2 - 3 6)E 1 (0/ 24) (0/ 8) (0/ 24) l Co 60 (48) 5 ( 1.8 t 7.0)E O 12 ( 2.2 210.2)E O ( 1.2 2 5.5)E O  !

(0) ( 2.0 - 19)E 1 ( 1.9)E i ( -7.5 - 14.0)E O l (1/ 24) (0/12) (0/ 24)

Zn-65 (48) 5 (-8.8

• 21.2)E O 15 ( 2.216.0)E O (-8.1212.9)E O (0) ( 7.5 - 0.8)E 1 ( -4 0 - 8.3)E O (-3.8 - 1.2)E 1 (0/ 24) (0/ 4) (0/ 24)

Cs-134 (48) 5 ( t.0 2 4 3)E O 12 ( 2.3 2 6.0)E O (-2.9 2 5.4)E O l (0) (-8.7 - 12.3)E O (-8.7 - 12.3)E O ( -1.4 - 1.0)E 1 i

(0/ 24) (0/12) (0/ 24) l Cs-137 (48) 5 ( 9.6 2 57.2)E -1 12 ( 1.8 2 8.3)E O (-2.6 2 7.0)E O (0) ( -1.1 - 1.7)E 1 ( 1.1 - 1.7)E 1 ( 19 - 0.9)E 1 (0/ 24) (0/12) (0/ 24)

Ce-144 (48) 15 (-3.1219.8)E O 13 ( 1.0 t 4.4)E 1 ( 6.0 2 35.8)E O (0) ( -5.9 - 3.1)E 1 ( -6.4 - 12.2)E 1 ( -6.4 - 12.2)E 1 (0/ 24) (0/16) (0/ 24)

Th-232 (48) ( 1.0 t 3.8)E 1 13 ( 4.0 2 6.5)E 1 ( 4.12 5.5)E 1 (0) (-1.4 0.8)E 2 (-3.7 - 18.5)E 1 ( -3.7 - 18.5)E 1 (4/ 24) (2/16) (6/ 24)

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in Technical Specification Table 7.1-1.

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

Page 50

l I

Table 2.15-1 Lobster Radioactivity Analyses l

Radio!ogical Environmental Program Summary l I Pilgrirn Nuclear Power Station, Plymouth, MA (January - December 1996)

MEDIUM: Lobster UNITS: oCi/ko wet

)

Indicatc r Str1QD3 Station With Hiahest Mean Control Stations Radionuclide Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (Non-Routine *) LLD (No. Detected") (No Detected") (No. Detected **)

Be-7 (5) (-3 3 t 8.7)E 1 13 ( 2.5 6.4)E 1 ( 2 5

• 6.4)E 1 (0) (-1.4 - 0.4)E 2 I K-40 (5)

(0)

(0/ 4)

( 2.4 2 0.3)E 3

( 2.2 -2.7)E 3 13 (0/1)

( 2.4 2 0.3)E 3 (0/1)

( 2.4

• 0.3)E 3 i

(4/ 4) (1/1) (1/1)

Mn-54 (5) 130 ( 4.4

• 8 8)E O 11 ( 4.4 2 8.8)E O (-1.12 0.8)E 1 (0) ( -3.7 - 15.1)E O ( -3.7 - 15.1)E O i (0/ 4) (0/ 4) (0/1)

Co-58 (5) 130 ( 1.7 213.2)E O 11 ( 1.7 213.2)E O ( 2.2 2 7.7)E O (0) ( -9.7 - 14.7)E O ( 9.7 - 14.7)E O (0/ 4) (0/ 4) (0/1)

Fe-59 (5) 260 (-3.9

• 236.7)E -1 13 ( 3.3 2 2.7)E 1 ( 3.3

• 2.7)E 1 (0) (-1.9 2.1)E 1 (0/ 4) (0/1) (0/1)

Co-60 (5) 130 (-2.1

• 9.3)E O 13 (-1.8 2 9.7)E O (-1.8 2 9.7)E O (0) (-1.2 - 0.3)E 1 (0/ 4) (0/1) (0/1) l I Zn-65 (5)

(0) 260 ( -3.5 1.2)E 1

( -3.9 - -2.9)E 1 (0/ 4) 12 (-1.3 21.8)E 1 (0/1)

( 1.3 21.8)E 1 (0/1)

Cs-134 (5) 130 (-3.0 2 9.8)E O 11 (-3.0 t 9.8)E O

' (-1.2 2 0 8)E 1 (0) (-1.2 - 0.8)E 1 ( -1.2 - 0.8)E 1 (0/ 4) (0/ 4) (0/1)

Cs-137 (5) 130 j (0)

( 1.0 t 5.7)E O

(-1.9 4 9)E O 11 ( 1.0 t 5.7)E O

( -1.9 - 4 9)E O

(-6.8

• 9.2)E O i

!g (0/ 4) (0/ 4) (0/1) l l

Th-232 (5) (-1.2 2 4.9)E 1 13 ( 3.6 2 3.5)E 1 ( 3.6

• 3.5)E 1 l I (0) (-5.9 - 3.2)E 1 (0/ 4) (0/1)

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in Technical Specification Table 7.1-1.

(0/1)

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

I

}

Page 51

Table 2.16-1 Fish Radioactivity Analyses

Radiological Environrnental Program Summary Pilgnm Nuclear Power Station, Plymouth, MA (January December 1996)

MEDIUM. Fish UNITS: DCi/ka wet J.adipptor Stations Station With Hiahest Mean QgnirgLStattigna Radionuclide Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (Non-Routine *) LLO (No. Detected") (No. Detected") (No Detected")

Be-7 (24) ( 1.5 t 75.5)E O 11 ( 1.5 t 75.5)E O (-3.2 t 4.3)E 1 (0)

.I

(-1.7 - 1.2)E 2 (0/16)

(-1.7 - 1.2)E 2 (0/16)

( -1.0 - 0.0)E 2 (0/ 8)

K-40 (24) ( 3.2 2 0.3)E 3 90 ( 4 0 2 0.4)E 3 ( 3.5 i 0 5)E 3 (0) ( 2.6 - 3.7)E 3 ( 3.8 4.2)E 3 ( 2.9 - 4.2)E 3 (16/16) (2/ 2) (8/ 8)

Mn 54 (24) 130 (-8.2 2 72.7)E -1 96 ( 4 3

• 81.3)E -1 ( 2.0 t 75.8)E -1 (0) ( -9.1 - 16.7)E O (-6.6 14.4)E O (-6.6 14.4)E O (0/16) (0/ 6) (0/ 8)

Co-58 (24) 130 ( 1.4 t 6.4)E O 90 ( 3.5 212.0)E O ( 2.0 211.7)E O (0) (-9.1 - 14.1)E O (-3.9 10.8)E O (-1.1 - 2.4)E 1 (0/16) (0/ 2) (0/ 8)

Fe-59 (24) 260 (-1.4126.2)E O 11 ( -1.4 26.2)E O ( 1.8 2 3.2)E 1 (0) ( -3.1 - 5.0)E 1 (-3.1 5 0)E 1 ( -6.3 - 3.3)E 1 (0/16) (0/16) (0/ 8)

Co-60 (24) 130 ( 2.2 210.7)E O 98 ( 2.0 210.8)E O ( 2.2 t 9.8)E O (0) ( 1.5 1.9)E 1 (-1.3 - 1.5)E 1 ( -1.3 - 1.5)E 1 l (0/16) (0/ 6) (0/ 8) l l Zn-65 (24) 260 ( -5.8 20.9)E O 11 (-5.8 2 20.9)E O (-1.0 t 2.1)E 1 (0) (-4.6 - 3.2)E 1 (-4.6 - 3.2)E 1 (-3.8 - 1.4)E 1 (0/16) (0/16) (0/ 8)

Cs-134 (24) 130 ( 2.9 2145.7)E -1 11 (2.9 145.7)E -1 (-5.2 t 99.2)E -1 (0) (-2.0 - 3.4)E 1 (-2.0 3.4)E 1 (-7.5 - 21.0)E O i (0/16) (0/16) (0/ 8) l l Cs-137 (24) 130 ( 3.4 t 9.2)E O 90 ( 4 3 t 9.7)E O ( 3.9 2 7.6)E O (0) (-9.1 22.7)E O ( 0.0- 8,7)E O ( -7.5 - 12.5)E O

( (0/16) (0/ 2) (0/ 8)

Th-232 (24) ( 8.6 2 31.3)E O 90 ( 2.8

• 12.1)E 1 ( 9.2 2 59.3)E O (0) (-3.7 - 7.5)E 1 (-5.5 11.2)E 1 ( -5.5 - 11.2)E 1 (0/16) (0/ 2) (0/ 8)

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in Technical Specificaten Table 7.1 1.

