ML20217N609

Radiological Environ Monitoring Program Rept No 30 for Jan-Dec 1997

ML20217N609
Person / Time
Site:	Pilgrim
Issue date:	12/31/1997
From:	Mauro W, Sejkora K, Smalley P BOSTON EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
30, BECO-2.98.062, NUDOCS 9805050384
Download: ML20217N609 (99)

Text

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b Technical Specification 6.9.C.2 Boston Edison Pilgrim Nuclear Power Station Rocky Hill Road

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Plymouth, Massachusetts 02360 5599 Nancy L. Desmond Regulatory Relations Group Manager April 30,1998 BECo Ltr. 2.98.062 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 License No. DPR-35 Docket No. 50-293 In accordance with the Pilgrim Nuclear Power Station Technical Specification 6.9.C.2, Boston Edison Company submits the Annual Radiological Environmental Monitoring Program Report for 1997 (Report #30).

N.L. Desmond PMK/deg 298062 Attachment cc: Mr. liubert Miller Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Alan B. Wang, Project Manager Project Directorate I-3 Office of Nuclear Reactor Regulation Mail Stop: OWFN 14B2

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g U. S. Nuclear Regulatory Commission I White Flint North

.11555 Rockville Pike Rockville, MD 20852 pf Senior Resident Inspector 9805050304 971231 PDR ADOCK 05000293 R

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PILGRIM NUCLEAR POWER STATION Radiological Environmental Monitoring Program Report No. 30 January 1 through December 31,1997 l

& Boston Edison

i

& Boston Edison PILGRIM NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT NO. 30 JANUARY 01 THROUGH DECEMBER 31,1997 Prepared by:

2a& /96 K.J. SejkoraL/ ()tal Radiochemist

~

Senior Envircnmen Reviewed I

b P.O. Smalley T

Chemistry Department Manager Approved by:

O

'f W.A. Mauro Radiation Protection Manager (acting)

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3 Pilgrim Nuclear Power Station Radiological Environmental Monitoring Program Report January-December 1997 '

TABLE OF CONTENTS SECTION SECTION TITLE PAGE EXECUTIVE

SUMMARY

5

1.0 INTRODUCTION

7 1.1

- Radiation and Radioactivity 7

1.2 Sources of Radiation 8

1.3 -

Nuclear Reactor Operations 9

1.4 Radioactive Effluent Control 14 1.5 RadologicalImpact on Humans 17 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 22 2.1 Pre-Operational Monitoring Results 22 l

2.2 Environmental Monitoring Locations 23 2.3 Interpretation of Radioactivity Analyses Results 24 2.4 Ambient Radiation Measurements 26 2.5 Air Particulate Filter Radioactivity Analyses 28 2.6 Charcoal Cartridge Radioactivity Analyses 28

]

2.7 Milk Radioactivity Analyses 28 2.8 Forage Radioactivity Analyses 29 2.9 Vegetable / Vegetation Radioactivity Analyses 29 2.10 Cranberry Radioactivity Analyses 30 2.11

-Soil Radioactivity Analyses

'30

)

2.12 Surface Water Radioactivity Analyses 30 2.13 trish Moss Radioactivity Analyses 31 2.14 Shellfish Radioactivity Analyses 31 2.15 Lobster Radioactivity Analyses

-32 2.16 Fish Radioactivity Analyses 32 2.17 Sediment Radioactivity Analyses 32 3.0

SUMMARY

OF RADIOLOGICAL IMPACT ON HUMANS 72

4.0 REFERENCES

74 i

APPENDIX A Special Studies.

75 APPENDIX B Effluent Release Information 77 APPENDIX C Land Use Census 90 APPENDIX D Environmental Monitoring Program Discrepancies 91 APPENDIX E Quality Assurance Program Results 94 1

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Pilgrim Nuclear Power Station Radiological Environmental Monitoring Program Report January-December 1997 LIST OF TABLES TABLE TABLE TITLE PAGE 1.2-1 Radiation Sources and Corresponding Doses 8

1.3-1 PNPS Operating Capacity Factor During 1997 9

2.2-1 Routine Radiological Environmental Sampling Locations 34 2.4-1 Off-site Environmental TLD Results 36 2.4-2 On-site Environmental TLD Results 38 2.4-3 Average TLD Exposures By Distance Zone During 1997 39 2.4-4 Beach Survey Exposure Rate Measurements 40 2.5-1 Air Particulate Filter Radioactivity Analyses 41 2.6-1 Charcoal Cartridge Radioactivity Analyses 42

.j 2.7-1 Milk Radioactivity Analyses 43 2.8-1 Forage Radioactivity Analyses 44 2.9-1 VegetableNegetation Radioact'vity Analyses 45 j

2.10-1 Cranberry Radioactivity Analyses 46 2.11-1 Soit Radioactivity Analyses 47 2.12-1 Surface Water Radioactivity Analyses 48 2.13-1 Irish Moss Radioactivity Analyses 49 2.14-1 Shellfish Radioactivity Analyses 50 2.15-1 Lobster Radioactivity Analyset 51

]

2.18-1 Fish Radioactivity Analyses 52 2.17-1 Sediment Radioactivity Analyses 53 2.17-2 Sediment Plutonium Analyses 54 3.0-1 Radiation Doses From 1997 Pilgrim Station Operations 73 r

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-Q Pilgrim Nuclear Power Station Radiological Environmental Monitoring Program Report January-December 1997 LIST OF FIGURES FIGURE FIGURE TITLE PAGE 1.3-1 Radioactive Fission Product Formation 11 1.3-2 Radioactive Activation Product Formation

.12 I

1.3-3 Barriers to Confine Radioactive Materials 13 1.5-1 Radiation Exposure Pathways 19

~2.2-1 Environmental TLD Locations Within the PNPS Protected Area 55 2.2-2 TLD and Air / Soil Sampling Locations: Within 1 Kilometer 57 2.2-3 TLD and Air /Soll Sampling Loca ons: 1 to 5 Kilometers 59 r

2.2-4 TLD and Air / Soil Sampling Locations: 5 to 25 Kilometers 61 2.2-5 Terrestrial and Aquatic Sampling Locations 63 2.2-6 Environmental Sampling and Measurement Control Locations 65 2.4-1 Historical Beach Survey Exposure Rate Measurements 67 2.5-1 Airbome Gross Beta Radioactivity Levels: Near Station 68 2.5-2 Airbome Gross Beta Radioactivity Levels: Property Line 69 2.5-3 Airbome Gross Beta Radioactivity Levels: Off-Site 70 2.7-t Levels of Strontium-90 in Milk Samples 71 i.

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. EXECUTIVE

SUMMARY

BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REFJRT JANUARY 01 THROUGH DECEMBER 31,1997 lNTRODUCTION 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 31,1997. 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 racioactivity 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, Amvican lobster, fishes, sediment, milk, cranberries, vegetation, and animal forage.

During 1997., there were 1,393 samples collected from the atmospheric, aquatic and terrestrial environments. In addition,'434 exposure measurements were obtained using environmental thermoluminescent dosimeters (TLDs) and six exposure rate measurements were performed using a high pressure ion chamber. All of the various samples and TLDs were collected by Boston Edison Company and Massachusetts Division of Marine Fisheries personnel. In situ (in-place) soil measurements were also made at 11 locations to assess. deposition of radioactivity on the soil.

l

' A small number of inadvertent issues were encountered during 1997 in the collection of

' environmental samples in accordance with the PNPS Technical Specifications. Six out of 440

' TLDs were unaccounted for during the quarterly retrieval process However, the 434 TLDs

.which were collected provided the information necessary to assess ambient radiation levels in the vicinity of Pilgrim Station. Equipment failures and power outages resulted in a small number of instances in which lower than normal volumes were collected at the airborne sampling stations. However, all 572 air particulate and charcoal cartridges were collected and analyzed as required, and required lower limits of detection were achieved without any anomalous resuits being observed.

Due to seasonal unavailability of Group I (bottom distribution) and Group II (near-bottom distribution) fishes in the vicinity of the discharge canal, the second subsample of these fish was unable to be obtained during the fourth and first quarters of 1997, respectively. A full description of any discrepancies encountered with the

- environmental monitoring program is presented in Appendix D of this report.

There were 1,571 analyses performed on the environmental media samples. Analyses were performed by the Duke Engineering and Services Environmental Laboratory in Westborough, Massachusetts. Samples were analyzed as required by the PNPS Technical Specifications.

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(

l LAND USE CENSUS f

l' The annual land use census in the vicinity of Pilgrim Station was conducted as required by

Technical Specifications between October 27 and 31,1997. A total of 30 vegetable gardens having an area of more than 500 square feet were identified within five kilometers (three miles) of PNPS. No new milk or meat animals were located during the census. Of the 30 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 l

During 1997, samples (except charcoal cartridges) collected as part of the REMP at Pilgrim l.

Station continued to contain detectable ' amounts of naturally-occurring and man-made radioactive materials. The only samples collected in 1997 which showed detectable activity potentially attributable to PNPS operations were blue mussel collected from the discharge canal outfall, and the composite water sample collected from the discharge canal during the month of March. The calculated dose to a maximum-expored individual from this radioactivity is estimated as being less than 0.005 mrem. Off-site ambient radiation measurements using environmental TLDs and a high pressure ion cFamber ranged between 44 and 101 i

milliRoentgens per year. The range of ambient radiation levels observed with the TLDs is consistent with natural background rad'ation levels for Massachusetts as determined by the Environmental Protection Agency (EPA).

RADIOLOGICAL IMPACT TO THE GENERAL PUE2LIC i

During 1997, radiation doses to the general public as a result of Pilgrim Stat lon's operation continued to be well below the federallimits and much less than the dose due to other sources of man-made (e.g., X-rays,- medical, fallout) and naturally-occurring (e.g., rosmic, radon) radiation.

The calculated total body dose to the maximally-exposed member of the general public from radioactive effluents and ambient radiation resulting from PNPS operations for 1997 was about i

2.3 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.

I l

CONCLUSIONS l

l The 1997 Radiological. Environmental Monitoring Program for Pilgrim Station resulted in the collection and analysis of hundreds of environmental samples and measurements. The data obtained were used to determine the impact of Pilgrim Station's operation on the environment and on the general public.

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

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

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i C

1.0 INTRODUCTION

The Radiological Environmental Monitoring Program for 1997 performed by Boston Edison Company for Pilgrim Nuclear Power Station (PNPS) is discussed in this report. Since the operation of a nuclear power plant results in the release of small amounts of radioactivity and low levels of radiation, the Nuclear Regulatory Commissicn (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 31,1997.

l 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 I

collected. These samples include, but are not limited to: air, soil, seawater, shellfish, lobster, fishes, milk, cranberries, vegetables, and forage. Thermoluminescent dosimeters (TLDs) are placed in the environment to measure gamma radiation levels. The TLDs are processed and the environmental samples are analyzed to measure the very low levels of radiation and radioactivity present in the environment as a result of PNPS operation and other natural and man-made sources. These results are reviewed by BECo's radiological staff and have been reported semiannually or annually to the Nuclear Regulatory Commission and others since 1972.

In order to more fully understand how a nuclear power plant' impacts humans and the environment, background information on radiation and radioactivity, natural and man-made sources of radiation, reactor operations, radioactive effluent controls, and radiological impact on humans is provided.

It is believed that this information will' assist the reader in understanding the radiologicalimpact on the environment and humans from the operation of Pilgrim Station.

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

Radioactive material exists naturally and has always been a part of our environment. The earth's crust, for example, contains radioactive uranium, radium, thorium, ind 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 ces'um-137, iodine-131, strontium-90, and cobalt-60.

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

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

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

Table 1.2-1 Radiation Sources and Correspondina Doses NATURAL MAN-MADE Radiation Dose-Radiation Dose Source -

(millirem / year)

Source (millirem / year)

Cosmic /cosmogenic 30 Medical / Dental X-Rays 39 Intemal 40 Nuclear Medicine 14 Terrestrial 30 Consumer Products 10 Radon / Thoron 200 Weapons Fallout 1

Nuclear Power Plants 1

Approximate Total 300

Approximate Total 60 Cosmic radiation from the sun and outer space penetrates the earth's atmosphere and continuously bombards us with rays and charged particles. Some of this cosmic radiation interacts with gases and particles in the atmosphere, making them radioactive in turn. These radioactive byproducts from cosmic ray bombardment are referred to as cosmogenic radionuclides. Isotopes such as beryllium-7 and carbon-14 are formed in this way. Exposure to cosmic and cosmogenic sources of radioactivity results in about 30 mrem of radiation dose per year.

Additionally, natural radioactivity is in our body and in the food we eat (about 40 millirem /yr),

the ground we walk on (about 30 millirem /yr) and the air we breathe (about 200 millirem /yr).

The majority of a person's annual dose results from exposure to radon and thoron in the air we breathe. These gases and their radioactive decay products arise from the decay of naturally occurring uranium, thorium and radium in the soil and building products such as brick, stone, and concrete. Radon and thoron levels vary greatly with location, primarily due to changes in the concentration of uranium and thorium in the soil. Residents at some locations in Colorado, New York, Pennsylvania, and New Jersey have a higher annual dose as a result of higher Page 8

a -

a l-1 levels of radon / thoron gases in these areas.. In total, these various sources of naturally-

. occurring radiation and radioactivity contribute to a total dose of about 300 mrem per year.

In addition to natural radiation, we are normally exposed to radiation from a number of man--

made sources. The single largest doses from man-made sources result from therapeutic and diagnostic applications of x-rays and radiopharmaceuticals. The annual dose to an individual in the U.S. from medical and dental exposure is about 50 mrem. Consumer products, such as i

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

)

l

- weapons fallout (less than 1 mrem) and nuclear power plants (less than'1 mrem /yr). Typically,.

the average person in the United States receives about 60 mrem per year from man-made l

sources.

I 1.3 '

Nuclear Reactor Operations Pilgrim Station generates about 670 megawatts of electricity at full power, which is enough

- electricity to supply the entire city of Boston, Massachusetts. Pilgrim Station is a boiling water

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reactor whose nuclear steam supply system was provided by General Electric Co. The nuclear station is located on a 1600 acre site about eight kilometers (five miles) east-southeast of -

Plymouth Center. Commercial operation bagan in December,1972.

Pilgrim Station was in a refueling outage from February 15 through~ April 12,1997. Forced outages to repair equipment also occurred in November and December. Monthly capacity factors are given in Table 1.3-1.

TABLE 1.3-1 PNPS OPERATING CAPACITY FACTOR DURING 1997 (Based on 670 megawatts electric)

Month Percent Capacity January -

-92.5 February 42.1 March 0.0 j

' April 21.4 May 97.4 q

June 98.1 j

July 95.5 August 96.4 i

September 97.4 October 98 7 November 69.5 December 68.8

~

Average 73.4-Page 9

Nuclear-generated electricity is produced at Pilgrim Station by many of the same techniques

)

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

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

Inside the rrector, a nuclear reaction called fission takes place. Particles, called neutrons,.

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

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 intemal surfaces of pipes and equipment. The radioactive fission products on I

the pipes and equipment emit radiation. Examples of some fission products are krypton-85 (Kr-85), strontium-90 (Sr-90), iodine-131 (1-131), xenon-133 (Xe-133), and cesium-137 (Cs 137).

I Page 10

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

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

Radiation Uranium

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

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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 neu.rons may react with the nuclei of these particles, producing radioactive products. So, actis ation products are nothing more than ordinary naturally-occurring atoms that are made unst>% 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).

4 Co-60 I

n Co-59 Stable Radioactive Neutron Cobalt Nucleus Cobalt Nucleus Figure 1.3-2 Radioactive Activation Product Formation At Pilgrim Nuclear Power Station there are five independent protective barriers that confine these radioactive materials.

These five barriers, which are shown in Figure 1.3-3 (Reference 5), are:

1) fuel pellets;

2) fuel cladding;

3) reactor vessel and piping;

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

5) secondary containment (reactor building).

)

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

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

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

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

The fourth barrier is the primary containment. This consists of the drywell and the torus. The drywell is a steellined enclosure that is shaped like an inverted light bulb. The drywell's steel pressure vessel is enclosed by an approximately five foot thick concrete wall. The torus is a donut shaped pressure suppression chamber. The steel walls of the torus are nine feet in diameter with the donut itself having an outside diameter of about 130 feet. Small amounts of radioactivity may be released from primary containment during maintenance.

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

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

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

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

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

reactor water cleanup system; liquid radwaste treatment system; e

sampling and analysis of the liquid radwaste tanks; and, e

liquid waste effluent discharge header radioactivity monitor.

e The purpose of the reactor water cleanup system is to continuously purify the reactor cooling water by removing radioactive atoms and non-radioactive impurities that may become activated by neutron bombardment. A portion of the reactor coolant water is diverted from the primary coolant system and is directed through ion exchange resins where radioactive elements, dissolved end suspended in the water, are removed through chemical processes.

The net effect is a substantial reduction of the radioactive material that is present in the primary coolant water and consequently the amount of radioactive material that might escape from the system.

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

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

Prior to release, the radioactivity in the liquid radwaste tank is semp!sd and analyzed to determine if the level of radioactivity is below the release limits and ta quantify the total amount of radioactive liquid effluent that would be released. If the Ir.vcls, are below the federal release limits, the tank is drained to the liquid effluent discharge header.

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

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

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

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

Page 15

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

_l limited, controlled, and monitored by a variety of systems and procedures which include:

reactor building ventilation system; e

reactor building vent effluent radioactivity monitor; e

sampling and analysis of reactor building vent effluents; e

standby gas treatment system; e

main stack effluent radioactivity monitor and sampling; e

sampling and analysis of main stack effluents; e

augmented off-gas system; e

steam jet air ejector (SJAE) monitor; and, e

off-gas radiation monitor.

e The purpose of the reactor building ventilation system is to collect and exhaust reactor building air. Air collected from contaminated areas is filtered prior to combining it with air collected from other parts of the building. This combined airflow is then directed to the reactor building ventilation plenum which is located on the side of the reactor building. This plenum, which vents to the atmosphere, is equipped with a radiation detector. The radiation level meter and strip chart recorder for the reactor building vent effluent radioactivity monitor _is located in the Control Room. To supplement the information continuously provided by.the detector, air samples are taken periodically from the reactor building vent and are analyzed to quantify the total amount of tritium and radioactive gaseous and particulate _ effluents released.

If air containing elevated amounts of noble gases is routed past the reactor building vent's effluent radioactivity monitor, an alarm will alert the Control Room operators that release limits are being approached. The Control Room operators, according to procedure, will isolate the reactor building ventilation system and initiate the standby gas treatment system to remove airbome particulates and gaseous halogen radioactivity from the reactor building exhaust.

