ML20082T772

Radiological Environ Monitoring Program Rept 27,Jan-Dec 1994

ML20082T772
Person / Time
Site:	Pilgrim
Issue date:	12/31/1994
From:	Boulette E, Montt D, Sejkora K BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
BECO-LTR95-058, BECO-LTR95-58, NUDOCS 9505040165
Download: ML20082T772 (102)

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Technical Specification 6.9.C.2 Boston Edison Pilgrim Nuclear Power Station Rocky Hill Road Plymouth, Massachusetts 02360 April 27, ,1995 BECo Ltr.95-058 E. T. Boulette, PhD Senior Vice President-Nuclear U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 License No. DPR-35 Docket No. 50-293

Dear Sir:

In accordance with the Pilgrim Nuclear Pover Station Technical Specification 6.9.C.2, the Boston Edison Company submits the Ar.nual Radiological Environmental Monitoring Program Report for 1994 (Report #27).

0-1 uk.L E. T. Boulette, PhD I WJM/ lam /9449 Af,tachment I

cc: Mr. Thomas T. Martin Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. R. B. Eaton Div. of Reactor Projects 1/11 Office of NRR - USNRC One White Flint North - Mail Stop 14D1 11555 Rockville Pike Rockville, MD 20852 l

Senior Reside:it inspector 9505040165 941231 PDR ADOCK 05000293 R ?DR s

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PILGRIM NUCLEAR POWER STATION I

Radiological Environmental Monitoring Program Report No. 27 January 1 through December 31,1994

& Boston Edison

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i BOSTON EDISON COMPANY j PILGRIM NUCLEAR POWER STATION -

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM  !

REPORT NO. 27 January 1 through December 31, 1994 l l

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Prepared by: ~

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K.5Aefpa Senior EWironmental Radiochemist i

Reviewed b - /

D. A. Koht't /~ .

Chemistry Division Manager l

Approved by: s 8 A S. R. Landahl i Radiological Protection Manager  !

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TABLE OF CONTENTS Section Paae EXECUTIVE

SUMMARY

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1.0 INTRODUCTION

8 1.1 Radiation and Radioactivity 8 1.2 Sources of Radiation 9 1.3 Nuclear Reactor Operations 10 L

1.4 Radioactive Effluent Control 16 1.5 Radiological Impact on Humans 19 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 24 2.1 Pre-Operational Monitoring Results 24 2.2 Environmental Monitoring Locations 25 2.3 Interpretation of Radioactivity Analyses Results 27 2.4 Direct Radiation Measurements 29 2.5 Air Particulate Filter Radioactivity Analyses 30 2.6 Charcoal Cartridge Radioactivity Analyses 30 2.7 Milk Radioactivity Analyses 31 2.8 Forage Radioactivity Analyses 32 2.9 Vegetable / Vegetation Radioactivity Analyses 32 2.10 Cranberry Radioactivity Analyses 33 2.11 Soil Radioactivity Analyses 33 2.12 Surface Water Radioactivity Analyses 34 2.13 Fish Radioactivity Analyses 34 2.14 Shellfish Radioactivity Analyses 35 2.15 Irish Moss Radioactivity Analyses 35 2.16 Lobster Radioactivity Analyses 35 2.17 Sediment Radioactivity Analyses 36 Page 2

TABLE OF CONTENTS (continued)

P Section Plae .

3.0

SUMMARY

OF RADIOLOGICAL IMPACT ON HUMANS 74 f

4.0 REFERENCES

76 APPENDIX A Special Studies 78 l APPENDIX B Effluent Release Information 79 l

APPENDIX C Land Use Census 92 APPENDIX D Environmental Monitoring Program Discrepancies 93  !

' APPENDIX E Quality Assurance Program Results 96 l t

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. . _. _ _ . . _ .~.._ _ _.._. _ _ _ .. _ _ _. .... .. . . . .._

l 4 i LIST OF TABLES  ;

l Table Pace

'1.2-1 Radiation Sources and Corresponding Doses 9 j 1.3-1 PNPS Operating Capacity Factor During 1994 11 2.2-1 Routine Radiological Environmental Sampling Locations 37 i l

2.4-1 Off-site Environmental TLD Results 39 2.4-2 On-site Environmental TLD Results 41 2.4-3 Average TLD Exposures By Distance Zone During 1.994 42  !

2.4-4 Beach Survey Exposure Rate Measurements 43 l

2.5-1 Air Particulate Filter Radioactivity Analyses 44  ;

2.6-1 Charcoal Cartridge Radioactivity Analyses 45 2.7-1 Milk Radioactivity Analyses 46

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. 2.8-1 Forage Radioactivity Analyses .

47 l 2.9-1 Vegetable / Vegetation Radioactivity Analyses 48  ;

1 2.10-1 Cranberry Radioactivity Analyses 49  ;

l 2.11-1 Soil Radioactivity Analyses 50 2.12-1 Surface Water Radioactivity Analyses 51 2.13-1 Fish Radioactivity Analyses 52 2.14-1 Shellfish Radioactivity Analyses 53 i 2.15-1 Irish Moss Radioactivity Analyses 54 2.16-1 Lobster Radioactivity Analyses 55 2.17-1 Sediment Radioactivity Analyses 56 l l

2.17-2 Sediment Plutonium Analyses 57 l

3.0-1 Radiation Doses From 1994 Pilgrim Station Operations 75 t

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

l-L LIST OF FIGURES Fiaure P_agg a

1.3-1 Radioactive Fission Product Formation 12 1.3-2 Radioactive Activation Product Formation 13 i

1.3-3 Barriers to Confine Radioactive Materials 15 -

1.5-1 Radiation Exposure Pathways 20 2.2-1 Air Sampling and T!.D Locations Within PNPS Exclusion Area 58 i

2.2-2 Air Sampling and TLD Locations Within Two Miles of PNPS 60 l 2.2-3 Air Sampling and TLD Locations Beyond Two Miles of PNPS 62 i i

2.2-4 Terrestrial and Aquatic Sampling Locations 64 i 2.2-5 Environmental Measurement Control Sampling Locations 66  !

2.4-1 Historical Beach Survey Exposure Rate Measurements 68 i

2.5-1 Airborne Gross Beta Radioactivity Levels: Near Station 69 i 2.5-2 Airborne Gross Beta Radioactivity Levels: Property Line' 70 f i

2.5-3 Airborne Gross Beta Radioactivity Levels: Off-Site 71 l l

2.7-1 Levels of Strontium-90 in Milk Samples 72 2.7-2 Levels of Cesium-137 in Milk Samples 73 l

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EXECUTIVE

SUMMARY

Boston Edison Company Pilarim Nuclear Power Station Radioloaical Environmental Monitorina Proaram Report January 1 throuah December 31. 1994 INTRODUCTION This report summarizes the results of the Boston Edison Company's Radiological Environmental Monitoring Program (REMP) conducted in the vicinity of Pilgrim Nuclear Power Station (PNPS) during the period from January 1 to December 31, 1994. 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.

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

During 1994, there were 1,423 samples collected fror. the atmospheric, aquatic and terrestrial environments. In addition, 433 exposure measurements were obtained using environmental thermoluminescent dosimeters (TLDs) and six exposure rate measurements were performed using a high pressure ion chamber. These 1,423 samples and 433 monitoring devices were collected by Boston Edison Company and Massachusetts Division of Marine Fisheries personnel.

A few minor problems were encountered during 1994 in the collection of environmental samples in accordance with the PNPS Technical Specifications. Six out of the required 140 TLDs were missing from their posted locations during the quarterly retrieval process. Equipment failures and power outages resulted in missing one out of the required 572 airborne particulate filters, and one of the 572 charcoal filters. Due to seasonal unavailability of Group I (bottom distribution) and Group II (near-bottom distribution) fishes in the vicinity of the discharge canal, these samples were missed during the first quarter of 1994. A few minor equipment failures and cold weather had some limited, short-term effects on composite water samples collected from the discharge canal . A full descrf' tion of the discrepancies encountered with the environmental monitoring prot'.m 's presented in Appendix D of this report.

There were 1,597 analyses performed on the environmental media samples. All analyses were performed by the Yankee Atomic Electric Company Environmental Laboratory in Westboro, Mass. All samples were analyzed as required by the PNPS Technical Specifications.

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LAND USE CENSUS The annual land use census in the vicinity of Pilgrim Station was conducted as required by Technical Specifications between September 20 and 23, 1994. A total of 34 gardens having an area of more than 500 square feet were identified within three miles of PNPS.

No new milk or meat animals were located during the census. Of the 34 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 1994, all samples (except charcoal cartridges) collected as part of the REMP at Pilgrim Station continued to contain detectable amounts of naturally-occurring and man-made radioactive materials. Only one sample collected during 1994 contained any detectable radioactivity attributable to PNPS operations. A single sample collected at a location in Plymouth Harbor contained low levels of cobalt-60, at a concentration of 70 pCi/kg. Off-site direct radiation measurements using environmental TLDs and a high j pressure ion chamber ranged between 48 and 98 mR/ year. This range of radiation levels is consistent with natural background radiation levels for Massachusetts as determined by the Environmental Protection Agency (EPA).

BADIOLOGICAL IMPACT TO THE GENERAL PUBLIC During 1994, radiation doses to the general public as a result of Pilgrim Station's operation continued to be well below the federal limits and much less than the dose due to other 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 direct radiation resulting from PNPS operations for 1994 was about 2.1 mrem for the year. This conservative estimate is well below the EPA's annual dose limit to any member of the general public and is a fraction of a percent of the typical dose received from natural and man-made radiation. Dadioactivity detected in environmental samples (soil) collected during 1994 yielded 0.e07 mrem to the ,

hypothetical maximally exposed individual. I CONCLUSIONS  !

The 1994 Radiological Environmental Monitoring Program for Pilgrim Station resulted in i the collection and analysis of hundreds of environmental samples and measurements. The l data obtained were used to determine the impact of Pilgrim Statica's operation on the i environment and on the general public.

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

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 1994 performed by Boston Edison Company for Pilgrim biuclear 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, ,

1994.

The Radiological Environmental Monitoring Program consists of taking radiation measurements and collecting samples from the environment, analyzing them for radioactivity content, and interpreting the results. With emphasis on the ,

critical radiation exposure pathways to humans, samples from the aquatic, atmospheric, and terrestrial environments are collected. These samples include, but are not limited to: air, soil, seawater, shellfish, lobster, fishes, milk, cranberries, vegetables, and forage. Thermoluminescent dosimeters (TLDs) are placed in the environment to measure gamma radiation levels. The TLDs are processed and the environmental samples are analyzed to measure the very low levels of radiation and radioactivity present in the environment as a result of i PNPS operation and other natural and man-made sources. These results are reviewed by BECo's radiological staff and have been reported semiannually or annually to the Nuclear Regulatory Commission and others since 1972. l In order to more fully understand how a nuclear power plant impacts humans and the environment, background information on radiation and radioactivity, natural and man-made sources of radiation, reactor operations, radioactive effluent controls, and radiological impact on humans is provided. It is believed that this information will assist the reader in understanding the radiological impact on the environment and humans from the operation of Pilgrim Station.

1.1 Radiation and Radioactivity All matter is made of atoms. An atom is the smallest part into which matter can be broken down and still maintain all its chemical properties.

Nuclear radiation is energy, in the form of waves or particles, that is  !

given off by unstable, radioactive atoms. i Radioactive material exists naturally and has always been a part of our environment. The earth's crust, for example, contains radioactive uranium, radium, thorium, and potassium. Some radioactivity is a result of nuclear weapons testing. Examples of radioactive fallout 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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d 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).

I Radioactivity is measured in curies. A curie is that amount of radioactive I 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 i environment is measured in picocuries. One picocurie is equal to one trillionth of a curie. '

1.2 Sources of Radiation l

As mentioned previously, naturally occurring radioactivity has always been  !

a part of our environment. Table 1.2-1 shows the sources and doses of I 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 /vearl Source (millirem /vear) l Cosmic /cosmogenic 30 Medical / Dental X-rays 39 Internal 40 Nuclear Medicine 14 [

Terrestrial 30 Consumer Products 10 Radon / Thoron 200 Weapons Fallout About 1 ,

Nuclear Power Plants About 1 l APPR0XIMATE APPR0XIMATE t TOTAL 300 TOTAL 60 Cosmic radiation from the sun and outer space penetrates the earth's atmosphere and continuously bombards us with rays and charged particles.. Some of this  ;

cosmic radiation interacts with gases and particles in the atmosphere, making ,

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

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. 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 i breathe (about 200 millirem /yr). All these sources contribute to a total dose of j about 300 mrem per year from all natural sources of radiation.

The majority of a person's annual dose results from exposure to radon and thoron

.in'the air we breath. These gases and their radioactive decay products arise from the decay of naturally occurring uranium, thorium and radium in the soil and building products such as brick, stone and concrete. Radon and thoron levels a vary greatly with location, primarily due to changes in the concentration of I 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 l levels of radon / thoron gases in these areas.

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

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

1.3 Nuclear Reactor Operations i Pilgrim Station generates about 670 megawatts of electricity at full power,  !

which is enough electricity to supply the entire city of Boston, Massachusetts. Pilgrim Station is a boiling water reactor wiiose nuclear i steam supply system was provided by General Electric Co. The nuclear  :'

station is located on a 1600 acre site about five miles east-southeast of Plymouth Center. Commercial operation began in December, 1972.  ;

Pilgrim Station was shut down for generator repair August 29 - November 29',  !

1994. Monthly capacity factors are given in Table 1.3-1.

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 corventional power i is the source of heat used to boil the water. Conventioul plants burn  :

fossil fuels in a boiler, while nuclear plants make use w ranium in a j nuclear reactor.

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TABLE 1.3-1 PNPS OPERATING CAPACITY FACTOR DURING 1994 OPERATING PERCENT CAPACITY (Based on 670 MWe)

Month Percent Capacity January 98.8 February 72.5 March 79.5 April 63.3 May 94.5 June 97.2 July 97.6 August 88.2 September

• 0.0 October

• 0.0 November

• 0.2 December 87.7 Average 65.0

• PNPS entered a forced outage on August 29, 1994 to perform generator repair. The plant was restarted on November 30, 1994.

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

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

Radioactive fission products, as illustrated in Figure 1.3-1 (Reference 5),

originate from the fissioning of the nuclear fuel. These fission products get into the reactor coolant from their release by minute amounts of uranium on the outside surfaces of the fuel cladding, by diffusion through the fuel pellets and cladding and, on occasion, through defects or failures in the fuel cladding.

These fission products circulate along with the reactor coolant water and will deposit on the internal surfaces of pipes and equipment. The radioactive fission products on the pipes and equipment emit radiation. Examples of some fission products are krypton-85 (Kr-85), strontium-90 (Sr-90), iodine-131 (I-131),

xenon-133 (Xe-133), and cesium-137 (Cs-137).

Radioactive activation products (see Figure 1.3-2), on the other hand, originate from two sources. The first is by neutron bombardment of the hydrogen, oxygen and other. gas (helium, argon, nitrogen) molecules in the reactor cooling water.

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

These activation products circulate along with the reactor coolant water and will deposit on the internal surfaces of pipes and equipment. The radioactive activation products on the pipes and equipment emit radiation. Examples of some

, activation products are manganese-54 (Mn-54), iron-59 (fe-59), cobalt-60 (Co-60),

and zinc-65 (Zn-65).

n 59 60 Neutron Stable Radioactive Cobalt Nucleus Cobalt Nucleus l

Figure 1.3-2 l t Radioactive Activation Product formation l l

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At Pilgrim Nuclear Power Station there are five independent protective barriers that confine these radioactive materials. These five barriers, which are shown 3 in Figure 1.3-3 (Reference 5), are: 1) fuel pellets; 2) fuel cladding; 3) reactor vessel and piping; 4) primary containment (drywell and torus); and 5) j secondary containment (reactor building).

The ceramic uranium fuel pellets provide the first barrier. Most of the

, radioactive fission products are either physically trapped or chemically bound )

between the uranium atoms, where they will remain. However, a few fission products which are volatile or gaseous may diffuse through the fuel pellets into small gaps between the pellets and the fuel cladding.

1 The second barrier, the fuel cladding, consists of zirconium alloy tubes that confine the fuel pellets. The small gaps between the fuel and the cladding  !

contain the noble gases and volatile iodines 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 cf the reactor pressure vessel, steel piping and i equipment that confines the reactor cooling water. The reactor pressure vessel, i

which holds the reactor fuel, is a 65 foot high by 19 foot diameter tank with l

! steel walls about nine inches thick. This provides containment for radioactivity -,

j in the primary coolant and the reactor core. However, during the course of operations and maintenance small amounts of radioactive fission and activation products can escape through valve leaks or upon breaching of the primary coolant system for maintenance. -

The fourth barrier is the primary containment. This consists of the drywell and  ;

the torus. The drywell is a steel lined enclosure that is shaped like an inverted light bulb. The drywell's steel pressure vessel is enclosed by an  ;

approximately five foot thick concrete wall. The torus is a donut-shaped i pressure suppression chamber. The steel walls of the torus are nine feet in diameter with the donut itself having an outside diameter of about 130 feet. 1 Small amounts of radioactivity may be released from primary containment during maintenance.

The fifth barrier is the secondary containment or reactor building. The reactor i building is the concrete building that surrounds the primary containment. This l 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 system that is used when needed to reduce the radioactivity that  !

escapes from the primary containment.

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SIMPLIFIED DIAGRAM 0F PILGRIM NUCLEAR POWER STATION

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3. REACTOR VESSEL

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2. FUEL CLADDING

5. SECONDARY CONTAINMENT

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Most of the radioactive fission and activation products are confined by the'five -

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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 i that do escape the various containment systems are further controlled by the liquid purification and ventilation filtration systems. Also, prior to a release  :

to the environment, control systems exist to collect and purify the radioactive  !

effluents in order to reduce releases to the environment to as low as is t reasonably achievable. The control of radioactive effluents at Pilgrim Station  !

will be discussed in more detail in the next section, t 1.4 fladioactive Effluent Control The small amounts of radioactive liquids and gases that might escape the i five barriers are purified in the liquid and gaseous waste treatment  !

systems, then monitored for radioactivity, and released only if the  !

radioactivity levels are below the federal release limits.

Radioactivity released from the liquid effluent system to the environment  !

is limited, controlled, and monitored by a variety of systems and i procedures which include:  ;

- reactor water cleanup system;

- liquid radwaste treatment system;

- sampling and analysis of the liquid radwaste tanks;

- liquid waste effluent discharge header radioactivity monitor.

The purpose of the reactor water cleanup system is to continuously purify ,

the reactor cooling water by removing radioactive atoms and non-radioactive  ;

impurities that may bec:,me activated by neutron bombardment. A portion of  :

the reactor coolant water is diverted from the primary coolant system and [

is purified by a high efficiency filter that removes radioactive particles suspended in the water. Subsequent to that, the flow is directed through ion exchange resins where radioactive elements, diluted in the water, are removed through chemical processes. The net effect is a drastic reduction i of the radioactive material that is present in the primary coolant water and consequently the amount of radioactive material that might escape from i the system. j Reactor cooling water that might escape the primary cooling system and other radioactive water sources is collected in floor and equipment drains.

These drains direct this radioactive liquid waste to large holdup tanks. l The liquid waste collected in the tanks is purified again using the liquid radwaste treatment system, which consists of a filter and ion exchange i resins. j Processing of liquid radioactive waste results in large reductions of I radioactive liquids discharged into Cape Cod Bay. Of all wastes processed  !

through liquid radwaste treatment, 90 to 95 percent of all wastes are i purified and the processed liquid re-used in plant systems.

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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 has a shielded radioactivity monitor located on it. 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.

Another means for adjusting liquid effluent concentrations to be below federal limits is by mixing plant cooling water from the condenser with the liquid effluents in the discharge canal. This larger volume of coo?ina ,

water further dilutes the radioactivity levels far below the relea:e limits.

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

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

- reactor building ventilation system;

- reactor building vent effluent radioactivity monitor;

- sampling and analysis of reactor building vent effluents;

- standby gas treatment system;

- main stack effluent radioactivity monitor and sampling;

- sampling and analysis of main stack effluents;

- augmented off-gas system;

- off-gas radiation monitor, lhe purpose of the reactor building ventilation system is to collect and exhaust reactor building air. Air collected from contaminated areas is filtered prior to combining it with air collected from other parts of the building. This combined airflow is then directed to the reactor building '

ventilation plenum which is located on the side of the reactor building.

This plenum, which vents to the atmosphere, has a shielded radiation detector located on it. The radiation level meter and strip chart recorder for the reactor building vent effluent radioactivity monitor is located in the Control Room. To supplement the information continuously provided by the detector, air samples are taken periodically from the reactor building vent and are analyzed to quantify the total amount of radioactive gaseous and particulate effluent released.

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If air containing elevated amounts of noble gases is routed past the >

reactor building vent's effluent radioactivity monitor, an alarm will alert the Control Room operators that release limits are being approached. The Control Room operators, according to procedure, will isolate the reactor building ventilation system and initiate the standby gas treatment system to remove airborne particulates and gaseous halogen radioactivity from the reactor building exhaust. This filtration assembly consists of high-efficiency particulate air filters and charcoal absorber 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 below the release limits as is reasonably achievable.

The approximately 330 foot tall main stack has a special probe inside it which draws a portion of the air out and passes it through a radioactivity monitoring system. This main stack effluent radioactivity monitoring ,

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

The purpose of the augmented off-gas system is to reduce the radioactivity from the gases that are removed from the condenser. This purification system consists of a 30-minute holdup line to reduce the radioactive gases with short half-lives, a pre-filter to remove radioactive particulates, and several charcoal absorbers to remove radioactive iodines and further retard the short half-life gases.

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 absorber inlet valve will automatically re-direct the off-gas into the charcoal absorbers if they are temporarily being bypassed. If the radioactivity levels are not returned to below the alarm setpoint within 13 minutes, the off-gas releases will be automatically isolated, thereby preventing any gaseous radioactivity from being released that may exceed the release limits.

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

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

Next, calculations of the dose impact to the general public from Pilgrim Station's radioactive effluents are performed. The purpose of these '

calculations is to periodically assess the doses to the general public resulting from radioactive effluents to ensure that these doses are being maintained as far below the federal dose limits as is reasonably achievable. This is the second stage for assessing releases to the environment.