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

I

. Page 52

Table 2.17-1 Sediment Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 1996)

MEDIUM. Sediment UNITS: DCi/ka drv Indicator Stationg Station With Hiahest Mean Control Stations Radionuclide Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (Non-Routine *) LLD (No. Detected") (No. Detected") (No. Detected")

Be-7 (56) ( 1.6 2 4.8)E 1 13 ( 1.2 2 3.3)E 2 ( 7.9 2 26.8)E 1 (0) (-5.7 17.1)E 1 ( 3.2 - 110,5)E 1 (-3.2 110.5)E 1 I K-40 (56)

(0)

(1/ 39)

( 8.8 t 0.7)E 3

( 7.3 10.3)E 3 13 (2/11)

( 1.2 2 0.1)E 4

( 9.9- 14.9)E 3 (2/17)

( 1.12 0.2)E 4

( 9.1 - 14.9)E 3 (39/39) (til11) (17/17)

Co-58 (56) 50 (-2.3 2 3.2)E O 14 (-1.2 2 4.5)E O (-3 3

• 3.1)E O (0) ( 8 0 - 5.3)E O (-6.7 - 5.3)E O ( -9.0 - 2.2)E O (0/ 39) (0/ 6) (0/17)

Co-60 (56) 50 ( 1.8

• 3 4)E O 11 ( 3.4 2 3.3)E O ( 5.6

• 37.5)E -1 (0) (-6.4 - 8.2)E O (-1.6 - 8.2)E O (-6.0 - 8.4)E O (0/ 39) (0/11) (0/17)

. Zn-65 (56) 50 ( 4.0 2 8.8)E O 24 ( 9.7 i 10.7)E O ( 7.5 213.0)E O E (0) (-9.0 - 23.1)E O (-7.7 17.8)E O ( -2.2 - 3.1)E 1 (0/ 39) (0/ 6) (0/17)

Zr-95 (56) 50 ( 3.6 2 6.6)E O 12 ( 5.7 2 6.0)E O ( 3.6 i 5.5)E O (0) (-9.1 16.1)E O ( -1.6 - 14.8)E O (-8.1 10.2)E O (0/ 39) (0/11) (0/17)

I Cs-134 (56)

(0) 50 ( -2.3 7.9)E O

( -2.3 - 1.7)E 1 (0/ 39) 14 ( 1.12 8.3)E O

( -6.7 - 16.6)E O (0/ 6)

(-4 0 2 5.7)E O

( -1.8 - 0.2)E 1 (0/17) 1 l

Cs-137 (56) 50 ( 5.9 2 9.0)E O 13 ( 2.6 1.2)E 1 ( 1.9 21.4)E 1 1 (0) (-6 0 - 25 4)E O ( 1.2 - 5.2)E 1 ( -5.7 - 523.0)E -1 l (9/ 39) (10/11) (10/17)

Ce-144 (56) 150 (-1.2 t 1.7)E 1 24 ( 9.9 219.8)E O (-7.4 2 34 3)E O (0) (-4.1 - 1.7)E 1 (-1.8 - 3.0)E 1 ( -6.3 - 3.2)E 1 i (0/ 39) (0/ 6) (0/17) )

Th-232 (56) ( 2.9 i 1.2)E 2 13 ( 4.6 2 0.7)E 2 ( 4.3 t 0.7)E 2 l I Pu-238 (0)

(6)

( 1.4 - 7.7)E 2 (39/39)

(-3.5 t 1.3)E O 12

( 3.8 - 6.2)E 2 (11/11)

( 3.4- 6.2)E 2 (17/17) i

(-2.6 t 1.9)E O (-4 4 2 2.1)E O

'I Pu-239 (0)

(6)

(-3.9 -2.6)E O (0/ 4)

( 2.614.6)E O 12 (0/1)

( 9.4 1.4)E O

( -5.2 - -3.6)E O (0/ 2)

( 9.114.1)E O i

(0) ( -4.6 - 94.0)E -1 ( 6.3 - 11.9)E O (1/ 4) (1/1) (2/ 2) l

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in Technical Specification Table 7.1-1.

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

lI Page 53

Table 2.17-2 I Sediment Plutonium Analyses Environmental Radiological Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 1996) i pCi/kg (dry) i 1 S.D.

Location Core Depth (cm) Plutonium-238 Plutonium-239/240 Discharge Canal Outfall 0-2 NDA NDA Discharge Canal Outfall 12-14 NDA NDA

.g

E.

Plymouth Harbor 0-2 NDA 9.4 i 1.4 Manomet Point 0-2 NDA NDA Duxbury Bay - Control 0-2 NDA 11.9 i 2.1 Duxbury Bay - Control 12-14 NDA 6.3 i 1.3

• NDA indicates no detectable activity.

t I

. Page 54

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

Desenption ~' Code Distance / Direction TLDs Within Protected Area O&M/RXB. BREEZEWAY P21 50 m SE EXEC, BUILDING P24 57 m W l FENCE-R SCREENHOUSE PO4 66 m N l O&M - 2ND W WALL P20 67 m SE EXEC. BUILDING LAWN P25 76 m WNW FENCE-WATER TANK POS 81 m NNE FENCE-OIL STORAGE P06 85 m NE l O&M - 2ND SW CORNER P19 86 m S O&M - 1ST SW CORNER P18 90 m S l COMPRESSED GAS STOR P08 92 m E i I FENCE-L SCREENHOUSE FENCE-EXEC. BUILDING O&M -2ND S WALL FENCE-INTAKE BAY P03 P17 P23 P07 100 m NW 107 m W 121 m ENE 121 m SSE I 134 m ESE FENCE-WAREHOUSE P26 l 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 i FENCE-ACCESS GATE P12 202 m SE l

FENCE-E SWITCHYARD P15 220 m S i I FENCE-TCF/ INTAKE BAY FENCE-MEDICAL BLDG.

FENCE-BUTLER BLDG FENCE-TCF/PRKNG LOT P10 P13 P14 P28 223 m E 224 m SSE 228 m S 259 m ESE i

I

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

l I

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Page 55

.I

I Figure 2.2-1 (continued)

Environrnental TLD Locations Within the PNPS Protected Area I MMitmpppp/

h 100 meters , !

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I i $l l r y m;tp f ,, , , , ,, , _ -; 7 p3 e Trash Main Stack pg J,e / , __. I

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-h -

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Bu dng n Met T r g

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Rocky Hill Ro I

Page 56

l

Figure 2.2-2 i TLD and Air Sampling Locations

Within 1 Kilometer I Description TLD Station Zone 1 TLDs,0-3 km

' Code Location

• Distance / Direction Desenption Air Sampler Station I Code Location

• Distance / Direction BOAT LAUNCH WEST BLW 0.11 km E OVERLOOK AREA OA 0.15 km W

,I OVERLOOK AREA HEALTH CLUB OA TC 015 km W 0.15 km WSW PEDESTRIAN BRIDGE MEDICAL BUILDING PB WS 0.21 km N 0.23 km SSE I BOAT LAUNCH EAST BLE 0.16 km ESE EAST BREAKWATER EB 0.44 km ESE PEDESTRIAN BRIDGE PB 0.21 km M PROPERTY LINE PL 0.54 km NNW

,I SHOREFRONT SECURITY MEDICAL BUILDING PARKING LOT P01 WS CT 0.22 km NNW 0.23 km SSE 0 31 km SE W ROCKY HILL ROAD E ROCKY HILL ROAD WR ER 0.83 km WNW 0 89 km SE SHOREFRONT PARKING PA 0.35 km NNW iI 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 .

I PNPS MET TOWER PMT 0.44 km WNW l STATION H H 0 47 km SW STATION I l 0.48 km WNW STATION L L 0.50 km ESE STATION G G 0.53 km W

,I STATION D PROPERTY LINE STATION C D

PL C

0.54 km NW 0.54 km NNW 0.57 km ESE 1

1 HALL'S BOG HB 0.63 km SE l GREENWOOD HOUSE GH 0.65 km ESE '

W ROCKY HILL ROAD WR 0.83 km WNW E ROCKY HILL ROAD  ! ER 0 89 km SE I

I I

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Page 57

Figure 2.2-2 (continued)

TLD and Air Sampling Locations: Within i Kilometer hf . . . .