This filtration assembly consists of high-efficiency particulate air filters and charcoal adsorber beds. The purified air is then directed to the main stack. The main stack has dilution flow j

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 whlen withdraws a portion of the air and passes it through a radioactivity monitoring system. This main stack i

effluent radioactivity monitoring system continuously samples radioactive particulates, iodines, and noble gases. Grab samples for a tritium analysis are also collected at this location.- The system also contains radioactivity dewetors 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, lodine, tritium, and gas samples are analyzed periodically to quantify the total amount of radioactive gaseous effluent being released.

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

I remove radioactive particulates. The recombiner collects free hydrogen and oxygen gas and j

recombines them into water. This helps reduce the gaseous releases of short lived isotopes of i

oxygen which have been made radioactive by neutron activation.

1 The radioactive off-gas from the condenser is then directed into a ventilation pipe to which the off-gas radiation monitors are attached. The radiation level meters and strip chart recorders for this detector are also located in. the. Control Room. if a radiation alarm setpoint is exceeded, an audible alarm will sound to alert the Control Room operators.. In addition, the off-gas bypass and charcoal adsorber inlet valve will automatically re-direct the off-gas into the charcoal adsorbers if they are temporarily being bypassed. If the radioactivity levels are not retumed 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 1

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

I 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 continuous radiation monitoring and periodic sampling and analysis i

is to measure the quantities of radioactivity being released to determine compliance with the radioactivity release limits. This is the first stage for assessing releases to the environment.

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

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

The types and quantities of radioactive liquid and gaseous effluents released from Pilgrim Station during 1997.were reported to the Nuclear Regulatory Commission semiannually. The 1997 Radioactive Effluents are provided in Appendix B and will be discussed in more detail in Section 3 of this report. These liquid and gaseous effluents were well below the federal release limits and were a small percentage of the PNPS Technical Specifications operational objectives.

These' measurements of the physical and chemical nature of the effluents are used to determine how the radionuclides will interact with the environment and how they can result in radiation exposure to humans. The environmental interaction mechanisms depend upon factors such as the hydrological (water) and meteorological (atmospheric) characteristics in the area. Information on the water flow, wind speed, wind direction, and atmospheric mixing characteristics are used to estimate how radioactivity will distribute and disperse in the ocean and the atmosphere.

Page 17

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

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

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

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

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

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

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

1) extemal radiation from an airborne plume of radioactivity;

2) Intemal radiation from Inhalation of airbome radioactivity;

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

4) intemal radiation from consumption of vegetation containing radioactivity absorbed from the soil due to ground deposition of radioactive effluents; and, 1

5) intemal radiation from consumption of milk and meat containing radioactivity deposited on forage which is eaten by cattle and other livestock, in addition, ambient (direct) radiation emitted from contained sources of radioactivity at PNPS contribute to radiation exposure in the vicinity of the plant. Radioactive nitrogen-16 contained in the steam flowing through the turbine accounts for the majority of this " sky shine" radiation exposure immediately adjacent to the plant. - Smaller amount of ambient radiation result from low-level radioactive waste stored at the site prior to shipping and disposal.

Tothe extent possible, the radiological dose impact on humans. is based on direct measurements of radiation and radioactivity in the environment. When PNPS-related activity is detected in samples which represent a plausible exposure pathway, the resulting dose from such exposure is assessed (see Appendix A). However, the operation of Pilgrim Nuclear Power Station results in releases of only small amounts of radioactivity, and; as a result of dilution in the atmosphere and ocean, even the most sensitive radioactivity measurement and analysis techniques cannot usually detect these tiny amounts of radioactivity above that which is naturally present in the environment. Therefore, radiation doses are calculated using radioactive effluent release data and computerized dose calculations that are based on very conservative NRC-recommended models that tend to result in over-estimates of resulting

' dose. These computerized dose-calculations are performed by or for Boston Edison Co.

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

In Regulatory Guide 1.109 (Reference 6). The dose calculations are documented and described in detail in the Pilgrim Nuclear Power Station's Off-site Dose Calculation Manual 1

(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 Duke Engineering and Services, using their advanced "YODA" computer program. It should be emphasized that because of the very conservative assumptions made in the computer code calculations, the maximum hypothetical dose to an individual is considerably higher than the dose that would actually be received by a j

real individual.

i l

Page 19

EXAMPLES OF PILGRIM STATION'S RADIATION EXPOSURE PATHWAYS I

i

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EFFLUENTS f psey 1

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3. DIRECT RADIATION

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2. AIR INHALATION

4. DIRECT RADIATION (SOIL DEPOSITION)

1. DIRECT RADIATION j

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1. SHORELINE DIRECT RADIATION (FISHING, PICNICING)

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DEPOSITION

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I Figure 1.5-1 Radiation Exposure Pathways Page 20

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

~ The NRC, in 10CFR 20.1301 (Reference' 8) limits the levels of radiation to unrestricted areas

- resulting from the possession or use of radioactive materials such that they limit any individual to a dose of:

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

e In addition to this dose limit, the NRC has established design objectives for nuclear plant 1

~ licensees.- Conformance to these guidelines ensures that nuclear power reactor effluents are.

. maintained as far below the legal limits as is reasonably achievable.

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

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

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

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

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

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

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

e The EPA, in 40CFR190.10 Subpart B (Reference 10), sets forth the environmental standards

. for the uranium fuel cycle. During normal operation, the annual dose to any member of the public from the entire uranium fuel cycle shall be limited to:

less than or equal to 25 mrem per year to the total body; e

less than or equal to 75 mrem per year to the thyroid; and, e

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

e The summary of the 1997 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 1997 is discussed in Section 2 of this report.

Page 21

2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2.1 Pre-Operational Monitorina Results The Radiological Environmental Monitoring Program (REMP) at Boston Edison Company's-Pilgrim Nuclear Power Station was first initiated in August 1968, in the form of a pre-operational monitoring program prior, to bringing the station on-line.

The NRC's intent (Reference 11) with performing a pre-operational environmental monitoring program is to:

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

2) evaluate procedures, equipment, and techniques for monitoring radiation and radioactivity in the environment.

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

Airbome Radioactivity Particulate Concentration (gross beta): 0.02 - 1.11 pCl/m ;

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

e Seawater Radioactivity Concentrations (gross beta): 12 - 31 pCi/ liter, I

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

Milk Radiocctive Strontium-90 Concentrations: 4.7 - 17.6 pCi/ liter; e

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

. Forage Radioactive Cesium-137 Concentrations: 150 - 290 pCl/kg.

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

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

2) monitoring the transfer and long-term buildup of specific radionuclides in the environment to revise the monitoring program and environmental models in response to changing conditions;

3) checking the condition of the station's operation, the adequacy of operation in relation to the adequacy of containment, and the effectiveness of effluent treatment so as to provide a mechanism of determining unusual or unforeseen conditions and, where appropriate,' to trigger special environmental monitoring studies; Page 22 1

j 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 and humans

. is significant.

3 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

- established guidelines (Reference 14) which specify an acceptable monitoring program. - The Boston Edison Company's Radiological Environmental _ Monitoring Program was. designed to i

meet and exceed these > guidelines;

' Guidance contained in ' the NRC's - Radiological Assessment Branch Technical Position on Environmental Monitoring (Reference 15) has been used to improve the program, in addition, the program has incorporated the provisions of an agreement made with the Massachusetts Wildlife Federation (Reference 16). The program was supplemented by including improved analysis of shellfish and sediment at substantially.

j 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 Plymouth area. The sampling locations are' i

divided into two classes, indicator and control.

Indicator locations are those which are

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

The environmental sampling media collected in the vicinity of Pilgrim Station during 1997 included air particulate filters, charcoal cartridges, seawater, shellfish, Irish moss, American lobster, fishes, sediment, milk, cranberries, vegetation, and forage. The sampling medium, station description, station number, distance, and direction for indicator and control samples are listed in Table 2.2-1. These sampling locations are also displayed on the maps shown in Figures 2.2-1 through 2.2-6.

The radiation monitoring locations for the environmental TLDs are shown in Figures 2.21 through 2.2-4. The frequency of collection and types of radioactivity analysis are described in Pilgrim Station's Technical Specifications, Sections 7.0/8.0.

The land-based (terrestrial) samples and monitoring devices are collected by Boston Edison personnel from the Electrical Engineering and Station Operation Department's Environmental Laboratory. The aquatic samples are collected by the Division of Marine Fisheries - Pilgrim Station Project - personnel.

The direct radiation measurements and soil radioactivity measurements are conducted by Duke Engineering and Services Radiological Engineering Group and Environmental Laboratory personnel, respectively. The radioactivity analysis of samples and the processing of the environmental TLDs is performed by Duke Engineering and Services Environmental Laboratory personnel.

The frequency, types, minimum number of samples, and maximum lower limits of detection

- (LLD) for the analytical measurements, are specified in the PNPS Technical Specifications.

Upon receipt of the analysis results from Duke Engineering and Services, the Boston Edison staff reviews the results. If the radioactivity concentrations are above the reporting levels, the Page 23

l NRC must be notified within 30 days. For radioactivity which is detected that is attributable to 1

Pilgrim Station's operation, calculations are performed to determine the cumulative dose j

contribution for the current year. Depending upon the circumstances, a special study may also be completed.(see Appendix A for 1997 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

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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 1997 Garden and Milk Animal Census are reported in Appendix C.

The accuracy of the data obtained through Boston Edison Company's Radiological Environmental Monitoring Program is ensured through a comprehensive Quality Assurance q

(QA) program.

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

Regular surveillances of the sampling and monitoring program; k

1 I

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

Spiked sample analyses by the analytical laboratory.

QA audits and inspections of the Radiological Environmental Monitoring Program are performed by the NRC, American Nuclear Insurers, and by Boston Edison Company's Quality Assurance Department.

The blind duplicates, split samples and spiked samples are analyzed by Boston Edison Company, Duke Engineering and Services Environmental Laboratory, and the other four sponsor companies. The 1997 results of this QA program are summarized in Appendix E.

These results indicate that the analyses and measurements performed during 1997 exhibited acceptable precision and accuracy.

2.3 Interpretation of Radioactivity Analyses Results The following pages summarize the analytical results of the environmental samples collected during.1997. 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 Duke Engineering and Services ERMAP computer program (Reference 17). The unit of measurement for each -

medium is listed at the top of each table. The left hand column contains the radionuclides-being ' reported, total number of. analyses of that radionuclide, and the number of measurements which exceed ten times the yearly average for the control station (s). The latter are classified as."non-routine" measurements. The next column lists the Lower Limit of Detection (LLD) for those radionuclides which have detection capability requirements specified in the PNPS Technical Specifications, j

l Page 24

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

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

This set of statistical parameters includes separate analyses for (1) the indicator stations, (2) the station having the highest annual mean concentration, and (3) the control stations. For

- each of these three groups of data, the Duke Engineering and Services ERMAP computer program calculates:

The mean value of ajl concentrations, including negative values and values below LLD; The standard deviation of the measurements; e

The lowest and highest concentrations; and, The number of positive measurements (activity which is three times greater than the standard deviation), out of the total number of measurements.

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

As an example of how to interpret data presented in the results tables, refer to the first entry on the table for air particulate filters (page 40). Gross beta (GR-8) analyses were performed 4

on 572 routine samples (11 stations /wk

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

For samples collected from the ten indicator stations, 518 out of 520 samples indicated detectable activity at the three-sigma (standard deviation) level. The mean concentration of gross beta activity in these 520 indicator station samples was 0.017 i 0.006 (1.7 i 0.6 E-2) pCi/m. Individual values ranged from 0.0027 to 0.0399 (2.7 - 39.9 E-3) pCl/m.

The monitoring station which yielded the highest mean concentration was station number 21 (East Weymouth), which yielded a mean concentration of 0.019 i 0.006 pCi/m, based on 52 3

observations. Individual values ranged from 0.0036 to 0.0395 pCi/m. Fifty-one of the fifty-two samples showed detectable act vity at the three-sigma level.

At the control location, 51 out of 52 samples f elded detectable gross beta activity, for an l

i average concentration of 0.019 i 0.006 pCi/m Individual samples at the control location l

ranged from 0.0036 to 0.0395 pCi/m.

i l

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

• 4 quarters). No samples exceeded ten times the j

i Page 25

mean control station concentration. There is no LLD value listed for K-40 in the PNPS Technical Specifications.

At the indicator stations, individual concentrations of K-40 ranged from -0.0084 to 0.0149 pCi/m*, for a mean concentration of 0.00097 i 0.00454 pCl/m3. However, none of the forty samples analyzed showed detectable amounts of potassium-40 at the three sigma level. : It is important to note that the mean value presented is' calculated from forty observations, all of which yielded p_o detectable activity.

The station which yielded the highest mean concentration of K-40 ws:, station 15. Again, the H

mean value of 0.0036 i 0.0057 pCi/m is based on four observations, none of which yielded i

any detectable activity. Therefore, no potassium-40 was detected in any of the samples 1

collected from the sampling stations.

The previous paragraphs illustrates an important point about applying the three-sigma criterion to determine if radioactivity is detected. While such a screening criterion can be applied to a sinole measurement, it is inappropriate to apply it to a mean value calculated from multiple measurements in the case of K-40 in air particulate filters, none of the 40 individual samples was " positive" at the 3-sigma, level. If the individual results are similar, even though they are "non-positive", the resulting standard deviation is artificially low, and does not reflect the total uncertainty associated with all of the measurements. This makes the 3-sigma criterion inappropriate for application to a mean and standard error calculation from several measurements.

2.4 Ambient Radiation Measurements The primary technique for measuring ambient radiation exposure in the vicinity of Pilgrim -

Station involves posting environmental thermoluminescent dosimeters (TLDs) at given monitoring locations and retrieving the TLDs after a specified time period. The TLDs are then taken to a laboratory and processed to determine the total amount of radiation exposure received over the period. Although TLDs can be used to monitor radiation exposure for short time periods, environmental TLDs are typically posted for periods of one to three months.

Such TLD monitoring yields averace exposure rate measurements over a relatively long time period. The PNPS environmental TLD monitoring program is based on a quarterly (three month) posting period, and a total of 110 locations are monitored using this technique. Forty of these -locations are listed as required monitoring locations in the PNPS Technical Specifications.

In addition, 27 of the 110 TLDs are-located on-site, within the PNPS protected / restricted area.

Out of the 440 TLDs (110 locations

• 4 quarters) posted during 1997,434 were retrieved and processed. Those TLDs missing from their monitoring locations were lost to storm damage and vandalism, and their absence is discussed in Appendix D. The results for environmental TLDs located off-site, beyond the PNPS protected / restricted area fence, are presented in Table 2.4-1. Results from on-site TLDs posted within the restricted area presented in Table 2.4-2.

In addition to TLD results for individual locations, results from off site TLDs were

' grouped according to geographic zone to determine average exposure rates as a function of distance. These results are summarized in Table 2.4-3.

All of the listed exposure values represent continuous occupancy (2190 hr/qtr or 8760 hr/yr).

Annual exposure rates measured at off-site locations ranged from 44 to 465 mR/yr. The

.veraae exposure rate at control locations greater than 15 km from Pilgrim Station (i.e., Zone

4) was 61.2 i 6.4 mR/yr. When the 3-sigma confidence interval is calculated based on these control measurements,99% of all measurements of backaround ambient exposure would be s

expected to be between 42 and 80 mR/yr.

Page 26

Inspection of on-site TLD results listed in Table 2.4 2 indicates that all of those TLDs located within the PNPS protected / restricted area yield exposure measurements higher than the expected background. These increases are due to the close proximity of these locations to radiation sources on-site. The radionuclide nitrogen-16 contained in steam flowing through the turbine accounts for most of the exposure on-site.' Although. this radioactivity is contained within the turbine and is not released to the atmosphere, the " sky shine" which occurs from the turbine increases the ambient radiation levels in areas near the turbine building. Some increases in exposure also occur from the transit and temporary storage of radioactive wastes

-on-site. Such TLD locations which experienced appreciable increases since 1996 due to

- turbine sky shine and/or from the temporary storage and movement of radioactive waste onsite are P11 and P25. TLD location P11 is near the gate to the trash compaction facility, where materials are process and staged for final shipping. TLD location P25 is located adjacent executive building, in a location which experiences significant N-16 skyshine from the turbine building. It must be emphasized that all of the -locations mentioned are within the protected / restricted area and are not accessible by members of the general public.

A small number of off-site TLD locations in close proximity to the protected / restricted area indicated ambient radiation exposure above expected background levels.

All of these locations are on Boston Edison controlled property, and experience exposure increases due to turbine sky shine (e.g., locations OA, TC, P01, WS, CT, and A) and/or transit and storage of radwaste on-site (e.g., location BLE). A hypothetical maximum exposed member of the public accessing these near-site areas on Boston Edison controlled property for limited periods of time would receive a maximum dose of about 2 mrem /yr above their average ambient background dose of 61 mrem /yr. One TLD, located in the basement of the Plymouth Memorial Hall, indicated an annual exposure of 99 mR. The increased exposure at this location is due to the close proximity of stone building material, which contains higher levels of naturally-occurring radioactivity, as well a from buildup of radon in this area of the building.

It should be noted that several of the TLDs used to calculate the Zone 1 averages presented in Table 2,4-3 are located on Boston Edison property. If the Zone 1 value is corrected for the near-site TLDs (those less than 0.6 km from the Reactor Building), the Zone 1 mean falls from a value of 91.8 i 70.5 mR/yr to 63.9 t 7.8 mR/yr. Additionally, exposure rates measured at areas beyond Boston Edison control did not indicate any increase in ambient exposure from Pilgrim Station operation. For example, the annual exposure rate at the nearest off site resident (location HB,0.6 km SE) was 66.8 i 4.4 mR/yr, which compares quite well with the average controllocation exposure of 61.2 i 6.4 mR/yr.

A second technique for measuring ambient radiation exposure utilizes a sensitive high-pressure ion chamber to make "real time" exposure rate measurements. This technique allows for instantaneous assessments, with the instrument providing a direct readout of exposure rates. Such monitoring with a high-pressure ion chamber can be used to perform rapid, short-term measurements at locations where it may be impractical to post long-term TLD monitors.

Annual measurements are taken with a high-pressure ion chamber at five locations on beaches in the Plymouth area, and at the control location in Duxbury. Results of these measurements (Reference 18) are listed in Table 2.4-4. These values, as well as historical measurements, are depicted graphically in Figure 2.4-1.