The types and quantities of radioactive liquid and gaseous effluents 4 released from Pilgrim Station during 1994 were reported to the Nuclear j Regulatory Commission semiannually. The 1994 Radioactive Effluents are i 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 (water) l and meteorological (atmospheric) characteristics in the area. Information l on the water flow, wind speed, wind direction, and atmospheric mixing characteristics are used to estimate how radioactivity will distribute and disperse in the ocean and the atmosphere.

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 impact on man. The movement of radioactivity through the environment and its transport to humans is portrayed in Figure 1.5-1.

l Page 19

1 Examples of Pilgrim Station's Radiation Exposure Pathways l a

GASEOUS

) EFFLUENTS 7%.

\

i

/

LIOUID 1TI A iJ ENEMS [ ~

)

'""'"^'^"

I' ~ 4. DIRECT RADIATION

~

(SIAII N) 2. AIR INHALATION SOIL DEPOSITION) 1. DIRECT RADIATION

.g BMERSION)

1. SHORELINTDIRECT RADIATION f (FISHING, PICNIC) i, )

d

5. CONSUMPTION 3 DEPOSITION

2. DIRECT RADIATION (IMMERSION IN OCEAN D(VEGETATION) 7 BOATING, SWIMMING)

/ V M

/

_fdMLG#em!ED eme \

6. CONSUMPTION DEPOSITlON INGESTION (MILK AND MEAT)

3. CONSL PTION f

(FISH AN: SHELLFISH)

D am G1.21.M , INGESTION

.-m-4 . ,.,,.,&..f n

. .l$h?. *:* .~.' '.':'y&i ..:

Figure 1.5-1 l Radiation Exposure Pathways l

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

1) external radiation from an airborne plume of radioactivity;  !

2) internal radiation from inhalation of airborne radioactivity;

3) direct radiation emitted from Pilgrim Station;

4) external radiation from depasition of radioactive effluents on i soil; I

5) internal radiation from consumption of vegetation containing  !

radioactivity absorbed from the soil due to ground deposition  !

of radioactive effluents; and, i

)

6) internal radiation from consumption of milk and meat c.ontaining  !

radioactivity deposited on forage which is eaten by cattle and i other livestock. 1

)

There are three major ways in which liquid effluents impact humans:  !

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

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

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

To the extent possible, the radiological dose impact on humans is. based on direct measurements of radiation and radioactivity in the environment (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 detect these tiny - ]

amounts of radioactivity above that which is naturally present in the )

environment. Therefore, radiation doses are calculated using radioactivity  ;

release data and computerized dose calculations that are based on very i conservative (over-estimated) NRC-recommended models. These computerized i dose calculations are performed by or for Boston Edison Co. personnel. l These computer codes use the guidelines and methodology set forth by .the  !

NRC in Regulatory Guide 1.109 (Reference 6). The dose calculations are  ;

documented and described in detail in the Pilgrim Nuclear Power Station's l 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 "Y0DA" 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.

Page 21  !

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After dose calculations are perform:d, the results are compared to the I federal dose limits for the public. The two federal agencies that are  :

charged with the responsibility of protecting the public from radiation and radioactivity are the Nuclear Regulatory Commission (NRC) and The -

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

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

In addition to this dose limit, the NRC has established design objectives '

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

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

e less than or equal to 3 mrem par year to the total body, t

-and- ,

• 1ess 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:

• 1ess than or equal to 10 mrad per year for gamma radiation,

-and-

• 1ess 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:

• 1ess than or equal to 15 mrem per year to any organ. 1 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:

• 1ess than or equal to 25 mrem per year to the total body,

• 1ess than or equal to 75 mrem per year to the thyroid,

-and- ,

• 1ess than or equal to 25 mrem per year to any other organ. ,

t Page 22

~ . - . . . .. - _ . .- -

i The. summary of the 1994 radiological impact for Pilgrim Station and comparison with.the EPA dose limits and guidelines, as well as a comparison with natural / man-made radiation levels, is presented in Section 3 of this report.-

The third stage of assessing releases to the environment is the .

Radiological Environmental Monitoring Program (REMP). The description and ,

results of the REMP at Pilgrim Nuclear Power Station during 1994 will be discussed in Section 2 of this report.

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~2.0 ' RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM l I

2.1 ~ Pre-Operational Monitorina Results I

The Radiological Environmental Monitoring Program (REMP) at Boston Edison Company's Pilgrim Nuclear Power Station was initiated in August of 1968.

The purpose of'the pre-operational environmental monitoring program i (Reference 11) was to:

1) measure background levels and their variations in the environment in the area surrounding Pilgrim Station; and, ,

2) evaluate procedures, equipment, and techniques. I The pre-operational program (Reference 12) continued for approximately three and a half years, from August 1968.to June 1972. Examples of ,

background radiation and radioactivity levels measured during this time  !

period are as follows: ,

AirborneRgdioactivityParticulateConcentration(grossbeta): 0.02~-

p 1.11 pCi/m ; i

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

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

• Fish Radioactivity Concentrations (gross beta): 2,200 - 11,300 pCi/kg; Milk Radioactive Cesium-137 Concentrations: 9.3 - 32 pCi/ liter;

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

• Cranberries Radioactive Cesium-137 Concentrations: 140 - 450 pCi/kg; ,

• Forage Radioactive Cesium-137 Concentrations: 150 - 290 pCi/kg. f 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 l 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 l environmental models in response to changing conditions;  !

3) checking the condition of the station's operation, the adequacy of operation in relation to the adequacy of containment, and the effectiveness of effluent treatment, so as to provide a mechanism of >

determining unusual or unforeseen conditions and, where appropriate, i to trigger special environmental monitoring studies; j Page 24 I

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 I and humans is significant.

The Nuclear Regulatory Commission requires that Boston Edison Company provide monitoring of the plant environs for radioactivity that will be released as a result of normal operations, including anticipated operational occurrences, and from postulated accidents. The NRC has l 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 l provisions of an agreement made with the Massachusetts Wildlife Federation I (Reference 16). The program was supplemented by including improved analysis of shellfish and sediment at substantially higher sensitivity ,

levels to verify.the adequacy of effluent controls at Pilgrim Station.  ;

2.2 Environmental Monitorina locations ,

Sampling locations have been established by considering meteorology, population distribution, hydrology, and land use characteristics of the i 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 miles of the plant, the control stations are generally located so as to be outside the influence of Pilgrim Station. l They provide a basis on which to evaluate fle:tuations at indicator locations relative to natural background rad:ation and natural  ;

radioactivity and fallout from prior nuclea' weapons test .

I The environmental sampling media collectea in the vicinity of Pilgrim  ;

Station during 1994 included air particulate filters, charcoal cartridges, 4 seawater, shellfish, Irish moss, American lobster, fishes, sediment, milk, cranberries, vegetation, and forage. The medium, station number, '

description, 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, 2, 3, 4, and 5.

The radiation monitoring locations for the environmental TLDs are shown in Figures 2.2-1, 2, and 3. The frequency of collection and types of l

radioactivity analysis are described in Pilgrim Station's Technical '

Specifications, Sections 7.0/8.0. i The land-based (terrestrial) samples and monitoring devices are collected by Boston Edison personnel from the Electrical Engineering and Station Operation Department's Environmental Laboratory. The aquatic samples are )

collected by the Division of Marine Fisheries - Pilgrim Station Project personnel. The direct radiation measurements and soil radioactivity i measurements are conducted by Yankee Atomic Electric Co. - 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.

Page 25 1

l The frequency, types, minimum number of samples, and maximum lover limits I 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 results. If the radioactivity ,

concentrations are above'the reporting levels, the NRC must be notified I within 30 days. For radioactivity which is detected that is attributable .l to Pilgrim Station's operation, calculations are performed to determine the i cumulative dose contribution for the current year. Depending upon the .

circumstances, a special study may also be completed (see Appendix A for '

1994 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 1994 Garden and Milk Animal Census are reported in Appendix C.

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 measurements and results of the radiological monitoring program through:

• Regular audits of the sampling and monitoring program; i e An annual audit of the analytical laboratory by the sponsor companies;

• Participation in the United States Environmental Protection Agency cross-check program;

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

• Spiked sample analyses by the analytical laboratory;  !

I

• Boston Edison Company's TLD QA Program and YAEL's TLD QA Program.

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.

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 1994 results of this QA program are summarized in Appendix E. These results indicate that the analyses and measurements which were performed during 1994 exhibited acceptable precision and accuracy.

Page 26

i 2.3 Intercretation of Radioactivity Analnes Results  !

The following pages summarize the analytical results of the environmental samples which were collected during 1994. 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 j Electric Company's ERMAP computer program (Reference 17). The unit of  !

measurerrent for each medium is listed at the top of each table. The left '

hand column contains the radionuclides which are 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 as specified in the PNPS Technical .

Specifications. l Those sampling stations which are within the range of influence of Pilgrim Station and which could conceivably be affected by its operation are called  :

" indicator" stations. Distant stations, which are beyond plant influence, are called " control" stations. Direct radiation monitoring stations are  ;

broken down into four separate zones to aid in data analysis.

For each sampling medium, each radionuclide is presented with a set of statistical parameters. This set of statistical parameters includes separate analyses for (1) the indicator stations, (2) the station having .

the highest annual mean concentration, and (3) the contial stations. For each of these three groups of data, the Yankee Atomic ERMAP computer program calculates:

• The mean value of all concentrations, including negative values and '

values below LLD; i

• The standard error of the mean; +

• The lowest and highest concentrations; i

• The number of pcsitive measurements (activity which is three times  :

greater than the standard deviation), out of the total number of l measurements. +

Each single radioactivity measurement datum is based on a single measurement and is reported as a concentration plus or minus one standard  :

deviation. The quoted uncertainty represents only the random uncertainty  ;

^

associated with the measurement of the radioactive decay process (counting statistic.s), and not the propagation of all possible uncertainties in the ,

sampling and analysis process. A sample or measurement is considered to t contain detectable radioactivity if the measured value (e.g., i concentration) exceeds three times its associated standard deviation. For ,

example, a milk sample with a strontium-90 concentration of 3.5 0.8 l pCi/ liter would be considered " positive" (detectable Sr-90), whereas l another sample with a concentration of 2.1 0.9 pCi/ liter would be  !

considered " negative", indicating no detectable strontium-90. The latter  :

sample may actually contain strontium-90, but the levels counted during its analysis were not significantly different than background levels. The j strontium-90 may be detectable at lower levels if the sample were counted >

for a longer period of time or analyzed in a different manner.

Page 27

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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 44). Gross beta (GR-B) analyses were performed-on 571 routine samples (11 i stations /wk

• 52 weeks, minus 1 missing sample). None of the samples  :

exceeded ten times the average concentration at the control location. The ,

lower 11mit of detection (LLD) required by Technical Specifications is 0.01

~

pCi/m3 .

For samples collected from the ten indicator stations, 519 out of 519 I samples indicated detectable activity at the three-sigma (standard -

deviation) level. Themeanconcentrationofgrossbetaactivityintgese '

519 indicator station samples was 0.017 0.000 (1.7 0.0 E-2) pCi/m Individual values ranged from 0.0064 to 0.0347 (6.4 - 34.7 E-3) pCi/m3 . ,

[ '

The monitoring station which yielded the highest mean concentration was stationnumber21(gastWeymouth),whichyieldedameanconcentrationof 0.019 0.001 pCi/m , based n smadons. InMual vakes ranged 3

from 0.0097 to 0.0325 pCi/m . All 52 out of 52 samples showed detectable activity at the three-sigma level.

i

At the control location, all 52 out of 52 samples yielded detectab gross ;

l beta activity, for an average concentration of 0.019 0.001 pCi/m -

. Indiv ual samples at the control location ranged from 0.0097 to 0.0326 ,

pCi/m  !

j Referring to-the third entry in the table, analyses for potassium-40 (K-40) i were performed 44 times (quarterly composites for 11 stations

• 4

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

3 l Attheindicatorstatiogs,individualconcentrationsofK-40rangedfrom 1

-0.00g4to0.0078pCi/m,forameanconcentrationof 0.00069 0.00044

, pCi/m . However, none of the forty samples analyzed showed detectable i amounts of potassium-40 at the three-signa level. It is important to note  !

that the mean value presented is calculated from forty observations, all of  ;

i' which yielded no detectable activity. '

i

The station which yielded the highest mean concentration of K-40 was  ;

station 15. Again, the mean value of 0.0027 0.0004 pCi/m3 is based on i

, four observations, none of which yielded any detectable activity. l

Therefore, no potassium-40 was detected in any of the samples collected  ;

from the sampling stations.

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2.4 Direct Radiation Measurements The primary technique for measuring direct radiation exposure in the vicinity of Pilgrim Station involves posting environmental thermoluminescent dosimeters (TLDs) at given monitoring locations and retrieving the TLD after a specified time period. The TLDs are then taken to a laboratory and processed to determine the total amount of radiation '

exposure received over the period. Although TLDs can be used to monitor radiation exposure for short time periods, environmental TLDs are typically posted for periods of one to three months. Such TLD monitoring yields averaae exposure rate measurement 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 109 locations are monitored using this. technique. Forty of these locations are listed as required monitoring locations in the PNPS Technical Specifications. In addition, 28 of the 109 TLDs are located on-site, within the PNPS protected / restricted area.

Out of the 436 TLDs (109 locations

• 4 quarters) posted during 1994, 430 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 -site TLDs posted within the restricted area .

presented in Table 2.4-2. n. addition to TLD results for individual locations, results from off-site TLDs were grouped according to geographic i zone to determine average exposure rates as a function of distance. These i results are summarized in Table 2.4-3. All of the listed exposure values represent continuous occupancy (2190 hr/qtr or 8760 hr/yr).

Annual exposure rates at off-site locations ranged from 46 to 377 mR/yr.

The averaae exposure rate at control locations greater than 15 km from Pilgrim Station (i.e., Zone 4) was 59.2 7.5 mR/yr. In other words, 99% ,

of all measurements of backaround exposure would be expected to be between r 37 and 82 mR/yr. A number of the on-site TLDs indicated direct radiation '

exposure above background levels due to their proximity to radiation sources within the PNPS protected / restricted area.  ;

A small number of TLDs (locations 0A, TC, BLW, BLE, PB, P01, and CT) in close proximity to the station indicated direct radiation exposure  :

resulting from PNPS operations. However, these TLDs are on Boston Edison  !

controlled property, and a maximum hypothetically exposed member of the l

public accessing such areas on Boston Edison property for limited periods of time would receive a maximum dose of 1.5 mrem /yr above their average l background doses of 59 mrem /yr. The exposure rates measured at areas l beyond Boston Edison control did not indicate any direct radiation exposure from Pilgrim Station operations. For example, the annual exposure rate at ,

the nearest off-site residence (location HB, 0.5 mi SE) was 63.8 1 5.3 l mR/yr, which compares quite well with the average control location exposure i of 59.2 mR/yr. l A second technique for measuring direct radiation exposure utilizes a l 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. j Page 29 t

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 direct radiation exposure around Pilgrim Station do not indicate any significant increase in exposure levels.

Although some increases in direct 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. '

2.5 Air Particulate Filter Radioactivity Analyses Airborne particulate radioactivity is sampled by drawing a stream of air through a glass fiber filter which has a very high efficiency for collecting airborne particles. 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 technique to monitor 10 locations in the  !

Plymouth area, along with the control location in East Weymouth.

Out of 572 filters (11 locations

• 52 weeks), 571 samples were collected and analyzed during 1994. There were a few instances where power was lost or pumps failed during the course of the sampling period at some of the air sampling stations, resulting in lower than normal sample volumes. These discrepancies are noted in Appendix D. Despite the prom ems listed above, the required LLDs were met on all 571 filters collected during 1994.

The results of the analyses performed on these 571 filter samples are summarized in Table 2.5-1. Trend plots for the gross beta radioactivity levels at the near station, property line, and off-site airborne monitoring locations are shown in Figures 2.5-1, 2.5-2 and 2.5-3, respectively. Gross beta radioactivity ws detected in 570 of the filter samples collected, ,

including all 52 centrol location samples. This gross beta activity arises from naturally-0ccurring radionuclides such as radon decay daughter products. Beryllium-7 was the only gamma emitting nuclide detected, and it was observed in all 44 of the quarterly composites analyzed. No radionuclides attributable to Pilgrim Station operations were detected in any of the air particulate samples collected.

2.6 Charcoal Cartridae Radioactivity Analyses Airborne radioactive iodine is sampled by drawing a stream of air through a charcoal cartridge after it has passed through the high efficiency glass  ;

fiber filter. As is the case with the air particulate filters, these '

samplers are operated continuously, and the resulting cartridges are collected weekly for analysis. Weekly cartridge samples are analyzed for radioactive iodine. The same eleven locations monitored for airborne particulate radioactivity are also sampled for airborne radiciodine.

)

Out of 572 cartridges (11 locations

• 52 weeks), 571 samples were collected l and analyzed during 1994. Although some samples had low volumes due to j power loss or pump failure, all required LLDs were met. These i discrepancies are noted in Appendix D. l l

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i The results of the analyses performed on these 571 charcoal cartridges are summarized in Table 2.6-1. No airborne radioactive iodine was detected in any of the charcoal cartridges collected.

2.7 Milk Radioactivity Analyses  !

I Samples of unprocessed milk are collected from the Plymouth County Farm and from the control location in Whitman. The Annual Land Use Census conducted within three miles of Pilgrim Station did not identify any additional milk animals requiring sampling. Results of this census are summarized in ,

Appendix C. Milk samples are collected monthly from November through April, and once every two weeks when animals are assumed to be on pasture during the period May through October. These milk samples are analyzed by gamma spectroscopy, low-level analysis for radioiodine and strontium 89 and 90.

All 38 samples scheduled for collection during the year were obtained and analyzed. No problems were encountered in sampling milk during 1994.

The results of the analyses performed on the 38 milk samples are summarized in Table 2.7-1. Naturally-occurring potassium-40 was detected in all 38 samples. No radioactive iodine was detected in any of the samples.

Strontium-90 was detected in 11 of the 19 samples from Plymouth County Farm, and in 10 of the 19 samples collected from the control location in Whitman. Cesium-137 was also detected in one of the samples collected from Plymouth County Farm. Concentrations of Sr-90 and Cs-137 as a function of time are shown in Figures 2.7-1 and 2.7-2, respectively.

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 detected 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 1994, the expected concentration would be 5 pCi/ liter. The concentrations of 3 to 4 pCi/ liter '

observed in 1994 samples are well below the expected Sr-90 concentrations resulting from weapons testing. It is clear that the Sr-90 observed did not arise from Pilgrim Station operations.

The highest concentration of Cs-137 detected in samples from Plymouth County Farm was 4.5 pCi/ liter. Cesium-137 is also a product of nuclear weapons testing, and was routinely detected in the preoperational i monitoring program at levels of 9 to 32 pCi/ liter. When the average  ;

preoperational Cs-137 concentration of 18 pCi/ liter is corrected for radioactive decay, the expected concentration in 1994 samples would be 11 pCi/ liter. Clearly, the Cs-137 concentrations observed in the two samples 1 collected from Plymouth County Farm are indicative of radioactivity arising i

from weapons testing fallout, and not Pilgrim Station operations.

Page 31 i

2.8 Foraae Radioactivity Analyses Samples of animal forage (hay) are collected from the Plymouth County Farm and from the control location in Whitman. Samples of corn to be used for '

silage at Plymouth County Farm were also collected from the Whipple Farm (1.8 mi. SW). Samples are collected annually and analyzed by gamma spectroscopy.

All samples of forage were collected and analyzed as required during 1994. ,

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 >

samples.

2.9 Veaetable/Veaetation Radioactivjtv Analyses Samples of vegetables are routinely collected from the Plymouth County Farm and from the control location at Bridgewater Farm. 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 seposition 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 1994. 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 four of the samples collected.

The highest level of cesium-137 (462 pCi/kg) was detected in a sample of naturally-growing vegetation, a mixture of grass, herbaceous plants, and leaves from bushes and trees, which was collected 1.46 km (0.91 mi) south- t souti.eest of the PNPS Reactor Building. As was the case for all samples of naturally-growing vegetation, these samples were collected and analyzed "as is", without processing the material to remove scil and dust on the surface i of the plants. As documented in section 2.11 of this report, Cs-137 was detected in nearly all of the soil surveys conducted during 1994, 1 indicating that Cs-137 is widespread in soil throughout New England. In l 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. A similar sample of naturally-growing vegetation collected at a control location 50 km (31 mi) west of Pilgrim Station also showed detectable levels of both Cs-137 and Th-232. It should be noted that the three samples collected at the control location (Bridgewater Farm), 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 most likely would have yielded i detectable levels of both Cs-137 and Th-232.

l l

I Page 32

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

pCi/kg. When corrected for radioactive decay, the expected concentration l

.in. samples of naturally-growing vegetation collected during 1994 would be ,

between 95 and 183 pCi/kg. Clearly, the average Cs-137 concentration of 37 pCi/kg observed in the four samples collected are indicative of radioactivity arising from weapons fallout, and not Pilgrim Station >

Operations. ,

2.10 Cranberry Radioactivity Analyses i

Samples of cranberries are routinely collected from two bogs in the  :

Plymouth area and from the control location in Halifax. Samples of cranberries are collected annually and analyzed by gamma spectroscopy.

All three samples of cranberries were collected and analyzed as required during 1994. Results of the gamma analyses of cranberry samples are -

summarized in Table 2.10-1. The only radionuclide detected in any of the samples was naturally-occurring potassium-40. No radionuclides attributable to Pilgrim Station operations were detected in any of the

• samples.

2.11 Soil Radioactivity Analyses e 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, 1 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 f 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 l 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.  ;

Cobalt-60 concentrations observed ranged from non-detectable to 117 pCi/kg. I Concentrations of cesium-137 ranged from non-detectable to 1440 pCi/kg.  !

The observed concentrations of both Co-60 and Cs-137 were consistent with  ;

levels observed in past soil surveys conducted in 1987, 1988, and 1991. In fact, concentrations of these nuclides decreased at all locations since the last survey conducted in 1991, indicating that no buildup of deposited radionuclides is occurring. Results of the in-field measurements with the portable gamma spectroscopy unit indicated Cs-137 concentrations consistent with those observed at other measurement sites throughout New England.

Such Cs-137 levels are the result of nuclear weapons testing, and none of the levels observed during the 1994 surveys were elevated over typical fallout levels. Therefore, the Cs-137 levels observed were assumed to have resulted from nuclear weapons testing, and not from PNPS operations.