~ ,

'l" l

.l

t

- 3, ,

1 m

y e-urd, i I

"'- 1.0 km d?

g

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i f

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, y 7. i Wk

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j

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a V

l 1 I l I ' * "

I Figure 2.2-3 TLD and Air Sampling Locations: 1 to 5 Kil0 meters l

TLD Station, Location

• Air Sampler _ Station Location *

.Desenption Code Distance / Direction Desenption Code Distance / Direction Zone 1 TLDs 0-3 km MICROWAVE TOWER MT 1.03 km SSW CLEFT ROCK CR 1.27 km SSW i CLEFT ROCK CR 1.27 km SSW MANOMET SUBSTATION MS 3 60 km SSE l BAYSHOREJGATE RD BD 1.34 km WNW MANOMET ROAD MR 1.38 km S I DIRT ROAD EMERSON ROAD EMERSON /PRISCILLA DR EM EP 1.48 km SW 1.53 km SSE 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 l I WHITEHORSE ROAD PLYMOUTH YMCA STATION K TAYLOR / THOMAS WH RC K

TT 2.09 km SSE 2.09 km WSW 2.17 km S 2.26 km SE I

j YANKEE VILLAGE YV 2.28 km WSW

'I GOODWIN PROPERTY RIGHT OF WAY TAYLOR / PEARL GN RW TP 2.38 km SW 2.83 km S 2 98 km SE Zone 2 TLDs: 3-8 km VALLEY ROAD VR 3.26 km SSW MANOMET ELEM ME 3.29 km SE WARREN /CLIFFORD WC 3 31 km W RT.3A/ BARTLETT RD BB 3 33 km SSE I MANOMET POINT MANOMET SUBSTATION BEACHWOOD ROAD MP MS BW 3 57 km SE 3 60 km SSE 3 93 km SE I

i 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.

I I

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Page 59

I Figure 2.2-3 (continued)

TLD and Air Sampling Locations: 1 to 5 Kilometers l

l u _

i k.%h.$E.8 .

g y .r u s j g .g g iy g+ 'E gm>S*' g 10

'.I j u hvc f i '. DR MT '(i eigg

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+, 3( j IfkhESi$

4'

(

h kl MM

,. .., nr i MR Eh E -

'N -tg*+-a$

s. a -

or , x. dywMtu

15 km KC BE SA 1311 km NNW 13.37 km S 13.43 km WSW I CEDARVILLE SUBST KINGSTON SUBST LANDING ROAD CHURCH / WEST CS KS LR CW 15 93 km S 16.15 km WNW 16 46 km NNW 16 56 km NW I 17.02 km WSW MAIN / MEADOW MM DIV MARINE FISH DMF 20 97 km SSE

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

I I

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Page 61

t

'l I

l Trigure 2.2-4 (continued) 5 i TLD and Air Sampling Locations: 5 to 25 Kilometers

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,lI Page 62 4

_ . _ _ _ _ . _ _ _ _ _ _ _ . . _ . - - , _ _ . . . ~ . _ . . . . _ _ ~ __ , _ _ _

I Figure 2.2-5 I

I Terrestrial and Aquatic Sampling Locations I Description MlW Plymouth County Farm Code CF Distance / Direction

• 5.6 km W Desenption SURFACE WATER Discharge Canal Code DIS Distance /Direcbon*

0.2 km N I Whitman Farm Control FORAGE WF 34 km WNW Bartlett Pond Powder Point Control BP PP 2.7 km SE 13 km NNW Whipple Farm WH 2.9 km SW IRISH MOSS Plymouth County Farm CF 5.6 km W Discharge Canal Outfall DIS 0.5 km N Whitman Farm Control WF 34 km WNW Manomet Point MP 3.9 km ESE Ellisville EL 13 km SSE VEGETABLES / VEGETATION Brant Rock Control BK 16 km NNW

>I Site Boundary C BC 0.5 km SW Site Boundary B BB 0.5 km ESE SHELLFISH I 0.9 km SE Rocky Hill Road RH Discharge Canal Outfall DlS 0.5 km N Site Boundary A BA 1.5 km SSW PWuth Harbor PLY-H 4 8 km W Clay Hill Road CH 1.6 km W Manomet Point MP 3.9 km ESE Brook Road BK 2.9 km SSE Duxbury Bay Control DUX-BAY 13 km NNW I Beaverdam Road Plymouth County Farm Div. Manne Fishenes BD CF DMF 3.4 km S 5.6 km W 21 km SSE Powder Point Control Green Harbor Control PP GH 13 km NNW 16 km NNW Bridgewater Farm Control BF 31 km W LOBSTER Norton Control NC 50 km W Discharge Canal Outfall DIS 0.5 km N DeVincent Farm Control DV 72 km NW Plymouth Beach PLB 4.0 km W I

Plymouth Harbor PLY-H 6.4 km WNW CRANBERRIES Duxbury Bay Control DUX-BAY 11 km NNW Manomet Point Bog MR 3 9 km SE Bartlett Road Bog BT 4.3 km SSE ELSHES I Pine Street Bog Control PS 26 km WNW Discharge Canal Outfall Plymouth Beach Jones River Control DlS PLB JR 0.5 km N 4 0 km W 13 km WNW I Cape Cod Bay Control N River-Hanover Control Cataumet Control CC-BAY NR CA 24 km ESE 24 km NNW 32 km SSW Provincetown Control PT 32 km NE Buzzards Bay Control BB 40 km SSW Pnest Cove Control PC 48 km SW Nantucket Sound Control NS 48 km SSE I Atlantic Ocean Control Vineyard Sound Control AO MV 48 km E 64 km SSW SEDIMENT Discharge Canal Outfall DlS 0.5 km N Plymouth Beach PLB 4.0 km W Manomet Point MP 3.9 km ESE Plymouth Harbor PLY-H 4 8 km W Duxbury Bay Control DUX-BAY 14 km NNW Green Harbor Control GH 16 km NNW

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

I e.,e e3 g

l Figure 2.2-5 (continued)

Terrestrial and Aquatic Sampling Locations l b=_

I N N .

MARSHFIELL h

mmm (M ' t E M'JSSEL)

I D M

fa'?f#$$

O msaums C LOBSTER h FISHES

,I [

t .aa .. C SURFACE WATER SEDIMENT l S8=% s

" o comm  :

if _,,,,\ fbmmm

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+

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== =,=_ =p ,

_=.,_

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g q==_

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

• Description Code Distance / Direction

• ILQ SURFACE WATER Cedarville Substation CS 16 km S Powder Point Control PP 13 km NNW Kingston Substation KS 16 km WNW Landing Road LR 16 km NNW IRISH MOSS Church & West Street CW 17 km NW Brant Rock Control BK 16 km NNW Main & Meadow Street MM 17 km WSW Div. Marine Fisheries DMF 21 km SSE SHELLFISH East Weymouth Substation EW 40 km NW Duxbury Bay Control DUX-BAY 13 km NNW Powder Point Control PP 13 km NNW AIR SAMPLER Green Harbor Control GH 16 km NNW EastWeymouth Substation EW 40 km NW LOBSTER MiB Duxbury Bay Control DUX-BAY 11 km NNW Whitman Farm Control WF 34 km WNW flStifa FORAGE Jones River Control JR 13 km WNW Whitman Farm Control WF 34 km WNW Cape Cod Bay Control CC-BAY 24 km ESE N River-Hanover Control NR 24 km NNW YEGETABLES/ VEGETATION Cataurnet Control CA 32 km SSW Div. Marine Fish. Control DMF 21 km SSE Provincetown Control PT 32 km NE Bridgewater Farm Control BF 31 km W Buzzards Bay Control BB 40 km SSW Norton Control NC 50 km W Priest Cove Control PC 48 km SW DeVincent Farm Control DV 72 km NW Nantucket Sound Control NS 48 km SSE Atlantic Ocean Control AO 48 km E CRANBERRIES Vineyard Sound Control MV 64 km SSW Pine Street Bog Control PS 26 km WNW SEDIMENT Duxbury Bay Control DUX-BAY 14 km NNW Green Harbor Control GH 16 km NNW

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

I i

I Page 65

Figure 2.2-6 (continued)

Environmental Sampling And Measurement Control Locations I 4 SYMBOL KEY I O suru nsu 04 BLUEMUSSEL)

(5 SCFT SIIELL CLAM)

QI IDutD SHELLCIAW Q IISIIMOSS C2 wsma

>I s - k umacuamur C FISHES o ---

I d Q CRAN 3ERRY l C VEGE"'ATICNTCBAGE g 0 *"

o B i o O O U

1. SCALE j

!I 1 s g h^ ,b ", &

I V "a ,y ,,_ },"

g s 3 g can amur 1 l

.I \

~ -

__ a r i.

E d hF can coocANAL

'q -  %, ,, sd , p *

,a . . e E .)