There are no apparent trends in exposure levels at these locations.

In conclusion, measurements of ambient radiation exposure around Pilgrim Station do not

~ indicate any significant increase in exposure levels. Although some increases in ambient 1

Page 27

)

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 Airbome particulate radioactivity is sampled by drawing a stream of air through a glass fiber filter which has a very high efficiency for collecting airbome particulates. These samplers are operatri 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.

i

' Out of 572 filters (11 locations

• 52 weeks), 572 samples were collected and analyzed during I

1997. 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 problems listed above, the required LLDs were met on 572 of the 572 filters collected during 1997.

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

Gross beta radioactivity was detected in 569 of the filter samples collected, including 51 of the 52 control location samples.

This gross beta activity arises from naturally-occurring 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 airborne particulate samples collected.

2.6 Charcoal Cartridae Radioactivity Analyses Airbome 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 airbome particulate radioactivity are also sampled for airbome radioiodine.

Out of 572 cartridges (11 locations

• 52 weeks), 572 samples were collected and analyzed during 1997. 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 problems listed above, the required LLDs were met on 572 of the 572 filters collected during 1997.

The results of the analyses performed on these 572 charcoal cartridges are summarized in Table 2.6-1. No airbome radioactive iodine was detected in any of the charcoal cartridges collected.

2.7 Milk Radioactivity Analyses

-Samples of unprocessed milk are collected from the Plymouth County Farm and from the controllocation in Whitman. The Annual Land Use Census conducted within five kilometers of Pilgrim Station did not identify any additional milk animals requiring sampling. Results of this Page 28

1 l

L 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 40 samples scheduled for collection during the year were obtained and analyzed. No problems were encountered in sampling milk during 1997.'

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

Naturally-occurring potassium-40 was. detected in all 40 samples. No radioactive iodine was j

detected in'any of the samples. Strontium-90 was detected in 14 of the 20 samples from-L Plymouth County Farm, and in 5 of the 20 samples collected from the control location in l=

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

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

The highest concentration of Sr-90,2.4 pCl/ 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 2.2 pCl/ liter. The Sr-90 detected in the samples resulted L

from radioar.tivity 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 l-for radioactive decay which occurred between 1972 and 1997,~ the expected concentration l'

would be about 5 pCi/ liter. The concentrations of 2 to 3 pCi/ liter observed in 1997 samples are well below the expected Sr-90 concentrations resulting from weapons testing. It is clear that the Sr-90 oburved did not arise from Pilgrim Station operations.

2.8 Forace Radioactivity Analyses 3

Samples of animal forage (hay) are collected from the Plymouth County Farm and from the control location in Whitman. Samples of com to be used for silage at Plymouth County Farm were also collected from the Whipple Farm (2.9 km SW). Samples are collected annually and analyzed by gamma spectroscopy.

i All samples of forage were collected and analyzed as required during 1997. Results of the gamma analyses of forage samples are summarized in Table 2.8-1. 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.

2.9.

Veaetable/Veoetation Radioactivity Analyses Scnples 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 l

were collected at or near a number of gardens identified during the Annual Land Use Census.

Results of this census are discussed in Appendix C. Samples were also collected from four iocations corresponding to the highest atmospheric deposition factors from the two PNPS

{

l.

release points. Samples of vegetables are collected' annually and analyzed by gamma j

. spectroscopy.

1 i

All samples of vegetables / vegetation were collected and analyzed as required during 1997.

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

. occurring beryllium-7, potassium-40, and thorium-232 were identified in most of the samples I

collected. Cesium-137 was also detected in six of the samples collected.

]

Page 29 i

J

The highest level of cesium-137 (160 pCi/kg) was detected in a sample of naturally-growing

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

- Cesium-137 is a' product of nuclear weapons testing, and was routinely detected in the preoperational monitoring program at levels of 150 to 290 pCi/kg.. When corrected for radioactive decay, the expected concentration in samples of naturally-growing vegetation collected during 1997 would be between 90 and 170 pCi/kg. Clearly, the average Cs 137 concentration of_31 pCi/kg observed in the samples collected are indicative of radioactivity

- arising from weapons fallout, and r>ot Pilgrim Station Operations.

2,10 ' Cranberry Radioactivity Analyses Samples of cranberries are routinely collected from two bogs in the Plymouth area and from j

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'1997 Results I

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 A survey of radioactivity in soil is conducted once every three years at the 10 air sampling stations in the Plymouth area and the control location in East Weymouth. These locations serve as fixed survey locations at which repeated measurements can be made to determine any buildup of radioactivity from deposition of airbome radionuclides. At each of these locations, in situ (in-field) measurements were made with a portable gamma spectroscopy unit and a high pressure ion chamber. The portable gamma spectrometer is used to identify radionuclides present across a large area beneath the detector, whereas the high pressure ion chamber is used to' detect exposure levels arising from naturally-occurring and deposited radionuclides in the soil.

The soil survey was performed as required in 1997. A total of_11 in situ measurements were analyzed. The results of the in situ analyses of these soil Iccations are summarized in Table 2.11-1. Naturally-occurring beryllium-7, potassium-40, thorium-232, and uranium-238 were detected in a number of the samples. Cesium-137 was detected in 7 of the 11 measurements.

The levels of Cs-137 detected (83-520 pCi/kg) are consistent with levels observed in past soil radioactivity _ surveys performed at PNPS, and are the result of activity deposited from atmospheric nuclear weapons testing during the 1950s and 60s.

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 Poiryt Bridge in Duxbury. The discharge Page 30

1 canal is sampled coritinuously by a composite sampler. Grab samples are collected weekly' i

from the Bartlett Pond and Powder Point Bridge locations. Samples of surface water are l

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 L

analysis is performed on this quarterly sample.

l A total of 36 samples (3 locations

• 12 sampling periods)'of surface water were collected and analyzed as required during 1997. Results of the analyses of water samples are summarized in Table 2.12-1. Naturally-occurring potassium-40 was detected in samples composed primarily of seawater. The only radionuclide attributable to Pilgrim Station operations was cobalt-60, 3

1 l

detected in the monthly composite sample from the discharge canal during the month of March -

1997. Pilgrim Station was in a refueling outage at the time, during which additional radioactive 1

wastes were processed and discharged. - This period was also marked with decreased flow in the discharge canal while maintenance on plant equipment was being performed.

An f-assessment of the dose resulting from this Co-60 was performed and is presented in Appendix A; This small amount of Co-60 resulted in an estimated dose impact of less than 0.005 mrem to the maximum-exposed individual.

i

.2.13 Irish Moss Radioactivity Analyses Samples of Irish moss are collected from the discharge canal outfall and two other' locations in the Plymouth area (Manomet Point, Ellisville), and from a control location in Marshfield (Green Harbor). All samples are collected on a quarterly basis, and processed in the laboratory for gamma spectroscopy analysis, i

l All 16 samples of Irish moss scheduled for collection during 1997 were obtained and analyzed.

Results of the gamma analyses of these samples are summarized in Table 2.13-1. Naturally-occurring beryllium-7 and potassium-40 were detected in a' number of the samples. No radionuclides attributable to Pilgrim Station operations were detected in any of the samples.

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

L

. All 48 samples of shellfish meat and shells scheduled for collection during 1997 were obtained j

- 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 i

L number of the samples. Low levels of cobalt-60 were detected in blue mussel shells and meat collected from the discharge canal outfall followino the refueling outage. Since the shells are l

not edible, such low-level contamination does not represent a normal exposure pathway, and l

no dose assessment was performed. The edible portions of mussel meat collected during the same period contained an average Co-60 concentration of 4.0 pCi/kg. This concentration was t

used to assess the resulting dose impact, as presented in Appendix A. This small amount of i

Co-60 is estimated to have resulted in a dose of less than 0.0002 mrem to the maximum-i exposed individual.

I l

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I Page 31 l'

-2.15 Lobster Radioactivity Analyses Samples of lobsters are routinely collected from the uutfall 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 1997. Results of the gamma analyses of lobster samples are summarized in Table 2.15-1.

The only radionuclide detected in any of the samples was naturally-occurring potassium-40.

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

2.16 Fish Radioactivity Analyses Samples of fish are routinely collected from the area at the outfall of the discharge canal and from the control locations in Cape Cod Bay and Buzzard's Bay. Fish species are grouped into

'l four major categories according to their biological requirements and mode of life. These major categories and the representative species are as follows:

Group I - Bottom Oriented: Winter Flounder, Yellowtail Flounder Group 11 - Near-Bottom Distribution: Tautog, Cunner, Pollock, Atlantic Cod, Hake Group 111-Anadromous: Alewife, Smelt, Striped Bass Group IV - Coastal Migratory: Bluefish, Herring, Menhaden, Mackerel

'Two subsamples of each category of fish are typically collected during each collection period.

Group I and 11 fishes are sampled on a quarterly basis from the outfall area of the discharge canal, and on an annual basis from a control location. Group 111 and IV fishes are sampled annually from the discharge canal outfall and control location. All samples of fish are analyzed by gamma spectroscopy.

Twenty-six samples of fish were collected during 1997. Only one subsample each of Group I and Group 11 species of fish were collected in the vicinity of the discharge canal during the fourth and first quarters of the year, respectively. This unavailability is believed to be due to low water temperatures and rough ceas. These discrepancies are noted in Appendix D.

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

The only radionuclide detected in any of the samples was naturally-occurring potassium-40.

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

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 aree (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 inc ments for analysis of radionuclide distribution by depth. During the first half of the' year, sampies 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, Page 32

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 1997. 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 6 of 39 indicator station samples and in 12 of 17 control station samples. Plutonium-239/240 was not detected in any of the four indicator station samples,~ but was detected in both of the control station samples.

- Cesium-137 levels in indicator samples ranged from non-detectable.to a maximum concentration of 24 pCi/kg. Concentrations in samples collected from the control locations beyond 'the influence of Pilgrim Station also ranged from non-detectable to a: maximum concentration of 30 pCl/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 was non-detectable. Concentrations in samples collected from the control locations beyond the influence of Pilgrim Station ranged from 6.8 pCi/kg to a maximum concentration of 22.4 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.

i Page 33

i Table 2.2-1 Routine Radioloaical Environmental Samplina Locations Pilarim Nuclear Power Station. Plymouth. MA l

Description No Code Distance Direction Air Particulate Filters. Charcoal Cartridoes. Soil Medical Building 00 WS 0.2 km SSE East Rocky Hill Road -

01 ER 0.9 km SE West Rocky Hill Road 03 WR 0.8 km WNW Property Line 06 PL 0.5 km NNW Pedestrian Bridge 07 PB 0.2 km N

Overlook Area 08 OA 0.1 km W

East Breakwater 09 EB 0.5 km ESE Cleft Rock 10 CR

- 1.3 km SSW Plymouth Center 15 PC 6.7 km W

Manomet Substation 17 MS 3.6 km SSE East Weymouth Control 21 EW 40 km NW Milk Plymouth County Farm.

11 CF 5.6 km W-Whitman Fa m Control 21 WF

-34 km WNW Forage Plymouth County Farm 11 CF 5.6 km W

Whitman Farm Control 12 WF 34 km WNW l

Whipple Farm 43 WH 2.9 km SW Veaetation Plymouth County Farm 11 CF 5.6 km W

Bridgewater Farm Control 27 BF 31 km W

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

Page 34 L

Table 2.2-1 (continued)

Routine Radioloaical Environmental Samolina Locations Pilorim Nuclear Power Station. Plymouth. MA Description No Code Distance Direction.

Surface Water Discharge Canal 11 DIS 0.2 km N

Bartlett Pond 17 BP 2.7 km SE

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

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

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

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

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

1

1 1

a 1

Table 2.4-1 Off-Site Environmental TLD Results l

TLD Statkm TLD Location * -

Exposure Rate. mR/ quarte,r,(Value t Std.Dev.)

1997 Annual" ID Description Distance / Direction Jan-Mar Apr-Jun Jul-Sep Oct-Dec Exposure.

mR/ year Zone 1 TLDs: 0-3 km BLW BOAT LAUNCH WEST 0.11 km E 43.112.8 66.7131 61.5 t 2.1 54622.6 225.8 i 41.2 OA OVERLOOK AREA 0.15km W 73 4 i 3.2 125.2 t 7.2 143.8 i 4 6 122.9 i 5.3 465.3 t 120.8 TC HEALTH CLUB 0.15 km WSW 27.0 i 1.7 40.9 t 1.9 48 4 i 1.6

- 42.0 t 2.2 158.2 t 36.2 BLE BOAT LAUNCH EAST 0.16 km ESE 38.8 t 2.9 61.3 i 3.4 58.4 i 3.0 54.0 i 4.5 212.5 t 40 6 PB PEDESTRIAN BRIDGE 0.21 km N 26.7 i 1.1 34.411.4 35.5 t 1.5 34.3 i 1.6 130.9 i 16.4 P01 SHOREFRONT SECURITY 0.22 km NNW 25.4 i 1.9 31.6 i 1.4 34.9 t 2.1 33.1 t 1.8 125.1 i 16.9 WS MEDICAL BUILDING 0.23 km SSE 24.5 i 1.1 33 7 t 2.9 34.7 i 1.2 32.5 i 1.4 125 5 t 19.0 CT PARKING LOT 0.31 km SE 24 8 i 1.3 31.5 t 1.4 34.3 t 5.7 29.111.5 119 8 t 17.2 PA SHOREFRONT PARKING 0.35 km NNW 17.2 t 0.7 21.211.1 22.310.9 20.3 t 0.8 81.0 t 8.9 A STATION A 0.37 km WSW 14 6 i 0.7 22.3 t 1.1 20.5 i 1.2 21.8 i 1.2 79.3 t 14 4 F STATION F 0.43 km NW 16.010.9 20.7 i 1.0 20.2 i 1.1 20.010.9 76.9 t 9 0 B STATION B 0.44 km S 21.6 t 1.1 23.211.0 26810.9 26.2 i 1.5 97.8 i 10.1 EB EAST BREAKWATER O.44 km ESE 17.1 t 0.9 22.9 t 1.1 21.8 t 0.7 21.4 f 1.4 83.3 i 10.6 PMT PNPS MET TOWER 0.44 km WNW 146i06 18.8 t 1.1 17.6 t 0.8 17.8 i 0.9 68 8 i 7.4 H STATION H 0.47 km SW 17.1 t 0.7 24.1 i 1.1 24.6 t 1.1 21.3 i 1.2 87.1113.9 i STATION I 0.48 km WNW 15.7 t 0.8 20.3 t 0.9 19.8 t 0 6 18.7 t 1.0 74.5 i 8.4 L STATION L 0.50 km ESE 17.410.9 19.7 i 0.9 20.4 t 1.0 19 6 i 1.1 77.1 i 5 6 G STATION G 0.53 km W 15.9 i 1.6 17.1 t 0.9 18.3 i 0.9 16 8 i1.0 68.1 + 4 6 D STATlON D 0.54 km NW 21.0 i 1.1 24.9 i 1.3 18.810.6 19.6 i 0.9 84.4 t 11.0 PL PROPERTY LINE 0.54 km NNW -

15 6 i 0.7 17.7 i 0.8 19410.7 17.410.7 70.0 t 6 4 C STATlON C 0.57 km ESE 15411.1 18.0 t 0.8 19.2 i 0.7 18 3 i 1.0 70.9 t 6.7 HB HALL'S BOG 0.63 km SE

- 15.9 t 1.7 17.4 t 0.8 15 9 i 0.8 17.6 i1.4 66.8 i 4 4 GH GREENWOOD HOUSE 0.65 km ESE 18.9 t 1.3 18.2 t 0.8 19.5 i 1.0 18.9 t 0.7 75.5 i 2 9 WR W ROCKY HILL ROAD 0.83 km WNW 18.2 t 0 $

20.011.0 20 9 t 1.0 19.9 i 0.9 79 0 i 4.9

{

ER E ROCKY HILL ROAD 0.89 km SE 13.3 i OT 14.6 i 1.0 15.3106 14.6 i 0.7 57.8 i 3.7 i

MT MICROWAVE TOWER 1.03 km SSW 15.6 i 1.1 18 4 i1.0 18.510.7 18.1 i1.0 70 6 i 5.8 CR CLEFT ROCK 1.27 km SSW 14.3 i 0.7 17.3 t 1.0 16 4 i 0.8 15.410.7 63.3 i 5 4 BD BAYSHORE/ GATE RD 1.34 km WNW 14.410.6 18.4 i 1.1 17.8 i 1.7 16.5 i 1.1 67.2 i 7.4 MR MANOMET ROAD 1.38 km S 11.7 t 0.7 16.010.9 15.5 i 0.6 14.1 ~i 0.8 57.3 i 7.8 DR DIRT ROAD 1.48 km SW 11.9 i 0 6 16.2109 15 8 t 0 6 15.110.9 58 9 i 8.0 EM EMERSON ROAD 1.53 km SSE 15.0 t 0.8 15.110.8 15.9 i 0.8 Missing 61.312.7 EP EMERSON /PRISCILLA 1.55 km SE -

16.311.1 15 1 i 0.8 16.211.0 15.2 i 0.8 62.9 i 3.2 AR EDISON ACCESS ROAD 1.59 km SSE 134i06 14 8 i 0.9 16.2 i 0.6 14.3 i 0.7 58.8 i 4 9 BS BAYSHORE 1.76 km W 15.7 i 0.7 19.611.0 17.910.6 17.5 i1.1 70.6 i 6.6 E STATION E 186 km S 14010.7 18.6 i1.0 183108 16.9 t 1.2 67.7 i 8.5 j

JG JOHN GAULEY 1JJ9km W 15.0 i 1.0 18.2 t 1.0 17.010.6 15.7 i 1.0 65.9 i 5.8 i

J STATION J 2.04 km SSE 139i06 15.5 i 0.8 17.3 t 1.1 14.8 i 0.8 61.5 i 5.9 WH WHITEHORSE ROAD 2.09 km SSE 15.7 + 1.7 14 8 i 0.7 16.7 i 0.6 16.4 t 1.3 63.7 i 4 0 RC PLYMOUTH YMCA 2.09 km WSW 13.7 i 0.8 18.4 i1.0 17.6 i 0.8 15.7 i 0 6 65.5 t 8.6 K STATION K 2.17 km S 13.8 i 0.7 15.210.9 16.6 i 0.6 15.2 i 0.6 60.8 i 4.6 TT TAYLOR / THOMAS 2.26 km SE 15.8 t 1.4 15.110.8 16 0 f 0.8 15.4 i1.0 62.2 t 2.6 YV YANKEE VILLAGE 2.28 km WSW 13 8

• 1.1 17.5 i1.0 17.3 t 0.8 15.6 i 0 7 64.2 i 7.2 GN GOODWIN PROPERTY 2.38 km SW 10.1108 134i07 13310.5 120106 48 8 i 6.3 RW RIGHT OF WAY 2 83 km S Messing 15.310.8 160106 14.1 i 1.2 60.5 i 4 4 TP TAYLOR / PEARL 2.98 km SE 15311.4 14 4 t 0.7 15 9 i 0.6 14.7 i 0.7 60.2 i 3.2

)

Distance and direction are measured fro n centerline of Reactor Building to the monitoring locasion.