Page 33 l

1

A special study was performed to determine the radiological impact to man from the cobalt-60 detected in soil samples collected from Boston Edison .

property adjacent to Pilgrim Station. This study is detailed in Appendix A. The concentration of Co-60 in soil at sampling location WS would result in a dose rate of about 0.0002 mrem /hr. By comparison, the dose rate from the naturally-occurring potassium-40, thorium-232, and uranium-238 in the i soil at this location was estimated as 0.004 mrem /hr. The maximum exposed  !

individual was assumed to be at this location on Boston Edison property from 40 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br />. The resulting annual maximum total body dose from the  ;

cobalt-60 in soil at this location was estimated to be 0.007 mrem.

2.12 Surface Water Radioactivity Analyses Samples of surface water are routinely collected from the Discharge Canal, Bartlett Pond in Manomet and from the control location at Powder Point .

Bridge in Duxbury. The Discharge Canal is sampled continuously by a composite sampler. Grab samples are collected weekly from the Bartlett ,

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

A total of 36 samples (3 locations

• 12 sampling periods) of surface water were collected and analyzed as required during 1994. There were a few instances of problems with obtaining composite samples from the Di.scharge  ;

Canal. Cold weather during the week of 25-Feb to 01-Mar 1994 froze the sample line to the composite sampler. The line was subsequently heat traced. A more detailed discussion of this discrepancy can be found in Appendix D.

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 Fish Radioactivity Analyses Samples of fish are routinely collected from the area at the outfall of the Discharge Canal and from the control locations in Cape Cod Bay and ,

Buzzard's Bay. Fish species are grouped into four major categories according to their biological requirements and mode of life. These major  !

categories and the representative species are as follows:

Group I - Bottom Oriented: Winter Flounder, Yellowtail Flounder Group II - Near-Bottom Distribution: Tautog, Cunner, Pollock, Atlantic Cod, Hake Group III - Anadromous: Alewife, Smelt, Striped Bass Group IV - Coastal Migratory: Bluefish, Herring, Menhaden, Mackerel Two subsamples of each category of fish are typically collected during each collection period. Group I and II fishes are sampled on a quarterly basis from the outfall area of the Discharge Canal, and on an annual basis from a control location. Group III and IV fishes are sampled annually from the Discharge Canal outfall and control location. All samples of fish are analyzed by gamma spectroscopy.

Page 34 l

r Twenty-four samples of fish were collected during 1994. Group I and  !

j Group II 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 discrepancies are noted in Appendix D.

Results of the gamma analyses of fish samples which were collected are summarized in Table 2.13-1. 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.

2.14 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 l (Manomet Point, Plymouth Harbor), and from control locations in Duxbury and j 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 i from samples collected from the Discharge Canal outfall and from all control location samples are also analyzed.  !

All 48 samples of shellfish meat and shells scheduled for collection during 1994 were obtained and analyzed. Results of the gamma analyses of these  :

samples are summarized in Table 2.14-1. Naturally-occurring beryllium-7, potassium-40, and thorium-232 were detected in a number of the samples. No ,

radionuclides attributable to Pilgrim Station operations were detected in  :'

any of the samples.

2.15 Irish Moss Radioactivity Analyses Samples of Irish moss are collected from the Discharge Canal outfall and two other locations in the Plymouth area (Manomet Point, Ellisville), and from a control location in Marshfield (Green Harbor). All samples are  !

collected on a quarterly basis, and processed in the laboratory for gamma -

spectroscopy analysis.

All 16 samples of Irish moss scheduled for collection during 1994 were  !

obtained and analyzed. Results of the gamma analyses of these samples are summarized in Table 2.15-1. 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.

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

All five samples of lobsters were collected and analyzed as required during 1994. Results of the gamma analyses of lobster samples are summarized in Table 2.16-1. The only radionuclide detected in any of the samples was naturally-occurring potassium-40. No radionuclides attributable to Pilgrim Station operations were detected in any of the samples.

Page 35

b 2.17 Sediment Radioactivity Analyses Samples of sediment are routinely collected from the outfall area of the Discharge Canal and from three other locations in the Plymouth area (Manomet Point, Plymouth Harbor and Plymouth Beach), and from control locations in Duxbury and Marshfield. Samples are collected twice per year and are analyzed by gamma spectroscopy. Sediment cores are subdivided into depth increments for analysis of radie.nuclide distribution by depth.

During the first half of the year, samples are divided into 2 cm increments, whereas samples for the second half of the year are divided into 5 cm increments. In addition to the gamma analyses, plutonium analyses are performed on the surface layer samples collected during the first half of the year from the Discharge Canal outfall, Plymouth Harbor, Manomet Point and Duxbury. Plutonium analyses are also performed on a mid-depth section from the Discharge Canal sample and Duxbury sample.

All 56 samples of sediment were collected and analyzed as required during 1994. Results of the gamma analyses of sediment samples are summarized in Table 2.17-1. Results of the plutonium analyses are presented in Table 2.17-2. Naturally-occurring beryllium-7, potassium-40 and thorium-232 were detected in a number of the samples. No cobalt-60 was detected in any of the 39 indicator samples. Cesium-137 was detected in 8 of 39 indicator station samples and in 13 of 17 control station samples. Plutonium-239/240 was detected in three of the four indicator station samples and in both of the control station samples.

Cesium-337 levels in indicator samples ranged from non-detectable to a maximum concentration of 56 pCi/kg. Concentrations in samples collected from the co1 trol locations beyond the influence of Pilgrim Station also ranged from non-detectable to a maximum concentration of 69 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 7.6 pCi/kg. Concentrations in samples collected from the control locations beyond the influence of Pilgrim Station ranged from 4.6 pCi/kg to a maximum concentration of 11.3 pCi/kg. The fact that the results from indicator 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.

1 l

Pags 36

Table 2.2-1 I Routine Radioloaical Environmental Samolina locations Pilarim Nuclear Power Station. Plymouth. MA Media Ho Code Description Dist. Dir.

Air Particulate 00 WS Warehouse 0.1 mi SSE Filters / 01 ER E. Rocky Hill Road 0.6 mi SE Charcoal Cartridaes 03 WR W. Rocky Hill Road 0.5 mi WNW Soil 06 PL Property Line 0.3 mi NW 07 PB Pedestrian Bridge 0.1 mi NNW 08 OA Overlook Area 0.1 mi W 09 EB East Breakwater 0.3 mi ESE 10 CR Cleft Rock 0.8 mi SSW 15 PC Plymouth Center 4.1 mi W 17 MS Manomet Substation 2.2 mi SSE 21 EW East Weymouth Control 25 mi NW Milk 11 CF Plymouth County Farm 3.5 mi W 21 WF Whitman Farm Control 21 mi WNW Foraae 11 CF Plymouth County Farm 3.5 mi W 12 WF Whitman Farm Control 21 mi WNW 43 WH Whipple Farm 1.8 mi SW Veaetation 11 CF Plymouth County Farm 3.5 mi W 27 BF Bridgewater Farm Ctrl 19 mi W Cranberries 13 MR Manomet Pt. Bog 2.4 mi SE 14 BR Bartlett Rd. Bog 2.7 mi SSE 23 PS Pine St. Bog Control 16 mi WNW Surface Water 11 DIS Discharge Canal 0.1 mi NNW 17 BP Bartlett Pond 1.7 mi SE 23 PP Powder Point Control 8 mi NNW Fishes 11 DIS Discharge Canal 0.2 mi N 29 PC Priest Cove Control 30 mi SW 30 JR Jones River Control 8 mi WNW 92 MV Vineyard Sound Control 40 mi SSW 98 CC-Bay Cape Cod Bay Control 15 mi ESE Shellfish 11 DIS Discharge Canal 0.2 mi N 12 Ply-H Plymouth Harbor 3 mi W 13 Dux-Bay Duxbury Bay Control 8 mi NNW 15 MP Manomet Point 3 mi ESE 23 PP Powder Point Control 8 mi NNW 24 GH Green Harbor Control 10 mi NNW l

l Page 37

c ,

Table 2.2-1 -(continued) l Routine Radioloaical Environmental Samplino Locations Pilarim Nuclear Power Station. Plymouth. MA

)

Media No Code Description Dist. Diri Irish Moss 11 DIS Discharge Canal 0.2 mi N 15 MP Manomet Point 2.2 mi SE 22 EL Ellisville 8 mi SSE I 34 BR Brant Rock Control 10 mi NNW i Lobster 11 DIS Discharge Canal 0.2 mi N 12 Ply-H Plymouth Harbor 4 mi WNW

• 13 Dux-Bay Duxbury Bay Control 7 mi NNW Sediment 11 DIS Discharge Canal 0.2 mi N 12 Ply-H Plymouth Harbor 3 mi W l 13 Dux-Bay Duxbury Bay 8 mi NNW i 14 PLB Plymouth Beach 2 mi W .

15 MP Manomet Point 3 mi ESE 24 GH Green Harbor Control 10 mi NNW i

t

(

1 i

i i

Page 38

l i

i Table 2.4-1 l Off-Site Environmental TLD Results l

1994 Mean" TLD Station Location

• Exposure Rate - mR/ quarter (Value i Std.Dev.) Annual Exposure ID Description Distance Sector First Second Third Fourth mR/ year BLW BOAT LAUNCH WEST 0.14 km E 51.5 i 4.2 50.71 2.7 4952 34 45.72 2.3 197.4 i 18.0 OA OVERLOOK AREA 015 km W 114 6 i 7.1 11691 7.2 8322 5.9 62.4 t 2.2 377.1 2108.4 TC ISS BUILDING 0.16 km W 46.42 2.2 51.41 30 30.7

• 1.1 2442 0.7 152.9 2 51.9 BLE BOAT LAUNCH EAST 0.17 km E 4411 30 4301 3.2 41.72 2.9 39.21 2.2 167.9 1 15.7 PB PEDESTRIAN BRIDGE 0.21 km N 32.6 i 0.9 30.31 1.3 2901 1.9 28.7 i 0.9 120.7 i 9 4 >

P01 SHOREFRONT SECURITY 0.22 km NNW 27.61 1.2 31.0 i 2.1 27.32 1.6 23.02 0.6 1089114.7 CT CNTR PARKING LOT 0.34 km SSE 21.02 0.8 22.21 1.5 25.02 1.3 23.0 t 0.7 91.32 8.5 PA SHFNT PARKING AREA 0 36 km NNW 18.71 0.8 1901 06 20.92 1.0 18.5 i 0.5 77.01 56 A STATION A 0 40 km W 17.82 0.7 1862 0.6 1892 09 17.31 0.5 72.61 44 ,

B STATlON B 0.40 km SSW 19 0 i 0.7 20.21 0.7 21.2 1 1.5 18.92 0.6 79.32 6.2 F STATlON F 0.43 km NW 17.2 t 0 8 18.02 0.7 1882 1.1 17.6 i 0.5 71.71 46 L STATION L 0.44 km ESE 16.12 04 16.91 0.7 19.51 09 17.72 09 70.1269 PMT PNPS MET TOWER 0.44 km NW 17.01 0.5 16.81 0.7 17.41 1.2 16.22 0.5 67.41 4.1 EB EAST BREAKWATER 0 47 km ESE 1851 0.7 19.12 0.7 22.12 1.0 20.6 i 0 6 80.21 7.4 i STATION I O 48 km WNW 16.92 06 17.51 06 18.3 i 1.2 17.4

• 0.8 7002 4.5 H STATION H 0 51 km SW 1962 0.9 20.51 06 21.21 1.1 1932 0.7 80.5 t 5.2 C STATION C 0.52 km SE 1542 06 15.7 i 0 4 17.4 t 1.3 17.0 i 0 4 6552 5.4 PL PROPERTY LINE O53km NW 16.32 0.4 1651 06 17.81 1.4 17.62 0.6 68.2 i 5.0 D STATION D 0.55 km NNW 21.21 08 Missing 22.72 1.2 22.4 i 0.7 88.41 5.7 HB HALL'S BOG 0 60 km SSE 1532 0.7 15.31 0.7 17.1 t 1.3 16.21 0.5 6382 5.3 ,

G STATION G 0 62 km W 1501 0.5 15.81 06 17.51 1.5 1662 0.4 649i 58 i GH GREENWOOD HOUSE 0.69 km SE 16.11 06 16.71 0.8 19.21 1.1 18.3 i 0.7 70.3 68 WR W ROCKY HILL ROAD 0 82 km WNW 17.31 04 18.21 0.6 20.21 0.9 1961 0.6 75.32 6.2 ER E ROCKY HILL ROAD 0 90 km SE 12.82 06 1382 0.5 15.51 0.9 14.31 0.6 5641 5.3 MT MICROWAVE TOWER 0.92 km SSW 15.61 0.5 15.92 0.7 17.82 1.1 16.92 0.9 66.22 5.6 CR CLEFT ROCK 1.23 km SSW 14.21 04 1491 06 16.4 i 1.3 15 6 i 0.5 61.02 5.3 DD BAYSHORE DRIVE 1.32 km WNW 16.31 06 16.5 i 0.5 17.7 i 1.0 17.71 0.6 68.12 45 MR MANOMET ROAD 1.38 km S 13.51 0.4 13 9 i 0.7 15.12 1.0 1442 0.6 56.92 4.3 DR DIRT ROAD 1.45 km SW 1332 0.5 14 0 i 0.7 15.11 1.1 14.7 i 0.5 57.0 t 4.7 EM EMERSON ROAD 1.54 km SSE 13.31 0.4 Missing 16.21 1.0 15.1 i O.4 5952 6.6 AR EDISON ACCESS ROAD 1.54 km SSE 1412 0.5 13.9 i 0 6 15.62 1.0 15.61 0.6 59.2 i 5.0 EP EMERSON & PRISCIL 1.56 km SE 1442 05 1442 0.7 Missing 16.12 1.8 59 9 i 7.0 BS BAYSHORE 1.73 km W 17.02 05 1681 0.5 18.72 0.9 1841 0.7 70.92 4.9 E STATION E 1.86 km S 15.31 0.6 15.82 06 17.6 i 1.2 17.4 t 0 6 6602 6.0 JG JOHN GAULEY 1.96 km W 143i 04 14 6

• 0.7 17.01 1.1 15 8 i 0.8 61.71 60 J STATION J 2 02 km S 1411 0.5 1442 0.5 16 4 i 1.0 1582 0.6 60.72 54 RC PLYMOUTH YMCA 2 06 km WSW 1442 0.4 14.91 0.7 16.82 0.7 1581 06 62.01 5.0 WH WHITEHORSE ROAD 2.13 km SSE 138i 06 13 9 i O 4 15 8 t 1.1 1542 0.7 58.92 5.4 K STATION K 2.14 km SSE 1412 0.4 1462 0.7 16.22 09 1611 0.5 61.01 5.2 TT TAYLOR & THOMAS 2.25 km SE 1662 2.2 13 5 i 0.6 16.3 0.9 1561 0.6 62.02 80 YV YANKEE VILLAGE 2.27 km V TW 14 5 i 0.5 14.5 t 0 8 16.91 0.7 16.21 0.9 62.21 6.0 Distance and direction are measured from centerline of Reactor Bulding to the monitonng location.

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

Page 39

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\

Table 2.4-1 (continued)

Off-Site Environmental TLD Results 1994 Mean" TLD Station Location

• Exposure Rate mR/ quarter (Value i Std.Dev.) Annual Exposure ID Description Distance Sector First Second Third Fourth mR/ year GN GOODWIN PROPERTY 2.43 km SW 10.91 0.5 it 4 2 0.4 12.510.7 12.020.5 4641 4.1 RW RIGHT OF WAY 2.83 km S 11.91 0.4 11.51 0.6 14.010.9 12.920.4 50.32 5.2 TP TAYLOR & PEARL 2.99 km SE 13.31 0.6 12.92 0.5 15.520.8 16.4 i 2.6 58.11 9.5  ;

VR VALLEY ROAD 3.26 km SSW 12.12 0.5 12.21 0.5 14.420.6 13.410.5 52.22 5.0 WC WARREN & CLIFFORD 3.30 km W 13.22 06 13.1

• 0.6 15.1 i 1.0 14.420.5 55.8 5.1 ME MANOMET ELEM 3.30 km SE 13.12 0.8 13.71 0.5 15.5 t 1.0 14.5 i 0.5 56.8

• 5.3 BB 3A & BARTLETT RD 3.37 km SSE 14.0 i 0.5 14.52 07 16.610.8 15.610.6 60.72 5.6 MP MANOMET POINT 3.57 km SE 14.72 0.7 14.5 i 0.5 15.320.6 14.7 i 0.6 59.32 3.1 MS MANOMET SUBST 3 59 km SSE 16.32 0.5 17.91 06 18.921.0 18020.6 71.02 5.5 BW BEACHWOOD ROAD 3 91 km SE 13.82 04 14.21 0.7 16.6106 15.620.8 60.32 6.0 PT PINES ESTATE 4 47 km SSW 13.0 t 0.4 13.3 i 0.5 15.2208 14.620.6 56.12 5.0 EA EARL ROAD 4 60 km SSE 11.8 t 0.5 12.4 i 0.5 13.420.5 13.6 i 0.4 51.12 4.0 ,

SP S PLYMOUTH SUBST 4.61 km W 13.42 0.5 14.32 0.4 16.110.9 16.120.5 59.92 6.2 RP ROUTE 3 OVERPASS 4.79 km SW 13.6 i 0.6 13.81 0.5 16.021.1 15.220.4 58.6

• 5.6 RM RUSSELL MILLS RD 4.82 km WSW 12.7 i 0.4 12.S i 0.4 15.110.9 14.5 t 0.6 54.81 5.9 HD HILLDALE ROAD 5.15 km W 14.32 0.7 1422 0.4 16.710.8 15.910.7 61.0 t 5.9 MB MANOMET BEACH 5.42 km SSE 13.71 1.0 Missing 15.3 t 0.9 14.310.6 57.81 5.3 BR BEAVERDAM ROAD 5.55 km S 11.62 0.5 11.8 i 0.6 14.020.8 13.6 t 0.5 51.02 5.6 PC PLYMOUTH CENTER 6.65 km W 10.81 0.4 10.22 0.5 11.810.7 11.220.4 44.11 3.6 i LD LCNG POND & DREW 6.96 km WSW 12.4 i 0.5 12.72 0.6 14.5 i 0.7 13620.4 53.12 46 [

HR HYANNIS ROAD 7.34 km SSE Missing 13.22 0.8 15.320.6 14.120.5 56.82 5.3 CP COLLEGE POND 7.51 km SW 13.02 0.8 13.52 0.6 14.910.7 14.610.7 56.22 4.9  ;

SN SAQUISH NECK 7.56 km NNW NewPosting 11.91 0.5 13.620.6 12.5

• 0.6 50.72 4.5 l MH MEMORIAL HALL 7.59 km WNW 23.4 t 0.8 22.42 0.8 25.122.5 23.920.7 94.72 7.8 l DW DEEP WATER POND 8.64 km W 15.02 1.0 15.42 0.7 18.220.7 16.720.5 65.32 6.8

~

LP LONG POND ROAD 8.86 km SSW 11 8 i 0.5 11.6 t 0.4 13.9 t 0.9 12.4 i 0 6 49.72 5.2 NP NORTH PLYMOUTH 9.36 km WNW 16.6 i 0.4 16.71 0.6 17.8 t 0.9 18.010.6 69.12 4.2 .j SS STANDISH SHORES 10.37 km NW 12.62 0.4 12.5 0.4 13.920.7 14.420.9 53.42 4.8 -

EL ELLISVILLE ROAD 11.53 km SSE 13.21 0.3 13.3 i 0 8 15.5 t 1.0 14420.6 56.5 i 5.5 UC UP COLLEGE POND RD 11.79 km SW 11.92 0.5 11.52 0.6 13.5 t 0.6 12.910.4 4982 4.4 l SH SACRED HEART 12.90 km W 13.5 t 0.5 1362 0.7 15.8 t 0.8 14.910.4 57.9 t 5.3 KC KING CAESAR ROAD 13.07 km NNW 14.5 t 0.5 13.4i 0.5 15.0 t 0.8 13.8 0.4 56.7 i 4.0 SA SHERMAN AIRPORT 13 36 km WSW 1332 0.4 1302 0.5 15.121.0 14.6 t 0.5 55.92 5.1 BE BOURNE ROAD 13.37 km S 12.0 i 0 6 11.72 0.6 14.010.8 12.920.4 50.72 5.0  !

CS CEDARVILLE SUBST 15 93 km S 14.1 i 0.6 15.02 0.7 16.9 t 1.2 16.010.8 62.01 6.3 KS KINGSTON SUBST 16.10 km WNW 12.92 0.6 12.91 0.6 14 9 t 0.5 14.020.6 54.7 t 4.8 LR LANDING ROAD 16.44 km NNW 13.12 08 13.62 0.6 15621.0 14.020.4 56.3 i 5.5 CW CHURCH & WEST 16,54 km NW 12.2 0.5 12.52 0.7 14.320.7 13.320.5 52.32 4.7 MM MAIN & MEADOW 16.99 km WSW 1362 0.5 13.62 0.4 15 4

• 0.7 14.310.5 57.02 4.2 DMF DIV MARINE FISH 20.97 km SSE 15.12 0.5 14.71 0.5 17.321.4 16.720.5 63.7 i 6.3 EW E WEYMOUTH SUBST 39 61 km NW 14.1 t 0.7 16.91 0.5 18.910.9 18.3

• 0.6 68.12 9.2

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

• • Mean annual value is based on arithmetic mean of the observed quar'erty values multiplied by four quarters / year.