• aF

.cuamar i unrucxnscwe e

M n _irus I

, e,. ee

Historical Beach Survey Exposure Rate Measurements 14 12

' s . A /\

l '

N/ A/A .\/,/.

i \_ / "'s -

.~/

! I: ..-

4 x s ~ [s\ .,/Y 2 I C? p s* u( \r'3 ,I'0\'N/'N.3

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77 79 81 83 85 87 89 91 93 95 Year

-+-Whitehorse Beach at Hilltop Avenue -m- Priscilla Beach at Full Sail Bar

- A- Plymouth Beach - Outer -x- Plymouth Beach - Inner

-x- Plymouth Beach at Berts -*- Duxbury Beach Control I

I I Figure 2.4-1 Historical Beach Survey Exposure Rate Measurements I

Page 67

i I

Airbome Gross-Beta Radioactivity Levels Near-Station Monitors 0.05 I

0.04 I -

j 0.03 ,

o l[ 5

, , b 0 02 I

, ..,m,h)kJhhf.h

f k b)!k f ,

I Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month - 1996

-+-- AP-00 Medical Building -m- AP-07 Pedestrian Bridge

- A- AP-08 Overlook Area -x- AP-09 East Breakwater

-X- AP-21 East Weymouth Control I

Figure 2.5-1 Airborne Gross-Beta Radioactivity Levels: Near Station Monitors I

. I ea . ee g

1 I t Airborne Gross-Beta Radioactivity Levels ,

Property Line Monitors l 0.05 I

0.04 I ,

g 0.03 X X I

o i 0.02 Y -- I ' 8E I }

I h..pf . .

. 1 I 0 , , , , , , , , , , ,

l j

Jan Feb Mar Apr May Jun I

Jul Aug Sep Oct Nov Dec Month - 1996

-+- AF'-01 E. Rocky Hill Road -u- AP-03 W. Rocky Hill Road

-A- AP-06 Property Line -x- AP-21 East Weymouth Control I

I Figure 2.5-2 I Airborne Gross-Beta Radioactivity Levels: Property Line Monitors I

g e.. 89

I Airborne Gross-Beta Radioactivity Levels Offsite Monitors 0.05 I

0.04 I ,

j 0.03 l

0 02 E -

-- E /

I i

L h\.p8lQTV. 1 n.r. s, r 4

4 0 , , , , , , , , , , , i Jan Feb Mar Apr May Jun Jul I

Aug Sep Oct Nov Dec Month - 1996

-+- AP-10 Cleft Rock --u- AP-15 Plymouth Center

-A- AP-17 Manomet Substation --x- AP-21 East Weymouth Control I

I Figure 2.5-3 I Airborne Gross-Beta Radioactivity Levels: Offsite Monitors I

g e... ze

l Levels of Strontium-90 in Milk Samples 5

I 4

j I 3 - E I

i e

'+

I .

I l II *! I 2

q /

I

\I

' ^ \ l\ l I  ; j j I 0  : ,0 ,= _

,1_,_,___I Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov I

Dec Month - 1996

-+-TM-11 Plymouth County Farm -s-TM-21 Whitman Farm (Control)

I I

Figure 2.7-1 Levels of Strontium-90 in Milk Samples I l 4

ea,. ,1 g

I 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:

1) calculations based on measurements of plant effluents; and

2) 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 1996 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:

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

2) extemal radiation from the ocean during boating and swimming; and

3) ingestion of fish and shellfish.

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

1) extemal radiation from cloud shine and submersion in gaseous effluents;

2) inhalation of airborne radioactivity;

3) extemal radiation from soil deposition;

4) consumption of vegetables; and

5) consumption of milk and meat.

The results frotn the dose calculations based on PNPS operations are presented in Table 3.0-

1. The dose assessment data presented was taken from the " Annual Dose Assessment to the General Public from Radioactive Effluents" report for the period of January 1 through December 31,1996.

g e... z2

l Table 3.0-1 l Radiation Doses from 1996 Pilgrim Station Operations I Maximum Individual Dose From Exposure Pathway - mrem /yr I Receptor Liquid Effluents Gaseous Effluents

• Ambient Radiation ** Total Total Body 0.004 0.9 1.8 2.7 Thyroid 0.002 i 1.4 1.8 3.2 4

Max. Organ 0.013 1.4 1.8 3.2 I

• Gaseous effluent exposure pathway includes combined dose from particulates, iodines and ,

tritium in addition to noble gases.

I

• • Ambient radiation dose for the hypothetical maximum-exposed individual at a location on l

Boston Edison property yielding highest ambient radiation exposure value as measured with l TLDs.

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

I 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 I

l l

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

I 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 1996, 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 I environmental media. During 1996, the only sample medium that indicated detectable radioactivity attributable to PNPS was non-edible mussel shells collected during the first quarter, which contained low levels of Co-60. The corresponding edible portions did not contain any PNPS-related activity. Therefore, no special dose assessment were performed I during 1996.

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 I radiation.

I I

I

4.0 REFERENCES

1) United States of America, Code of Federal Regulations, Title 10, Part 50, Appendix A l 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, "lonizing Radiation Exposures of the Population of the United States," September 1987.

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

I l

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

E

6) United States Nuclear Regulatory Commission, Regulatory Guide 1.109, " Calculation of l l

Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1," Revision 1, October 1977.

I 7) Boston Edison Company, Pilgrim Nuclear Power Station Off-site Dose Calculation Manual, Revision 7, November 1996.

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

9) United States of Americs., Code of Federal Regulations, Title 10, Part 50, Appendix 1.

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 l Monitoring Radioactivity in the Environs of Nuclear Power Plants," Revision 1, April 1975,

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

13) International Commission of Radiological Protection, Publication No. 43, " Principles of l' 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 Off-site Radiological Monitoring - June 9,1977.

17) E. Vossahlik, Yankee Atomic Electric Company, Computer Program "ERMAP," Version 3.1

- January 9,1979.

18) G. St. John, Yankee Atomic Electric Company, "1996 Annual Direct Radiation Survey at Beaches Near Pilgrim Station," EL 53/97, January 30,1997.

Page 74

APPENDIX A l

SPECIAL STUDIES  ;

1 There was no PNPS-related radioactivity detected in environmental samples which represent a l normal exposure pathway. One sample of non-edible mussel shells collected from the l discharge canal outfall during first quarter contained detectable cobalt-60 at a concentration of l 2.710.5 pCi/kg. Since mussel shells are not edible, they do not constitute a normal exposure pathway. The corresponding portions of edible mussel meat did not contain any detectable radioactivity attributable to PNPS.

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APPENDIX B

,I Effluent Release information TABLE TITLE PAGE

- Supplemental Information: January-June 1996 77 W 1A Gaseous Effluents Summation of All Releases 78 January-June 1996 1B Gaseous Effluents - Elevated Releases 79 January-June 1996

a 1C Gaseous Effluents - Ground Level Releases 80

E January-June 1996 2A Liquid Effluents Summation of All Releases 81 January-June 1996

2B Liquid Effluents: January-June 1996 82

-- Supplemental Information: July-December 1996 83 84 I

1A Gaseous Effluents Summation of All Releases July-December 1996 1B Gaseous Effluents - Elevated Releases 85 July-December 1996 1C Gaseous Effluents - Ground Level Releases 86 July-December 1996 2A Liquid Effluents Summation of All Releases 87 2B Liquid Effluents: July-December 1996 88 O

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e.g. 7e g

I Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Supplemental information January-June 1996 i FACILITY: PILGRIM NUCLEAR POWER STATION LICENSE: DPR-35

1. REGULATORY LIMITS l

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

>8 days, tritium I d. Liquid effluents: 0.06 mrem / month for whole body and 0.2 mrem / month for any organ l (without radwaste treatment) j

2. EFFLUENT CONCENTRATION LIMITS

a. Fission and activation gases: 10CFR20 Appendix B Table 11

b. lodines: 10CFR20 Appendix B Table ll l

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

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

3. AVERAGE ENERGY Not Applicable 1

4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY

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

b. todines: for all gamma emitters; radiochemistry ,

c. Particulates: analysis for H-3, Fe-55 (liquid effluents), j

d. Liquid effluents: Sr-89, and Sr-90

{

1

5. BATCH RELEASES Jan-Mar 1996 Apr-Jun 1996 I

a. Liquid Effluents '