" Annual value is based On arithmetic mean of the Observed quarterly values multiplied by four quarters / year.

Page 36

1 Table 2.4-1 (continued) l Off-Site Environmental TLD ReSultS TLD Station TLD Location

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

1997 Annual" ID Description Distance / Direction Jan-Mar Apr.Jun Jul-Sep Oct-Dec Exposure mR/ year Zone 2 TLDs: 3-8 km VR VALLEY ROAD 3.26 km SSW 12.0 i O.9 14.8 t o.7 14.5 t 0.9 13.8 f 0.7 55.115.3 ME MANOMET ELEM 3.29 km SE 12.3

• 0 6 Missing 16.6 i 0.8 14.710.9 58.2 i 8.7 WC WARREN /CLIFFORD 3 31 km W 12.5 i1.1 15.911.0 15.4 i 0.6 14.5 i1.2 58 4 i 6.4 BB RT.3A/ BARTLETT RD 3.33 km SSE 14.3 1.3 14610.8 15.7 i 0.6 14.4 t 1.3 58.9 i 3.3 MP MANOMET POINT 3.57 km SE 14 5 i 0.7 14.1 i 0.7 15.4 i 0.5 15.5 t 0.7 59.5 i 3 0 MS MANOMET SUBSTATION 3.60 km SSE 16 6 i 0.9 18.7 i1.1 18.7 i 0.6 18 8 t 1.2 72.8 i 4 6 BW BEACHWOOD ROAD 3.93 km SE 13.S i O.8 15 3 f o.7 17.411.6 15.211.2 61.S f 6.7 PT P!NES ESTATE 4.44 km SSW 12.610.8 14.310.9 14.6 i 0.6 14.110.6 55.5 39 EA EARL ROAD 4.60 km SSE 11.3 i 0 6 12.7 i 0.7 14.0 t 0.5 12.9 i 0.8 509i46 SP S PLYMOUTH SUBST 4 62 km W 14.5 t 0.9 16.711.5 16.210.6 15.4 i 0.8 62.9 i 4 4 RP ROUTE 3 OVERPASS 4.81 km SW 13.8 i 0.8 15 7 i 0.9 15.0 t 0.6 14.7 i 0.7 59.2 i 3.4 RM RUSSELL MILLS RD 4 85 km WSW 12.710.7 13.8 i 0.8 13910.4 12.9 i 0.5 53.3 i 2.8 HD HILLDALE ROAD 5.18 km W 13.5 t 0 8 17.1 t 0.9 16.610.6 16.3 t 1.0 614i6.6 MB MANOMET BEACH 5.43 km SSE 12.5 t 0.7 13.9 i 0.8 15.110.6 13.8 i 0.9 55.3146 BR BEAVERDAM ROAD 5.52 km S 12.5 f 0.6 13.8 i 0,9 14.1 t 0.6 13.7 t 0.7 54.113.2 l

PC PLYMOUTH CENTER 6.69 km W 10.6i 0.9 10.9 i 0.6 11.1 i 0 4 11.0107 43.711.5 i

LD LONG POND / DREW RD 6.97 km WSW 11.9 0.7 15.3 t i.0 15.2108 14.211.1 56.6 t 6.6 i

HR HYANNIS ROAD 7.33 km SSE 13.510.7 Missing 15 6 i 0.6 13.510.7 56.8 i 5 2 l

MH MEMORIAL HALL 7.58 km WNW 24.5 t 1.4 25.2 i 1.3 25.110.9 23 9 i 1.2 98 8 t 3.5 l

SN SAQUISH NECK 7.58 km NNW 10.7 i 0.9 13.210.9 12.110.5 11.2 t 0.8 47.2 t 4 8 CP COLLEGE POND 7.59 km SW 12.0 t 0.6 14.9 i 0.9 14.8106 14.510.9 57.214.1 l

Zone 3 TLDs: 8-15 km

[

DW DEEP WATER POND 8 59 km W 15 6 i1.1 17.611.0 18.4 i 0 6 17.4 i 1.3 69 0 i 5.1 LP LONG POND ROAD 8.88 km SSW 12.211.0 13.4 t 0.8 13410.5 12.5 t 0.8 51.5 i 2.9 l

NP NORTH PLYMOUTH 9 38 km WNW 17.6 i1.3 19.1 i 1.1 17.4 i 0.7 19.9 t 3 8 740i64 l

SS STANDISH SHORES 10.39 km NW 14.111.2 12.6 t 0.6 14.1 i 1.0 13.8 i 0.8 54.5 t 3.4 EL ELLISVILLE ROAD 11.52 km SSE 13510.8 14.3 i 0.9 16.3 t 0.6 13 5 t 0.8 57.6 i 5.5 UC UP COLLEGE POND RD 11.78 km SW 12.2 t 0.9 13 8 i 0.7 13.710.5 129i06 52.6133 l

SH SACRED HEART 12.92 km W 13 6 t 1.0 15.310.9 15.9i 0 5 14,3 i 0.8 590i44 i

KC KING CAESAR ROAD 13.11 km NNW 14.3109 14 2 t 0.9 14 8 i 0.7 14 3 i 0.7 57.5120

{

BE BOURNE ROAD 13.37 km S 128108 13.7 t 0.7 14.2 i1.0 12.910.7 53.6 i 3.1 j

SA SHERMAN AIRPORT 13.43 km WSW 13.411.0 14 3 i 0.9 14910.5 13.0 t 0 9 56.5 t 3.0 i

i Zone 4 TLDs: >15 km l

CS CEDARVILLE SUBST 15.93 km S Mtssing 15.910.9 16.6 i 0.6 15.310.7 63.6 i 3.2 i

KS KINGSTON SUBST 16.15 km WNW 13.3 i1.0 14.7 i 0.9 14.6 i 0 9 14 3 t 0.6 57.013.1 LR LANDING ROAD 16.46 km NNW 14 5 t 1.1 14510.7 15.3105 141110 583126 CW CHURCH / WEST 16.56 km NW 13.511.4 12.710.9 13.7 0.5 12.6 f 0.9 52.5 t 2 9 j

MM MAIN / MEADOW 17.02 km WSW Missing 158108 16.0 t 0.5 14.810.9 62.113.2 j

DMF DIV MARINE FISH 20.97 km SSE 15.510.9 16.311.0 17.8 i 0.6 15.6 i 0.8 65.2 i 4 6 j

EW E.WEYMOUTH SUBST 39.69 km NW 17.111.1 17.7 i 0.9 18.410.5 17.7 i1.2 70.8130

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

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

1 1

Page 37 l

l I

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Table 2.4-2 i

On-Site Environmental TLD Results l

TLD Stat'on TLD Location

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

1997 Annual" 10 Description Distance / Direction Jan-Mar -

Apr-Jun Jul-Sep Oct-Dec Exposure mR/vear Onsite TLDs P21 O&M/RXB. JREEZEWAY 50 m SE 24.2 t 1.6 31.5 i 1.4 28.7 t 1.5 26.9 t 1.6 111.3 112.6 P24 EXEC. BUILDING 57 m W 37,6 t 2.6 60 5 t 3.1 58.114.9 531 t 2.5 209.4 i 41.7 PO4 FENCE-R SCREENHOUSE 66 m N 74 8 i 4.1 106.9 i 6 4 93.0 t 9 9 104.3 i 6.2 379.1 1 60.0 P20 O&M - 2ND W WALL 67 m SE -

41.4

• 3.0 75.213.4 71.7 i 3.0 63.514.5 251 8 i 61.2 P25 EXEC. BUILDING LAWN 76 m WNW 278.2 1 12.7 137.8 i 5 3 126.8 i 8.4 112.516.7 655.1 t 308.3 POS FENCE-WATER TANK 81 m NNE 31.911.8 44.112.6 37.4 t 2.2 37.5 i 3.0 150.9 i 20.5 P06 FENCE-OIL STORAGE 85 m NE 46.5 t 3.0 80.5146 54.3 i 3.7 48 4 i 1.6 229 7 i 63.4 P190&M.2ND SW CORNER 86 m S 50.9 i 3 4 81.1139 98.0 t 8.1

- 86.2 i 4.5 316.1 i 80.9 P180&M 1ST SW CORNER 90 m S 35.4 i 3.1 74.4 i 7.6 63.3 t 4 6 57.3 i 4.3 230.4 i 66.5 P06 COMPRESSED GAS STOR 92 m E 43.6 t 2.9 70.1 t 3.8 63.0 t 3.5 56.2 t 3.4 232.8 i 45.6 P03 FENCE-L SCREENHOUSE 100 m NW 64.8 i 3.4 133.5 i 6.8 102.3 t 5.7 84 6 t 4.7 385.2 t 117.0 P17 FENCE-EXEC. BUILDING 107 m W 90.4 i 7.4 170.1 i 13.6 186.7 i10.4 152.3 i 10.4 599.5 i 169.7 P23 O&M - 2ND S WALL 121 m ENE 28.8 t 1.5 53.8 i 2.2 54.5 t 1.6 47.5 t 2.5 184.7 i 48.2 P07 FENCE-INTAKE BAY 121 m SSE 51.6 i 3.2 71.8 t 4.8 63.223.3 57.2 t 2.8 243 8 t 35.4 P26 FENCE-WAREHOUSE 134 m ESE -

37.5 t 2.7 60.0 t 4.1 55.4 t 2.9 52.2 + 2.7 205.2 1 39.5 P02 FENCE-SHOREFRONT 135 m NW 40.0 t 3.6 62.0 t 4.7 64.1 i 4.3 56.9 t 3 6

' 223.0 t 44 4 P09 FENCE-W BOAT RAMP 136 m E 34.5 t 2.2 51.8 t 3.7 47.3 i 4 6 44 5 t 2.5 178.0 t 30.0 P22 O&M 2ND N WALL 137 m SE 28.5 t 1.1 -

47.212.3 45.011.9 40.9 t 2.0 161.5 t 33 6 P16 FENCE-W SWITCHYARD 172 m SW 69.9 i 4.2 126.7 i 7.6 141.2 i 7.6 116.1169 453.8 t 124 0 P11 FENCE-TCF GATE 183 m ESE 75.1 i 3.2 73.114.3 66.3 i 3.0 69.4 i 5.3 283 9 i17.7 P27 FENCE-TCF/ BOAT RAMP 185 m ESE 67.014.3 63 3 i 3.9 54 0 t 3 6 54 7

• 3.0 239 0 t 26.8 P12 FENCE-ACCESS GATE 202 m SE 23 8 i 2.0 36.211.7 36.012.7 34.711.3 130.7 t 24.2 P15 FENCE-E SWITCHYARD 220 m S 28.212.1 46.4 i 2.4 49.5 t 2.7 41.6 t 2.6 165.6 i 37.9 P10 FENCE-TCF/ INTAKE BAY 223 m E 39 2 i 2.3 55.5 i 3.3 53 0 t 3.3 50.4 i 2.8 198.1 t 29.4 P13 FENCE-MEDICAL BLDG.

224 m SSE 24.7 t 1.0 37.213.1 34.8 i 2.9 33.5 i 1.9 130.1 i 22 4 P14 FENCE-BUTLER BLDG.

228 m S 23 3 i 1.3 33.8 t 1.7 32.7 t 1.8 32.8 i 1.9 122.6 i 19 9 P28 FENCE-TCF/PRKNG LOT 259 m ESE 98 0 t 8.2 104 3 i 7.8 113.5 i 7.2 96.5 t 5.6 412.2 1 34.2

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

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

Page 38

Table 2.4 3 Average TLD Exposures By Distance Zone During 1997 l

Average Exposure i Standard Deviation: mR/ period Exposure.

Zone 1*

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

>15 km Jan-Mar 19.1 i 10.6 13.5 i 2.9 13.9 i 1.7 14.7 i 1.6 L

Apr-Jun 24.3 i 18.9 15.3 i 3.0 14.8 i 2.1 15.4 i 1.6 Jul-Sep 25.0 i 21.0 15.6 i 2.7 15.3 1.7 16.1 1.7 Oct-Dec 23.3 i 18.1 14.7 i 2.7 14.5 i 2.4 14.9 i 1.6 Jan-Dec 91.8 i 70.5**

59.0 i 11.5 58.6 i 7.7 61.2 i 6.4

• Zone 1 extends from the PNPS restricted / protected area boundary outward to 3 kilometers (2 miles),

and includes several TLDs located within the site boundary.

• • When TLDs located within the site boundary are excluded, the Zone 1 annual average is calculated to be 63.9 i7.8 mR/yr.

I l

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l Page 39 i

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.=

Table 2.4-4 Beach Survey Exposure Rate Measurements Ambient Radiation Survey Results I

Exposure Rate i 1 std. dev.

Location pR/hr mR/yr,

Beach Terrain White Horse Beach (Near Hilltop Ave) 7.0 i 0.1 61 i 0,9 Sandy, Few granite boulders 2.62 km SE within thirty feet.

Priscilla Beach (in Back of Full Sail Bar) 10.7 i 0.1 94 i 0.9 Sandy with small amounts of 1.89 km SE gravel.

Plymouth Beach (Outer Beach) 6.7 i 0.1 59 i 0.9 Sandy.

7.21 km WNW Plymouth Beach (Inner Beach) 6.4 i 0.1 56 i 0.9 Sandy.

6.07 km WNW Plymouth Beach (Behind Bert's Restaurant) 11.510.1 101 i O.9 Sandy with gravel. Breakwater 3.66 km W and seawall nearby.

Duxbury Beach (Control) 6.9 i 0.1 60 i 0.9 Sandy with coarse gravel and 10.94 km NNW exposed cobble.

q Page 40

Table 2.5-1 Air Particulate Filter Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January December 1997)

MEDIUM: Air Particulates UNITS: pCl/ cubic meter i

lodic h A*=6 H a

• • ='H with Hiaheat Mean Control SM---..

Radionuclides.

Mean -

Sta.. Mean -

~- Mean (No. Analyses)

Required Range -

ID Range

' Range (Non-Routine *)

LLD (No M ae*ad")

(No. Ma**ad")

(No. D=8ae+=d")

GR B (572)

Of;

( 1.7

• O.6)E 2 21- ( 1.9 2 0.6)E-2

. (.1.9 2 0.6)E-2 (0)

( 2.7-39.9)E-3

( 3.6 39.5)E-3

( 3.6 39.5)E-3 (518/520)-

(51152)

' (51/ 52) -

Be (44)

- ( 9.5 t 2.0)E-2 09 ( 1.12 0.2)E 1

( 9.8 t 1.6)E-2 (0)

( 6.5 - 14.7)E-2

( 8.6 12.7)E-2

( 8.5 11.4)E-2 (40/40)

(4/ 4)

(4/ 4)

K-40 ~ (44) '

( 9.7

• 45.4)E 4 15 ( 3.6 t 5.7)E-3

( 3.12 4.8)E 3 (0)

- (-8.4 14.9)E 3

( -4.1 - 7.0)E-3

(-3.2 - 5.7)E-3 (0/ 40)

(0/4)

(0/ 4) L Cs-134 (44) 0.01

(-5.8130.9)E-5 15 - ( 1.4 2 2.6)E-4

( 1.0

• 1.7)E 4 (0)

(-8.8 4.4)E-4

(-1.0 3.6)E-4

( -2.3 - 0.6)E-4 (0/ 40)

(0/ 4)

(0/4)

- co-137 - (44) 0.01

(' 6.1 279.4)E 6 09 ( 3.9 2 2.4)E-4

( 2.5 t 22.9)E-5 (0)

. (.4.5 6.2)E-4

( 1.5 6.2)E-4

(-1.8 2.7)E-4 '

' (0/ 40)

' (0/ 4)

, 0/ 4) -

(

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

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

I Page 41 I-

i l

' Table 2.6-1 Charcoal Cartridge Radioactivity Analyses l

1 i

. Radiological Environrnental Program Summary l

Pilgrim Nuclear Power Station, Plymouth, MA J

(January-December 1997)

-)

MEDIUM: CharcoalFilter UNITS: pCl/ cubic meter j

Indicator Stations Station with Hiahest Mean Control Statior.s Radionuclides Mean Sta. Mean Mean (No. Analyses)

Required Range ID Range Range

)

(Non-Routine *)

LLD (No. Detected")

(No.Dd - W ")'

(No. Detected")

l j

)

\\

I-131 (572) 0.07

( 2.6 81.0)E-4 10 ( 1.6 t 7.9)E-3

(-1.1 i 8.0)E-3 (0)

(-2.7 2.7)E-2

( 1.2 - 2.5)E-2

(-1.7 - 1.8)E-2 j

(0/520)

(0/ 52)

(0/ 52) -

.l I

l

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

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

1 l

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Table 2.7-1 l

Milk Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January-December 1997)

MEDIUM: Milk UNITS: pCi/kg Indicator Stahons S'=% with Hiaheat Mean Control St=%s Radionuclides Mean Sta. Mean Mean (No. Anetyses)

Required Range ID Range Range (Non-Routine *)

LLD (No. Da(Mad")

(No. DaMM")

(No. n.se.a**)

K-40 (40)

( 1.4 2 0.1)E+3 21 ( 1.5 2 0.1)E+3 (1.5 0.1)E+3 (0) '

( 1.3 - 1.7)E+3

( 1.3 - 1.6)E+3

~( 1.3 - 1.6)E+3 (20/20)

(20/ 20)

(20/20)

Sr-89 (40)

(-4.2 i 13.0)E 1 11

(-4.2 213.0)E 1

(-1.0

• 1.5)E+0 t

~(0)

(-2.4 2.8)E+0

(-2.4 - 2.8)E+0

(-4.7-1.6)E+0 -

(0/ 20)

(0/ 20)

~

(0/ 20)

- Sr-90. (40).