1 Page 40

Table 2.4-2 On-Site Environmental TLD Results m 4 mean

• TLD Station Location

• Exposure Rate - rnR/ quarter (Value i Std.Dev.) Annua 1 Exposure ID Descript6on Distance Sector First Second Third Fourt'. mR/ year P21 WW ADMIN & PROC 50 m SE 38.81 1.0 3802 2.5 38.011.6 33.3 i 0.8 148.2 i 12.5 P24 OLD ADMIN 57 m W 39 5 i 1.1 3952 2.4 36.811.7 32.311.1 148.1 2 15.5 PO4 FENCE /R SCREENH 66 m N 94.12 2.9 83.9 t 4.3 75.725.8 72.911.9 326.5 t 42.4 P20 RP WINDOW 66 m SE 6451 3.2 68.21 6.5 54923.6 41.621.2 2293251.1 P25 FIRST AID TRAll 76 m WNW 78.02 40 96.52 6.5 73.0 i 5.1 58.012.4 305.4 2 67.2 P05 FENCE / WATER TANK 81 m NNE 32.21 1.5 29.82 2.0 32.221.3 31.2 i 1.0 125.42 8.2 P06 FENCE / CULVERT 84 m NE 53.92 2.5 4652 1.8 45.412.0 57.8 i 2.7 203.6 1 26.0 P19 COMPLIANCE AREA 85 m SSE 73.1 i 5.2 71.4 3.6 56.123.3 41.211.3 241.8

• 62.0 P18 ISC NEW ADMIN 90 m S 61.61 2.5 59.52 5.3 53.226.3 40.912.7 215.2 1 42.7 P08 FENCE /NEW ADMIN 92 m ENE Missing 5402 5.4 48.814.0 44921.3 197.0

• 27.6 P03 FENCE /L SCREENH 100 m NW 67.31 2.6 69 0 i 2.9 55.814.8 46.621.9 2388144.7 P17 FENCE /SHF M GATE 108 m W 129.1 1 11.2 136.21 7.8 100.2 15.4 72.613.9 438.1 1121.7 P23 CMG CORNER 120 m SSE 40.82 2.2 42.61 2.6 05222.1 27.2 i 0.9 145.8 1 29.2 P07 FENCE / INTAKE 121 m ENE 40.51 1.3 3892 3.3 38.412.5 44.311.1 162.1 2 14.9 P02 SHOREFRONT FENCE 135 m NW 52.92 1.4 55.02 2.7 45.8 i 1.4 37.811.2 191.5 2 32.0 P09 FENCE /TCF SIDE 136 m 39.21 2.0 38.11 4,2 38.012.4 35.8

• 1.6 151.2 2 13.9 P22 QA/QC CORNER 137 m E 37.01 1.2 36.92 1.0 34.421.8 29.220.7 137.5 t 15.8 1 P26 FENCE / WAREHOUSE 149 m "ESE 45 0 t 1.8 47.9 i 4 1 45.912.7 43.1

• 1.7 182.0 1 15.0 P16 FENCE /SWY M GATE 172 m SW 101.0 t 3.1 103.12 5.2 77.523.3 60.3 i 2.4 342.0 t 83.2 WS WAREHOUSE 181 m SSE 37.92 2.3 40.12 2.6 34.9 i 3.1 30.511.5 143.4 1 20.1 P11 FENCE /TCF GATE 188 m ESE 66.51 5.2 76.2 i 2.8 159.2 15.7 161.2 16 8 463.1 1207.4 P27 TCF/ BOAT RAMP 195 m ESE 87.12 2.1 63.51 3.9 61.722.2 70.011.5 282.3 1 47.9 P12 FENCE /CNTR GATE 202 m SE 29.11 2.0 30.41 2.2 27.120.9 24.420.7 111.0 t 12.8 I P15 FENCE / UNIT #9 21m S 37.91 1.4 40.31 2.6 33.5 t 1.9 28.310.9 1399122.6 j P10 FENCE / INTAKE TCF 2. '

E 29.31 0.8 44.31 3.2 31.521.9 28820.7 133.91 30.5 P13 FENCE / CON & RHR 224 m SSE 28.32 2.2 29.71 1.3 27.412.6 24.3 i 0.7 109.8 2 12.6 P14 FENCE / BUTLER BLDG 227 m S 2961 08 31.42 1.2 27.721.3 23.710.9 112.4 214.2 P28 TCF/CNTR LOT 244 m ESE 31.111.2 38.11 3.8 33812.6 27.020.5 129.91 21.7

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

• • Mean annual value is based on arithmetic mean of the observed quarterly values multiphed by four quarters / year.

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Page 41

Table 2.4-3 AVERAGE TLD EXPOSURES BY DISTANCE ZONE DURING 19fe Average Exposure Standard Deviation (mR/ period)

Zone 1* Zone 2 Zone 3 Zone 4 0 km - 3 km 3 km - 8 km 8 km - 15 km > 15 km Period Avg StD Avg StD Avg StD Avg StD Qtr-1 20.7 17.0 13.7 2.7 13.4 1.7 13.6 1.1 Qtr-2 21.3 17.7 13.8 2.6 13.3 1.8 14.2 1.6 Qtr-3 21.4 12.0 15.7 2.8 15.3 1.9 16.2 1.9 Qtr-4 19.7 9.0 14.9 2.5 14.5 1.8 15.2 1.9 Year 83.1 57.0 58.3 10.9 56.5 7.6 59.2 7.5 o Zone 1 extends from the restricted / protected area boundary outward to 3 kilometers (2 miles).

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1

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Table 2.4-4 j Beach Survey Exposure Rate Measurements  !

Direct Radiation Survey Results i June 14. 1994 ,

l Exposure Rate Beach Terrain .

Location Micro-R/hr + 1 std. dev.  !

White Horse Beach 7.5 0.1 Sandy. Few granite  !

(Near Hilltop Ave) boulders within thirty feet.

White Horse Beach 8.3 0.1 Sandy sith small amounts l (In Back of Full of gravel.  :

Sail Bar)

Plymouth Beach 6.1 0.1 Sandy. . '

(Outer Beach)

Plymouth Beach 5.5 0.1 Sandy.  !'

(Inner Beach)

Plymouth Beach 9.9 i 0.1 Sandy with gravel. j (Behind Bert's Breakwater and seawall  ;

Restaurant) nearby.  ;

Duxbury Beach 8.1 0.1 Sandy with coarse (Control) gravel and exposed l cobble. 1 1

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Page 43

- - p-- =-m+ ggy

Table 2.5-1 1 Air Particulate Filter Radioactivity Analyses ,

i ENVIRONMENTAL RADIOLOGICAL PROGRAM SLAN4ARY PILGRIM NUCLEAR POWER STATION PLYMOUTH, MA JANUARY - DECEMBER 1994 i

MEDIUM: AIR PARTICULATE UNITS: PCI/CU. M

!!!!!!!W.!!!!!!!  !!!!!M.Vl!!.!!!!!!!.52 SW!!S.!!!!!W!

RADIONUCLIDES MEAN MEAN MEAN '

(NO.ANALYSESj REQUIRE 0 RANGE STA. RANGE RANGE (NON-ROUTINE) LLD NO. DETECTED ** NO. NO. No

............. ........ ..................... ........... DETECTED

...............** ..... DETECTED GR B (571) .01 ( 1.7 t 0.0)E -2 21 ( 1.9 0.1)E -2 ( 1.9 2 0.1 [

( 0) ( 6.4 - 34.7)E -3 ( 9.7 - 32.6)E -3 ( 9.7 - 32.6)E -2

)E -3

• (519/519)* *( 52/ 52)* *( 52/ 52)* 4 BE 7 ( 44) ( 9.3 2 0.2)E -2 17 ( 1.0 2 0.1)E -1 ( 9.8 2 0.5)E -2

( 0) ( 7.2 - 13.0)E -2 ( 8.7 - 13.0)E -2 ( 8.8 - 11.0)E -2

• ( 40/ 40)* *( 4/ 4)* *( 4/ 4)*

K-40 ( 44) ( 6.9 2 4.4)E -4 15 ( 2.7 1 0.4)E -3 ( 6.2 2 19.5)E -4

( 0) ( -5.4 - 7.8)E -3 ( 1.6 - 3.7)E -3 ( 2.7 - 5.0)E -3

• ( 0/ 40)* *( 0/ 4)* *( 0/ 4)*

CS-134 ( 44) .01 ( -1.5 t 0.4)E -4 01 ( 3.9 2 8.9)E -5 ( -1.2 2 0.2)E -4

( 0) ( -6.9 - 3.0)E -4 ( -2.0 - 1.9)E -4 ( -1.8 - -0.7)E -4

• ( 0/ 40)* *( 0/ 4)* *( 0/ 4)* ,

CS-137 ( 44) .01 ( 1.1 2 2.7)E -5 21 ( 1.3 2 0.3)E -4 ( 1.3 2 0.3)E -4 I

( 0) ( -3.0 - 5.2)E -4 ( 8.6 - 21.2)E -5 ( 8.6 - 21.2)E -5 ,

• ( 0/ 40)* *( 0/ 4)* *( 0/ 4)* 1

• Non-Routine refers to the runber of separate measurements which were greater than ten (10) times the average backgromd for the period of the report. t The fraction of saaple analyses yielding detectable measurements (i.e. > 3 Std. Deviations) is indicated with *( )*.

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l Page 44

Table 2.6-1 Charcoal Cartridge Radioactivity Analyses i

l I

I ENVIRONMENTAL RADIOLOGICAL PROGRAM SLSetARY PILGRIM NUCLEAR POWER STATION PLYMOUTH, MA JANUARY - DECEMBER 1994 MEDILM: CHARCOAL CARTRIDGE UNITS: PCI/CU. M

.I.ND..I

.. . .CATO.R.S.T

• • • . A T.I O.N.S S.T* A.T I O.N..W..I

. .. CON.T.RO.L.S.T

.T H.H.I..G..HE..S.T.M.E

... AN.. .. A.T.I O.N S RADIONUCLIDES MEAN MEAN MEAN (NO.ANALYSESj REQUIRED RANGE STA. RANGE RANGE (NON-ROUTINE) LLD NO. DE NO. NO. NO. DETECTED **

............. ........ .........TECTED**

............ ........... DETECTED **............... .....................

1-131 (5 71) .07 ( 3.5 2 4.1)E -4 17 ( 1.62 1.4)E -3 ( 1.4 2 15.7)E -4

( 0) ( -3.0 - 2.9)E 2 ( -2.5 - 2.2)E -2 ( -2.8 - 2.9)E -2

• ( 0/519)* *( 0/ 52)* *( 0/ 52)*

• Non-Routine refers to the rumber of separate measurements which were greater than ten (10) times the average background for the period of the report.

The fraction of indicated with *( samp)le * .

analyses yielding detectable measurements (i.e. > 3 Std. Deviations) is 1

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Page 45

Table 2.7-1 ,

Milk Radioactivity Analyses ,

i ENVIRONMENTAL RADIOLOGICAL PROGRAM SIA34ARY PILGRIM NUCLEAR POWER STATION PLYMOUTH, MA JANUARY-DECEMBER $994 MEDIUM: MILK UNITS: PCI/KG

!!".150!5.!!!!!W!  !!!!!W.Vl!!.!!!!!!!.50! EW!!E!!!!!H!

RADIDNUCLIDES MEAN MEAN MEAN RANGE STA. RANGE RANGE (No. ANALYSES) REQUIRED (NON-ROUTINE) NO NO. NO. DETECTED ** NO

............. ...L.LD

.... ..... DETECTED

............... ** .......................... ..... DETECTED SR-89 ( 38) ( 5.3 2 3.5)E -1 11 ( 5.3 2 3.5)E -1 ( -2.3 2 5.7)E -1

( 0) ( -1.9 - 4.5)E O ( -1.9 - 4.5)E O ( -4.0 - 5.5)E O .

• ( 0/ 19)* *( 0/ 19)* *( 0/ 19)*

SR-90 ( 38) ( 1.7 2 0.2)E O 11 ( 1.7 t 0.2)E O ( 1.5 t 0.2)E O

( 0) ( 7.8 - 33.3)E -1 ( 7.8 - 33.3)E -1 ( -7.5 - 28.2)E -1

• ( 11/ 19)* *( 11/ 19)* *( 10/ 19)*

K-40 ( 38) ( 1.4 2 0.0)E 3 11 ( 1.4 2 0.0)E 3 ( 1.4 2 0.0)E 3

( 0) ( 1.2 - 1.5)E 3 ( 1. 2 - 1.5)E 3 ( 1.3 - 1.5)E 3

• ( 19/ 19)* *( 19/ 19)* *( 19/ 19)*

I-131 ( 38) 1. ( 2.5 1 1.6)E -2 21 ( 6.5 2 1.3)E -2 ( 6.5 2 1.3)E -2

( 0) ( -10.0 - 12.0)E -2 ( -3.3 - 17.0)E -2 ( -3.3 - 17.0)E -2

• ( 0/ 19)* *( 0/ 19)* *( 0/ 19)*

CS-134 ( 38) 15. ( -9.9 2 2.5)E -1 21 ( -8.7 1 3.4)E -1 ( -8.7

• 3.4)E -1

( 0) ( -3.0 - 1.5)E O ( -3.5 - 1.6)E O ( -3.5 - 1.6)E O

• ( 0/ 19)* *( 0/ 19)* *( 0/ 19)*

CS-137 ( 38) 15. ( 1.82 0.4)E O 11 ( 1.8 2 0.4)E O ( 6.2 2 3.3)E -1

( 0) ( -1.5 - 4.5)E O ( -1.5 - 4.5)E O ( -1.9 - 3.0)E O

• ( 1/ 19)* *( 1/ 19)* *( 0/ 19)*

BA-140 ( 38) 15. ( 5.3 2 459.5)E -3 11 ( 5.3 t 459.5)E -3 ( -3.8 2 3.1)E -1

( 0) ( -4.5 - 3.3)E O ( -4.5 - 3.3)E O ( -3.2 - 1.3)E O

• ( 0/ 19)* *( 0/ 19)* *( 0/ 19)*

• Non-Routine refers to the runber of separate measurements which were greater than ten (10) times the average background for the period of the report.

The fraction of indicated with *( sanp)le analyses yielding detectable measurements (i.e. > 3 Std. Deviatio 4) is Page 46

Table 2.8-1 l

Forage Radioactivity Analyses )

l ENVIRONMENTAL RADIOLOGICAL PROGRAM SLNWARY PILGRIM NUCLEAR POWER STATION PLYMOUTH, MA JANUARY-DECEMBER 1994 MEDIUM: BEEF FORAGE UNITS: PCl/KG WET

!!?!Et!M.!!!!!W!  !!!!!W.V!!!.!!S!!!.5t! EHI!E!!!!!M!

RADIONUCLIDES MEAN MEAN MEAN RANGE STA. RANGE RANGE (NO.

(NON ANALYSES)

ROUTINE) REQUIRED NO NO. NO. DETECTED ** NO

............. ...L.LD .... ..... DE.TECTED**

.. ........... .......................... ..... DETECTED BE-7 ( 3) ( 1.6 2 0.5)E 3 11 ( 2.1 2 0.0)E 3 ( 6.3 2 1.4)E 2

( 0) ( 1.2 - 2.1)E 3

• ( 2/ 2)* *( 1/ 1)* *( 1/ 1)*

K-40 ( 3) ( 4.92 2.8)E 3 21 ( 1.4 0.1)E 4 ( 1.4 2 0.1)E 4

( 0) ( 2.1 - 7.7)E 3

• ( 2/ 2)* *( 1/ 1)* *( 1/ 1)*

1 1-131 ( 3) ( -2.1 2 1.5)E 1 21 ( -3.6 2 19.5)E O ( -3.6 t 19.5)E O

( 0) ( -3.6 - -0.6)E 1

• ( 0/ 2)* *( 0/ 1)* *( 0/ 1)*

CS-134 ( 3) 130. ( -1.9 2 1.0)E 1 11 ( -8.1 15.1)E O ( -1.9 2 1.5)E 1

( 0) ( -2.9 - 0.8)E 1

• ( 0/ 2)* *( 0/ 1)* *( 0/ 1)* I CS-137 ( 3) 130. ( 2.8 2 1.4)E 1 11 ( 4.3 2 1.7)E 1 ( -2.0 t 1.5)E 1

( 0) ( 1.4 - 4.3)E 1

• ( 0/ 2)* *( 0/ 1)* *( 0/ 1)*

TH-232 ( 3) ( 1.0 2 1.3)E 2 11 ( 2.3 2 0.9)E 2 ( 7.3 1 6.1)E 1

( 0) ( -2.0 - 23.1)E 1 .

• ( 0/ 2)* *( 0/ 1)* *( 0/ 1)* 1 l

• Non-Routine refers to the rumber of separate measurements which were greater than ten (10) times the average background for the period of the report.

The fraction of indicated with *( sanp)le * .

analyses yielding detectable measurements (i.e. > 3 Std. Deviations) is 1

1 Page 47 1

[ - - _ - - _ - _ _ _ . _ _ _ . .__ -. - _ _ _

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Table 2.9-1 l Vegetable / Vegetation Radioactivity Analyses l

ENVIRONMENTAL RADIOLOGICAL PROGRAM Stae4ARY PILGRik NUCLEAR POWER STATION PLYMOUTH, MA JANUARY - DECEMBER 1994 MEDIUM: VEGETABLES /VEGETATIDN UNITS: PCI/KG WET

!!!!!!!?!.!!!!!?!!  !!!!!?!."!!"."!!"!!!."!!! E9!!!?!.!!!!!!!!

RADIDNUCL! DES MEAN MEAN MEAN (NO. ANALYSESj REQUIRED RANGE STA. RANGE RANGE (NON-ROUTINE) LLD NO. DETECTED ** NO. NO NO. DETECTED **

............. ........ ..................... ......... DETECTED BE-7 ( 17) ( 1.5 2 0.5)E 3 32 ( 4.72 0.2)E 3 ( 1.0 t 1.0)E 3

( 0) ( -3.2 - 465.0)E 1 ( 2.8 - 400.0)E 1

• ( 7/ 13)* *( 1/ 1)* *( 1/ 4)*

K-40 ( 17) ( 3.3 2 0.4)E 3 35 ( 5.8 0.3)E 3 ( 3.3 2 0.5)E 3

( 0) ( 7.4 - 58.1)E 2 ( 2.2 - 4.4)E 3

• ( 13/ 13)* *( 1/ 1)* *( 4/ 4)*

I-131 ( 17) ( -5.6 2 4.1)E O BA ( 1.72 1.6)E 1 ( -6.0 t 5.4)E O

( 0) ( -3.3 - 1.7)E 1 ( -1.9 - 0.5)E 1

• ( 0/ 13)* *( 0/ 1)* *( 0/ 4)*

CS-134 ( 17) 60. ( -B.0 1.6)E O BA ( -1.5 2 11.7)E O ( -1.1 1 0.7)E 1 i

( 0) ( -2.1 - 0.1)E 1 ( -2.8 - 0.2)E 1

• ( 0/ 13)* *( 0/ 1)* *( 0/ 4)*

CS 137 ( 17) 60. ( 5.4 2 3.5)E 1 BA ( 4.6 2 0.3)E 2 ( 4.4 2 4.1)E 1

( 1) ( -3.5 - 462.0)E O ( -3.2 - 166.0)E O

• ( 4/ 13)* *( 1/ 1)* *( 1/ 4)*

TH-232 ( 17) ( 6.5 2 2.3)E 1 BA ( 2.8 2 0.5)E 2 ( 7.4 t 4.8)E 1

( 0) ( -2.8 - 28.0)E 1 ( 6.7 - 216.0)E O '

• ( 2/ 13)* *( 1/ 1)* *( 1/ 4)*

• Non-Routine refers to the tuber of separate measurements which were greater than ten (10) times the average background for the period of the report.

The fraction of indicated with *( samp)le analyses yielding detectable measurements (i.e. > 3 Std. Deviations) is t

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Page 48

4 Table 2.10-1 i Cranberry Radioactivity Analyses j

ENVIRONMENTAL RADIOLOGICAL PROGRAM SUMARY l PILGRIM NUCLEAR JANUARY POWER STATION {994 PLYMOUTH, MA

- DECEMBER MEDIUM: CRANBERRIES UNITS: PCI/KG WET r

.IND..IC.A..TO.R

. .eee **STATION..S ..

S.T A.T.I O.N..W..I T H.H..I GHEST ME.

.. . ******* CO.NT AN.

... RO..L.ST

.e** AT I O.N..S RADIONUCLIDES MEAN MEAN MEAN (NO.ANALYSESj REQUIRED RANGE STA. RANGE RANGE (NON-ROUTINE) LLD NO. DETECTED ** No. NO. DETECT NO. DETECTED **

............. ........ ..................... .................E.D**........ ........... .........

BE-7 ( 3) ( -8.8 2 7.0)E O 13 ( -1.7 t 82.0)E O ( -1.0 2 6.6)E 1

( 0) ( -1.6 - -0.2)E 1

• ( 0/ 2)* *( 0/ 1)* *( 0/ 1)*

K-40 ( 3) ( 7.0 2 1.0)E 2 14 ( 8.0 2 1.9)E 2 ( 7.9 2.0)E 2

( 0) ( 6.0 - 8.0)E 2

• ( 2/ 2)* *( 1/ 1)* *( 1/ 1)*

I-131 ( 3) ( 7.5 902.5)E -2 14 ( 9.1 2 13.0)E O ( -8.8 t 8.6)E O

( 0) ( -8.9 - 9.1)E O

• ( 0/ 2)* *( 0/ 1)* *( 0/ 1)*

CS-134 ( 3) 60. ( -4.9 2 6.1)E O 23 ( 1.0 t 0.9)E 1 ( 1.0 t 0.9)E 1

( 0) ( -1.1 - 0.1)E 1

• ( 0/ 2)* *( 0/ 1)* *( 0/ 1)*

CS-137 ( 3) 60. ( -2.8 t 5.9)E o 14 ( 3.1 1 7.8)E D ( 0.0 8.2)E O

( 0) ( -8.6 - 3.1)E O

• ( 0/ 2)* *( 0/ 1)* *( 0/ 1)*

TH 232 ( 3) ( 2.0 2 2.5)E 1 13 ( 4.4 t 4.0)E 1 ( 2.9 2 4.1)E 1 1

( 0) ( -5.0 - 44.3)E O  !

• ( 0/ 2)* *( 0/ 1)* *( 0/ 1)*

• Non-Routine refers to the ramber of separate measurements which were greater than ten (10) times the average background for the period of the report.

The fraction of indicated with *( sanp)le

• analyses yielding detectable measurements (i.e. > 3 Std. Deviations) is e

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Page 49 l 1

Table 2.11-1 Soil Radioactivity Analyses ENVIRONMENTAL RADIOLOGICAL PROGRAM SLMMARY PILGRIM NUCLEAR POWER STATION PLYMOUTH, MA JANUARY - DECEMBER 1994 MEDIUM: SOIL UNITS: PCI/KG DRY

!!!!E!!W.!!!!!?!!  !!!!!W.Y!!!.!!!!!!!.5^! EW!!?L!!!!!W!

RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES REQUIRED RANGE STA. RANGE RANGE (NON-ROUTINE))

LLD NO. DETECTED **

No. No. DETECTED ** No. DETECTED **

BE-7 ( 35) ( 8.4 2 3.1)E 1 03 ( 2.5 2 0.4)E 2 ( 1.6 2 0.8)E 2

( 4) ( -3.2 - 5.2)E 2

• ( 4/ 34)* *( 1/ 1)* *( 0/ 1)*

K-40 ( 35) ( 1.0 2 0.0)E 4 21 ( 1.5 0.1)E 4 ( 1.5 2 0.1)E 4

( 0) ( 6.9 - 13.5)E 3

• ( 34/ 34)* *( 1/ 1)* *( 1/ 1)* .