1. Total number of releases: 2.60E+01 1.30E+01 1

2. Total time period (minutes): 1.43E+03 6.08E+02 l

3. Maximum time period (minutes): 5.50E+02 1.50E+02 l I 4. Average time period (minutes):

5. Minimum time period (minutes):

6. Average stream flow (Liters / min):

5.50E+01 2.50E+01 1.17E+06 4.70E+01 2.30E+01 1.03E+06 I during periods of release of effluents '

into a flowing stream

b. Gaseous Effluents None None

6. ABNORMAL RELEASES I a. Liquid Effluents

b. Gaseous Effluents None None None None Page 77

Table 1 A Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Summation of All Releases January-June 1996 Period: Period: Estimated Jan-Mar 1996 Apr-Jun 1996 Total Error A. FISSION AND ACTIVATION GASES Total Release: Ci 9.34E+01 8.45E+01 22 % l Average Release Rate During Period: Ci/sec 1.18E+01 1.07E+01 Percent of Technical Specification Limit * *

8. IODINES Totallodine-131 Release: Ci l 1.01 E-03 1.77E-03 20% l Average Release Rate During Period: pCi/sec 1.28E-04 2.24E-04 Percent of Technical Specification Limit *

• C. PARTICULATES Total Release: Cl 7.42E-04 6.55E 04 21 % l Average Release Rate During Period: pCi/sec 9.41 E-05 8.31 E-05 Percent of Technical Specification Limit *

• Gross Alpha Radioactivity: Ci NDA NDA D. TRITIUM I Total Release: Cl Average Release Rate During Period: Ci/sec Percent of Technical Specification Limit 1.53E+01 1.94E+00 1.08E+01 1.37E+00 20% l Notes for Table 1 A:

• Percent of Technical Specification limit values in above sections are based on dose assessments not performed as part of this report. These will be provided in the annual supplemental dose assessment I report to be issued prior to April 1,1997.

1. NDA stands for No Detectable Activity.

2. LLD for airbome gross alpha activity listed as NDA is 1E-11 Ci/cc.

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Page 78 i

Table 1B Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Elevated Release January-June 1996 Continuous Mode Batch Mode Nuclide Released Jan-Mar 1996 l Apr-Jun 1996 Jan-Mar 1996 l Apr-Jun 1996

1. FISSION AND ACTIVATION GASES -Ci N-13 NDA NDA N/A N/A Kr 85m 7.73E+00 9.79E+00 N/A N/A _

Kr-87 NDA NDA N/A N/A Kr-88 5.72E+00 1.8SE+00 N/A N/A Xe-133 1.93E+01 2.39E+01 N/A N/A Xe-135 1.20E+00 2.34E+00 N/A N/A Xe-135m NDA NDA N/A I

N/A Xe-138 3.15E+00 6.77E+00 N/A N/A Total for period 3.71 E+ 01 4.47E+01 N/A N/A

2. lODINES - Ci 1-131 6.03E-04 8.89E-04 N/A N/A l-133 1.39E-03 2.28E-03 N/A N/A Total for period 1.99E-03 3.17E-03 N/A N/A

3. PARTICULATES -Ci Mn-54 NDA 2.25E-06 N/A N/A Co-60 NDA 3.17E-06 N/A N/A Sr-89 1.86E-05 4.01 E-05 N/A N/A Sr-90 NDA NDA N/A N/A Cs-134 NDA NDA N/A N/A I Cs-137 Ba/La-140 NDA 9.87E-06 1.84E-06 5.57E-05 N/A N/A N/A N/A Total for period 2.85E-05 1.03E-04 N/A N/A

4. TRITIUM - Ci l H-3 l 6.07E-01 l 7.93E-01 l N/A l N/A l Notes for Table 18:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

Fission Gases: 1 E-04 Ci/cc I lodines:1E-12 Ci/cc Particulates: 1 E-11 Ci/cc I

I g .. . . z.

1 I  !

Table 1C Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Ground Level Release January-June 1996 j Continuous Mode Batch Mode j Nuclide Released Jan-Mar 1996 l Apr-Jun 1996 Jan-Mar 1996 l Apr-Jun 1996 l

1. FISSION AND ACTIVATION GASES - Ci I N-13 Kr-85m Kr-87 NDA NDA NDA NDA NDA NDA N/A N/A N/A N/A N/A N/A I Kr-88 Xe-133 Xe-135 NDA NDA 5.63E+01 NDA NDA 3.87E+01 N/A N/A N/A N/A N/A N/A Xe-135m NDA I

NDA N/A N/A Xe-138 NDA 1.10E+00 N/A N/A Total for period 5.63E+01 3.98E+01 N/A N/A

2. IODINES - Ci 1-131 4.08E-04 8.76E-04 N/A N/A l-133 1.91 E-03 5.28E-03 N/A N/A Total for period 2.32E-03 6.16E-03 N/A N/A

3. PARTICULATES - Cl Co-60 NDA NDA N/A N/A Sr-89 5.49E-04 2.78E-04 N/A N/A

'l Sr-90 Cs-134 NDA NDA NDA NDA N/A N/A N/A N/A Cs-137 NDA NDA N/A N/A Ba/La-140 1.64E-04 2.74E-04 N/A N/A Total for period 7.13E-04 5.52E-04 N/A N/A

4. TRITIUM - Cl l H-3 l 1.47E+01 l 1.00E+01 l N/A l N/A l Notes for Table 1C:

1. N/A stands for not applicable.

I 2. NDA stands for No Detectable Activity.

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

Fission Gases: 1E-04 Ci/cc lodines: 1E-12 Ci/cc Particulates: 1 E-11 Ci/cc Page 80

Table 2A I Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents - Summation of All Releases I January-June 1996 Period: Period: Estimated Jan-Mar 1996 Apr-Jun 1996 Total Error A. FISSION AND ACTIVATION PRODUCTS Total Release (not including H-3, noble gas, or alpha): Ci 2.93E-04 4.34E-04 12% l Averaoe Diluted Concentration During Period: Ci/mL 1.75E-10 6.94E-10 Percent of Effluent Concentration Limit

• 4.15E-03% 2.86E-02%

B. TRITIUM Total Release: Ci 4.02E-02 9.83E-03 9.4% l Average Diluted Concentration During Period: pCi/mL 2.41 E-08 1.57E-08 Percent of Effluent Concentration Limit

• 2.41 E-03% 1.57E-03%

C. DISSOLVED AND ENTRAINED GASES Total Release: Ci NDA NDA 16% l Average Diluted Concentration During Period: Ci/mL NDA NDA Percent of Effluent Concentration Limit

• NDA NDA D. GROSS ALPHA RADIOACTIVITY l Total Release: Ci l NDA l NDA l 34 % l E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION l Waste Volume: Liters l 7.89E+04 l 2.10E+04 l 5.7% l F. VOLUME OF DILUTION WATER USED DURING PERIOD l Dilution Volume: Liters l 1.67E+09 l 6.25E+08 l 10% l Notes for Table 2A:

• Additional percent of Technical Specification limit values based on dose assessments will be provided in the annual supplemental dose assessment report to be issued prior to April 1,1997.

1. NDA stands for No Detectable Activity.

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

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

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Page 81

l Table 2B I Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents January-June 1996 Continuous Mode Batch Mode Nuclide Released Jan-Mar 1996 l Apr-Jun 1996 Jan-Mar 1996 l Apr-Jun 1996

1. FISSION AND ACTIVATION PRODUCTS -Cl Na-24 N/A N/A NDA 1.21 E-06 Cr-51 N/A N/A NDA NDA Mn-54 N/A N/A 2.75E-05 6.54E-05 I Fe-55 Fe-59 Co-58 N/A N/A N/A N/A N/A N/A 1.49E-04 NDA NDA 6.55E-05 1.48E-06 6.22E-06

)

l Co-60 N/A N/A 7.45E-05 1.70E-04 Zn-65 N/A N/A NDA 2.27E-06 l Sr-89 N/A N/A NDA 1.81 E-06 l Sr-90 N/A N/A NDA 1.66E-06 Zr/Nb-95 N/A N/A NDA NDA Mo-99/Tc 99m N/A N/A NDA NDA Ag-110m N/A N/A NDA NDA Sb-124 N/A N/A NDA NDA l-131 N/A N/A 1.98E-07 3.36E-07 l-133 N/A N/A NDA NDA Cs-134 N/A N/A NDA NDA I Cs-137 Ba/La-140 N/A N/A N/A N/A 4.18E-05 NDA 1.14E-04 4.54E-06 Ce-141 N/A N/A --..