( 1.5 t 0.6)E+0 11 ( 1.5 2 0.6)E+0

( 8.2 2 6 4)E-1

- (0)

( 4.4 -24.2)E-1

( 4.4 24.2)E 1

(-3.6 - 21.5)E 1

- (14/ 20)

(14/20)

(5/ 20) 1-131 (40) 1

(-1.12 6.4)E-2 21 ( 3.5 t 6.3)E-2

( 3.5 t 6.3)E-2 (0)

(-1.3 1.1)E-1

( -6.2 - 17.8)E-2

..(-6.2 17.8)E-2 (0/ 20)

(0/20)

(0/ 20)

Cs-134 (40) 15

(-2.121286.0)E-3 11 - - ( 2.1 t 1286.0)E 3

(-7.4 16.6)E 1 (0)

. (-2.1 - 1.9)E+0

(-2.1 - 1.9)E+0

(-3.9 2.9)E+0 (0/ 20)

(0/ 20)

(0/ 20)

Cs-137 ' (40) 15

( 8.7 217.9)E-1 11 ( 8.7

• 17.9)E 1

( 4.9 210.9)E-1 (0)

(-4.0 3 8)E+0

(-4.0 3.8)E+0

( 1.0-2.4)E+0 (0/ 20)

(0/ 20)

(0/ 20)

' Ba-140 (40) 15

( 8.0 24.6)E-1 21

(-2.3 2 21.2)E-1

( 2.3 2 21.2)E 1 (0)

( 7.8 - 5.3)E+0

(-3.8 - 3.4)E+0

(-3.8 3.4)E+0 (0/ 20)

(0/ 20)

(0/ 20)

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

" The fraction of sample analyses yielding detectable measurements (i.e. 23 standard deviations) is shown in parentheses.

I l

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Page 43 1

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l 4

I Table 2.8-1

- Forage Radioactivity Analyses Radiologeal Environmental Program Summary l

Pilgrim Nuclear Power Station, Plymouth, MA (January-December 1997) '

l MEDIUM: Forage ' UNITS: pCi/kg wet Indicator Stations Station with Hiahest Mean Control StMians Radionuclides Mean Sta. Mean

. Mean (No. Analyses)

Required Range ID Range Range

- (Non-Routine *)

LLD (No. Detected **)

(No. DdMM")

(No.Daertad")

1 Be-7 (3)

( 2.1 i 2.0)E+2 33 ( 3.5 21 Ti 1

( 1.9 2 4.1)E+1 (0)

( 8.5 - 34.5)E+1 (0/ 2)

(0/1)

(0/1)

K-40 (3)

( 1.4 21.1)E+3.

33 ( 2.2 2 0.4)E+3

( 5.311.7)E+2 (0)

( 6.8 - 22.1)E+2 (2/ 2)

(1/1)

(t/1) 1-131.

(3)-

( 1.3 2 2.8)E+1 33 ( 2.8 2 3.3)E+1

( 1.2 21.0)E+1 (0)

(-2.9 28.3)E+0 (0/ 2)

(0/1)

(0/1)

Cs-134 (3) 130

(-8.3 2 6.0)E+0

'21

( 2.7 2 7.3)E+0

( 2.7 t 7.3)E+0 (0)

(-1,1 --0.6)E+1 (0/2)

(0/1)

(0/1) 1 Cs-137 (3) 130

.- ( 6.2 t 7.9)E+0 11 ( 1.0 2 0.4)E+1

( 1.1183.0)E-1

{

(0)

( 2.2-10.3)E+0 (0/ 2) '

(0/1)

_ (0/1)

.Th-232 - (3)

(-4.5 t 298.1)E-1 33 ( 1.12 4.6)E+1

( 7.0 2 27.4)E+0

-(0)

( 1.2 1.1)E+1 (0/ 2)

(0/1)

(0/1)

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

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

l Page 44

.I L Table 2.9-1 l

VegetableNegetation Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January December 1997)

.j MEDIUM: Ve9etable/ Vegetation UNITS: pCilkg wet -

trh~ 9di~m Nm with Hiahest Mean Cgatrol Stations I

Radionuclides

[

(No. Analyses)

Mean '

Sta. Mean Mean Required Range-ID Range, 4

- Range

(Non-Routine *)

LLD (No. W =d")-

(No.Da** ad")

- (No. Ddar4ad**)

Be-7 (16)

_-(-1.2 22.3)E+2

( -5.5 - 144.4)E +1.

( 1.1 0.8)E+3 01 ( 2.2 2 0.1)E+3

( 4.7 * (s.8)E+2

- (0).

(8/11)

- (1/1) -

(2/ 5) j K-40 _

(16)

( 2.611.0)E+3 03 -' ( 3.6 2 0.2)E+3

- ( 2.8 2 0.7)E+3 l

(0)

( 1.5 4.5)E+3

- (1/1)

(5/ 5) -

j

( 1.9 3.4)E+3 (11/11)

-l-131 -

(16) 60

(-1.9112.8)E+0

04 ( 2.6 t 1.3)E+1

( 1.9 2 4.3)E+1 j

-(0)

(-3.3 - 1.3)E+1 -

(-8.1 2.6)E+1 -

(0/11)

(0/1)

L (0/ 5)

Cs-134. (16) 60

(-3.12 4.3)E+0 30 's ( 5.0 t 4.5)E+0

( 3.2 2 9.6)E+0 1

- (0)

- (-8.9 5.0)E+0

- (-9.5 15.2)E+0 3

(0/11).

(0/1)

~

- _ (0/ 5) -

Cs-137 (16) 60

- ( 3.1 t 5.1)E+1 01 ( 1.6 2 0.1)E+2 -

( 2.0 i 4.5)E+1 -

3 (0)

(-1.8 15.9)E+1 -

. (-6.3 96.1)E+0 (5/11)

' (1/1)

' (1/ 5) l' Th-232 - (16).

( 7.613.9)E+1 03 ( 1.4 t 0.2)E+2

( 7.9 2 73.0)E+0 -

j (0)

( 5.6 138.8)E+0

( 1.0 0 8)E+2 l

(6/11)

. (1/1)

(1/ 5) :

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

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

q 1

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Page 45

{

e

i I

Table 2.10-1 Cranberry Radioactivity Analyses I

Rachological Environrnental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January December 1997)

MEDIUM: Cranberries UNITS: pCilkg wet Indicator Stations Station with Hichest Mean Control SM%s -

l Radionuclides -

Mean Sta. ' Mean Mean (No. Analyses)

Required Range ID Range Range (Non-Routine *)

LLD (No. Detected")

(No. DdMM**)

(No. DdMM").

Be-7 (3)

( 1.4 2 0.6)E+2 14 _ ( 1.4 2 0.8)E+2

( 1.0 2 6.4)E+1 (0)

( 1.3 1.4)E+2 l'

(0/ 2)

(0/1)

(0/1)

K-40

-(3)

( 5.0 2.4)E+2 23 ( 9.0 2 2.3)E+2

( 9.0 2 2.3)E+2 (0)

( 3.8 6.2)E+2 (0/ 2)

(il1)

(1/1) '

l-131 (3).

(-8.0 2 65.0)E+0 14 ( 3.5 t 3.4)E+1

( 2.0 21.9)E+1 (0)

(-5.1 3.5)E+1 l

(0/ 2)

(0/1)

(0/1)

{

- Cs-134 (3) 60

( 3.3 2 6.1)E+0 14- ( 4.2 9.6)E+0

(-7.3 t 7.5)E+0 l

.(0):

( 2.4 - 4.2)E+0 (0/ 2)

(0/1)

(0/1) l

~

Cs-137 ' (3) 60

. ( 8.7 2 6.2)E+0 13 ( 9.7

• 9.7)E+0

( 7.2 2 9.5)E+0 (0)

.( 7.7 9.7)E+0 (0/ 2)

(0/1)

(

l Th-232 (3)-

( 4.6 2 50.7)E+0 14 ( 3.5 2 4.0)E+1

(-3.7 2 3.7)E+1 (0)

. (-2.6 - 3.5)E+1 (0/ 2)

(0/1)

(0/1)

• Non Routine refers to those radionuclides that exceeded the Reportirig Levels in Technical Specification Table 7,1-1,

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

i l

f l

l Page 46

E Table 2.11-1 l.

Soil' Radioactivity Analyses Raddogical Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January December 1997) l MEDIUM; in situ Soll UNITS: pC1/kg I

Indicator Stations Station with Hiahest Mean Control Stations l

Radmuclides Mean Sta. Mean Mean (No. Analyses)

Required - Range ID Range Range (Hon-Routine *)

LLD (No. Detected")

(No.D* W ")

(No. Detad")

Be-7 (11)

( 2.212.9)E 2 17 ( 6.811.8)E 2

( 2.2 1.3)E 2 l

(-1,1 6.8)E 2 (0)

(1/10)

(1/1)

(0/1)

K-40 (11)

( 10.9 i 3.6)E 3 03 ( 18.8 2 0.4)E 3

( 16.2 2 0.4)E 3

( 6.7 18.8)E 3 (0)

(10/10)

(1/1)

- (1/1),

Co-58 (11)

(-2.3 216.7)E O 00 ( 34 5

• 15.8)E O

( 5.6 t 11.8)E O

(-18.7 - 34.5)E O (0)

- (0/10)

(0/1)

(0/1)

Co-60 (11)

( 1.2116.2)E O 00 ( 23.1212.3)E O

( -6.0 t 8.8)E O

(-16.2 - 23.1)E O (0)

(0/10)

(0/1)

_ (0/1)

Zn-65 (11)

( 5.0 2 48.7)E O 08 ( 60.1 i 36.2)E O

( -5.4 t 5.2)E 1

( 7.9-6.0)E 1 (0)

(0/10)

(0/1)

(O' 1)

Zr-95 (11)

( 6.3 t 24 9)E O 09 ( 53.2 24.4)E O (24.0 23.2)E O

(-3.0 5.3)E 1 (0)

(0/10)

(0/1)

(0/1)

Cs-134 (11)

(1.0 24.4)E O 08 ( 31,5 t 22.5)E O

( 9.0 t 34.0)E O l

(-3.2 - 3.2)E 1 I

(0)

(0/10)

(0/1)

(0/1)

Cs 137 (11)

( 2.3 t 1.9)E 2 01 ( 5.2 2 0.3)E 2

( 5.6 2 2.1)E 1 I

(1.6 52.0)E 1 (0)

(7/10)

(1/1)

(0/1) -

Ce-144 (11)

( 2.2 2 42.2)E i

- 00 ( 9.0 2 6.4)E 2

- (-1.2 t 2.8)E 2

(-5.1 - 9.0)E 2 (0)

(0/10)

(0/1)

(0/1)

Th-232 (11)

( 7.3 21.8)E 2

- 03 ( 117.3 t 3.6)E 1

( 81.4 t 3.3)E 1

( 5.4 - 11,7)E 2 (0)

(10/10)

(1/1)

(1/1)

U-238 (11)

( 5.5 21.2)E 2 03 ( 77.8 2 3.9)E i

( 56.4 3.2)E i

( 4.4 - 7.8)E 2 (0)

(10/10)

(1/1)

(1/1)

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

" The fraction of sample analyses yielding detectable measurements (ii 33 standard deviations) is shown in parentheses.

Page 47 l

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Table 2.12-1 Surface Water Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Pt/ mouth, MA (January December 1997)

MEDIUM: SurfaceWater UNITS: pCl/kg Indicator Stations Station with Hiahest Mean Control StmHans Radionuclides Mean Sta. Mean Mean

'(No. Analyses)

Required Range ID Range Range (Non-Routine *)

LLD (No. Detected")

(No. D#a^d**)

(No Datae+ad")

H-3 (12) 3000

( 9.8 t 35.2)E+1 11 (1.8 4.5)E+2

(-5.8 t 21.6)E+1 (0)

( -3.0 - 8.1)E+2

(-1.6 8.1)E+2

(-2.1 - 1.6)E+2 (0/ 8)

(0/ 4)

(0/ 4)

K-40 (36)

( 1.4 21.5)E+2 11 ( 2.9 2 0.4)E+2

( 2.8 2 0.4)E+2 (0)

(-2.2 37.7)E+1

( 2.0 3.8)E+2

( 1.9 - 3.2)E+2 (12/ 24)

(12/12)

(12/12)

Mn-54 (36) 15

(-1.0 t 11.0)E 1 11 ( 1.2112.6)E-1

(-5.12 8.9)E-1 (0)

( 1.6 2.8)E+0

(-1.2 2.8)E+0

(-1.7 0.8)E+0 (0/ 24)

(0/12)

(0/12)

Co-58 (36) 15

(-7.7 t 121.1)E-2 :

17 ( 7.6 2101.5)E-2

( -6.5 i 9.9)E-1 (0)

( -3.3 - 1.7)E+0

(-1.3 1.7)E+0

(-1.6 1.9)E+0 -

(0/ 24)

(0/12)

(0/12)

Fe-59 (36) 30

( '7.3 2 31.5)E 1 11 ( 1.512.9)E+0

( 5.9 2 29.8)E-1 (0)

( -5.3 - 6.9)E +0

(-2.8 6.2)E+0

( -3.9 - 4.2)E+0 (0/ 24)

(0/12)

(0/12)

Co-60 (36) 15

( 2.0 t 4.6)E+0 11 ( 3.12 6.4)E+0

( 3.2 212.0)E-1 (0) -

( 1.6 - 22.6)E+0

( 1.6 22.6)E+0

(-6.2 36.6)E-1 (1/ 24)

(1/12)

(0/12)

Zn-65 (36) 30

( 1.9 2 31.9)E 1 11 ( 6.12 37.5)E-1

( 4.0 2 25.3)E 1

]

(0)

(-4.2 7.8)E+0

( -4.0 - 7.8)E+0

( -3.9 - 5.3)E+0

' (0/ 24)

(0/12)

(0/12) i Zr 95 (36) 15

(-4.8 t 21.9)E-1 11 ( 2.1 21.2)E-1

(-2.9 t 11.9)E 1 (0)

(-4.4 3.7)E+0

(-2.5 3.7)E+0

(-2.4 1.0)E+0 (0/ 24)

(0/12)

(0/12) 1-131 (36) 1

( 2.9 2 9.5)E-2 17 ( 7.7 t 9.5)E-2

( 5.0 2 8.1)E-2 (0)

(-1.0 2.6)E 1

(-3.8 25.9)E-2

( -6.9 - 19.9)E-2 (0/ 24)

(0/12)

(0/12)

Cs 134 (36) 15

( 1.2 211.9)E-1 11

(-9.1 1145.9)E-2

(-5.2 2 22.8)E 1

- (0)

- (-2.1 2.7)E+0

(-2.1 - 2.7)E+0

( -5.9 - 3.6)E+0 (0/ 24)

(0/12)

(0/12)

Cs-137 (36) 18

(-7.12105.9)E-2 23 ( 9.4 i 86.1)E-2

( 9.4 t 86.1)E-2 (0)

( -2.2 - 1.4)E+0

( -1.2 - 1.4)E+0

(-1.2 1.4)E+0 (0/ 24)

(0/12)

(0/12)

Ba-140 (36) 15

( 6.0 t 237.1)E-2 11 ( 6.12 24.6)E-1

(-8.9 2 23.6)E-1 (0)

( -3.7 - 7.0)E+0

(-2.2 7.0)E+0

(-4.7 2.3)E+0 (0/ 24)

(0/12)

(0/12)

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

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

Page 48

Table 2.13-1 Irish Moss Radioactivity Analyses Radiological Erwironmental Program Summary Pilgrim fluclear Power Station, Plymouth, MA

- (January - December 1997)

MEDIUM: Irish Moss UNITS: pCilkg wet Indicator Stations -

Station with Hiahest Mean Control mdb Radionuclides Mean Sta. Mean Mean (No. Analyses) -

Reqdred Range 10 Range Range

. (Non-Routine *)

' LLD (No. Detected")

(No. DdM_ad")

(No.DdMtM"1 Be 7 (16)

( 2.3 21.6)E+2 '

22. ( 3.7 21.4)E+2

( 1.2 21.0)E+2 (0)

( 2.4 52.4)E+1

( 2.1 -5.2)E+2

( 2.4 22.4)E+1 (3/12)

(1/ 4)

(0/ 4)

K-40 (16)

( 6.3 21.3)E+3 34 - ( 7.4 t 1.5)E+3 -

( 7.4 21.5)E+3 (0)

( 4.7 - 8.2)E+3

( 5.8 -8.9)E+3

( 5.8 8.9)E+3 (12/12)

(4/ 4)

' (4/ 4)

Mn-54 (16)

( -2.2 i 6.6)E+0 34 ( 4.1

• 7.0)E+0

( 4.12 7.0)E+0 (0)

. (-1.3 0.6)E+1

( 1.1 9.1)E+0

(-1,1 - 9.1)E+0 (0/12)

(0/ 4)

(0/ 4)

Co-58 (16)

( 2.7 210.2)E+0 11 ~ ( 6.8

• 15.5)E+0

( 4.8 t 194.5)E 1 l f

(0)

( 1.2 2.7)E+1

( -5.5 - 27.3)E+0

(-2.1 2.5)E+1 -.

l (0/12)

(0/ 4)

(0/ 4)

Fe-59 (16)

( 3.7 2 30.2)E+0 11 ( 2.3 i 3.1)E+1

. ( 7.12 66.6)E+0

'l

- (0)

(-5.5 5.0)E+1

( -1.3 - 5.0)E+1

( -4.6 - 10.0)E+1 (0/12)

(0/4)

- (0/ 4) l Co-60 (16)

( 6.4 t 9.9)E+0 11 ( 1.6 i 1.1)E+1

- ( 5.2 2 8.7)E+0 (0)

(-3.7 29.4)E+0 -

( 6.3 29.4)E+0

(-2.4 14.1)E+0 (0/12)

(0/ 4)

(0/ 4)

Zn-65 (16)

( 4.2 t 34.0)E+0 11 ( 3.8

• 3.7)E+1

( -2.3 24.9)E+0 (0)

( -3.6 - 8.3)E+1

( 0.0 8.3)E+1

(-3.3 - 1.5)E+1 (0/12)

(0/4)

(0/ 4).

l' Cs-134 (16)

(-7.1 t 12 0)E+0 11 ( 3.7 10.9)E+0

(-4.3 t 4.7)E+0 (0)

(-3.8 1.1)E+1

( 1.2 - 1.1)E+1

(-6.9 0.3)E+0 (0/12)

(0/ 4)

(0/ 4) l Cs-137 (16)

(-4 6 2 63.7)E-1 15 ( 3.218.8)E+0

(-3.8

• 11.2)E+0

. (0)

(-1.1 1.2)E+1

(-7.0 11.5)E+0

( 1.9 - 0.4)E+1 (0/12)

(0/ 4)

(0/ 4)

Th-232 (16)

( 2.4 2 3.6)E+1 22 ( 6.2 2 2.2)E+1

(-8.6 2 29.6)E+0 (0).