MN-54 ( 35) ( -2.1 2 3.3)E O 17 ( 1.5 2 1.3)E 1 ( -1.9 2 1.1)E 1

( 0) ( -5.4 - 4.8)E 1 ( -1.7 - 4.8)E 1

• ( 0/ 34)* *( 0/ 4)* *( 0/ 1)*

Co-58 ( 35) ( -5.5 t 2.2)E O 10 ( 1.0 0.5)E 1 ( -7.2 2 9.0)E O

( 0) ( -2.5 - 2.4)E 1 ( -1.5 - 19.7)E O

• ( 0/ 34)* *( 0/ 4)* *( 0/ 1)*

FE-59 ( 35) ( -5.7 2 10.1)E O 17 ( 4.6 t 1.o)E 1 ( 8.1 2 21.2)E O

( 0) ( -1.3 - 1.7)E 2 ' 2.7 - 87.8)E O

• ( 0/ 34)* *( 0/ 4)* *( 0/ 1)*

Co-60 ( 35) ( 1.3 2 0.6)E 1 00 ( 4.4 2 1.9)E 1 ( 1.5 2 10.2)E D

( 3) ( -5.5 - 11.7)E 1 ( 1. 7 - 11.7)E 1

• ( 3/ 34)* *( 1/ 5)* *( 0/ 1)*

2N-65 ( 35) ( -5.1 2 6.6)E O 01 ( 4.4 2 1.1)E 1 ( -1.7

• 2.5)E 1

( 0) ( -1.1 - 0.7)E 2 ( 7.5 - 71.5)E O

• ( 0/ 34)* *( 0/ 5)* *( 0/ 1)*

ZR-95 ( 35) ( 1.4 1 0.7)E 1 01 ( 5.2 t 1.7)E 1 ( 9.3 t 17.4)E O

( 0) ( -8.6 - 9.9)E 1 ( 1.5 - 9.9)E 1

• ( 0/ 34)* *( 0/ 5)* *( 0/ 1)*

I 131 ( 35) ( -1.0 2 10.7)E O 06 ( 6.6 2 2.7)E 1 ( -6.0 t 16.5)E O

( 0) ( -1.4 - 1.2)E 2 ( 1.9 - 120.0)E O

• ( 0/ 14)*

• ( 0/ 4)* *( 0/ 1)* i CS-134 ( 35) 50. ( 5.3 2 3.0)E O 08 ( 1.4 t 1.1)E 1 ( 4.0 2 9.1)E O

( 0) ( -2.5 - 4.1)E 1 ( -1.3 - 4.1)E 1

• ( 0/ 34)* *( 0/ 4)* *( 0/ 1)*  ;

CS-137 ( 35) 50. ( 2.8 2 0.6)E 2 03 ( 8.1 2 0.1)E 2 ( 5.72 1.5)E 1

( 5) ( -6.2 - 1440.0)E O '

• ( 25/ 34)* *( 1/ 1)* *( 1/ 1)*

BA-140 ( 35) ( 1.9 2 0.9)E 1 06 ( 6.3 2 3.0)E 1 ( -6.3 t 12.4)E D

( 0) ( -9.7 - 14.8)E 1 ( 6.3 - 147.0)E O  !

• ( 0/ 34)* *( 0/ 4)* *( 0/ 1)*

TH-232 ( 35) ( 7.2 2 0.3)E 2 06 ( 8.2 2 1.3)E 2 ( 6.4 2 0.6)E 2 e

( 0) ( 4.4 - 11.9)E 2 ( 4.7 - 10.9)E 2

• ( 34/ 34)* *( 4/ 4)* *( 1/ 1)*

Non-Routine refers to the ruber of separate measurements which were greater than ten (10) times the average backgrotrid for the period of the report.

The fraction of indicated with *( sanp)le

• analyses yielding detectable measurements (i.e. > 3 Std. Deviations) is Page 50

o Table 2.12-1 Surface Water Radioactivity Analyses ENVIRONMENTAL RADIOLOGICAL PROGRAM SLM4ARY PILGRIM NUCLEAR POWER STATION PLYMOUTH, MA JANUARY - DECEMBER $994 MEDIUM: SURFACE WATER UNITS: PCI/KG

!!!!E!!95.!!!!!9!!  !!!!!!!.WI!!.!!E!!!!."!^! E9!!!?!.!!!!!2!!

RADIONUCLIDES MEAN MEAN MEAN (NO.ANALYSESj REQUIRED RANGE STA. RANGE RANGE (NON-ROUTINE) LLD WO. DETECTED ** NO. No. DETECTED ** No.

............. ........ ..................... .......................... ....... DETECTED **..............

F K-40 ( 36) ( 1.5 0.3)E 2 23 ( 2.9 2 0.1)E 2 ( 2.9 1 0.1 E 2

( 0) ( -1.2 - 33.5)E 1 ( 2.5 - 3.4)E 2 ( 2.5 - 3.4))E 2

• ( 12/ 24)* *( 12/ 12)* *( 12/ 12)*

MN-54 ( 36) 15. ( -3.2 1.7)E -1 23 ( 4.2 1 36.6)E -2 ( 4.2 2 36.6)E -2

( 0) ( -2.5 - 1.1)E O ( -2.0 - 2.2)E O ( -2.0 - 2.2)E O

• ( 0/ 24)* *( 0/ 12)* *( 0/ 12)*

Co-58 ( 36) 15. ( -2.6 2 1.7)E -1 23 ( -9.4 2 33.8)E -2 ( -9.4 1 33.8)E -2

( 0) ( -2.6 - 1.3)E O ( - 1. 7 - 2.0)E O ( -1.7 - 2.0)E O

• ( 0/ 24)* *( 0/ 12)* *( 0/ 12)*

FE-59 ( 36) 30. ( 1.8 2 4.1)E -1 11 ( 3.7 2 5.5)E -1 ( -2.0 2 0.9)E O

( 0) ( -3.0 - 4.4)E O ( -2.0 - 4.1)E O ( -7.3 - 3.2)E O

• ( 0/ 24)* *( 0/ 12)* *( 0/ 12)*

Co-60 ( 36) 15. ( 1.2 2 221.4)E -3 23 ( 2.0 1 4.5)E -1 ( k.0 4.5)E -1

( 0) ( -1.2 - 3.4)E O ( -2.6 - 2.2)E D ( -2.6 - 2.2)E O

• ( 0/ 24)* *( 0/ 12)* *( 0/ 12)*

ZN-65 ( 36) 30. ( 3.3 t 54.4)E -2 17 ( 1.0 2 0.5)E O ( -1.1 2 6.4)E -1

( 0) ( -5.3 - 5.4)E O ( -2.3 - 5.4)E O ( -4.3 - 3.5)E O

• ( 0/ 24)* *( 0/ 12)* *( 0/ 12)*

ZR-95 ( 36) 15. ( 1.7

• 3.1)E -1 23 ( 6.4 1 4.4)E -1 ( 6.4 t 4.4)E -1

( 0) ( -2.9 - 2.7)E O ( -1,2 - 3.7)E O ( -1.2 - 3.7)E O

• ( 0/ 24)* *( 0/ 12)* *( 0/ 12)*

l-131 ( 36) 1. ( 3.0 1 4.6)E -2 23 ( 1.3 2 1.3)E -1 ( 1.3 2 1.3)E -1

( 0) ( -7.0 - 3.8)E -1 ( -2.4 - 15.5)E -1 ( -2.4 - 15.5)E -1

• ( 0/ 24)* *( 0/ 12)* *( 0/ 12)*

CS-134 ( 36) 15. ( -1.1 2 0.3)E O E3 ( -6.2 1 3.1)E -1 ( -6.2 2 3.1)E ~1

( 0) ( -3.3 - 1.5)E O ( -2.5 - 1.1)E D ( -2.5 - 1.1)E O

• ( 0/ 24)* *( 0/ 12)* *( 0/ 12)*

CS-137 ( 36) 18. ( -6.9 2 17.4)E -2 23 ( 1.6 2.7)E -1 ( 1.62 2.7)E -1

( 0) ( -1.9 - 1.9)E O ( -1.6 - 1.6)E O ( -1.6 - 1.6)E O

• ( 0/ 24)* *( 0/ 12)* *( 0/ 12)*

BA-140 ( 36) 15. ( 2.1 2 4.5)E -1 23 ( 1.0 2 0.7)E O ( 1.0 2 0.7)E O

( 0) ( -4.4 - 4.1)E O ( -1.5 - 6.8)E O ( -1.5 + 6.8)E O

• ( 0/ 24)* *( 0/ 12)* *( 0/ 12)*

H-3 ( 12) 3000. ( -3.5

• 5.2)E 1 23 ( 2.0 t 9.3)E 1 ( 2.0 t 9.3)E 1

( 0) ( -3.3 - 1.6)E 2 ( -9.9 - 29.7)E 1 ( -9.9 - 29.7)E 1

• ( 0/ 8)* *( 0/ 4)* *( 0/ 4)*

Non-Routine refers to the rnaber of separate measurements which were greater than ten (10) times the average backgromd for the period of the report.

The fraction of sample analyses yielding detectable measurements (i.e. > 3 Std. Deviations) is indicated with *( )*.

Page 51

Table 2.13-1 Fish Radioactivity Analyses ENVIRONMENTAL RADIOLOGICAL PROGRAM SLM4ARY PILGRIM NUCLEAR POWER STATION PLYMOUTH, MA JANutRY - DECEMBER 1994 [

[ MEDIUM: FISH UNITS: PCI/KG WET

!!o!E!!5.!!!!!W!  !!!!!W.W!!!."!25!!40! E2!!S.!!!!!W!

RADIONUCLIDES MEAN MEAN MEAN (NO. ANALYSES REQUIRED RANGE STA. RANGE RANGE (NON-ROUTINE))

LLD NO. DETECTED **

h0. No. DETECTED ** No. DETECTED **

BE-7 ( 24) ( -5.1 2 2.4)E 1 98 ( 4.1 t 5.0)E 1 ( 4.1 t 5.0)E 1

( 0) ( -2.9 - 0.9)E 2 ( -1.1 - 2.4)E 2 ( -1.1 - 2.4)E 2

• ( 0/ 16)* *( 0/ 8)* *( 0/ 8)*

K-40 ( 24) ( 3.0 2 0.1)E 3 11 ( 3.0 1 0.1)E 3 ( 2.6 2 0.1)E 3

( 0) ( 2.2 - 4.3)E 3 ( 2.2 - 4.3)E 3 ( 2.1 - 3.0)E 3

• ( 16/ 16)* *( 16/ 16)* *( 8/ 8)*

MN-54 ( 24) 130. ( 1.0 2 1.6)E O 11 ( 1.0 2 1.6)E O ( -2.1 2 2.0)E O

( 0) ( -9.5 - 13.5)E O ( -9.5 - 13.5)E O ( -1.2 - 0.3)E 1

• ( 0/ 16)* *( 0/ 16)* *( 0/ 8)*

Co-58 ( 24) 130. ( -3.5 t 3.0)E O 98 ( -4.0 2 58.2)E -1 ( -4.0 t 58.2)E -1

( 0) ( -3.3 - 1.7)E 1 ( -3.3 - 2.0)E 1 ( -3.3 - 2.0)E 1

• ( 0/ 16)* *( 0/ 8)* *( 0/ 8)*

FE-59 ( 24) 260. ( 5.3 2 5.9)E O 98 ( 5.3 1 18.9)E o ( 5.3 2 18.9)E O

( 0) ( -3.8 - 4.1)E 1 ( -4.4 - 11.9)E 1 ( -4.4 - 11.9)E 1

• ( 0/ 16)* *( 0/ 8)* *( 0/ 8)*-

Co-60 ( 24) 130. ( 3.3 2 2.4)E 0 11 ( 3.3 1 2.4)E D ( 3.1 2 3.7)E O i

( 0) ( -1.6 - 1.6)E 1 ( -1.6 - 1.6)E 1 ( -1.5 - 1.6)E 1 1

• ( 0/ 16)* *( 0/ 16)* *( 0/ 8)*  ;

ZN-65 ( 24) 260. ( -8.6 t 7.5)E O 98 ( 4.7 8.9)E 0 ( 4.7

• 8.9)E 0

( 0) ( -7.0 - 4.7)E 1 ( -4.9 - 3.9)E 1 ( -4.9 - 3.9)E 1 l

• ( 0/ 16)* *( 0/ 8)* *( 0/ 8)*

CS-134 ( 24) 130. ( -9.5 1.9)E O 11 ( -9.5 1.9)E 0 ( -9.5 2.2)E O

( 0) ( -2.4 - 0.0)E 1 ( -2.4 - 0.0)E 1 ( -1.7 - -0.1)E 1

• ( 0/ 16)* *( 0/ 16)* *( 0/ 8)*

CS-137 ( 24) 130. ( 4.2 t 2.5)E O 11 ( 4.22 2.5)E O ( 2.3 2 4.6)E O

( 0) ( -2.0 - 2.0)E 1 ( -2.0 - 2.0)E 1 ( -9.2 - 31.5)E O i

• ( 0/ 16)* *( 0/ 16)* *( 0/ 8)*  !

i CE-144 ( 24) ( -8.8 t 8.7)E 0 98 ( 8.2 1 13.8)E O ( 8.2 2 13.8)E O

( 0) ( -8.7 - 4.7)E 1 ( -5.8 - 7.3)E 1 ( -5.8 - 7.3)E 1

• ( 0/ 16)* *( 0/ 8)* *( 0/ 8)*

TM-232 ( 24) ( 6.5 t 10.6)E O 98 ( 1.1 2 1.2)E 1 ( 1.1 2 1.2)E 1

( 0) ( 5.8 - 10.9)E 1 ( -5.4 - 6.8)E 1 ( -5.4 - 6.8)E 1

• ( 0/ 16)* *( 0/ 8)* *( 0/ 8)*

Non-Routine refers to the runber of separate measurements which were greater than ten (10) times the average backgromd for the period of the report.

The fraction of sample analyses yleiding detectable measurements (i.e. > 3 Std. Deviations) is indicated with *( )*.

l 1

i l

l i

l l

l l

l Page 52  ;

Table 2.14-1 Shellfish Radioactivity Ana' lyses l 1

l I

ENVIRONMENTAL RADIOLOGICAL PROGRAM SUMARY PILGRIM NUCLEAR POWER STATION PLYMOUTH, MA JANUARY - DECEMBER $994 MEDIUM: SHELLFISH UNITS: PCl/KG WET

!!!!E!!?!.!!!!!?!!  !!!!!?!.V!!"."!E"!!!."S*! E?!!!?!.!!!!!?!!

RADIONUCLIDES MEAN MEAN MEAN (NO.ANALYSESj REQUIRED RANGE STA. RANGE RANGE (NON-ROUT!NE) LLD WO. DETECTED ** WO. NO. DETECTED ** NO. DETECTED **

BE-7 ( 48) ( 3.9 t 1.1)E 1 12 ( 5.1 2 2.2)E 1 ( 2.9 2 0.9)E 1

( 0) ( -5.2 - 23.8)E 1 ( -5.2 - 23.8)E 1 ( -7.5 - 9.6)E 1

• ( 4/ 24)* *( 1/ 12)* *( 4/ 24)*

K-40 ( 48) ( 7.9 2 0.9 2 15 ( 9.9 2 0.7)E 2 ( 7.6 2 1.2)E 2

( 0) ( 1.3 - 13.5)E

)E 2 ( 8.7 - 11.6)E 2 ( -3.4 - 204.0)E 1

• ( 21/ 24)* *( 4/ 4)* *( 21/ 24)*

MN-54 ( 48) 130. ( 1.4 2 9.1)E -1 15 ( 8.1 2 4.4)E -1 ( -1.4 2 1.2)E O

( 0) ( -1,3 - 0.9)E 1 ( -1.4 - 18.5)E -1 ( -2.2 - 0.9)E 1

• ( 0/ 24)* *( 0/ 4)* *( 0/ 24)*

Co-58 ( 48) 130. ( -6.8 2 4.8)E -1 13 ( 2.1 2 18.0)E -1 ( 8.5 2 118.7)E -2

( 0) ( -5.7 - 5.0)E O ( -1.4 - 1.8)E 1 ( -1.4 - 1.8)E 1

• ( 0/ 24)* *( 0/ 16)* *( 0/ 24)*

FE-59 ( 48) 260. ( -2.0 1 2.0)E O 13 ( 2.8 3.2)E O ( 2.1 e 2.1)E O

( 0) ( -3.1 - 1.6)E 1 ( -2.7 - 2.1)E 1 ( -2.7 - 2.1)E 1

• ( 0/ 24)* *( 0/ 16)* *( 0/ 24)*

Co-60 ( 48) 5. ( -1.1 2 6.8)E -1 13 ( 1.5 1 1.1)E O ( 1.2 2 0.8)E O

( 0) ( -8.4 - 6.9)E 0 ( -5.7 - 8.9)E O ( -5.7 - 8.9)E O

• ( 0/ 24)* *( 0/ 16)* *( 0/ 24)*

ZN-65 ( 48) 5. ( 2.f 2 2.9)E O 12 ( 6.0 2 5.7)E 0 ( -4.7 2 3.2)E O

( 0) ( -1,3 - 6.1)E 1 ( -1.8 - 6.1)E 1 ( -4.7 - 2.9)E 1

• ( 0/ 24)* *( 0/ 12)* *( 0/ 24)*

CS-134 ( 48) 5. ( -4.4 1 5.2)E -1 24 ( 7.1 2 58.6)E -2 ( -3.9 2 1.4)E O

( 0) ( -7.9 - 4.1)E O ( -2.5 - 2.5)E O ( -2.2 - 0.4)E 1

• ( 0/ 24)* *( 0/ 8)* *( 0/ 24)*

CS-137 ( 48) 5. ( 2.7 6.0)E -1 13 ( 3.2 2 1.3)E O ( 2.3 0.9 O

( 0) ( -6.9 - 7.5)E O ( -6.1 - 12.4)E O ( -6.1 - 12.4)E

)E O

• ( 0/ 24)* *( 0/ 16)* *( 0/ 24)*

CE-144 ( 48) 15. ( 2.1 2 428.0)E -2 11 ( 5.9 t 1.7)E O ( 2.3 2 4.9)E O

( 0) ( -7.1 - 4.5)E 1 ( -8.2 - 119.0)E -1 ( -4.9 - 7.8)E 1

• ( 0/ 24)* *( 0/ 8)* *( 0/ 24)*

TH-232 ( 48) ( 2.4 1 0.5)E 1 13 ( 4.5 1.1)E 1 ( 3.8 2 0.8)E 1

( 0) ( -2.5 - 8.1)E 1 ( -4.9 - 14.5)E 1 ( -4.9 - 14.5)E 1

• ( 6/ 24)* *( 6/ 16)* *( 10/ 24)*

Non-Routine refers to the runber of separate measurements which were greater than ten (10) times the average background for the period of the report.

The fraction of sanple analyses yielding detectable measurements (i.e. > 3 Std. Deviations) is indicated with *( )*.

I Page 53

Table 2.15-1 I 1

Irish Moss Radioactivity Analyses ENVIRONMENTAL RADIOLOGICAL PROGRAM St9 MARY PILGRIM NUCLEAR POWER STATION PLYMOUTH, MA JANUARY-DECEMBER $994 MEDIUM: IRISH MOSS UNITS: PC1/KG WET

!!!!E0!5.!!!!!2!  !!?!!5.W!!!."!!5!!.50! EMI!S.!!!!!M!

RADIONUCLIDES MEAN MEAN MEAN RANGE STA. RANGE RANGE (NO. ANALYSES) REQUIRED (NON ROUTINE) LLD NO. DETECTED ** NO. NO NO. DETECTED **

............. ........ ..................... ......... DETECTED **

BE 7 ( 16) ( 1.9 2 0.3)E 2 22 ( 2.1 1 0.5)E 2 ( 1.5 0.3)E 2

( 0) ( 4.5 - 39.0)E 1 ( 9.4 - 31.3)E 1 ( 4.8 - 31.3)E 1

• ( 6/ 8)* *( 4/ 4)* *( 5/ 8)*

K-40 ( 16) ( 6.6 2 0.5)E 3 11 ( 7.6 2 0.3)E 3 ( 6.7 2 0.4)E 3

( 0) ( 4.5 - 8.5)E 3 ( 6.8 - 8.5)E 3 ( 5.4 - 7.9)E 3

• ( 8/ 8)* *( 4/ 4)* *( 8/ 8)*

MN-54 ( 16) ( 2.6 1 2.6)E O 11 ( 7.6 2 3.2)E O ( -5.4 1 124.4)E -2

( 0) ( -8.7 - 17.0)E O ( 3.2 - 17.0)E O ( -4.0 - 5.2)E O

• ( 0/ 8)* *( 0/ 4)* *( 0/ 8)*

CO-58 ( 16) ( -3.4 t 2.3)E o 22 ( 2.3 2 2.5)E O ( 2.3 2 2.4)E O

( 0) ( -1.4 - 0.6)E 1 ( -5.0 - 6.2)E O (- -5.0 - 15.6)E O

• ( 0/ 8)* *( 0/ 4)* *( 0/ 8)*

FE-59 ( 16) ( 1.3 2 6.0)E O 15 ( 1.5 0.4)E 1 ( 6.2 2 34.6)E -1

( 0) ( -2.7 - 2.4)E 1 ( 6.6 - 24.2)E O ( -1.4 - 1.5)E 1

• ( 0/ 8)* *( 0/ 4)* *( 0/ 8)*

Co-60 ( 16) ( -1.5 t 27.7)E -1 11 ( 2.3 t 2.8)E O ( 5.4 2 11.8)E -1

( 0) ( -1.5 - 1.0)E 1 ( -3.3 - 9.6)E D ( -3.7 - 4.5)E O

• ( 0/ 8)* *( 0/ 4)* *( 0/ 8)*

2N 65 ( 16) ( -1.2 2 0.5)E 1 22 ( -2.0 2 2.6)E O ( -2.6 2 3.8)E O

( 0) ( -3.4 - 0.9)E 1 ( -8.6 - 4.1)E O ( -1.9 - 1.2)E 1

• ( 0/ 8)* *( 0/ 4)* *( 0/ 8)*

CS-134 ( 16) ( -4.1 2 12.2)E -1 15 ( -2.2

• 26.1)E -1 ( -7.2 1 16.1)E -1

( 0) ( -4.5 - 7.3)E O ( -4.5 - 7.3)E O ( -6.7 - 4.8)E O

• ( 0/ 8)* *( 0/ 4)* *( 0/ 8)*

CS-137 ( 16) ( 3.0 1 1.9)E O 22 ( 4.1

• 4.4)E O ( 2.0 2 2.2)E O

( 0) ( -5.3 - 11.1)E O ( -2.0 - 16.9)E O ( -2.0 - 16.9)E O

• ( 0/ 8)* *( 0/ 4)* *( 0/ 8)*

TH 232 ( 16) ( 9.9 2 6.6)E O 22 ( 1.9 1.6)E 1 ( 1.4 2 1.0)E 1

( 0) ( -1.5 - 3.4)E 1 ( -2.5 - 5.1)E 1 ( -2.5 - 5.1)E 1

• ( 0/ 8)* *( 0/ 4)* *( 0/ 8)*

• Non-Routine refers to the ramber of seperate measurements which were greater than ten (10) times the average background for the period of the report.