NDA NDA Total for period l N/A N/A 2.93E-04 4.34E-04

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 28:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

Strontium: SE-08 Ci/mL lodines: 1E-06 Ci/mL Noble Gases: 1E-05 Cl/mL All Others: SE-07 Ci/mL I

Page 82

i Pilgrim Nuclear Power Station I Effluent and Waste Disposal Report Supplemental Information July-December 1996 FACILITY: PILGRIM NUCLEAR POWER STATION LICENSE: DPR-35

1. REGULATORY LIMITS

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

>8 days, tritium i I d. Liquid effluents: 0.06 mrem / month for whole body and 0.2 mrem / month for any organ l (without radwaste treatment)

I 2. EFFLUENT CONCENTRATION LIMITS

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

b. lodines: 10CFR20 Appendix B Table 11 i

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

-I d. Liquid effluents: 2E-04 Ci/mL for entrained noble gases; 1

10CFR20 Appendix B Table il values for all l other radionuclides

3. AVERAGE ENERGY Not Applicable

4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY

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

b. lodines: for all gamma emitters; radiochemistry ,

c. Particulates:

analysis for H-3, Fe-55 (liquid effluents),

d. Liquid effluents: Sr-89, and Sr-90

5. BATCH RELEASES Jul-Sep 1996 Oct-Dec 1996

a. Liquid Effluents

1. Total number of releases: 2.70E+01 2.30E+01

2. Total time period (minutes): 1.61 E+03 9.05E+02

3. Maximum time period (minutes): 1.90E+02 1.00E+02

4. Average time period (minutes): 5.96E+01 3.93E+01

5. Minimum time period (minutes): 1.00E+01 2.00E+01

6. Average stream flow (Liters / min): 1.12E+06 1.17E+06 during periods of release of effluents into a flowing stream

b. Gaseous Effluents None None

6. ABNORMAL RELEASES I a. Liquid Effluents

b. Gaseous Effluents 1

None None None Page 83

Table 1 A I Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Summation of All Releases I July-December 1996

~

Period: Period: Estimated Jul-Sep 1996 Oct-Dec 1996 Total Error A. FISSION AND ACTIVATION GASES Total Release: Ci

I Average Release Rate During PLNd: pCl/sec 1.41 E+02 1.79E+01 1.63E+02 2.07E+01 22 % l Percent of Technical Specification Limit *

• B. lODINES Total lodine-131 Release: Ci 3.33E-03 1.05E-03 20 % l

Average Release Rate During Period

Ci/sec 4.22E-04 1.33E-04

Percent of Technical Specification Limit *

• C. PARTICULATES

"*l Total Release: Ci Average Release Rate During Period: Ci/sec 7.10E-04 2.87E-04 21 % l 9.00E-05 3.64E-05 Percent of Technical Specification Limit *

• Gross Alpha Radioactivity: Ci NDA NDA D. TRITIUM l Total Release: Ci 1.77E+01 2.90E+01 20 % l

': - Average Release Rate During Period: Ci/sec 2.25E+00 3.68E+00 Percent of Technical Specification Limit *

• Notes for Table 1 A:

• Percent of Technical Specification limit values in above sections are based on dose assessments not performed as part of this report. These will be provided in the annual supplemental dose assessment report to be issued prior to April 1,1997.

1. NDA stands for No Detectable Activity.

2. LLD for airbome gross alpha activity listed as NDA is 1E-11 Ci/cc.

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Table 1B Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Elevated Release July-December 1996 Continuous Mode Batch Mode Nuclide Released Jul-Sep 1996 l Oct-Dec 1996 Jul-Sep 1996 l Oct-Dec 1996

1. FISSION AND ACTIVATION GASES -Ci l Kr-85m 1.24E+01 3.00E+01 N/A N/A

'E Kr-87 7.70E-01 NDA N/A N/A Kr-88 1.17E+00 2.22E+01 N/A N/A Xe-131m 2.06E+00 NDA N/A N/A Xe-133 7.61 E+01 7.05E+01 N/A N/A Xe-135 2.99E+00 1.89E+00 N/A N/A Xe-195m 1.63E+00 1.12E+00 N/A N/A Xe-138 1.78E+01 1.50E+01 N/A N/A

Total for period 1.15E+02 1.41 E+02 N/A N/A

g IE 2. IODINES - Ci 1-131 1.46E-03 5.28E-04 N/A N/A l l-133 3.52E-03 2.10E-03 N/A N/A l Total for period 4.98E-03 2.63E-03 N/A N/A

3. PARTICULATES - Cl Co-60 1.68E-06 NDA N/A N/A Sr-89 5.05E-05 4.27E-05 N/A N/A l Sr-90 NDA NDA N/A N/A Cs-134 NDA

)

NDA N/A N/A Cs-137 NDA NDA N/A N/A '

Ba/La-140 6.76E-05 2.27E-05 N/A N/A Tota l for period 1.20E-04 6.54E-05 N/A N/A

4. TRITIUM - Cl l H-3 i 9.31E-01 l 4.22E-01 l N/A l N/A l Notes for Table 18:

1. N/A stands for not applicable.

I 2. NDA stands for No Detectable Activity.

3. LLD for airbome radionuclides listed as NDA are as follcws:

Fission Gases: 1 E-04 Cl/cc lodines: 1 E-12 Ci/cc Particulates: 1 E-11 Ci/cc I

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Table 1C Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Ground Level Release July-December 1996 Continuous Mode Batch Mode i Nuclide Released Jul-Sep 1996 l Oct-Dec 1996 Jul-Sep 1996 l Oct-Dec 1996 l

1. FISSION AND ACTIVATION GASES -Ci  !

!l

m Kr-85m Kr-87 NDA NDA NDA NDA N/A N/A N/A N/A j Kr-88 NDA NDA N/A N/A  ;

Xe-133 NDA NDA N/A N/A  !

Xe-135 2.61 E+01 1.42E+01 N/A N/A Xe-135m NDA 8.12E+00 N/A N/A Xe-138 NDA NDA N/A N/A i Total for period 2.61 E+01 2.23E+01 N/A N/A

.l 2. lODINES - Ci E l-131 1.87E-03 5.22E-04 N/A N/A l-133 8.48E-03 3.40E-03 N/A N/A Total for period 1.04E-02 3.92E-03 N/A N/A

3. PAR flCULATES - Cl .

Mn-54 1.40E-05 NDA N/A N/A Co-60 2.34E-05 NDA N/A N/A Sr-89 2.30E-04 8.82E-05 N/A N/A I Sr-90 Cs-134 Cs-137 NDA NDA NDA NDA NDA NDA N/A N/A N/A N/A N/A N/A l

l l

Ba/La-140 3.23E-04 1.34E-04 N/A N/A Total for period 5.90E-04 2.22E-04 N/A N/A

4. TRITlUM - Ci l H-3 l 1.68E+01 l 2.86E+01 l N/A l N/A I Notes for Table 1C:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

Fission Gases: 1 E-04 Ci/cc lodines: 1E-12 Ci/cc Particulates: 1E-11 Ci/cc lg Page 86 IE

Table 2A

Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents - Summation of All Releases July-December 1996 Period: Period: Estimated Jul-Sep 1996 Oct-Dec 1996 Total Error A. FISSION AND ACTIVATION PRODUCTS

• g Total Release (not including H-3, noble gas, or alpha): Ci 6.48E-03 1.88E-03 12 % l

5 Average Diluted Concentration During Period: Ci/mL 3.58E-09 1.78E-09 Percent of Effluent Concentration Limit

• 4.88E-02% 3.11E-02%

B. TRITIUM Total Release: Ci 1.07E+01 3.90E+00 9.4% l Average Diluted Concentration During Period: pCi/mL 5.91 E-06 3.68E-06 Percent of Effluent Concentration Limit

• 5.91 E-01 % 3.68E-01%

C. DISSOLVED AND ENTRAINED GASES Total Release: Cl 4.64E-05 NDA 16% l l Average Diluted Concentration During Period: Ci/mL 2.56E-11 NDA Percent of Effluent Concentration Limit

• 1.28E-05% -

! D. GROSS ALPHA RADIOACTIVITY l Total Release: Ci l NDA l NDA l 34 % l E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION l Waste Volume: Liters l 7.21 E+05 l 3.03E+05 { 5.7% l F. VOLUME OF DILUTION WATER USED DURING PERIOD l Dilution Volume: Liters l 1.81 E+09 l 1.06E+09 l 10% l Notes for Table 2A:

• Additional percent of Technical Specification limit values based on dose assessments will be provided in the annual supplemental dose assessment report to be issued prior to April 1,1997.