(-3.7 7.3)E+1

( 4.4 7.3)E+1

( 3.4 - 2.2)E+1 (0/12)

(0/ 4)

(0/ 4) l

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

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

l l

l Page 49 L

r:

l:.

j J

)

Table 2.14-1 l-Shellfish Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station. Plymouth, MA (January December 1997)

MEDIUM: Shellfish UNITS: pC1/kg wet Indicator Stations Station with Hiohest Mean Control Stations -

Radionuclides Mean Sta. Mean Mean

, (No. Analyses)

Required Range ID ' Range Range (Non-Routme*)

LLD INo. Detected **)

(No. Detected")

(No. Detected")

Be 7 (48)

- ( 2.6

• 6.6)E+1 11 ( 3.4 2 2.2)E+1

( 2.8 t 7.9)E+1 (0)

(-8.2 27.4)E+1

( 1.5 7.0)E+1

( -5.9 - 33.4)E+1 (4/ 24)

(3/ 8)

(2/ 24)

K-40 (48)

( 8.9

• 4.9)E+2 15 ( 1.12 0.2)E+3

( 7.6 2 6.2)E42 (0)

( 0.0 - 1.7)E+3

( 9.1 - 13.0)E+2

( 5.0 - 200.0)E+1 (20/24)

(4/4)

(19/24)

Mn-54 '(48) 130

(-1.2139.1)E-1 13 ( 1.3 2 6.0)E+0

( 7.4

• 55.6)E-1 (0)

( -9.3 - 9.1)E+0

( -1.2 - 1,1)E+1

(-1.2 1.1)E+1 (0/ 24)

(0/16)

(0/ 24)

Co 58 (48) 130

( 9.1146.9)E-1 12 ( 1.6 t 6.8)E+0

(-8.3 t 71.8)E-1 (0)

( -9.6 - 12.9)E+0

(-9.6 12.9)E+0

( -2.0 - 2.0)E+1 I

(0/ 24)

(0/12)

(0/ 24)

' Fe-59 (48)-

260

( 9.0198.4)E-1 13 ' ( 4.8 2 20.0)E+0

( 2.8 216.2)E+0 (0)

( -3.2 - 2.2)E+1

( 3.0 - 4.4)E+1

( -3.0 - 4.4)E+1 (0/ 24)

(0/16)

(0/ 24)

Co-60.(48) 5

( 2.4 t 6.4)E+0 11 ( 4.9

• 3.8)E+0

( 1.6

• 6.4)E+0 (0)

( -1.0 - 2.1)E+1

( 1.2 - 10.3)E+0

(-6.3 21.8)E+0 (5/ 24)

(5/ 8)

(0/ 24)

]

Zn-65 (48) 5

( 2.5 2 30.4)E+0 12 ( 3.5 t 44.2)E+0

(-2.2 216.2)E+0 (0)

(-7.4 9.0)E+1

(-7.4 9.0)E+1

(-3.9 2.9)E+1 (0/ 24)

(0/12)

(0/ 24)

Zr-95 (48) 5

( 2.7 t 8.7)E+0 13 ( 5.3 t 14.1)E+0

( 3.5 211.6)E+0 (0)

(-1.2 2.8)E+1

( -1.0 - 3.8)E+1

(-1.0 3.8)E+1 (0/ 24)

(0/16)

(0/ 24) j Cs-134 (48) 5

(-2.0 t 8.4)E+0 24 ( 3.6 t 16.1)E-1

( 1.0 t 6.4)E+0 (0)

(-3.1 - 1.0)E+1

(-1.5 3.9)E+0

(-1.6 1.2)E+1 (0/ 24)

. (0/ 8)

(0/ 24)

Cs-137 (48) 5

(-5.3 t 377.5)E-2 12 ( 1.8 2 5588.7)E-3

(-1.0 2 8.6)E+0

- (0)

(-9.8 12.1)E+0

(-9.8 12.1)E+0

( -2.6 - 1.8)E+1 (0/ 24)

(0/12)

(0/ 24)

Ce-144 (48) 15

( 6.3 t 32.1)E+0 13 ( 1.7 2 40.6)E+0

( 1.2 t 32.6)E+0

')

(0)

(-1,1 0.5)E+2

( -5.4 - 9.3)E+1

( -5.4 - 9.3)E+1 1

(0/ 24)

(0/16)

(0/ 24)

Th-232 (48)

( i.2 2 2.9)E+1 13 (4.5 5.7)E+1

( 3.4 2 4.9)E+1 (0)

(-6.6 8.3)E+1

(-6.1 15.9)E+1

( -6.1 - 15.9)E+1 (4/ 24)

(6/16)

(10/24)

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

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

Page 50

Table 2.15-1 Lobster Radioactivity Analyses.

Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (Jariuary-December 1997) 1 I

MEDIUM: Lobster UNITS: pCl/kg wet -

Indicator Stations Station with Hiahest Mean Control S+=hans Radionuclides Mean -

Sta. Mean Mean (No. Analyses)

Required Range ID Ran9e Range (Non-Routine *)

LLD (No. Detected **)

(No.Da8M e*)'

(No. D=8MW*)

Be-7 (5)

( 7.1 t 8.5)E+1 11 - ( 7.12 8.5)E+1

(-1.0 21.1)E+2 (0)

(-3.5 - 13.1)E+1

( 3.5 - 13.1)E+1 (0/ 4)

(0/ 4)

(0/1)

K-40 (5)

( 2.2 0.6)E+3 98 ( 2.4 2 0.4)E+3 -

( 2.4 i o.4)E+3 (0)

( 1.6 - 3.0)E+3 (4/ 4) '

- (1/1)

(1/1)

Mn-54 ' (5) 130

(-9.4 2 85.3)E-1 11

(-9.4 t 85.3)E-1

(-2.0 21.2)E+1 (0)

(-6.9 8.9)E+0

( 6.9 - 8.9)E+0 (0/ 4).

(0/ 4)

(0/1)

- Co-58 (5) 130

(-3.6 t 13.0)E+0 98 ' ( 4.7 t 16.0)E+0

'~( 4.7 t 16.0)E+0

-(0)

( 1.5 1.2)E+1 j

(0/ 4)

(0/1)

(0/1)

]

Fe-59 ~ (5) 260

( 5.0 t 21.1)E+0 98 ( 5.9 2 3.6)E+1

( 5.9 t 3.6)E+1 (0) -

(-1.5 2.6)E+1 (0/ 4)

(0/1)

(0/1) l Co.60 (5) 130

( 9.6 2 61.0)E-1 98 ( 4.6 t 12.1)E+0

( 4.6 212.1)E+0 (0)

(-4.0 3.0)E+0 (0/ 4)

(0/1)

(0/1)

)

Zn-65 (5) 260

( 1.1 t 3.4)E+1 98 ( 1.6 2 3.2)E+1

( 1.613.2)E+1 (0)

( -2.2 - 4.1)E+1

{

(0/ 4)

(0/1)

(0/1)

Cs 134 (5) 130

( 1.8

• 13.7)E+0 98 ( 1.4 i 1.4)E+1

( 1.4 21.4)E+1 (0)

(-1.8 1.3)E+1 (0/ 4)

(0/1)

(0/1)

Cs-137 (5) 130

(-5.3 21222.7)E 2 98 ( 1.2 t 1.4)E+1

( 1.2 21.4)E+1 (0)

(-1.5 1.0)E+1 (0/ 4)

(0/1)

(0/1)

Th-232 (5)

( 1.4 2 3.0)E+1 11 ( 1.4 2 3.0)E+1

(-3.2 2 4.6)E+1 (0)

(-1.4 3.5)E+1

( -1.4 - 3.5)E+1 (0/ 4)

(0/ 4)

(0/1)

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

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

Page 51

l Table 2.16-1 l'

Fish Radioactivity Analyses Radiological Environmental Program Summary

[

- Pilgrim Nuclear Power Staten, Plymouth, MA (January December 1997)

MEDIUM: Fish. UNITS: pCi/kg wet Indicator Stations '

Station with Hlahest Mean Control Stations Radionuclides Moon

- Sta. Mean Mean

- (No. Analyses)

Required Range ID Range Range (Non-Routine *)

LLD (No Detected")

(No. DMMM*)

(No.DM M e ')

l Be-7 (26)

( 3.917.6)E+1 97 ( 4.1 i 5.6)E+1

( 1.9 2 5.4)E+1 i

(0) -

(-8.7 19.2)E+1

( 8.9 89.1)E+0

(-3.8 8.9)E+1 (0/18)

(0/ 4)

(0/ 8)

. K (20)

( 3.0 t 0.6)E+3 98 ( 3.3

• 0.5)E+3 -

( 2.9 2 0.7)E+3 (0)

( 1.7 3.9)E+3

( 2.7 - 3.8)E+3

( 1.7 3.8)E+3 (18/18)

(4/ 4)

(8/ 8)

Mn-54. (26)-

130

( 1.6 i 11.6)E+0 98 - ( 2.1 t 12.0)E+0

( -5.4 103.0)E-1 (0)

(-1.7 3.3)E+1

(-9.1 - 10.7)E+0

( 1.7-1.1)E+1 (0/18) '

(0/ 4)

. (0/ 8)

Co-58 (26) 130

(-2.4 2 9.7)E+0 08 - ( 1.4 2 0.9)E+1

( 6.7 215.7)E+0 (0) -

( -2.0 - 1.3)E+1

( 7.8 - 20.2)E+0

(-1.8 2.5)E+1 (0/18)

(0/ 4)

(0/ 8)

Fe (26) 260

( 6.2124.8)E+0 11 ( 6.2 2 24.8)E+0

( 1.813.8)E+1 (0)

(-5.1 5.3)E+1

(-5.1 5.3)E+1

( 9.1 - 1.4)E+1 (0/18)

(0/18)

(0/ 8)

[

Co-60 (26) 130

( 7.0 t 14.3)E+0 11 ( 7.0 214.3)E+0

' (-1.5 t 12.8)E+0 (0)

(-2.0 3.7)E+1

(-2.0 3.7)E+1

( -1.8 - 1.5)E+1 (0/18)

' (0/18)

(0/ 8)

Zn-65 (26) 260

( 7.3 28.8)E+0 98 ( 2.5 1.8)E+1

( 1.3 t 2.3)E+1 (0)

( -4.4 - 5.3)E+1

( 1.9 3.2)E+1

( 2,1 - 3.6)E+1 (0/18)

(0/ 4)

(0/ 8)

Cs-134 (26) 130

(-1.5 t 8.0)E+0 98 ( 3.7 t 136.4)E-1

(-1.9 212.3)E+0 (0)

( -1.9 - 1.1)E+1

( 1.2 1.7)E+1

(-1.6 1.7)E+1 (0/18)

(0/ 4)

(0/ 8)

Co 137 (26) 130

( 2.4 t 71.4)E 1 97 ( 5.5 t 16.0)E+0

( 1.6 212.0)E+0.

(0).

( 1.0 1.3)E+1

( 7.6 25.0)E+0

( 1.1 2.5)E+1 (0/18)

(0/ 4)

(0/ 8)

Th-232 (26)

( 5.0 41.7)E+0 98 ( 6.2 2 5.4)E+1

( 3.4 i 5.5)E+1 (0)

( -6.6 - 11.1)E+1

( 3.6 - 101.3)E+0

( -2.8 - 10.1)E+1 (0/18)

(0/ 4)

(0/ 8)

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

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

l l

Page 52

i j

Table 2.171 Sediment Radioactivity Analyses o

R6 % logical Environrnentas Program Summary Pilge Nuclear Power Station, Plymouth, MA '

(January December 1997)

MEDIUM: Sediment UNITS: pCl/kg dry Indcator Stations Station with Hiahest Mean Control Swians Radionuclides Mean Sta. Meen Mean (No. Analyses)

Required Range ID Range Range (Non-Routine *)

LLD-(No. Detected") -

(No. rwe.a**) '

(No. Da**")

l Be-7

-(56)

( 1.4 2 3.0)E+1 -

13 ( 5.7

• 13.5)E+1

( 4.5 210.9)E+1 (0)

(-3.6 a 10.0)E+1

(-1.7 44.8)E+1

(-1.7 44.8)E+1 (1/ 39)

(1/11)

(1/17)

- K-40

-(56)

( 8.710.9)E+3 13 ' ( 1.12 0.1)E+4

( 1.1 i 0.1)E+4 (0)

( 6.6 10.5)E+3

( 1.0 - 1.3)E+4

( 9.3 13.4)E+3 (39/39)

(11/11)

(17/17)

~ Co-58 (56) 50

( 2.2 2 2.8)E+0

-24

(-9.12 28 8)E-1

(-2.4 2 3.3)E+0 (0)

( 7.8 - 2.8)E+0

(-5.3 2.2)E+0

( 7.9 4.5)E+0 1

(0/ 39)

(0/ 6)

(0/17)

Co.60 (56) 50

( 7.0 2 28.8)E 1 12 ( 1.5't 2.4)E+0

( 3.7 2 23.5)E-1 (0)

(-7.3 6.0)E+0

~ (-2.3 - 4.1)E+0

(-3.0 4.5)E+0 l

(0/ 39)

(0/11)

(0/17)

Zn-65 (56) 50

( 7.0 210.2)E+0 24 ( 1.2 21.6)E+1

( 4.4 215.3)E+0 (0)

( 1.4 2.8)E+1 '

( -3.9 - 27.6)E+0

(-1.0 2.8)E+1 (0/ 39)

(0/ 6)

(0/17)'

Zr-95 (56) 50

. ( 4.8 2 5.5)E+0 13 ( 6.4 t 5.1)E+0

( 4.7 & 6.4)E+0 (0)

(-7.0 19.2)E+0

(-3.0 13.5)E+0

( 1.1 1.4)E+1 (0/ 39)

(0/11)

(0/17)

Cs-134 (56) 50

( 2.5 2 5.9)E+0 24 ' ( 2.5 2 242.7)E-2

(-2.2 2 3.1)E+0 (0)

(-1.4 1.1)E+1

(-2.5 3.0)E+0 -

(-7.9 - 3.0)E+0 -

(0/ 39)

(0/ 6)

(0/17)

. Cs-137 (56) 50 (4.2 7.5)E+0 13 ( 2.0 2 0.5)E+1

( 1.5 t 0.9)E+1 (0)

( -4.8 - 23.6)E+0

( 1.4 3.0)E+1

( 8.7 296.9)E 1 (6/ 39)

(11/11)

(12/17)

Ce-144 (56) 150

(-6.1 i 11.3)E+0 14. ( 1.5 t 1631.9)E-2

( -4.4 i 16.9)E+0 (0).

(-2.8 2.4)E+1

(-2.1 2.4)E+1

( 3.6 - 2.8)E+1 (0/ 39)

(0/ 6)

(0/17)

Th-232 (56)

( 3.5 t 1.1)E+2 11 ( 4.5 1.1)E+2

( 4.12 0.6)E+2 (0)

( 1.2-6.8)E+2

( 2.7 6.8)E+2

( 3.0 5.6)E+2 (39/39)

(11/11)

(17/17)

Pu-238 (6)

(-1.7 2 0.7)E+0 13 ( 6.8 210.3)E 1

( 6.8 t 10.3)E-1 (0)

(-2.1 1.0)E+0

( 5.0 - 130.0)E-2

( 5.0 130.0)E-2 (0/ 4)

(0/ 2)

(0/ 2)

Pu-239 (6)

( 1.010.4)E+0 13 ( 1.5 21.1)E+1

( 1.5 i 1.1)E+1 '

(0)

( 6.4 - 13.1)E-1

( 6.8 - 22.4)E+0

( 6.8 - 22.4)E+0 (0/4)

(2/ 2)

(2/ 2)

• Non-Routine refers to those radionuclides that exceeded the Reporting Levels in Techncal Specif' ation Table 7.1 1.

c

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

r Page 53

Table 2.17-2 Sediment Plutonium Analyses

-l l

Environmental Radiological Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 1997)

I pCi/kg (dry)i1 S.D.

{

l Location Core Depth (cm)

Plutonium-238 Plutonium-239/240 Discharge Canal Outfall 0-2 NDA NDA 1

Discharge Canal Outfall -

12-14 NDA NDA Plymouth Harbor '

0-2 NDA NDA Manomet Point 0-2 NDA NDA-Duxbury Bay - Control 0-2 NDA 22.4 i 1.5 Duxbury Bay - Control 12-14 NDA 6.8 i 1.0

-* NDA indicates no detectable activity.

Page 54

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

• Descnotion TCode Distance / Direction ~

TLDs Within Protected Area O&M/RXB. BREEZEWAY P21 50 m SE EXEC. BUILDING P24 57 m W FENCE-R SCREENHOUSE '

PO4 66 m N O&M - 2ND W WALL P20 67 m SE EXEC. BUILDING LAWN P25 76 m WNW FENCE-WATER TANK POS 81 m NNE FENCE-OIL STORAGE P06 85 m NE l

O&M 2ND SW CORNER -

P19 86 m S OSM 1ST SW CORNER P18 90 m S COMPRESSED GAS STOR P08 92 m E FENCE-L SCREENHOUSE -

P03 100 m NW -

FENCE-EXEC. BUILDING P17 107 m W O&M -2ND S WALL P23 121 m ENE FENCE-INTAKE BAY P07 121 m SSE i

FNCE WAREHOUSE P26 134 m ESE

{

l 'MCE-SHOREFRONT P02 135 m NW l

INCE-W BOAT RAMP P09 136 m E O&M - 2ND N WALL P22-137 m SE FENCE-W SWITCHYARD P16 172 m SW FENCE-TCF GATE P11 183 m ESE FENCE-TCF/ BOAT RAMP P27 185 m ESE FENCE-ACCESS GATE P12 202 m SE FENCE-E SWITCHYARD P15 220 m S FENCE-TCF/lNTAKE BAY P10 223 m E

{

FENCE-MEDICAL BLDG.

P13 224 m SSE FENCE-BUTLER BLDG P14 228 m S FENCE-TCF/PRKNG LOT P28 259 m ESE Distance and direction are measured from contarline of Reactor Buil ding to the monitoring location.