The fraction of indicated with *( samp)le analyses yieldsng detectable measurements (i.e. > 3 Std. Deviations) is I

l 1

Page 54 l

l Table 2.16-1 Lobster Radioactivity Analyses i

i l

ENVIRONMENTAL RADIOLOGICAL PROGRAM St#54ARY PILGRIM NUCLEAR POWER STATION PLYMOUTH, MA <

JANUARY

• DECEMBER 1994 l i

MEDILM: AMERICAN LOBSTER UNITS: PCI/KG WET l d h$3.!$ N!  ! $ IE Y. !*!IhN! .N$! h3 N.!$ O!

RADIONUCLIDES MEAN MEAN MEAN l RANGE STA. RANGE RANGE 1 (NO.

(NON ANALYSES) REQUIRED LLP NO. DETECTED ** No. No. DETECTED ** NO. DETECTED **

.....-ROUTINE)

BE-7 ( 5) ( 8.72 678.1)E -1 11 ( 8.7 2 678.1?E -1 ( 4.6 i 6.8)E 1

( 0) ( -1.4 - 1.5)E 2 ( -1.4 - 1.5)E 2

• ( 0/ 4)* *( 0/ 4)* *( 0/ 1)*

K-40 ( 5) ( 2.6 2 0.3)E 3 89 ( 2.7 2 0.2)E 3 ( 2.72 0.2)E 3

( 0) ( 2.0 - 3.4)E 3

• ( 4/ 4)* *( 1/ 1)* *( 1/ 1)* 6 MN-54 ( 5) 130. ( -1.0 t 0.5)E 1 89 ( 1.1 2 0.7)E 1 ( 1.1 2 0.7)E 1

( 0) ( 2.3 - 0.0)E 1

• ( 0/ 4)* *( 0/ 1)* *( 0/ 1)*  !

r CC-58 ( 5) 130. ( 5.6 2 4.0)E O 11 ( 5.6 2 4.0)E O ( -2.4 2 8.1)E O

( 0) ( -3 4 - 15.8)E O ( -3.4 - 15.8)E O ,

• ( 0/ 4)* *( 0/ 4)* *( 0/ 1)*

FE-59 ( 5) 260. ( 7.6 2 11.6)E O 11 ( 7.6 2 11.6)E O ( -2.0 1 2.0)E 1

( 0) ( -2.0 - 3.2)E 1 ( -2.0 - 3.2)E 1

• ( 0/ 4)* *( 0/ 4)* *( 0/ 1)*

Co-60 ( 5) 130. ( 8.6 i 5.5)E O 11 ( 8.6 t 5.5)E O ( -4.7 2 8.2)E D

( 0) ( -2.9 - 23.6)E O ( -2.9 - 23.6)E O  !

• ( 0/ 4)* *( 0/ 4)* *( 0/ 1)*

7N-65 ( 5) 260. ( -2.8 t 1.6)E 1 89 ( -4.2 t 17.6)E D ( -4.2 1 17.6)E O

( 0) ( -5.9 - 1.4)E 1

• ( 0/ 4)* *( 0/ 1)* *( 0/ 1)* ,

CS-134 ( 5) 130. ( 1.1 2 10.7)E O 11 ( 1.1 2 10.7)E O ( -6.0 t 8.7)E O

( 0) ( -2.6 - 2.6)E 1 ( -2.6 - 2.6)E 1 =

• ( 0/ 4)* *( 0/ 4)* *( 0/ 1)*

CS-137 ( 5) 130. ( -4.9 2 6.7)E O 89 ( 5.2 t 8.1)E O ( 5.2 2 8.1)E D

( 0) ( 2.1 - 0.8)E 1

• ( 0/ 4)* *( 0/ 1)* *( 0/ 1)* -

TH-232 ( 5) ( 1.6 2 2.1)E 1 11 ( 1.6 2 2.1)E 1 ( 1.6 t 3.4)E 1

( 0) ( -2.7 - 7.2)E 1 ( -2.7 - 7.2)E 1

• ( 0/ 4)* *( 0/ 4)* *( 0/ 1)*

• Non-Routine refers to the rumber of separate measurements which were greater than ten (10) times the average background for the period of the report.

The fraction of indicated with *( saf)e* analyses yielding detectable measurements (i.e. > 3 Std. Deviations) is Page 55

Table 2.17-1

. Sediment Radioactivity Analyses ENVIRONMENTAL RADIOLOGICAL PROGRAM SLBetARY PILGRIM NUCLEAR POWER STATION PLYMOUTH, MA JANUARY - DECEMBER 1994 MEDIUM: SEDIMENT UNITS: PCl/KG DRY

!!"21!!!E!!^!!W!  !!^!!W.Y!!!.!!!"!!!."!^! !WI!E!!!!!W!

RAD 10NUCLIDES MEAN MEAN MEAN (NO.ANALYSESj REQUIRED RANGE STA. RANGE RANGE LLD NO No. No. DETECTED ** No. DETECTED **

...........E)

(NON-ROUTIN

.. ........ ..... DETECTED PU-238 ( 6) ( i.3

• 3.8)E -1 15 ( 1.1 t 1.3)E O ( 2.0 2 4.6)E -1

( 0) ( -7.7 - 11.0)E -1 ( -2.5 - 6.6)E -1

• ( 0/ 4)* *( 0/ 1)* *( 0/ 2)*

PU-239 ( 6) ( 4.C t 1.2)E O 13 ( 7.9 t 3.4)E O ( 7.9 2 3.4)E O

( 0) ( 2.2 - 7.6)E O ( 4.6 - 11.3)E O ( 4.6 - 11.3)E O

• ( 3/ 4)* *( 2/ 2)* *( 2/ 2)*

BE-7 ( 56) ( T.7t- 31.8)E 1.2)E 1 13 ( 1.1 0.7)E 2 ( 1.0 1 0.6)E 2

( 0) ( -4.5 1 ( -4.2 - 79.9)E 1 ( -5.9 - 79.9)E 1

• ( 3/ 39)* *( 2/ 11)* *( 3/ 17)*

K-40 ( 56) ( 8.9 2 0.1)E 3 13 ( 1.2 1 0.1)E 4 ( 1.1 1 0.0)E 4

( 0) ( 6.4 - 10.3)E 3 ( 1.0 - 1.5)E 4 ( 8.3 - 15.3)E 3

• ( 39/ 39)* *( 11/ 11)* *( 17/ 17)*

Co-58 ( 56) 50. ( -3.7 2 0.7)E O 12 ( -2.2 2 1.8)E O ( 4.4 1 1.2)E O

( 0) ( -1.1 - 0.8)E 1 ( -1.0 - 0.8)E 1 ( -1.1 - 0.4)E 1

• ( 0/ 39)* *( 0/ 11)* *( 0/ 17)*

Co-60 ( 56) 50. ( 1.9 2 0.7)E O 24 ( 4.0 2 2.2)E O ( 1.61 1.2)E O

( 0) ( -1.0 - 1.3)E 1 ( -3.1 - 8.9)E O ( -6.3 - 8.9)E O

• ( 0/ 39)* *( 0/ 6)* *( 0/ 17)*

ZN-65 ( 56) 50. ( 1.3 1.9)E O 13 ( 5.6 3.1)E O ( 4.0 1 2.7)E 0

( 0) ( -2.1 - 2.0)E 1 ( -9.5 - 19.8)E O ( -1.6 - 2.0)E 1

• ( 0/ 39)* *( 0/ 11)* *( 0/ 17)*

ZR-95 ( 56) 50. ( 4.6 2 1.6)E O 12 ( 7.3

• 1.9)E O ( 4.9 1 2.0)E O

( 0) ( -1.5 - 2.1)E 1 ( -4.5 - 13.7)E O ( -9.5 - 18.6)E O

• ( 0/ 39)* *( 0/ 11)* *( 0/ 17)*

CS-134 ( 56) 50. ( 5.5 t 86.9)E -2 15 ( 2.4 t 1.3)E O ( -3.2 2 11.3)E -1

( 0) ( -1.3 - 1.0)E 1 ( -5.4 - 10.0)E O ( -8.7 - 9.6)E O

• ( 0/ 39)* *( 0/ 11)* *( 0/ 17)*

CS-137 ( 56) 50. ( 7.5 1 2.5)E 0 13 ( 3.1 2 0.5)E 1 ( 2.3 1 0.5)E 1

( 0) ( -9.3 - 55.9)E O ( 10.0 - 69.2)E O ( -7.8 - 69.2)E O

• ( 8/ 39)* *( 11/ 11)* *( 13/ 17)*

CE-144 ( 56) 150. ( 4.2 2 4.3)E O 12 ( 9.1 2 9.7)E D ( 4.4 1 59.9)E -1

( 0) ( -5.5 - 6.1)E 1 ( -4.2 - 6.1)E 1 ( -5.3 - 4.6)E 1

• ( 0/ 39)* *( 0/ 11)* *( 0/ 17)*

TM 232 ( 56) ( 3.72 0.1)E 2 13 ( 4.8 2 0.3)E 2 ( 4.2 2 0.3)E 2

( 0) ( 2.5 - 5.4)E 2 ( 3.8 - 6.6)E 2 ( 2.6 - 6.6)E 2

• ( 39/ 39)* *( 11/ 11)* *( 17/ 17)*

• Non-Routine refers to the tuber of separate measurements which were greater than ten (10) times the average background for the period of the report.

The fraction of indicated with *( sanp)le

• analyses yielding detectable measurements (i.e. > 3 Std. Deviations) is Page 56

- - . . . . .. .-. ... . .- .- -- -- - ... ~ - . . . .

t Table 2.17-2 r Sediment Plutonium Analyses Environmental Radiological Program Summary Pilgrim Nuclear Power Station, Plymouth, MA l (January - December 1994) l Results Location Core Depth (cm) oci/Ko (dr") +-l S.D.

Plutonium 238 Plutonium 239, Plutonium 240 Rocky Point 0-2 NDA 2.75 0.70 Rocky Point 12-14 NDA 2.15 0.47 Plymouth Harbor 0-2 NDA 7.63 0.76 l l

Manomet Point 0-2 NDA NDA j Duxbury Bay - Control 0-2 NDA 11.3 i 2.0 l

Duxbury Bay - Control 12-14 NDA 4.57 0.99 i o NDA indicates no detectable activity. l t

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I f

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i l

Page 57 l l

Figure 2.2-1 Environmental Thermoluminescent Dosimeter. and Air Sampling Locations Within Exclusion Area ENVIRONMENTAL TLD LOCATIONS AIR SAMPLE LOCATIONS

[od; o Descriotion Dist.* Dir.* Code Description Dist.* Dir.*

A' Station A 0.25 mi W EB East Breakwater 0.33 mi ESE i 8 Station B 0.25 mi SSW OA Overlook Area 0.09 mi W C Station C 0.32 mi SE PB Pedestrian Bridge 0.13 mi N ,

Property Line CT Contractor Lot 0.21 mi SSE PL 0.32 mi NW 0 Statton D 0.34 mi NNW WR W. Rocky Hill Road 0.51 mi WNW EB East Breakwater 0.29 mi ESE WS Warehouse 0.11 mi SSE F Station F 0.26 mi NW G Station G 0.39 mi V HB Hall's Bog 0.37 mi SSE I Station 1 0.30 mi WNW L Station L 0.27 mi ESE OA Dverlook Area 0.10 mi W P01 Sec H Shore 0.14 mi NNW l P02 Fence Shore 0.08 mi NW >

P03 Fen L Screenh 0.06 mi NW PO4 Fen R Screenh 0.04 mi N P05 Fen Water Tank D.05 mi NNE P06 Fen Culvert 0.05 mi NE P07 Fen Intake 0.08 mi ENE P08 Fen New Admin 0.06 mi ENE P09 Fen TCF Side 0.08 mi E PID Fen Intake TCF 0.14 mi E P11 Gate Wh to TCF 0.12 mi ESE ,

P12 Fen Wh Con Gate 0.13 mi SE P13 Fen Con & RHR 0.14 mi SSE P14 Fen Butler B 0.14 mi S P15 Fen Unit #9 0.14 mi S P16 Fen Swy M Gate 0.11 mi SW P17 Fen Shf M Gate 0.07 mi W PIB 1&C N Admin 0,06 mi S P19 Compliance Area 0.05 mi SSE P20 Dosimetry Window 0.04 mi SE P21 WW Admin & Turb 0.03 mi SE P22 QA/QC Area 0.09 mi SE P23 CMG Area 0.07 mi SSE P24 Old Admin Bld 2nd 0.04 mi W P25 First Aid Trailer 0.05 mi WNW P26 Fence Warehouse 0.09 mi ESE P27 TCF Boat Launch 0.12 mi ESE i P28 TCF Cont. Lot 0.15 mi ESE PA Parking Area 0.22 mi NNW PS Pedestrian Bridge 0.13 mi N PL Property Line 0.33 mi NW PMT PNPS Met Twr 0.27 mi NW TC Training Center 0.10 mi W UR W. Rocky Hill Road 0.51 mi WNW US Warehouse 0.11 mi SSE o Distance and direction are measured from the centerline of the reactor to the sampling / monitoring location.

Page 58

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Figure 2.2-2  !

Environmental Thermoluminescent Dosimeter and Air Sampling Locations Outside Exclusion Area to About Two Miles ,

ENVIRONMENTAL TLD LOCATIONS AIR SAMPLE LOCATIONS M Description Dist.* Dir.* [o,d_e Description Dist.* Dir.*

AR Access Road 0.96 mi SSE CR Cleft Rock 0.76 mi SSW BB 3A & Bartlett Rd 2.1 mi SSE MS Manomet Substation 2.2 mi SSE BD Bayshore Drive 0.81 mi WNW ER East Rocky Hill Rd 0.56 mi SE BS Bayshore 1.1 mi V BU Beachwood Road 2.5 mi SE CR Cleft Rock 0.76 mi SSW DR Dirt Road 0.94 mi SW E Station E 1.2 mi S EM Emerson Road 0.96 mi SSE EP Emer Rd & Pris 0.98 mi SE ,

ER E Rocky Hill Rd 0.56 mi SE ,

GH Greenwood House 0.43 mi SE GN Goodwin Property 1.5 mi SW H Station H 0.32 mi SW J Station J 1.3 mi S JG John Gauley 1.2 mi W K Station K 1.3 mi SSE ME Manomet Elm 2.1 mi SE MP Manomet Pt 2.2 mi SE MR Manomet Road 0.86 mi S MS Manomet Subst 2.2 mi SSE MT Micro Tower 0.58 mi SSW PT Pines Estate 2.8 mi SSW RC Rec Pool 1.3 mi WSW RU Right of Way 1.8 mi S SP S Ply. Sub 2.9 mi W TP Taylor & Pearl 1.9 mi SE TT Taylor & Tom Ave 1.4 mi SE VR Valley Road 2.0 mi SSW UC Warren & Clifford 2.1 mi V WH White Horse Rd 1.3 mi SSE VV Yankee Village 1.4 mi WSW o Distance and direction are measured from the centerline of the reactor to the sampling / monitoring location.

Page 60

Figure 2.2-2 (cont.)

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O TLD i O AIR SAMPLER l

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Page 61

- _ _ _ _ _ _ = _

i Figure 2.2-3 l l

Environmental Thermoluminescent Dosimeter and i Air Sampling Locations Outside Property Boundary i

ENVIRONMENTAL TLD LOCATIONS AIR SAMPLE LOCATIONS i i

Qtdg > Descriotion E Dir.* [osig .Descriction Dist.* Dir.'

{

BB 3A & Bartlett 2.1 mi SSE. CR Cleft Rock 0.76 mi SSW  ;

. BD - Bayshore Drive 0.81 mi WNW EW East Weymouth 25 mi NW l BE Bourne Road 8.3 mi S MS Manomet Subst 2.2 mi SSE i BR Beaver Dam RoaJ 3.5 mi S PC Plymouth Center 4.1 mi W j BS Bayshore 1.1 mi W SN Saguish Neck 4.7 mi NNW l BU Beachwood Road 2.4 mi SE j CR Cleft Rock 0.76 mi SSW 3 CS Cedarville Sub 9.9 ml 5  !

CP College Pond 4.7 mt SW j CU Church & West 10 mi NW DMF Div. Mar. Fish. 13 mi SSE i DU Deep Water S.4 mi W  !

EA Earl Road 2.9 mi -SSE f

EL Ellisville Road 7.2 ml SSE i EP Emer. Rd & Pris 0.97 mi SE [

Ed E. Weymouth Sub 25 mi NW l HD ' Hilldale Road 3.2 mi W  !

HR Hyannis Road 4.6 ml SSE l JG John Gauley 1.2 mi W  !

KC ~ King Ceasar Road 8.1 mi NNW  !

KS XSgs: subst. 10' mi WNW f LD

' t Drew 4.3 mi WSW LP Long .. soad 5.5 mi SSW .j LR Landing Road 10 mi NNW  ;

MB Manomet Beach 3.4 ml SSE j ME Manomet Elem 2.1 mi SE l

MH Memorial Hall 4.7 mi WNW ,

MM ' Main & Meadow 11 mi WSW  ;

MP Manomet Point 2.2 mi SE I MS Manomet Subst 2.2 mi SSE NP North Plymouth S.B mi WNW PC Plymouth Center 4.1 mi V  ;

PT Pine Estates 2.8 mi SSW {

RC Rec Pool 1.3 mi WSW  !

RM Russell Hill 3.0 mi WSW  !

RP Rt 3 Overpass 3.0 mi SW f SA Sherman Airport 8.3 mi WSW SH Sacred Heart B.O mi W

. 55 Standish Shores 6.4 mi NW SP 5. Plymouth Sub 2.9 mi W l TP Taylor & Pearl 1.9 mi SE I TT Taylor & Thomas 1.4 mi SE UC Up Coll. Pnd. Rd 7.3 mi SW t BC Warren & Clifford 2.1 mi W  ;

YV Yankee Village 1.4 mi WSW [

l 0 Distance and direction are measured from the centerline of the reactor to the t sampling / monitoring location. '

Page 62

. ~ . . .._ _ _ _ _

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l Figure 2.2-4 I l

Terrestrial and Aquatic Sampling Locations  !

l

[2d2 Description Dist.* Dir.* [odg od Descript ion Dist.* Dir.*

l SURFACE VATER SEDIMENT DIS Discharge Canal 0.13 mi f! RP Rocky Point 0.21 mi N ,

BP Bartlett Pond 1.7 mi SE PLY-H Plymouth Harbor 3.0 mi W PP- Powder Point Control 7.9 mi NNW PLB Plymouth Beach 2.5 mi W MP Manomet Point 2.5 mi ESE l SHELLFISH DUX-BAY Duxbury Bay Control B.7 mi NNW DIS Discharge Canal 0.21 mi N GH Green Harbor Control 10 mi NNW PLY-H Plymouth Harbor 2.8 mi W MP Manomet Point 3.0 mi ESE !4JJ.K DUX-BAY Duxbury Bay Control 7.8 mi NNW CF Plymouth County Farm 3.5 mi W PP Powder Point Control 8.0 mi NNW WF Whitman Farm Control 21 mi WNW GH Gre.n Harbor Control 9.9 mi NNW IRISH MOSS CRANBERRIES DIS Discharge Canal 0.21 mi N MR Manomet Pt. Bog 2.4 mi SE MP Manomet Point 2.2 mi ESE BT *artlett Rd. Bog 2.7 mi SSE EL E111sville 7.9 mi SSE PS Pine St. Bog Control 16 mi WNW BK Brant Rock Control 10 mi NNW AMERICAN LOBSTER VEGETABLES DIS Discharge Canal 0.21 mi N CF Plymouth County Farm 3.5 mi W PLY-H Plymouth Harbor 4.0 mi WNW BF Bridgewater Farm Ctrl 19 mi W DUX-BAY Duxbury Bay Control 7.1 mi NNW RH Rocky Hill Road 0.5 mi SE PLB Plymouth Beach 2.5 mi W BK Brook Road 1.8 mi SSE BD Beaverdam Road 2.1 mi S FISHES CH Clay Hill Road 1.0 mi W j

DIS Discharge Canal 0.21 mi N BA Site Boundary A 0.9 mi SSW j PLB Plymouth Beach 2.5 mi W BB Site Boundary B 0.2 mi ESE l

JR Jones River Control 7.8 mi WNW BC Site Boundary C 0.2 mi SW l CC-BAY Cape Cod Bay Control 15 mi E NC Norton Control 31 mi W NR N River-Hanover Control 15 mi NNW j CA Cataumet Control 20 mt SSW

{

PT Provincetown Control 20 mi NE BB Buzzards Bay Control 25 mi SSW PC Priest Cove Control 30 mi SW FORAGE NS Nantucket Sound Control 30 mi SSE CF Plymouth County Farm 3.5 mi W A0 Atlantic Ocean Control 30 mi E WF Whitman Farm Control 21 mi WNW MV Vineyard Sound Control 40 mi SSW WH Whipple Farm 1.8 mi SW O Distance and direction are measured from the ce terline of the reactor to the sampling / monitoring location.

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Page 64

Figure 2.2-4 (cont.)