1. NDA stands for No Detectable Activity.

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

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

1 Page 87

q Table 2B Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents July-December 1996 Continuous Mode Batch Mode Nuclide Released Jul-Sep 1996 l Oct-Dec 1996 Jul-Sep 1996 l Oct-Dec 1996

1. FISSION AND ACTIVATION PRODUCTS - Cl Cr-51 N/A N/A NDA NDA Mn-54 N/A N/A 3.90E-05 1.01 E-04 Fe-55 N/A N/A 5.02E-03 1.05E-03 Fe-59 N/A N/A 1.63E-05 6.91E-07 Co-58 N/A N/A 5.84E-07 NDA Co-60 N/A N/A 6.39E-04 6.33E-04 Zn-65 N/A N/A NDA NDA Sr-69 N/A N/A NDA NDA Sr-90 N/A N/A 1.50E-06 6.17E-06 Zr/Nb-95 N/A N/A NDA NDA I Mo-99/Tc-99m Ag-110m Sb-124 N/A N/A N/A N/A N/A N/A 1.04E-05 NDA NDA NDA NDA NDA l-131 N/A I l-133 Cs-134 N/A N/A N/A N/A N/A NDA NDA NDA 6.11 E-06 NDA NDA Cs-137 N/A N/A 5.93E-04 8.64E-05 Ba/La-140 N/A N/A 1.65E-04 NDA Ce-141 N/A N/A NDA NDA Total for period N/A N/A 6.48E-03 1.88E-03

2. DISSOLVED AND ENTRAINED GASES - Ci Xe-133 I Xe-135 N/A N/A N/A N/A NDA 4.64E-05 NDA NDA Total for period N/A N/A 4.64E-05 NDA Notes for Table 28.

I 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: SE-08 Ci/mL I lodines: 1E-06 Ci/mL Noble Gases: 1E-05 Ci/mL All Others: SE-07 Ci/mL I

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APPENDIX C LAND USE CENSUS RESULTS 3 The annual land use census for gardens and milk and meat animals in the vicinity of Pilgrim 3 Station was performed between October 10 and 31,1996. The census was conducted by driving along each improved road / street in the Plymouth area wiinin 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 and NNW sectors), the survey was extended to 8 km (5 mi). A total of 33 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 I to those for the existing sampling program locations. These comparisons enabled Boston Edison Company 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 identiCM duc.ig the 1996 land use census, samples of I garden-grown vegetables or naturally-growing vegetation (e.g. grass, leaves from bushes or trees, etc.) were coffected at or near the closest gardens in each of the following landward compass s' m These locations, and their distance and direction relative to the PNPS Reactor Bt ,, are as follows:

Rocky Hill Road 0.9 km SE Brook Road 2.9 km SSE I Beaverdam Road Clay Hill Road 3.4 km S 1.6 km W 1

In addition to these special sampling locations identified and sampled in conjunction with the i 1996 land use census, samples were also collected at or near the Plymouth County Farm I (5.6 km W), Whipple Farm (2.9 km SW), and from a control location at DeVincent Farm in Waltham (72 km NW). The sam. oles from DeVincent Farm were used as substitutes for control samples normally obtained from Bridgewater Farm, which were temporarily unavailable during 1996.

l Samples of naturally-growing vegetation were also collected from the site boundary locations yielding thn 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 -

2nd highest D/O, both release points: 0.5 km SW Control sample of naturally-growing vegetation were collected at the DMF shop in Sandwich (21 km SSE) and in Norton, MA (50 km W).

No new milk or meat animals were identified during the land use census. In addition, the Town of Plymouth Animal Inspector stated that their office is not aware of any animals at locations I 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 1996 sampling program.

I Page 89

l APPENDIX D

-I ENVIRONMENTAL MONITORING PROGRAM DISCREPANCIES There were a number of instances during 1996 in which problem were encountered in the collection of environmental samples. Most of these problems were minor in nature and did not g have an adverse affect on the results or integrity of the monitoring program. Details of these iE various problems are given below.

g In 1996, eight thermoluminescent dosimeters (TLDs) were not recovered from their assigned

.g locations during the quarterly retrieval process. During the first quarter, the TLD was not recovered at Memorial Hall (MH). In this case, the TLD missing from its posted location and was presumably lost to vandalism. During the second quarter retrieval, TLDs were missing at

.I Station J (J), transmission line right of way (RW), Earl Road (EA), and Upper College Pond (UC). In each of these cases, the plastic straps, plastic cages, and TLDs were missing and l

presumably lost due to vandalism. During retrieval of TLDs posted during the third quarter, the TLD at Microwave Tower (MT) was missing and presumable lost to vandalism. The TLDs at i Earl Road (EA) and Upper College Pond (UC) were also missing during the fourth quarter l retrieval, and were presumably lost to vandalism. In all cases of TLD losses, the TLDs were re-located in the immediate vicinity, but steps were taken whenever possible to post the TLD cages in a less conspicuous manner.

Within the air sampling program, there were a few instances in which continuous sampling was interrupted at the eleven airbome sampling locations during 1996. Most of these interruptions l were due to short-term power losses and were sporadic and of limited duration (less than 24 l hours out of the weekly sampling period). Such events did not have any significant impact on the scope and purpose of the sampling program, and all lower limits of detection (LLDs) were met for both particulates and iodine-131 on the filters.

There was one instance in which an air particulate filter was lost between filter collection and processing. Air particulate filters and charcoal cartridges for the period 25-Jun-96 through 02-Jul-96 were collected on 02-Jul-96 and delivered to the Yankee Atomic Environmental Laboratory (YAEL) on 05-Jul-96. The air particulate filter for location WS (near the PNPS Fitness for Duty Building) became lodged in the envelope used to deliver filters to the lab. This envelope was subsequently discarded into the trash. When YAEL personnel began to in-process the filters, the filter was identified as missing. Attempts were made to locate the discarded transfer envelope, but the dumpster had been emptied prior to identification of the missing filter. Steps were taken by YAEL and BECo personnel to fully inventory all filters upon delivery to the lab. This event did not affect the analysis of the charcoal filter collected during that week.

When sampling interruptions resulted from power losses, steps were taken to restore power as soon as possible. Power was interrupted at the Pedestrian Bridge when the ground fault interrupt circuit tripped during the period of 09-Apr-96 through 17-Apr-96 (18 hour2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> run time).

I This breaker trip was due to salt spray entering the sampler enclosure during high winds. Due to the low run time and sample volumes, the required LLDs were not met on the particulate filter and charcoal cartridge collected during this week, and the results were not included in the values presented in Tables 2.5-1 and 2.6-1.

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!E Interruptions to power service were experienced at Manomet Substation (MS) and Plymouth l E Town Hall (PC) due to construction /remodeling which took place during 1996. At Manomet  ;

Substation, switch yard and transformer modifications were made between 26-Mar-96 and 23-

. Apr-96. These interruptions led to complete loss of power (i.e., no sample collection) for the '

weeks of 26-Mar through 02-Apr,02-Apr through 09-Apr, and 09-Apr through 17-Apr. During the week of 17-Apr through 23-Apr, the sampler ran for 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />. Due to the small sample I volume, the required LLDs were not met on the particulate filter and charcoal cartridge.

1 Renovation and remodeling activities at the Plymouth Town Hall (PC) resulted in power j interruptions during the period between 02-Jul and 27-Aug. The sampler ran 25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> during '

the week of 02-Jul through 09-Jul, and required LLDs were met on the particulate filter and charcoal cartridge analyzed. Power was completely lost (i.e., no sample collection) during the l weeks of 09-Jul through 16-Jul, and 16-Jul through 23-Jul. Ongoing construction activities '

also interrupted power during the weeks of 23-Jul through 30-Jul (150 hour0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br /> run time), 30-Jul through 06-Aug (116 hour0.00134 days <br />0.0322 hours <br />1.917989e-4 weeks <br />4.4138e-5 months <br /> run time), 06-Aug through 13-Aug (39 hour4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> run time),13-Aug through 20-Aug (130 hour0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> run time), and 20-Aug through 27-Aug ( 21 hour2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> run time). Follow-

up construction activities during the week of 23-Dec through 31-Dec also resulted in an interruption of power (99 hour0.00115 days <br />0.0275 hours <br />1.636905e-4 weeks <br />3.76695e-5 months <br /> run time).

E Despite the lower-than-normal sampling volumes in the various instances involving power IE interruptions and equipment failures, required LLDs were met on 574 of the 576 particulate filters and 576 of the 577 iodine cartridges collected during 1996. The required LLDs were not lg achieved only on those samples when the sampler run time was very short (<24 hours) out of

B the weekly period due to equipment failure or power losses described above. Despite the low sample volumes in these cases, the samples were still counted for screening purposes. None

E of the 1197 sample analyses performed indicated any questionable or anomalous results.