4 Page 55

Figure 2.2-1 (continued)

Environmental 7LD Locations Within the PNPS Protected Area

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Page 56

l i

Figurn 2.2-2 TLD and Air / Soil Sampling Locations: Within 1 Kilometer TLD Station -

Location

• Air / Soil Sampji,ng Station, Locatum*

Description Code Distance / Direction Description Code Distance / Direction Zone i TLDs: n.3 km BOAT LAUNCH WEST BLW 0.11 km E OVERLOOKAREA OA 0.15 km W OVERLOOK AREA OA 0.15 km W PEDESTRIAN BRIDGE PB 0.21 km N HEALTH CLUB.

TC 0.15 km WSW MEDICAL BUILDING WS 0.23 km SSE BOAT LAUNCH EAST BLE 0.16 km ESE EAST BREAKWATER EB 0.44 km ESE PEDESTRIAN BRIDGE.

PB 0.21 km N PROPERTY LINE

- PL 0.54 km NNW -

SHOREFRONT SECURITY

. P01.

0.22 km NNW W ROCKY Hit '.

• 0AD WR 0.83 km WNW MEDICAL BUILDING WS 0.23 km SSE E Rt,KY HILL ROAD ER-0.89 km SE PARKING LOT -

CT 0.31 km - SE SHOREFRONT PARKING PA 0.35 km NNW STATION A A-0.37 km WSW STATIOli F F

0.43 km NW STATION B B

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

0.47 km SW STATION I I

0.46 km WNW STATION L L

0.50 km ESE STATION G G

0.53 km W STATION D D

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

0.57 km ESE HALL'S BOG HB 0.63 km SE GREENWOOD HOUSE

-GH 0.65 km ESE W ROCKY HILL ROAD WR 0.83 km WNW E ROCKY HILL ROAD ER 0.89 km SE Page 57

Figure 2.2-2 (continued)

TLD and Air /SoilSampling Locations: Within 1 Kilometer N

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J Page 58

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Figure 2.2 3 i

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

_ TLD Station Location

• Air / Soil Samp{ng State Location

• Description '

I Code-Distance / Direction Description l Code Drstance/Directe l

Zone 1 TLDs: 0-3 km MICROWAVE TOWER MT 1.03 km SSW CLEFT ROCK CR 1,27 km SSW j

CLEFT ROCK ~

CR 1.27 km SSW MANOMET SUBSTATION MS 3 to km SSE BAYSHORE/ GATE RD BD 1.34 km WNW MANOMET ROAD MR' 1.38 km S DIRT ROAD DR 1.48 km SW EMERSON ROAD EM 1.33 km SSE EMERSON /PRISCILLA EP 1.55 km SE EDISON ACCESS ROAD AR 1.59 km SSE BAYSHORE BS 1.76 km W STATION E E-1.86 km S JOHN GAULEY JG 1.99 km W STATION J J

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

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

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

1 I

i l

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Page 59

4 l

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1 Figure 2.2-3 (continued)

TLD and Air /Soll Sampling Locations: 1 to 5 Kilometers 9i -

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Figure 2.2-4

. TLD and Air / Soil Sampling Locations: 5 to 25 Kilometers TLD Station Location

• Air /SoilSamphng Station Location

• Description Code Distance / Direction Description Code Distance / Direction Zone 2 TLDs: 3-8 km HILLDALE ROAD

-HD 5.18 km W PLYMOUTH CENTER PC' 6.69 km W MANOMET BEACH

.MB 5.43 km SSE BEAVERDAM ROAD BR 5.52 km S PLYMOUTH CENTER PC 6.69 km W LONG POND / DREW RD LD 6.97 km WSW HYANNIS ROAD HR 7.33 km SSE 1

MEMORIAL HALL -

MH 7.58 km WNW SAQUISH NECK SN 7.58 km NNW COLLEGE POND

-CP 7.59 km SW Zone 3 TLDs: 8-15 ja DEEP WATER POND DW 8.59 km W LONG POND ROAD LP 8.88 km SSW NORTH PLYMOUTH NP 9.38 km WNW STANDISH SHORES SS 10.39 km NW ELLISVILLE ROAD EL 11.52 km SSE UP COLLEGE POND RD UC 11.78 km SW SACRED HEART SH 12.92 km W KING CAESAR ROAD KC 13.11 km NNW BOURNE ROAD BE 13.37 km S SHERMAN AIRPORT SA 13.43 km WSW Zme 4 TLDs >15 km CEDARVILLE SUBST CS 15.93 km S KINGSTON SUBST KS 16.15 km WNW LANDING ROAD Ut 16.46 km NNW CHURCH / WEST CW 16.56 km NW MAIN / MEADOW MM 17.02 km WSW DIV MARINE FISH DMF 20.97 km SSE

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

Page 61

4 6

Figure 2.2-4 (continued)

TLD and Air /Soll Sampling Locations: 5 to 25 Kilometers

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

• Description Cods Distance / Direction

• MILK SURFACE WATER Plymouth County Farm CF 5.6 km W Discharge Canal DIS 0.2 km N Whitman Farm Control WF 34 km WNW Bartiett Pond BP 2.7 km SE Powder Point Control PP 13 km NNW f_QB8Gf.

Whipple Farm WH 2.9 km SW IRISH MOSS j

Plymouth County Farm CF 5.6 km W Discharge Canal Outfa5 DlS 0.7 km NNE Whitman Farm Control WF 34 km WNW Manomet Point MP 4.0 km ESE Ellisville EL 12 km SSE YLQETABLESNEGETATION Brant Rock Control BK 18 km NNW Site Boundary C BC 0.5 km SW Site Boundary B BB 0.5 km ESE SHELLFISH Rocky Hill Road RH 0.9 km SE Discharge Canal Outfall DIS 0.7 km NNE Site Boundary D Bd 1.1 km SSW Plymouth Harbor PLY-H 4.1 km W Site Boundary A BA 1.5 km SSW Manomet Point MP 4.0 km ESE Clay Hill Road CH 1.6 km W Duxbury Bay Control DUX-BAY 13 km NNW Brook Road BK 2.9 km SSE Powder Point Control PP 13 km NNW Beaverdam Road BD 3.4 km S Green Harbor Control GH 16 km NNW Plymouth County Farm CF 5.6 km W Div. Marine Fisheries DMF 21 km SSE LOBSTER Bridgewater Farm Control BF 31 km W Discharge Canal Outfall DlS 0.5 km N Norton Control NC 50 km W Plymouth Beach PLB 4.0 km W Plymouth Harbor PLY-H 6.4 km WNW CRANBERRIES Duxbury Bay Control DUX-BAY 11 km NNW Manomet Point Bog MR 3.9 km SE Bartlett Road Bog BT 4 3 km SSE FISHES Pine Street Bog Control PS 26 km WNW Discharge Canal Outfall DIS.

0.5 km N Plymouth Beach PLB 4.0 km W Jones River Control JR 13 km WNW Cape Cod Bay Control CC-BAY 24 km ESE N River-Hanover Cortrol NR 24 km NNW Cataumet Control CA 32 km SSW Provincetown Control PT 32 km NE Buzzards Bay Control BB 40 km SSW Priest Cove Control PC 48 km SW Nantucket Sound Control NS 48 km SSE Atlantic Ocean Control AO 48 km E Vineyard Sound Control MV 64 km SSW SEDIMF.HI l

Discharge Canal Outfall DlS 0.8 km NE l

Plymouth Beach PLB 4 0 km W l

Manomet Point MP 3.3 km ESE Plymouth Harbor PLY-H 4.1 km W Duxbury Bay Control DUX-BAY 14 km NNW Green Harbor Control GH 16 km NNW

)

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

Page 63

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Page 64

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Figure 2.2-6 J

' Environrnental Sampling And Measurernrat Control Locations Description Code Distance / Direction * '

Description Code Distance / Direction

• ILQ SURFACE WATER Cedarville Sub.tation CS 16 km S Powder Point Control PP 13 km NNW Kingston Substation KS 16 km WNW Landing Road '

LR 16 km. NNW '

181S]1 MOSS Church & West Street CW 17 km NW Brant Rock Control BK 18 km NNW Main & Meadow Street MM 17 km WSW l

Div. Marine Fishenes DMF 21 km SSE SHELLFISH East Weymouth Substation EW 40 km NW Duxbury Bay Control DUX-BAY 13 km NNW Powder Point Control PP' 13 km NNW AIR SAMPLER Green Harbor Control GH 16 km NNW EastWeymouth Substatum EW 40 km NW LOBSTER M!!$

Duxbury Bay Control DUX-BAY 11 km NNW j

Whttman Farm Control WF 34 km WNW FISHES EQBAGE Jones River Control JR 13 km WNW Whitrnan Farm Control WF 34 km WNW Cape Cod Bay Control CC-BAY 24 km ESE N River-Hanover Control NR 24 km NNW YEQETABLES/ VEGETATION Cataumet Control CA 32 km SSW Div. Marine Fish. Control DMF 21 km SSE Provincetown Control PT 32 km NE Bridgewater Farm Control BF 31 km W Buzzards Bay Control BB 40 km SSW Norton Control NC SO km W Priest Cove Control PC 48 km SW Nantucket Sound Control NS 48 km SSE Atlantic Ocean Control AO

- 48 km E CRANBERRIES Vineyard Sound Control MV 64 km SSW Pine Street Bog Control PS 26 km WNW SEDIMENT I

EQJL Duxbury Bay Control DUX-BAY 14 km NNW EastWeymouth Substation EW 40 km NW.

Green Harbor Control GH 16 km NNW

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

l l

Page 65 I

s Figut e 2.2-6 (continued)

Environmental Sampling And Measurement Control Locations SYMBOL KEY O Smunsu 04 BLUEMVSSEL)

($ SOFT SEELLCULM)

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)

Historical Beach Survey Exposure Rate Measurements i

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0 77 79 81 83 85 87 89 91 93 95 97 Year

-+-Whitehorse Beach at Hilltop Avenue

-m-Priscilla Beach at Full Sail Bar

-A-Plymouth Beach - Outer

-x-Plymouth Beach - Inner

-*-Plymouth Beach at Berts

-*- Duxbury Beach Control Figure 2,4-1 Historical Beach Survey Exposure Rate Measurements Page 67

Airborne Gross-Beta Radioactivity Levels Near Station Monitors l

0.05 0.04 g

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Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month - 1997

-+- AP-00 Warehouse

- m-AP-07 Pedestrian Bridge

-A-AP-08 Overlook Area

-x-AP-09 East Breakwater

-*- AP-21 East Weymouth Control Figure 2,5-1 Airbome Gross-Beta Radioactivity Levels: Near Station Monitors Page 68 j

l i

Airborne Gross-Beta Radioactivity Levels Property Line Monitors l

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Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month - 1997

-+- AP-01 E. Rocky Hill Road

-u-AF-03 W. Rocky Hill Road

-A-AP-06 Property Line

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

l l

l Airborne Gross-Beta Radioactivity Levels Offsite Monitors 0.05 0.04 O.03 E

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Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month - 1997

-+- AP-10 Cleft Rock

-s-AP-15 Plymouth Center

-A-AP-17 Manomet Substation

-x-AP-21 East Weymouth Control l

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

l Page 70

(

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Levels of Strontium-90 in Milk Samples 4

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Figure 2.7-1 Levels of Strontium-90 in Milk Samples i

Page 71

3.0

SUMMARY

OF R.ADIOLOGICAL IMPACT ON HUMANS I

The radiological impact to humans from the Pilgrim Station's radioactive liquid and gaseous j

releases has been estimated using two methods:

l

(

1) calculations based on measurements of plant effluents; and

2) calculations based on measurements of environmental samples.

l 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 i

radioactive liquid and gaseous effluents released from Pilgrim Station during 1997 were l

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 l

calculations are listed in Appendix A.

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

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

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

3) ingestion of fish and shellfish.

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

i

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

2) inhalation of airbome radioactivity;

3) textemal 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 preserted 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 i

December 31,1997.

Page 72

Table 3.0-1 Radiation Doses from 1997 Pilgrim Station Operations Maximum Individual Dose From Exposure Pathway - mrem /yr Liquid Gaseous Ambient Receptor Effluents Effluents

• Radiation **

Total Total Body 0.02 0.45 1.8 2.3 Thyroid '

O.004 1.0 1.8 2.8 Max. Organ 0.07 1.0 -

1.8 2.9

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

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

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

The Nuclear Regulatory Commission (NRC) specifies a whole body dose limit of 100 mrem /yr to be received by the maximum exposed member of the general public. This limit is set forth in Section 1301, Part 20, Title 10, of the U.S. Code of Federal Regulations (10CFR20). By comparison, the Environmental Protection Agency (EPA) limits the annual whole body dose to 25 mrem /yr, which is specified in Section 10, Part 190, Title 40, of the Code of Federal Regulations (40CFR190).

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

As can be seen from the doses resulting from Pilgrim Station Operations during 1997, all values are well within the federal limits specified by the NRC and EPA. In addition, the calculated doses from PNPS operation represent only a fraction of a percent of doses from natural and man-made radiation.

A second method of dose estimation involves calculations based on radioactivity detected in environmental media.

During 1997, the only sample media that indicated detectable radioactivity attributable to PNPS were seawater collected from the discharge canal during the l

month of March, and blue mussels collected during the second and third quarters, all of which contained low levels of Co-60. The dose resulting from these pathways is estimated at 0.005 mrem, and would be included as part of the 0.02 mrem total body dose from liquid effluents listed in the table above. A more detailed calculation of these doses from specific pathways can be found in Appendix A.

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

Page 73 L

4.0 REFERENCES

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

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

j l

3)- National Council on Radiation Protection and Measurements, Report No. 03, "lonizing Radiation Exposures of the Population of the United States," September 1987.

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

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

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

7) Boston Edison Company, Pilgrim Nuclear Power Station Off-site Dose Calculation Manual, Revision 7, November 1997.

i

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

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

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

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

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

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

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

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

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

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

- January 9,1979.

18) D. Keefer, Duke Engineering and Services, "1997 Annual Direct Radiation Survey at Beaches Near Pilgrim Station," EL 16/98, January 20,1998.

Page 74

' APPENDIX A'

~ SPECIAL STUDIES

. A. SEAWATER RADIOACTIVITY DOSE IMPACT Pilgrim Station was involved in a refueling outage from mid-February through'mid-April 1997.

- During such refueling outages, more radioactive liquids are typically processed and discharged from the plant. During the month of. March, liquids-discharged from the plant following processing contained about 0.033 Curies (33 millicuries) of cobalt-60. This amount is about-

'87 times that normally released during a monthly period. Coupled with this higher than normal release of radioactivity, the plant's circulating water _ pumps were shut down for maintenance,-

and operated only during periods of liquid discharges. This resulted in a monthly circulating water volume of about 40% of normal. The net result is that the effective concentration of t

Co-60 in the discharge canal was about 225-times higher than normal. Even though the-concentration of Co-60 discharged during the month of March was much higher than normal, the concentration in the discharge canal was still well below (less' than 0.06%) the effluent concentration limit specified by the NRC in 10CFR20, Appendix B,' Table 2.

The composite water sample collected from the discharge canal during the month of March was the only sample during the year which contained detectable levels of cobalt-60. Routine dose calculations performed for liquid effluents during the month of March yielded a total body dose to the maximum-exposed individual from Co-60 of 0.005 mrem. This dose would be included as a component of the 0.02 mrem tots! body dose presented in Table 3.0-1 of this-report. As such, this total body dose would include dose contributions from various pathways, including Ingestion of fish and shellfish, radiation " shine" from radioactivity deposited in shoreline sediments, and recreational dose from swimming and boating.

The dose assessment methodology used to estimate dose consequences from liquid effluent releases yields conservative values. As an intermediate step to calculate the resulting dose,

- the concentrations of Co-60 are estimated within each of the various environmental pathways.

Using the values for the_ month of March, the doses were based on predicted concentrations of

- cobalt-60 of 35 pCi/kg !n. fish, 350 pCi/kg in shellfish, and 370 pCi/kg in sediment. By comparison, the environmental monitoring program conducted at PNPS during 1997 yielded no detectable Co-60 in fish (<23 pCi/kg) and sediment (<10 pCi/kg) collected following the outage. Although Co-60 was detected in mussel samples collected after the outage, the observed concentrations of 5.8 and 2.1 pCi/kg, respectively, for the second and third quarters, were well below the predicted concentration of 350 pCi/kg. Therefore, although the dose calculations are conservatively based on predicted pathway concentrations which should be

)

readily detectable, the monitoring program validates that the resulting doses are much less than those predicted by the dose assessment method.

B. SHELLFISH RADIOACTIVITY DOSE IMPACT During 1997, cobalt-60 was detected in edible portions of blue mussels collected from the discharge canal outfall during the second and third quarters. These were the first samples collected following the refueling outage, which took place between February and April,1997.

During the refueling outage, additional liquid radioactive wastes were processed and discharged. Circulating water flow was also diminished during the refueling outage. Although concentrations.of radionuclides were always maintained well below concentration limits specified in 10CFR20, the combination of larger releases and lower water flow resulted in higher than normal concentrations of radioactivity in the discharge canal. Concentrations of Page 75

r

=

)

]

5.8 and 2.1 pCi/kg were observed in the mussel samples collect during the second and third

. quarters, respectively. Samples. collected during the fourth quarter yielded no detectable l

Co-60 activity (less than 1.2 pCi/kg).

Ingestion of shellfish is considered within the routine dose assessments performed for liquid discharges. ' Therefore, any dose resulting from this pathway is already accounted for in the l

dose values presented in Section 3 of this report. However, since Co-60 was detected in blue ll mussels, an assessment of the dose resulting specifically from the ingestion of this medium

..was perfonned. An average concentration of 4.0 pCl/kg for edible portions of blue mussels

(.

' was used. Ingestion rates of shellfish for the maximum exposed individual in each age class.

as listed in the PNPS ODCM were assumed (adult = 9 kg/yr, teen = 6 kglyr, child = 3 kglyr) to determine the amount of Co-60 ingested via this pathway. The resulting dose was estimated l-by multiplying the ingestion intake (pCi) of cobalt-60 by the total body dose conversion factor 1

(mrem /pCi ingested) as listed in Regulatory Guide 1.109. Results of these calculations are l

listed below.

pCi Co-60 Total Body DCF Total Body Dose Age Class Ingested mrem /pCi mrem Adult 36 4.72E-06 1.70E-04 Teen 24 6.33E-06 1.52E-04 Child 12 1.56E-05 1.87E-04 i

Based on the above calculations, the mcximum total body dose received from the ingestion of i.

shellfish containing cobalt-60 is less than 0.0002 mrem. This additional dose would be l

considered negligible in comparison to the 300-400 mrem received by the average individual each year from other sources of radiation exposure.