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Page 65 Edk!N

Figure 2.2-5 Environmental Sampling And Measurement Control Locations t

[sst.e Description Dist.* Dir.* Code Descriotion Dist.* Dir.*

i AIR SAMPLE T1,D EU East Weymouth 25 mi NW KS Kingston Subst 10 mi WNW LR Landing Road 10 mi NNW ,

SEDTMENT CS Cedarville Sub 9.9 mi S GH Green Harbor Control 10 mi NNW CW Church & West 10 mi NW DUX-BAY Duxbury Bay Control 8.7 mi NNW MM Main & Meadow 11 mi WSW DMF Div. Mar. Fish 13 mi SSE EW East Weymouth Sub 25 mi NW SURFACE WATER M PP Powder Point Control 7.9 mi NNW WF Whitman Farm Control 21 mi WNW SHELLFISH CRANBERRIES r DUX-BAY Duxbury-Bay Control 7.B mi NNW PS Pine St. Bog Control 16 mi WNW r PP Powder Point Control P.0 mi NNV '

GH Green Harbor Control 9.9 mi NNW IRISH MOSS VEGETABLES / VEGETATION BK Brant Rock Control 10 mi NNW BF Bridgewater Farm Control 19 mi W NC Norton Control 31 mi W AMERICAN LOBSTER FORAGE DUX-BAY Duxbury Bay Control 7.1 mi NNW WF Whitman Farm Control 21 mi WNW FISHES JR Jones River Control 7.8 mi WNW CC-BAY Cape Cod Bay Control 15 mi E NR N. River Hanover Control 15 mi NNW CA Cataumet Control 20 mi SSW PT Provincetown Control 20 mi NE BB Buzzards Bay Control 25 mi SSW PC Priest Cove Control 30 mi SW NS Nantucket Sound Control 30 mi SSE A0 Atlantic Ocean Control 30 mi E MV Vineyard Sound Control 40 mi SSW o Distance and direction are measured from the centerline of the reactor to the sampling / monitoring location.

Page 66

Figure 2.2 5 (cont.)  ;

SYMBDL KEY:

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PILGB NUCIIAR POER STAT!0N i k ENVIRONMENTAL SAMPUNG AND MEASUREMENT CONTROL LOCATIONS Page 67 i

l FIGURE 2.4-1 HISTORICAL BEACH SURVEY EXPOSURE RATE -

MEASUREMENTS  :

Rom April 1977'Ihrough December 1994  !

14 14 {

12 -- -12  !

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. O I 1977 1979 1981 1983 1985 1987 1989 1991 1993  !

v o Whitehorse Beach at Hilltop Avenue

-v- Priscilla Beach at Full Sall Bar I e Plymouth Beach - Outer i 1

-o- Plymouth Beach -Inner  !

Plymouth Beach at Berts x- Duxbury Beach Control Page 68 )

FIGURE 2.5-1 AIRBORNE GROSS-BETA RADIOACTIVITY LEVELS: NEAR STATION 0.08 0.08 0.06- -0.06 3 _

$ ^

2 0.04- -0.04 l 8  !

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-f3- AP-00 Warehouse  !

--v - AP-07 Pedestrian Bridge

-e- AP-08 Overlook Area

! -o- AP-09 East Breakwater

-x- AP-21 East Weymouth Control l

l l

Page 69

1 l

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FIGURE 2.5-2 AIRBORNE GROSS-BETA RADIOACTIVITY LEVELS: PROPERTY LINE 0.08 0.08

- t

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-v- AP-03 W. Rocky Hill Road

- AP-06 Property Line

--x- AP-21 East Weymouth Control l

i Page 70

h J

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FIGURE 2.5-3 AIRBORNE GROSS-BETA RADIOACTIVITY LEVELS: OFF-SITE ,

t 0.08 0.08 ,

e l

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-o- AP-10 Cleft Rock

-v- AP-15 Plymouth Center

-n--- AP-17 Manomet Substation

+ AP-21 East Weymouth Control t

Page 71

I FIGURE 2.7-1 ,

i i

LEVELS OF STRONTIUM - 90 IN MILK SAMPLES i 15 15 ,

12- -

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I 1994 i

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-x- TM-21 Whitman Farm Control 1 h

Page 72

I FIGURE 2.7-2 LEVELS OF CESIUM-137 IN MILK SAMPLES 15 15

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l l'

Page 73

r 3.0

SUMMARY

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

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 1994 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) external radiation from the ocean during boating and swimming; and

3) ingestion of fish and shellfish.

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

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

2) inhalation of airborne radioactivity;

3) external radiation from soil deposition;

4) consumption of vegetables; and

5) consumption of milk and meat.

The results from the dose calculations based on PNPS operations are presented in Table 3.0-1. The dose assessment data presented was taken from the " Annual Dose Assessment to the General Public from Radioactive Effluents" report for the period of January 1 through December 31, 1994.

Page 74

Table 3.0-1 ,

Radiation Doses from 1994 Pilgrim Station Operations Maximum Individual Dose From Exposure Pathway - mrem /yr Liquid Gaseous Direct Receptor Effluents Effluents

• Radiation ** Total Total Body 0.0002 1.3 1.5 2.8 Thyroid 0.00008 2.8 1.5 4.3 3 Max. Organ 0.0003 2.8 1.5 4.3 )

l 1

• Gaseous effluent exposure pathway includes combined dose from particulates, )

iodines and tritium in addition to noble gases.

N Direct radiation dose for the hypothetical maximum-exposed individual at a location on Boston Edison property yielding highest direct radiation exposure i value as measured with TLDs.

Two federal agencies establish dose limits to protect the public from radiation and radioactivity. The Nuclear Regulatory Commission (NRC) specifies a whole i body dose limit of 100 mrem /yr to be received by the maximum exposed member of the general public. This limit is set forth in Section 1301, Part 20, Title 10, ,

of the U.S. Code of Federal Regulations (10CFR20). By comparison, the I Environmental Protection Agency (EPA) limits the annual whole body dose to 25 mrem /yr, which is specified in Section 10, Part 190, Title 40, of the Code of Federal Regulations (40CFR190).

Another useful " gauge" of radiation exposure is provided by the amount of dose a typical individual receives each year from natural and man-made (eg. 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 1994, 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.

l A second method of dose estimation involves calculations based on radioactivity detected in environmental media. During 1994, soil was the only exposure pathway sample that contained detectable radioactivity potentially attributable to PNPS operations. The low levels of cobalt-60 detected in soil would present a dose contribution of about 0.007 mrem to the maximum exposed hypothetical individual.

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

Page 75

4.0 REFERENCES

1

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

1

2. Donald T. Oakley, " Natural Radiation Exposure in the United States."  !

U. S. Environmental Protection Agency, ORP/SID 72-1, June 1972.

3. National Council on Radiation' Protection and Measurements, Report No. 93,

" Ionizing Radiation Exposures of the Population of the United States,"

September 1987.

4. United States Nuclear Regulatory Commission, Regulatory Guide 8.29, '

" Instructions Concerning Risks from Occupational Radiation Exposure,"

Revision 0, July 1981.

5. Boston Edison Company, " Pilgrim Station" Public Information Brochure 100M,

, WNTHP, September 1989.

6. United States Nuclear Regulatory Commission, Regulatory Guide 1.109, i

" Calculation of Annual Doses to Man from Routine Releases of Reactor  !

Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, ,

Appendix I," Revision 1, October 1977.

7. Boston Edison Company, Pilgrim Nuclear Power Station Off-site Dose Calculation Manual, Revision 6, August 1994.  ;

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

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

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

l

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

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

13. International Commission of Radiological Protection, Publication No. 43,

" Principles of Monitoring for the Radiation Protection of the Population,"

May 1984.

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

Revision 3, September 1982.

1 Page 76 l i

l 1

'4.0 EffERENCES (continued) l

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

November 1979.  !

t

16. Settlement Agreement Between Massachusetts Wildlife Federation-and Boston '

Edison Company Relating to Off-site Radiological Monitoring - June 9,1977.

17. J. E. Vossahlik, Yankee Atomic Electric Company, Computer Program "ERMAP,"  ;

Version 3.1 - January 9, 1979. j

18. E. R. Cumming, Yankee Atomic Electric Company, "1994 Annual Direct  ;

Radiation Survey at Beaches Near Pilgrim Station," REG 6/95, January 16, 1995. ';

i i

l i

l I

I i

l l

l l

Page 77

APPENDIX A l i

4 SPECIAL STUDIES l S0ll RADI0 ACTIVITY DOSE IMPACT During 1994, samples of soil were collected at the eleven designated survey sites. l Semples of topsoil were collected at each site, and where possible, soil cores were  !

collected for depth-incremental analyses. A total of 35 samples were collected and  !

enalyzed by gamma spectroscopy.  ;

Cobalt-60 was detected in three samples collected from three different locations on  :

Boston Edison property adjacent to Pilgrim Station. The highest concentration of 117 [

pCi/kg was observed in the 15-20 cm (6-8 in.) depth increment collected at the t Warehouse (WS) location near the Fabrication Shops. Topsoil and all other depth ,

increments collected at this location contained no detectable Co-60.

Due to the absence of Co-60 in the topsoil and other depth increments at this location, l it is unlikely that the cobalt-60 detected arose from releases which occurred during [

1994. Rather, the activity observed was probably due to material which was released i and deposited from operations of PNPS in past years.  !

The Co-60 in soil represents an external exposure pathway. Since soil is not ingested, no internal exposure pathways directly exist from the soil. Dose assessment methods i outlined in the PNPS ODCM and Regulatory Guide 1.109 were used to calculate the i external radiation dose to the hypothetical maximally exposed individual. Such an  :

individual is assumed to stand on soil containing Co-60 at the average concentration  !

observed at location WS. The following values were obtained from Regulatory Guide  !

1.109 and were assumed in the dose assessment: l 2

External dose conversion factor: 1.7E-8mgem/hr/pci/m j Areal density of soil: 240 kg/m j When coupled with the observed mean concentration of 44 pC1/kg and an exposure time of 40 hr/yr for a site on Boston Edison property, a maximum dose rate of 7.2E-3 mrem /yr -

was calculated. In actuality, the dose would be lower due to the additional shielding provided by the 15 cm (6 inches) of soil overlying the deposited activity. -

In conclusion, the very low level of cobalt-60 observed in soil on Boston Edison  !

property would result in a negligible increase of about 0.007 mrem over the typical ,

exposure of 300-400 mrem received each year by the average individual i

'l i

l Page 78

. - ..- .- . - . - . ~ . . . . - - . . ~ . .

APPENDIX B- 'l EFFLUENT RELEASE INFORMATION l

I Table Paae  ;

-- . Supplemental Information: January-June 1994 80 ,

L

.lA' Gaseous Effluents Summation of All Releases: 81 }

January-June 1994 IB Gaseous Effluents - Elevated Release: 82 [

January-June 1994 j IC Gaseous Effluents - Ground Level Release: 83  !

January-June 1994 2A Liquid Effluents Summation of All Releases: 84 i January-June 1994 l 2B Liquid Effluents: January-June 1994: 85  !

I Supplemental Information: July-December 1994 86 l 1A Gaseous Effluents Summation of All Releases: 87 July-December 1994 IB Gaseous Effluents - Elevated Release: 88 l July-December 1994 ,

1C Gaseous Effluents'- Ground Level Release: 89  !

July-December 1994 i i

2A Liquid Effluents Summation of All Releases: 90 July-December 1994 l

2B Liquid Effluents: July-December 1994 91 j l

l i

l Page 79  !

)

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~

\

PILGRIM NUCLEAR POWER STATION l EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT l SUPPLEMENTAL INFORMATION 1994 January'- June 1994 )

Facility Pilarim Nuclear Power Station Licensee DPR-35

1. Regulatory Limits.

a. Fission and activation gases: 500 mrem /yr total body and 3000 mrem /yr i for skin at site boundary. i b,c. Iodines, particulates with l half-lives >8 days, tritium: 1500 mrem /yr to any organ at site boundary. i

d. Liquid effluents: 0.06 mrem / month for total body and  ;

0.20 mrem / month for any organ (without radwaste treatment).

2. Maximum Permissible Concentration j

a. Fission and activation gases: 10 CFR 20 Appendix B Table II

b. Iodines: 10 CFR 20 Appendix B Table II

c. Particulates, half-lives >8 days: 10 CFR 20 Appendix B Table II

d. Liquid effluents: 2E-4 Ci/ml for entrained noble gases; 10CFR20 Appendix B Table II values for all other radionuclides.

3. Average Energy: Not applicable j

4. Measurements and Approximations of Total Radioactivity

a. Fission and activation gases: High-purity Ge gamma spectroscopy for

b. Iodines: all gamma emitters; radiochemistry i

c. Particulates: analysis for H-3, Fe-55 (liquids only), ii

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

5. Batch Releases  ;

Quarter i

a. Liquid: 1st 2nd

l. Number of batch releases: 20 22

2. Total time period for batch releases (minutes): 1.40E+3- 1.67E+3 ,

3. Maximum time period for a batch release (minutes): 2.40E+2 3.15E+2 l

4. Average time period for batch releases (minutes): 6.98E+1 7.57E+1

5. Minimum time period for a batch release (minutes): 2.50E+1 2.50E+1

6. Average stream flow during periods of release of i effluents into a flowing stream (liter;/ min): 1.14E+6 1.14E+6

b. Gaseous: Not applicable -

6. Abnormal Releases .

t

a. Liquid: None

b. Gaseous: One l Page 80

TABLE lA '

PILGRIM NUCLEAR POWER STATION ,

' EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1994 GASE0US EFFLUENTS-SUMMATION OF ALL RELEASES January - June 1994 ,

Quarter Quarter Est. Total Unit 1st 2nd Error %

A. Fission and Activation Gases '

l. Total release Ci 5.47E+2 5.30E+2 22% l

2. Averaae release rate for period uCi/sec 6.94E+1 6.72E+1

3. Percent of Technical Specification limit  % * * <

B. Iodines

1. Total iodine-131 release Ci ' 3.77E-3 5.llE-3 20% l  ;

2. Averaae release rate for period uCi/sec 4.78E-4 6.48E-4 +

3. Percent of Technical Specification limit  % *

• l C. Particulates

1. Particulates with half-lives >8 days Ci 2.61E-3 2.45E-3 21% l

2. Averaae release rate for period uCi/sec 3.31E-4 3.llE-4

3. Percent of Technical SDecification limit  % * *

4. Gross alpha radioactivity Ci NDA NDA ,

l l

D. Tritium

l. Total release rate for oeriod Ci 8.45E+0 7.78F+0 20% l ,

2. Averaae release rate for period uCi/sec 1.07E+0 9.87E-1 l

3. Percent of Technical SDecification limit  %

• j

• Notes for Table IA:

• Percent of Technical Specification Limit Values in Sections A.3, B.3, C.3, and D.3 1 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, 1995.

1. NDA is no detectable activity.

2. LLD for gross alpha listed as NDA is lE-11 pCi/ml.

Page 81

TABLE IB PILGRIM NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1994

'GASE0US EFFLUENTS-ELEVATED RELEASE January - June 1994 CONTINUOUS MODE BATCH MODE Nuclides Released Unit Ouarter Quarter Quarter Quarter 1st 2nd N/A N/A )

I

1. Fission and Activation Gases  !

N-13 Ci NDA 3.59E+0 Kr-85m Ci 2.75E+1 5.15E+1 Kr-87 Ci 2.63E+1 2.72E+1 Kr-88 Ci 4.09E+1 7.25E+1 Xe-133 Ci 2.76E+1 6.80E+1 Xe-135 Ci 5.27E+1 4.46E+1 Xe-135m Ci 2.08E+1 2.33E+1 Xe-138 Ci 7.26E+1 1.08E+2  ;

Total for period Ci 2.68E+2 3.99E+2

2. Iodines I-131 Ci 1.89E-3 2.82E-3 I-133 Ci 9.12E-3 1.49E-2 Total for Derind Ci 1.10E-2 1.77E-2

3. Particulates Sr-89 Ci 3.22E-4 6.10E-4 Sr-90 Ci NDA 2.12E-6 Cs-134 Ci NDA NDA Cs-137 Ci 1.95E-6 1.16E-5 Ba/La-140 Ci 4.34E-4 8.17E-4 Total for period Ci 7.58E-4 1.44E-3

4. Tritium l H-3 I Ci l 2.04E-1 l 2.52E-1 l l l Notes for Table 1B:  ;

1. NDA is no detectable activity.

2. LLDs for nuclides listed as NDA are as follows:

Fission gases: lE-4 pCi/ml lodines: lE-12 pCi/ml Particulates: 1E-Il pCi/ml Page 82

TABLE 10 PILGRIM NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1994 GASE0US EFFLUENTS-GROUND LEVEL RELEASE January - June 1994 CONTINUOUS MODE BATCH MODE Nuclides Releayed Unit Ouarter Guarter Quarter Ouarter 1st 2nd N/A N/A

1. Fission and Activation Gases Kr-85m Ci 1.25E+0 NDA Kr-87 Ci 8.72E+0 NDA Kr-88 Ci 4.98E+0 NDA Xe-133 Ci NDA NDA Xe-135 Ci 1.62E+2 1.31E+2 Xe-135m Ci 1.99E+1 NDA Xe-138 Ci 8.09E+1 NDA Total for oeriod Ci 2.78E+2 1.31E+2

2. Iodines 1-131 Ci 1.88E-3 2.29E-3 i ___ I-133 Ci 1.62E-2 1.96E-2

[-' al for period Ci 1.81E-2 2.19E-2

3. Particulates Co-60 Ci NDA 5.39E-6 Sr-89 .Ci 1.10E-3 4.82E-4 Sr-90 Ci NDA NDA Cs-134 Ci NDA NDA Cs-137 C1 1.06E-5 4.69E-6 Ba/La-140 Ci 7.42E-4 5.14E-4 Total for period Ci 1.85E-3 1.01E-3

4. Tritium l H-3 I Ci l 8.25E+0 l 7.53E+0 l l l Notes for Table IC:

1. NDA is no detectable activity.

2. LLDs for nuclides listed as NDA are as follows:

Fission gases: 1E-4 pCi/ml lodines: lE-12 pCi/ml Particulates: lE-ll pCi/ml

)

Page 83 .

l

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TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1994 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES January - June 1994 Quarter Quarter Est. Total Unit 1st 2nd Error.%

1 A. Fission and Activation Products

1. Total release (not including tritium, i noble aases, or aloha) Ci 3.40E-4 2.52E-4 12%

2. Average diluted concentration durina period uCi/ml 4.97E-10 3.70E-10

3. Percent of Effluent Concentration Limit *  % 1.65E-2 1.67E-2 B. Tritium

1. Total release Ci 9.74E-2 1.31E-1 9.4% l

2. Average diluted concentration durina period uCi/ml 1.42E-7 1.93E-7 i

3. Percent of Effluent Concentration Limit *  % 1.42E-2 1.93E-2 l C. Dissolved and Entrained Gases

1. Total release Ci NDA NDA 5.7% l

2. Average release rate for period durina period uCi/ml NDA NDA

3. Percent of Effluent Concentration Limit *  % 0.00E+0 0.00E+0 D. Gross Alpha Radioactivity l 1. Total release l Ci l NDA l NDA l 5.7% l E. Volume of Waste Released (prior to dilution) I liters l1.81E+5 12.38Ed l 5.7% l F. Volume of Dilution Water Used Durino Period I litersl6.84E+8 16.81E+8 l 10% l Notes for Table 2A:

• Additional percent of Technical Specification Limit Values based on resulting dose will be provided in the annual supplemental dose assessment report to be issued

, prior to April 1, 1995.

1. NDA is no detectable activity.

2. LLD for gross alpha listed as NDA is lE-7 pCi/ml,

3. LLD for dissolved and entrained gases listed as EA is lE-5 pCi/ml.

Page 84

TABLE 2B PILGRIM NUCLEAR POWER STATION 1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1994 ,

LIQUID EFFLUENTS  !

January - June 1994 l CONTINU0US MODE BATCH MODE Nuclides Released i Unit Ouarter l Ouarter Quarter Quarter Not ADDlicable lSt 2nd

1. Fission and activation products ,

l Cr-51 Ci N/A N/A 8.77E-7 NDA Mn Ci N/A N/A 2.92E-5 1.49E-5 Fe-55 Ci N/A N/A 7.16E-5 4.47E-5 l Fe-59 Ci N/A N/A NDA NDA I' Co-58 Ci N/A N/A 4.68E-6 NDA Co-60 Ci N/A N/A 1.72E-4 1.26E-4 Zn-65 Ci N/A N/A NDA NDA Sr-89 Ci N/A N/A 1.25E-5 1.78E-6 Sr-90 Ci N/A N/A 3.35E-6 5.49E-6 Zr/Nb-95 Ci N/A N/A NDA NDA Mo-99/Tc-99m Ci N/A N/A NDA NDA Aa-110m Ci N/A N/A NDA NDA Sb-122 Ci N/A N/A NDA NDA 1-131 Ci N/A N/A NDA NDA 1-133 Ci N/A N/A NDA NDA Cs-137 Ci N/A N/A 4.57E-5 5.95E-5 Ba/La-140 Ci N/A N/A NDA NDA Ce-141 Ci N/A N/A NDA NDA Total for period Ci N/A N/A 3.40E-4 2.52E-4

2. Dissolved and entrained gases Xe-133 Ci N/A N/A NDA NDA Xe-135 Ci N/A N/A NDA NDA Total for oeriod Ci N/A '/A

. NDA NDA Notes for Table 28:

1) NDA is no detectable activity.

2) LLDs for nuclides listed as NDA are as follows:

Sr-89 SE-8 pCi/ml I-131 lE-6 pCi/ml Xe-133, Xe-135 1E-5 pCi/ml i All others SE-7 pCi/ml Page 85

PILGRIM NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION 1994 July - December 1994 Facility Pilarim Nuclear Power Station Licensee 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. Iodines, particulates with half-lives >8 days, tritium: 1500 mrem /yr to any organ at site boundary.

d. Liquid effluents: 0.06 mrem / month for total body and 0.20 mrem / month for any organ (without radwaste treatment).

2. Effluent Concentration Limits l

a. Fission and activation gases: 10 CFR 20 Appendix B Table II i b. lodines: 10 CFR 20 Appendix B Table II l c. Particulates, half-lives >8 days: 10 CFR 20 Appendix B Table II

d. Liquid effluents: 2E-4 yCi/ml for entrained noble gases; 10CFR20 Appendix B Table II values for all i

other radionuclides.