E When viewed collectively during the entire year of 1996, the following sampling recoveries were achieved in the airbome sampling program:

Location Recovery Location Recovery Location Recovery WS 100.0 % PB 98.0 % PC 89.2 %

, ER 99.9 % OA 100.0 % MS 92.7 %

WR 100.0 % EB 100.0 % EW 100.0 %

PL 100.0 % CR 99.8%

Due to a shortage of state funds during 1996, the agricultural program was not sponsored at Bridgewater Farm. This meant that control samples from that location were temporarily unavailable during 1996. Substitute control samples of vegetables were obtained at a farm stand in Waltham (72 km NW). Resumption of farm activities, and availability of control samples, at the Bridgewater Farm is expected to resume in 1997.

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 !ocations would be 2 to 10 times higher than at the l gardens identified during the land use census. No radionuclides attributed to PNPS operations j Page 91

were detected in any of the samples. Additional details regarding the land use census can be found in Appendix E of this report.

Samples of Group I (bottom-distribution) and Group ll (near-bottom distribution) fishes were not collected in the vicinity of the discharge canal outfall during the first quarter of 1996. Fish species in these categories tend to move to deeper water during the colder months and were not available in the area for collection. Although concerted and repeated efforts were made by personnel from the Massachusetts Division of Marine Fisheries to collect the fish, they were not able to obtain the required samples in summary, the various problems encountered in collecting environmental samples during 1996 were relatively minor when viewed in the contaxt of the entire monitoring program.

Required LLDs were achieved on over 99.7% of all samples collected, and no anomalous or I questionable results were obtained None of the discrepancies resulted in an adverse impact on the overall monitoring program.

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1 APPENDIX E j l

QUALITY ASSURANCE PROGRAM RESULTS l 1

e

1. Introduction

'3 The accuracy of the data obtained through Boston Edison Company's Radiological E 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 Boston Edison from the Yankee Atomic Electric Company's Environmental Laboratory (YAEL), Much of the information contained herein has been summarized from the YAEL " Semi-Annual Quality Assurance Status Report: January -

June 1996," and the YAEL " Semi-Annual Quality Assurance Status Report: July - December

I l

1996."

2. Laboratory Analyses

The quality control programs that were performed during 1996 to demonstrate the validity of laboratory analyses by YAEL include the following

. YAEL intralaboratory quality control program to assure the validity and reliability of the data. This program includes quality control of laboratory equipment, use of reference l standards for calibration, and analysis of blank and spiked samples. The records of l the quality control program are reviewed by the responsible cognizant individual, and

corrective measures are taken, as appropriate.

. YAEL participation in the Environmental Protection Agency (EPA) Interlaboratory Comparison (cross-check) program for drinking water samples routinely analyzed by the laboratory. This provides an independent check of accuracy and precision of the laboratory analyses. When the results of the cross-check analysis fall outside of the control limit, an investigation is made to determine the cause of the problem, and corrective measures are taken, as appropriate.

. YAEL participation in a cross-check program with Analytics, Inc. for environmental water and milk samples.

I

. YAEL participation in cross-check programs with the Department of Energy's Quality Assessment Program (QAP) and Mixed Analyte Performance Evaluation Program (MAPEP). Sample of air filters, soil, water, and vegetation are analyzed in this program for comparison to DOE's quality standards.

. YAEL participation in a cross-check program with the National Institute of Standards

'I 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.

. A blind duplicate program is maintained in which paired samples from the five sponsor companies, including Boston Edison, 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.

The results of these studies are discussed below.

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A. YAEL Intralaboratory and independent interlaboratory Results Results of the Quality Assurance Program are reported in two separate categories base;d upon l YAEL acceptance criteria. The first criterion concems accuracy, which is defined as the l 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 l I comparison of an individual result to the mean of all results for a given sample set. In addition to evaluating all individual samples against the YAEL acceptance criteria, if the mean result of an EPA cross-check analysis exceeds the 3-sigma control limit (as defined by the EPA in their known value summary report) an investigation is conducted by YAEL personnel to determine I the reason for the deviation. Similar criteria exist for other aspects of the independent interfaboratory comparisons for Analytics, DOE, and NIST cross-check samples.

The Quality Assurance Program implemented at the analytical laboratory indicated good precision and accuracy in reported values. Table 1 shows the cumulative results of accuracy j and precision for laboratory analyses in 1996 for YAEL intralaboratory analyses, as well as '

EPA, Analytics, DOE, and NIST interfaboratory cross-check analyses. A total of 931 analyses were performed for accuracy cross-comparisons, while 803 cross-check analyses were performed to assess precision. For accuracy,66% and 86% of the results were within 5 and 10 percent of the known values, respectively, with 97% of all results falling within the laboratory criterion of 15 percent. For precision,87% and 96% of the results were within 5 and 10 percent of the mean, respectively, with >99% of all results meeting the laboratory criterion of 15 percent.

The results of the EPA Interlaboratory Comparison program, when considered apart from the remainder of the Quality Assurance program, were satisfactory with respect to accuracy and precision in 1996. A total of 177 analyses were performed. Based upon this sample analysis total,171 analyses (i.e., 96%) met the EPA's definition of " control limit" acceptance criteria for accuracy, while 176 analyses (i.e.,99%) met the acceptance criteria for precision.

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TABLE 1 INTRALABORATORY AND INTERLABORATORY RESULTS - 1996 Fraction of Measurements Total Number of within deviation range Category Measurements 15% 10% i 15%*

YAEL INTRALABORATORY ANALYSES Accuracy 214 82.2 % 93.0 % 98.6 %

Precision 90 71.1 % 87.8 % 98.9 %

EPA INTERLABORATORY ANALYSES Accuracy 177 46.3 % 79.7 % 96.6 %

Precision 177 81.9 % 95.5% 99.4 %

ANALYTICS INTERLABORATORY ANALYSES Accuracy 297 64.0 % 84.2 % 97.0 %

Precision 297 91.6 % 97.0 % 99.7 %

DOE MAPEP/QAP INTERLABORATORY ANALYSES Accuracy 201 65.2 % 86.6 % 97.0 %

Precision 197 88.3% 95.9 % 100.0 %

NIST INTERLABORATORY ANALYSES Accuracy 42 88.1 % 92.9 % 100.0 %

Precision 42 97.6 % 100.0 % 100.0 %

TOTAL COMBINED ANALYSES Accuracy 931 66.2 % 86.3 % l 97.4 %

Precision 803 86.7% 95.5 % 99.6 %

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

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Page 95

B. Blind Duplicate Proaram I A total of 49 paired samples were submitted by the five sponsor companies for analysis during 1996. The database used for the duplicate analysis consisted of paired measurements of 26 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 criteria 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.

From the 49 paired samples,1283 paired duplicate measurements were analyzed during

, I 1996. Out of thesc rneasurements, 1273 (99.2%) fell within the established criteria discussed above. No trend was evident with respect to repeated failings of measurements for the listed radionuclides and media.

4 I C. EnvironmentalTLD Measurements I

jI Quality control testing was performed during 1996 to demonstrate the performance of the routine environmental TLD processing by YAEL. The quality of the dosimetric resuits is evaluated relative to independent third party testing and intemal performance testing. These g tests were performed independent of the processing of environmental TLDs at YAEL. In all of g these tests, dosimeters were irradiated to known doses and submitted to YAEL 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 tum points out any trends or changes in performance. ,

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

l A i 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)." Acceptance criteria for accuracy and precision to be used in 1996 was adopted by the Laboratory Quality Control Audit Committee (LOCAC) on November 13,1987. Recognizing the inherent variability associated with each dosimeter type, control limits for both accuracy and precision of i 3 sigma plus 5%

(for bias) were set by the LQCAC. The actual magnitude of the 3 sigma plus 5% controllimits 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 I 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 1996, there were 96 quality control tests. All 48 environmental TLDs tested during January - June 1996 were within the control limits for both accuracy and precision. The comparisons yielded a mean accuracy of -3.0%. The comparisons exhibited a precision value with an overall standard deviation of 1.1%. The 48 TLDs tested in July - December 1996 showed a mean accuracy of +0.7%. TLDs measured during the second semiannual period exhibited a precision value with a standard deviation of Page 96

1.4%, well within the acceptance criteria. In total, all 84 environmental TLDs tested during 1996 were within the control limits for both accuracy (i 20.1%) and precision ( 12.8%).

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

I EPA, Analytics, DOE, and NIST), the YAEL intrataboratory quality control program, and the sponsor companies blind duplicate program met the laboratory criterion of less than 15%

deviation in more than 97% of all cases.

4 I The environmental TLD measurements for intralaboratory and independent third party comparisons resulted in both mean accuracy and precision within 5 percent deviation.

Therefore, the quality assurance programs for the Boston Edison Company's Radiological Environmental Monitoring Program indicated that the analyses and measurements performed i' by Yankee Atomic Environmental Laboratory during 1996 exhibited acceptable accuracy and precision.

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