3. Average Energy: Not applicable

4. Measurements and Approximations of Total Radioactivity

a. Fission and activation gases: High-purity Ge gamma spectroscopy for

b. Iodines: all gamma emitters; radiochemistry

c. Particulates: analysis for H-3, Fe-55 (liquids only),

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

5. Batch Releases Quarter

a. Liquid: 3rd 4th

1. Number of batch releases: 20 22

2. Total time period for batch releases (minutes): 2.19E+3 9.52E+2

3. Maximum time period for a batch release (minutes): 2.40E+2 1.62E+2

4. Average time period for batch releases (minutes): 1.09E+2 4.33E+1

5. Minimum time period for a batch release (minutes): 2.50E+1 2.00E+1

6. Average stream flow during periods of release of effluents into a flowing stream (liters / min): 8.81E+5 7.30E+5

b. Gaseous: Not applicable

6. Abnormal Releases

a. Liquid: None

b. Gaseous: None Page 86

TABLE 1A PILGRIM NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1994 GASE0US EFFLUENTS-SUMMATION OF ALL RELEASES July - December 1994 ,

l Quarter Quarter Est. Total Unit 3rd 4th Error %

A. Fission and Activation Gases

1. Total release Ci 3.37E+02 4.41E+02 22% l

2. Averaae release rate for oeriod uCi/sec 4.28E+01 5.60E+01

3. Percent of Technical Specification limit  % *

• B. Iodines

[1. Total iodine-131 release Ci 3.71E-03 8.02E-04 20% l

2. Averaae release rate for period uCi/sec 4.70E-04 1.02E-04

3. Percent of Technical SDecification limit  % *

• l C. h'rticulates

1. P articulates with half-lives >8 days Ci 9.99E-04 6.27E-04 21% l A ;.verage release rate for period uCi/sec 1.27E-04 7.95E-05

3. Percent of Technical Specification limit  % * *

4. Gross alpha radioactivity Ci NDA NDA D. Tritium j

1. Total release rate for period Ci 1.43E+01 5.51E+00 20% l

2. Averaae release rate for Deriod uCi/sec 1.81E-00 6.99E-01

3. Percent of Technical Soecification limit  % *

• Notes for Table IA:

• Percent of Technical Specification Limit Values in Sections A.3, B.3, C.3, and D.3 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, 1995.

1. NDA is no detectable activity.

2. LLD for gross alpha listed as NDA is lE-11 Ci/ml.

l l

I Page 87

TABLE 1B PILGRIM NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1994 GASE0US EFFLUENTS-ELEVATED RELEASE July - December 1994 CONTINU0US MODE BATCH MODE Nuclides Released Unit Ouarter Guarter Quarter Quarter 3rd 4th N/A N/A

1. Fission and Activation Gases Kr-85m Ci 4.39E+01 7.50E+01 Kr-87 Ci 6.15E+00 8.01E+01 Kr-88 Ci 5.39E+01 1.81E+02 Xe-133 Ci 6.40E+01 2.70E+01 Xe-135 Ci 8.59E+00 3.01E+01 Xe-135m Ci 6.83E+00 NDA Xe-138 Ci 2.25E+01 6.90E+00 Total for period Ci 2.06E+02 4.00E+02

2. Iodines 1-131 Ci 1.74E-03 6.15E-04 I-133 Ci 9.50E-03 5.56E-03 Total for period Ci 1.12E-02 6.18E-03 ,

3. Particulates Mn-54 Ci NDA NDA Co-60 Ci NDA NDA Sr-89 Ci 2.52E-05 5.65E-05 Sr-90 Ci NDA NDA Cs-134 Ci NDA NDA Cs-!37 Ci 8.47E-06 NDA Ba/La-140 Ci 1.87E-04 1.03E-04 Total for period Ci 2.21E-04 1.60E-04 l

4. Tritium l H-3 I Ci  ! 3.69E-Oll 2.89E-Oll l l J

Notes for Table 1B:

1. NDA is no detectable activity.

2. LLDs for nuclides listed as NDA are as follows:

Fission gases: lE-4 pCi/ml lodines: lE-12 pCi/ml Particulates: lE-Il pCi/ml Page 88 -

TABLE IC PILGRIM NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1994 GASEOUS EFFLUENTS-GROUND LEVEL RELEASE July - December 1994 CONTINUOUS MODE BATCH MODE Nuclides Released Unit Ouarter Quarter Quarter Quarter 3rd 4th N/A N/A

1. Fission and Activation Gases Kr-85m Ci NDA NDA Kr-87 Ci NDA NDA Kr-88 Ci NDA NDA Xe-133 Ci NDA NDA Xe-135 Ci 1.31E+02 4.llE+01 Xe-135m Ci NDA NDA Xe-138 Ci NDA NDA Total for period Ci 1.31E+02 4.llE+01

2. Iodines I-131 Ci 1.97E-03 1.87E-04 I-133 Ci 1.49E-02 2.05E-03 Total for period Ci 1.69E-02 2.24E-03

3. Particulates Sr-89 Ci 1.91E-04 3.40E-04 Sr-90 Ci NDA NDA Cs-134 Ci NDA NDA Cs-137 Ci NDA 2.04E-06 Ba/La-140 Ci 5.87E-04 1.25E-04 Total for period Ci 7.78E-04 4.67E-04

/

4. Tritium l H-3 I Ci l 1.39E+0ll 5.22E+001 l l Notes for Table IC:

1. NDA is no detectable activity.

2. LLDs for nuclides listed as NDA are as follows:

Fission gases: lE-4 pCi/ml Iodines: lE-12 pCi/ml Particulates: IE-11 pCi/ml Page 89 _a

TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1994  ;

LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES July - December 1994 Quarter Quarter Est. Total Unit 3rd 4th Error.%

A. Fission and Activation Products 1

1. Total release (not including tritium,  ;

noble cases, or aloha) Ci 1.78E-03 3.59E-04 12%

2. Average diluted concentration durina period uCi/ml 9.24E-10 5.17E-10

3. Percent of Effluent Concentration Limit *  % 4.82E-02 2.87E-02

8. Tritium

1. Total release Ci 1.48E-01 5.61E-01 9.4% l

2. Average diluted concentration curina ceriod uCi/ml 7.67E-08 8.07E-07

3. Percent of Effluent Concentration Limit *  % 7.67E-03 8.07E-02

C. Dissolved and Entrained Gases

l. Total release Ci NDA NDA 16% l

2. Average release rate for period durina period uCi/ml NDA NDA

3. Percent of Effluent Concentration Limit *  % 0.00E+0 0.00E+0 D. Gross Alpha Radioactivity l 1. Total release I Ci i NDA l NDA l 34% l E. Volume of Waste Released (prior to dilution) I liters l3.33E+05l1.98E+05l 5.7% l F. Volume of Dilution Water Used Durina Period I litersil.93E+0916.95E+081 10% l Notes for Table 2A:

Additional percent of Technical Specification Limit Values based on resulting dose will be provided in the annual supplemental dose assessment report to be issued prior to April 1, 1995.

1. NDA is no detectable activity.

2. LLD for gross alpha listed as NDA is lE-7 pCi/ml.

3. LLD for dissolved and entrained gases listed as NDA is 1E-5 Ci/ml.

Page 90

TABLE 2B PILGRIM NUCLEAR POWER STATION EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1994 LIQUID EFFLUENTS July - December 1994 CONTINU0US MODE BATCH MODE Nuclides Released i Unit Ouarter l Ouarter Quarter Quarter ,

Not ADD 11 cable 3rd 4th

1. Fission and activation products Cr-51 Ci i N/A N/A NDA NDA Mn-54 Ci N/A N/A 7.43E-06 9.65E-06 Fe-55 Ci N/A N/A 4.79E-05 6.38E-05 Fe-59 Ci N/A N/A NDA NDA Co-58 Ci N/A N/A NDA NDA Co-60 Ci N/A N/A 3.37E-04 1.27E-04

Zn-65 Ci N/A N/A NDA NDA l Sr-89 Ci N/A N/A 7.49E-04 6.78E-06 Sr-90 Ci N/A N/A 8.12E-05 3.84E-06 Zr/Nb-95 Ci N/A N/A NDA NDA Mo-99/Tc-99m Ci N/A N/A NDA NDA l Ru-103 Ci N/A N/A NDA NDA Aa-110m Ci N/A N/A NDA NDA l I-131 Ci N/A N/A NDA NDA Cs-134 Ci N/A N/A 1.22E-06 NDA Cs-137 Ci N/A N/A 5.59E-04 1.48E-04 Ba/La-140 Ci N/A N/A 1.40E-06 NDA Ce-141 Ci N/A N/A NDA NDA Ce/Pr-144 Ci N/A N/A NDA NDA Total for period Ci N/A N/A 1.78E-03 3.59E-04

2. Dissolved and entrained gases Xe-133 Ci N/A N/A NDA NDA Xe-135 Ci N/A N/A NDA NDA Total for period Ci N/A N/A NDA NDA Notes for Table 28:

1) NDA is no detectable activity.

2) LLDs for nuclides listed as NDA are as follows:

Sr-89 SE-8 pCi/ml I-131 lE-6 pCi/ml I Xe-133, Xe-135 lE-5 pCi/ml All others SE-7 pCi/ml l

l Page 91

APPENDIX C j LAND USE CENSUS RESULTS 1

The annual land use census for gardens and milk and meat animals in the vicinity of I Pilgrim Station was performed between October 28 and 31, 1994. The census was conducted by driving along each improved road / street in the Plymouth area within three 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 three miles (SSW and NNW sectors), the survey was extended to five miles. A total of 32 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.

j Atmospheric deposition (D/Q values) at the locations of the identified gardens were compared to those for the existing sampling program locations. These comparisons enabled 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 identified during the 1994 land use census, samples of garden-grown vegetables or naturally-growing vegetation (e.g. grass, leaves from i bushes or trees, etc.) were collected at or near the closest gardens in each of the following landward compass sectors. These locations, and their distance and direction relative to the PNPS Reactor Building, are as follows:

Rocky Hill Road 0.54 mi SE Brook Road 1.76 mi SSE Beaverdam Road 2.14 mi S Clay Hill Road 1.02 mi W In addition to these special sampling locations identified and sampled in conjunction with the 1994 land use census, samples were in also collected at or near the Plymouth County Farm (3.5 mi W), Whipple Farm (1.8 mi SW), and from the control location at Bridgewater Farm (19 mi W).

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

Highest Main Stack D/Q: 0.91 mi SSW Highest Reactor Building Vent D/Q: 0.21 mi ESE 2nd highest D/Q, both release points: 0.22 mi SW No new milk or meat animals were identified during the land use census. In addition, the Town of Plymouth Animal Inspector stated that their office is not aware of any animals at locations other than the Plimoth Plantation and the Plymouth County Farm.

Samples of milk and forage have historically been collected from the Plymouth County Farm and were part of the 1994 sampling program.

Page 92

APPENDIX D ENVIRONMENTAL MONITORING PROGRAM DISCREPANCIES There were a number of instances during 1994 in which problems were encountered in the collection of environmental samples. Most of these problems were minor in nature and did not have an adverse affect on the results or integrity of the monitoring program.

Details of these various problems are given below.

In 1994, six thermoluminescent dosimeters (TLDs) were not recovered from their assigned locations during the quarterly retrieval process. During the first quarter, TLDs were not recovered at Hyannis Road (HR) and an onsite location on the fence near the Office and Maintenance Building (P08). In the case of location P08, the fence to which the TLD had been attached had been replaced. At location HR, the plastic enclosure and its enclosed TLD were missing. During the second quarter, TLDs were not recovered at Manomet Beach (MB), Emerson Road (EM), and Station D. In all three cases, the plastic housing holding the TLDs were also missing. During the third quarter, the TLD enclosure at Emerson and Priscilla (EP) was also missing. The specific causes for

'~~

these losses could not be identified, but losses could potentially be attributed to vandalism or normal weathering of the plastic enclosures. 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 airborne sampling locations during 1994. Most of these interruptions were due to short-term power losses and were sporadic and of limited duration (less than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> out of the weekly sampling period). Such events did not have any significant impact on the scope and purpose of the sampling program, and all lower limits of detection (LLDs) were met for both particulates and iodine-131 on the filters.

In addition to the short-term interruptions, there were several instances where equipment malfunctions or power outages affected more than one sampling station or resulted in missing more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of sampling capability out of the weekly (168 hour0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br />) period. In those cases involving equipment failure, the sampling rack was changed out and replaced with an operational unit. Pump malfunction was attributed to a brief sampling loss at East Rocky Hill (148 hour0.00171 days <br />0.0411 hours <br />2.44709e-4 weeks <br />5.6314e-5 months <br /> run time) between 15-Nov-94 and 22-Nov-94.

When sampling interruptions resulted from power losses, steps were taken to restore power as soon as possible. Continued construction activitier in the new parking lot at Pilgrim Station caused interruptions to power and loss of sampling at the East Breakwater (EB) sampling station twice during 1994. Power was interrupted on 04-Jan-94 and restored on 17-Jan-94, affecting the sampling periods of 28-Dec-93 to 05-Jan-94 (174 hour0.00201 days <br />0.0483 hours <br />2.876984e-4 weeks <br />6.6207e-5 months <br /> run time out of 196 hour0.00227 days <br />0.0544 hours <br />3.240741e-4 weeks <br />7.4578e-5 months <br /> sampling period); 05-Jan-94 to 11-Jan-94 (0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> run time: no samples collected); and ll-Jan-94 to 18-Jan-94 (144 hour0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> run time).

Power was again interrupted at East Breakwater during the period of 03-May-94 to 10-May-94 (144 hour0.00167 days <br />0.04 hours <br />2.380952e-4 weeks <br />5.4792e-5 months <br /> run time) when a backhoe dug up the underground service. The service was repaired within one day of the incident.

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1 An apparent power loss of unknown origin resulted in sampling of a lower than normal volume of air at the Pedestrian Bridge during the period 28-Dec-93 to 05-Jan-94. While the pump was running at the time of filter collection, the volume of air sampled indicated an estimated run time of approximately 148 hours0.00171 days <br />0.0411 hours <br />2.44709e-4 weeks <br />5.6314e-5 months <br /> out of the 196 hour0.00227 days <br />0.0544 hours <br />3.240741e-4 weeks <br />7.4578e-5 months <br /> period.

Another power interruption of unknown nature occurred at the Overlook Area sampler during the period of 13-Sep-94 to 20-Sep-94 resulted in a run time of 116 hours0.00134 days <br />0.0322 hours <br />1.917989e-4 weeks <br />4.4138e-5 months <br />.

Again, the pump was running at the time of filter collection, and a specific cause of the power interruption could not be identified.

Despite the lower-than-normal sampling volumes in the various instances involving power interruptions and equipment failures, all required .LDs were met on the 571 particulate filters and 571 iodine cartridges collected during 1994. None of the 1186 sample analyses performed indicated any questionable or anomalous results. When viewed collectively during the entire year of 1994, the following sampling recoveries were l achieved in the airborne sampling program:

Location Recovery Location Recovery Location Recovery WS 99.9% PB 99.9% PC 100.0%

ER 99.8% OA 99.3% MS 100.0%

WR 100.0% EB 97.6% EW 100.0%

PL 100.0% CR 100.0%

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 j airborne releases from PNPS. Such samples represent " worst case" samples for comparison, as the deposition and resulting ground-level concentrations of radionuclides at these locations would be 2 to 10 times higher than at the gardens identified during the land use census. No radionuclides attributed to PNPS operations were detected in any of the samples. Additional details regarding the land use census can be found in Appendix E of this report.

One problem was encountered with the collection of composite water samples from the Discharge Canal during 1994. Between 25-Feb-94 and 01-Mar-94, cold weather froze the sampling line to the composite sampler. The plant was shut down at the time, resulting in diminished flow through the canal during the period. To prevent additional problems from the cold weather, the sample line was heat traced and insulated.

Samples of Group 1 (bottom distribution) and Group II (near-bottom distribution) fishes were not collected in the vicinity of the Discharge Canal during the first quarter of 1994. Fish species in this category 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.

A delay occurred in the delivery of some marine samples to the Yankee Atomic Environmental Laboratory for analysis. An administrative guideline of a maximum of 10 days between sample collection and delivery was exceeded on three samples collected in January. Samples of mussels and Irish moss were collected at Manomet Point (MP) on 19-Jan-94, and mussels at Green Harbor (GH) on 20-Jan-94. Due to inclement weather, the pickup of the samples by General Test Division personnel was delayed until 01-Feb-94, and the samples were delivered to the analytical laboratory on 04-Feb-94. Since the delay was due to weather, no further actions were taken. Despite the extended delivery time, all samples had been preserved (frozen) prior to delivery, and the minimal amount of radioactive decay resulting from the delay had negligible impact on analyses performed (all required LLDs were met).

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In summary, the various problems encountered in collecting environmental samples during 1994 were relatively minor when viewed in the context of the entire monitoring program.

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

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APPENDIX E QUALITY ASSURANCE PROGRAM RESULTS A. Introduction The accuracy of the data obtained through Boston Edison Company's Radiological Environmental Monitoring Program (REMP) is ensured through a comprehensive Quality Assurance Program. This appendix addresses those aspects of quality assurance that deal with the accuracy and precision of the analytical sample results and the environmental TLD measurement results that are obtained by 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 1994," and the YAEL

" Semi-Annual Quality Assurance Status Report: July - December 1994."

B. Laboratory Analyses The quality control programs that were performed during 1994 to demonstrate the validity of laboratory analyses by YAEL include the following:

1. YAEL participation in the Environmental Protection Agency (EPA)

Interlaboratory Comparison (cross-check) program for those types of samples routinely analyzed by the laboratory. This provides an independent check of accuracy and 3recision 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 i

measures are taken, as appropriate.

2. YAEL interlaboratory quality control program to assure the validity and reliability of the data. This program includes quality ccntrol of laboratory eoaipment, use of reference standards for calibration, and analysis of blank and spiked samples. The records of the quality control program are reviewed by the responsible cognizant individual, and corrective measures are taken, as appropriate.

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

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 and precision for .

laboratory analyses in 1994 for YAEL intralaboratory analyses and EPA l l interlaboratory cross-check analyses. For accuracy, 59 and 86 l percent of the results were within 5 and 10 percent of the known values, respectively, with 95 percent of all results falling within the laboratory criterion of 15 percent. For precision, 75 and 92 percent of the results were within 5 and 10 percent of the mean, respectively, with 99.4 percent of all results meeting the laboratory criterion of 15 percent.

The results of the EPA Interlaboratory Comparison program, when i considered apart from the remainder of the Quality Assurance program, l l were satisfactory with respect to accuracy and precision in 1994. A I total of 132 analyses were performed on air particulate filters, milk, and water. Based upon this sample analysis total,119 analyses (i.e., 90.2 percent) met the EPA's definition of " control limit" acceptance criteria for accuracy. I l

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TABLE I INTRALABORATORY AND EPA INTERLABORATORY RESULTS - 1994 Total Fraction of Measurements Number of within deviation ranae Cateaory Measurements 0-5% 0-10% 0-15%*

YAEL INTRALABORATORY ANALYSES Accuracy 378 74.9% 94.4% 98.9%

Precision 172 80.8% 98.8% 100.0%

l EPA INTERLABORATORY ANALYSES Accuracy 153 45.1% 70.6% 94.1%

Precision , 153 76.5% 94.1% 99.3%

TOTAL COMBINED ANALYSES Accuracy 531 66.3% 87.6% 97.6%

Precision 325 78.8% 96.6% 99.7%

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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b. Blind Duplicate Proaram A total of 50 paired samples were submitted by the five sponsor companies for analysis during 1994. The database used for the duplicate analysis consisted of paired measurements of 26 gamma-emitting nucl Jdes, H-3, Sr-89, Sr-90, low-level I-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 percent of their average value, then agreement between the measurements has been met. If the value falls outside of the 15 percent 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 50 paired samples,1309 paired duplicate measurements were analyzed during 1994. Out of these measurements, 1306 (99.8%) fcil within the established criteria discussed above. No trend was ,

evident with respect to repeated failings of measurements for the '

listed radionuclides and media.

C. Environmental TLD Measurements Two separate quality control programs were performed during 1994 to demonstrate I the performance of the routine environmental TLD processing by YAEL. The quality of the dosimetric results is evaluated relative to independent third party testing and internal performance testing. These tests were performed independent of the processing of environmental TLDs at YAEL. In all of these tests,  ;

dosimeters were irradiated to known doses and submitted to YAEL for processing as l unknowns. The quality control programs provide a statistical measure of '

accuracy, precision and consistency of the processing against a reliable standard, which in turn points out any trends or changes in performance.

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. Boston Edison conducted quarterly tests on the environmental TLDs via an independent third party during 1994.

1. Intralaboratory and Independent Third Party Results A 30 percent 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 1994 was adopted by the Laboratory Quality Control Audit Committee (LQCAC) on November 13, 1987. Recognizing the inherent variability associated with each dosimeter type, control limits for both accuracy and precision of 3 sigma plus 5 percent (for bias) were set by the LQCAC. The actual magnitude of the 3 sigma plus 5 percent control limits depends on the historical performance of each type of dosimeter, with each response being indicative of random and systematic uncertainties, combined with any deviation attributable to TLD operation.

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

The quality control program implemented for dosimetry processing indicated good precision and accuracy in the reported values. In 1994, there were 84 quality control tests. All 36 environmental TLDs tested during January -

June 1994 were within the control limits for both accuracy and precision.

The comparisons yielded a mean accuracy of +2.1 percent, with an associated standard deviation of 3.7 percent. The comparisons exhibited a precision value with an overall standard deviation of 1.3 percent. The 48 TLDs tested in July - December 1994 showed a mean accuracy of -1.9 percent with an associated standard deviation of 3.5 percent. TLDs measured during the second semiannual period exhibited a precision value with a standard deviation of 1.4 percent, well within the acceptance criteria. In total, all 84 environmental TLDs tested during 1994 were within the control limits  ;

for accuracy ( 20.1%) and precision ( 12.8%).

2. Boston Edison's TLD QA Program )

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Boston Edison Company personnel evaluate the accuracy of the environmental 1 TLDs on a quarterly basis. The following acceptance criteria have been i established: 1) the average of the percentage differences must be within 10%; and, 2) no one result can be greater than 15%. For the 71 environmental TLDs tested during 1994, the average difference was +0.7%.

All calculated averages of the percentage differences were within the 10%

acceptance criterion, and no individual result exceeded the 15% criterion.

D. Conclusions Laboratory analysis results for the EPA Interlaboratory Comparison program, the YAEL intralaboratory quality control program, and the sponsor companies blind duplicate program met the laboratory criterion of less than 15% deviation in more than 94% of all cases.

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 analysis and measurements which were performed by Yankee Atomic Environmental Laboratory during 1994 exhibited acceptable accuracy and precision.

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