1 1

1 lI l

l Page 76

]

l l

APPENDIX B l

Effluent Release Information i

TABLE TITLE PAGE SupplementalInformation: January June 1997 77 1A Gaseous Effluents Summation of All Releases 78 January-June 1997

~

18 Gaseous Effluents - Elevated Releases 79 January-June 1997 1C Gaseous Effluents - Ground Level Releases 80

~

~

January-June 1997 2A Liquid Effluents Summation of All Releases 81 January-June 1997:

2B Uquid Effluents: January-June 1997 82 SupplementalInformation: July-December 1997 83

~

1A Gaseous Effluents Summation of All Releases 84 July-December 1997 1B Gaseous Effluents - Elevated Releases 85 July-December 1997

~

~

1C Gaseous Effluents - Ground Level Releases 86 July-December 1997 2A Liquid Effluents Summation of All Releases 87 2B Liquid Effluents: July-December 1997 88 Page 77

Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Supplementalinformation January-June 1997 FACILITY: PILGRIM NUCLEAR POWER STATION LICENSE: DPR-35

1. REGULATORY LIMITS

a. Fission and activation gases:

500 mrem /yr total body and 3000 mrem /yr for

_ skin at site boundary b,c. lodines, particulates with half-life:

1500 mrem /yr to any organ at site boundary

>8 days, tritium

d. Liquid effluents:

0.06 mrem / month for whole body and 0.2 mrem / month for any organ (without radwaste treatment)

2. EFFLUENT CONCENTRATION LIMITS

a. Fission and activation gases:

10CFR20 Appendix B Table Il

b. lodines:

10CFR20 Appendix B Table Il

c. Particulates with half-life > 8 days:

10CFR20 Appendix B Table ll

d. Liquid effluents:

2E-04 Cl/mL for entrained noble gases; 10CFR20 Appendix B Table il values for all other radionuclides

3. AVERAGE ENERGY Not Applicable

4. EIEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY

a. Fission and activation gases:

High purity germanium gamma spectroscopy

b. lodines:

for all gamma emitters; radiochemistry

c. Particulates:

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

d. Liquid effluents:

Sr-89, and Sr-90

5. DATCH RELEASES Jan-Mar 1997 Apr-Jun 1997

a. Liquid Effluents

~

1. Total number of releases:

3.20E+01 3.70E+01

2. Totaltime period (minutes):

3.32E+03 2.68E+03

3. Maximum time period (minutes):

9.25E+02 2.40E+02

4. Average time period (minutes):

1.04E+02 7.25E+01

5. Minimum time period (minutes):

2.00E+01 2.00E+01

6. Average stream flow (Liters / min):

1.55E+05 9.29E+05 during periods of release of effluents into a flowing stream

b. Gaseous Effluents None None

6. ABNORMAL RELEASES

a. Liquid Effluents None None

b. Gaseous Effluents None None

{

Page 78

l l

Table 1A l

Pilgrim Nuclear Power Station Effluent and Waste Disposal Report i

Gaseous Effluents - Summation of All Releases January-June 1997 Period:

Period:

Estimated Jan-Mar 1997 Apr-Jun 1997 Total Error A. FISSION AND ACTIVATION GASES TotalRelease: Cl 5.53E+01 6.47E+01 i22 %

l Average Release Rate During Period: uCi/sec 7.01 E+00 8.20E+00 Percent of Technical Specification Limit B. IODINES j

Total lodine-131 Release: Ci 4.69E-03 3.49E-04 i20%

l Average Release Rate During Period: nCl/sec 5.95E-04 4.43E-05 Percent of Technical Specification Limit

.]

C. PARTICULATES Total Release: Cl 8.70E-04 4.41E 121 %

l Average Release Rate During Period: nCi/sec 1.10E-04 5.59E-05 Percent of Technical Specification Limit Gross Alpha Radioactivity: Cl NDA NDA D. TRITIUM Total Release: Ci 1.12E+01 7.01E+00

• 20%

l Average Release Rate During Period: pCi/sec 1.42E+00 8.89E-01 Percent of Technical Specification Limit Notes for Table 1 A:

• Percent of Technical Specification limit values in above sections are based on dose assessments not performed as part of this report. These will be provided in the annual supplemental dose assessment report to be issued prior to April 1,1998.

1. NDA stands for No Detectable Activity.

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

I l

Page 79

Table 1B Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents Elevated Release January-June 1997 Continuous Mode Batch Mode Nuclide Released Jan-Mar 1997 l Apr Jun 1997 Jan-Mar 1997 l Apr-Jun 1997

1. FISSION AND ACTIVATION GASES - Cl Kr-85m 1.04E+01 1.31E+01 N/A N/A Kr-87 NDA 5.11E+00 N/A N/A Kr-88 3.54E+00 1.97E+01 N/A N/A Xe 131m NDA NDA N/A N/A Xe-133 4.00E+01 1.01 E+01 N/A N/A Xe 135 1.39E+00 3.04E+00 N/A N/A Xe-135m NDA 2.53E+00 N/A N/A Xe-137 NDA 1.12E+01 N/A N/A i

Xe-138 NDA NDA N/A N/A Total for period 5.53E+01 6.47E+01 N/A N/A

2. IODINES - Ci 1-131 7.85E-04 2.04E-04 N/A N/A l-133 7.86E-04 8.98E-04 N/A N/A Total for period 1.57E-03 1.10E-03 N/A N/A

3. PARTICULATES -Cl Mn-54 1.53E-06 NDA N/A N/A Co-60 1.97E-06 5.69E-06 N/A N/A Sr-89 8.60E-06 8.91 E-05 N/A N/A Sr-90 NDA NDA N/A N/A Cs-124 NDA NDA N/A N/A Cs-137 NDA 1.61 E-06 N/A N/A Ba/La-140 1.10E-05 2.42E-04 N/A N/A Total for period -

2.31 E-05 3.38E-04 N/A N/A

4. TRITIUM - Cl l H-3 l

2.51 E-01 l

6.88E-01 l

N/A l

N/A l

Notes for Table 18:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

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

1E 12 Cl/cc Particulates:

1 E-11 Cl/cc Page 80

l Table 1C Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Ground Level Release January-June 1997 Continuous Mode Batch Mode Nuclide Released Jan-Mar 1997 l Apr-Jun 1997 Jan-Mar 1997 l Apr-Jun 1997

1. FlSSION AND ACTIVATION GASES -Cl Kr-85m NDA NDA N/A N/A Kr 87 NDA NDA N/A N/A Kr-88 NDA NDA N/A N/A Xe-133 NDA NDA N/A N/A Xe-135 NDA NDA N/A N/A Xe-135m NDA NDA N/A N/A Xe 138 NDA NDA N/A N/A Total for period NDA NDA N/A N/A

2. IODINES - Cl 1131 3.90E 03 1.45E-04 N/A N/A l133 3.22E-03 9.52E-04 N/A N/A Total for period 7.12E-03 1.10E-03 N/A N/A

3. PARTICULATES - Cl Cr 51 7.99E-05 NDA N/A N/A Mn-54 2.48E-04 1.52E-05 N/A N/A Fe-59 8.93E-05 NDA N/A N/A Co-58 1.25E-05 NDA N/A N/A Co-60 2.92E-04 3.19E-05 N/A N/A Sr 89 4.20E-05 5.62E-05 N/A N/A Sr-90 NDA NDA N/A N/A Ru-103 1.13E-05 NDA N/A N/A Cs-134 NDA NDA N/A N/A Cs-137 NDA NDA N/A N/A Ba/La 140 7.20E-05 NDA N/A N/A Total for period 8.47E 04 1.03E-04 N/A N/A l H-3 l

1.09E+01 l

6.32E+00 I

N/A l

N/A l

Notes for Table 1C:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

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

1E-12 Ci/cc Particulates:

1E-11 C1/cc Page 81

j l

Table 2A Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents - Summation of All Releases January-June 1997 Period:

Period:

Estimated Jan-Mar 1997 Apr-Jun 1997 Total Error A. FISSION AND ACTIVATION PRODUCTS Total Release (not including H-3 noble gas, or alpha): Ci 6.30E-02 5.91 E-02 i12%

l Average Diluted Concentration During Period: pCi/mL 1.22E-07 2.37E-08 j

Percent of Effluent Concentration Limit

• 2.51 E+00%

2.79E-01 % _

B. TRITIUM Total Release: Ci 4.47E+00 1.34E+01

.i9.4%

l Average Diluted Concentration During Period: Cl/mL 8.69E-06 5.38E-06 i

Percent of Effluent Concentration Limit

• 8.69E-01%

5.38E-01%

C. DISSOLVED AND ENTRAINED GASES Total Release: Ci NDA NDA i16 %

l Average Diluted Concentration During Period: nCl/mL NDA NDA Percent of Effluent Concentration Limit

• NDA NDA D. GROSS ALPHA RADIOACTIVITY l TotalRelease: Ci l

NDA l

NDA l

i34 %

l l

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

4.94E+05 l

1.38E+06 l

i5.7%

l F. VOLUME OF DILUTION WATER USED DURING PERIOD

. l Dilution Volume: Liters l

5.14E+08 l

2.49E+09 l

f10%

l Notes for Table 2A:

• Additional percent of Technical Specification limit values based on dose assessments will be provided in the annual supplemental dose assessment report to be issued prior to April 1,1998.

1. NDA stands for No Detectable Activity.

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

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

i Page 82

Table 2B Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents January-June 1997 Continuous Mode Batch Mode Nuclide Released Jan-Mar 1997 l Apr-Jun 1997 Jan-Mar 1997 l ' Apr-Jun 1997

'1. FISSION AND ACTIVATION PRODUCTS -Cl Cr-51 N/A-N/A 4.24E-03 3.67E-03 Mn-54 N/A N/A 4.18E-03 1.60E-02 Fe-55 N/A N/A 1.13E-02 1.70E-02 Fe-59 N/A N/A-1.02E-03 4.44E 03 Co 58 N/A N/A 2.37E-03 9.73E-04 Co-60 N/A N/A 3.29E-02 1.59E-02 Zn-65 N/A.

N/A 5.93E-03 1.26E-04 Sr-89 N/A N/A NDA NDA Sr 90 N/A N/A 1.59E 06 3.19E-05 Zr/Nb-95 N/A N/A 1.15E-04 2.23E-05 l

Mo-99/Tc-99m N/A N/A NDA NDA Ru-103 N/A N/A 4.58E-04 NDA Aa-110m N/A N/A 2.69E 04 4.52E-04 Sb-124 N/A N/A 9.98E-07 1.64E-04 l-131 N/A N/A NDA NDA l-133 N/A N/A NDA NDA Cs-134 N/A N/A NDA NDA Cs-137 N/A N/A 2.01E-04 2.69E-04 Ba/La-140 N/A N/A NDA NDA Ce 141 N/A N/A 6.82E-05 4.13E-05 Total for period N/A N/A 6.30E-02 5.91E 02

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

1. N/A stands for not applicable.

2.- NDA stands for No Detectable Activity.

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

Strontium:

SE-08 Cl/mL lodines:

' 1 E-06 Cl/mL Noble Gases: 1E-05 pCl/mL All Others:

SE-07 Cl/mL Page 83

(

l l

l l

Pilgrim Nuclear Power Station j

Effluent and Waste Disposal Report SupplementalInformation July-December 1997 FACILITY: PILGRIM NUCLEAR POWER STATION LICENSE: DPR-35

1. REGULATORY LIMITS

a. Fission and activation gases:

500 mrern/yr total body and 3000 mrem /yr for skin at site boundary b,c. lodines, particulates with half-life:

1500 mrem /yr to any organ at site boundary

]

>B days, tritium

d. Liquid effluents:

0.06 mrem / month for whole body and 0.2 mrem / month for any organ (without radwaste treatment)

2. EFFLUENT CONCENTRATION LIMITS

a. Fission and activation gases:

10CFR20 Appendix B Table ll

b. lodines:

10CFR20 Appendix B Table ll

c. Particulates with half-life > 8 days:

10CFR20 Appendix B Table ll

)

d. Liquid effluents:

2E-04 Cl/mL for entrained noble gases:

10CFR20 Appendix B Table Il values for all other radionuclides

3. AVERAGE ENERGY Not Applicable

4. MEASUREMENTS AND APPROXIMATIONS OF TOTAL RADIOACTIVITY

a. Fission and activation gases:

High purity germanium gamma spectroscopy

b. lodines; for all gamma emitters; radiochemistry

c. Particulates:

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

d. Liquid effluents:

Sr-89, and Sr-90

5. BATCH RELEASES Jul-Sep 1997 Oct-Dec 1997

a. Liquid Effluents 0

x

1. Totalnumberof releases:

1.30E+01 1.10E+01

2. Totaltime period (minutes):

7.20E+02 1.40E+03

3. Maximum time period (minutes):

1.90E+02 2.80E+02

~ 4. Average time period (minutes):

5.54E+01 1.27E+02

5. Minimum time period (minutes):

2.00E+01 2.00E+01

6. Average stream flow (Liters / min):

1.18E+06 1.17E+06 during periods of release of effluents into a flowing stream

b. Gaseous Effluents None None

6. ABNORMAL RELEASES

a. Liquid Effluents None None i

b. Gaseous Effluents None None Page 84

Table 1 A Pilgrim Nuclear Power Station Effluent and Waste Disposal Report.

Gaseous Effluents - Summstion of All Releases July-Decemt,r 1997 -

Period:

Period:

Estimated Jul-Sep 1997 Oct-Dec 1997 Total Error A. FISSION AND ACTIVATION GASES

]

Total Release: -Cl 3.14E+01 4.22E+01

• 22% -l' Average Release Rate During Period: pCi/sec ~

3.98E+00 5.35E+00 Percent of Technical Specification Limit B. lODINES Totallodine-131 Release: Cl 3.89E-04 3.64E-04 i20 %

l Average Release Rate During Period: Cl/sec 4.93E-05 4.61 E-05 Percent of Technical Specification Limit -

C. PARTICULATES -

Total Release: Cl 5.07E-04 5.43E-04 i21 %

-l

\\verage Release Rste During Period; nCl/sec 6.43E-05 6.89E 'ercent of Technical Specification Limit l Gross Alpha Radioactivity: Cl NDA NDA D. TRITIUM Total Release: Cl 1.63E+01 7.97E+00 20%

l Average Release Rate Durin0 Period: Cl/sec 2.07E+00 1.01E+00 Percent of Technical Specification Limit Notes for Table 1A:

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

- raport to be issued prior to April 1,1998.

1.. NDA stands for No Detectable Activity.

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

Pags 85

c..

Table 1B Pilgrim Nuclear Power Station Effluent and Waste Disposal RQort Gaseous Effluents - Elevated Release July-December 1997 Continuous Mode Batch Mode Nuclide Released Jul-Sep 1997 - l Oct-Dec 1997 Jul-Sep 1997 l Oct-Dec 1997

1. FISSION AND ACTIVATION GASES -Ci-Kr-85m 9.28E+00 1.08E+01 N/A N/A Kr-87 NDA 3.84E+00 N/A N/A Kr-88 8.62E+00 1.74E+01 N/A N/A Xe-131m NDA NDA N/A N/A Xe-133 1.35E+01 9.85E+00 N/A N/A 9

~

Xe-135 NDA 3.10E-01 N/A N/A Xe-135m NDA NDA N/A N/A Xe-137 NDA NDA N/A N/A Xe-138 NDA NDA N/A N/A Total for period 3.14E+01 4.22E+01 N/A N/A

2. lODINES - Ci 1-131 2.26E-04 2.35E-04 N/A N/A l-133 7.67E-04 7.39E N/A N/A Total for period 9.93E-04 9.74E-04 N/A-N/A

3. PARTICULATES - Ci Mn-54 l

NDA 2.37E-05 N/A N/A Fe-59 NDA 5.44E-06 Co-60 NDA 2.35E-05 N/A N/A Sr-89 4.89E 05 9.87E-05 N/A N/A Sr-90 NDA NDA N/A N/A Cs-134 NDA NDA N/A N/A Cs-137 NDA 1.93E-06 N/A N/A Ba/La-140 2.08E-04 1.39E-04 N/A N/A Total for period 2.57E-04 2.92E-04 N/A N/A

4. TRITIUM - Ci l H-3 l

1.21 E+00 l

5.83E-01 l

N/A l

N/A l

Notes for Table 1B:

1. N/A stands for not applicat'e;

2. NDA stands for No Detectable Activity.

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

j Fission Gases: 1E-04 Cl/cc lodines:

1E-12 Cl/cc Particulates:

1E-11 Ci/cc Page 86

Table 1C i

Pilgrim Nuclear Power Station i

Effluent and Waste Disposal Report I

Gaseous Effluents - Ground Level Release

{

July-December 1997 I

Continuous Mode Batch Mode Nuclide Released Jul-Sep 1997 l Oct-Dec 1997 Jul-Sep 1997 l Oct-Dec 1997

1. FISSION AND ACTIVATION GASES -Cl i

~

Kr-85m NDA NDA N/A N/A Kr-87 NDA NDA N/A N/A Kr-88 NDA NDA N/A N/A Xe-133 NDA NDA N/A N/A Xe-135 NDA NDA N/A N/A Xe-135m NDA NDA N/A N/A Xe-138 NDA NDA N/A N/A Total for period NDA NDA N/A N/A j

I

2. IODINES - Ci

-I-131 1.63E-04 1.29E-04 N/A N/A l-133 1.37E-03 1.27603 N/A N/A

)

Total for oeriod 1.53E-03 1.40E-03 N/A N/A

3. PARTICULATES - Cl Mn-54 NDA NDA N/A N/A Co-60 2.47E-05 9.59E-06 N/A N/A Sr-89 2.08E-04 2.09E-04 N/A N/A 1

Sr-90 NDA NDA N/A N/A Cs-134 NDA NDA N/A N/A Cs-137 9.19E-06 NDA N/A N/A Ba/La-140 7.83E-06 3.25E-05 N/A N/A Total for period 2.50E-04 2.51 E-04 N/A N/A l H-3 l

1.51 E+01 l

7.39E%

l N/A l

N/A l

i i

Notes for Table 1C:

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

Fission Gases: 1E-04 Cl/cc l

lodines:

1E-12 Cl/cc Particulates:

1E-11 Cl/cc Page 87

Table 2A Pilgrim Nuclear Power Station Effluent and Waste Disposal Re port Liquid Effluents - Summation of All Releases July-December 1997 Period:

Period:

Estimated Jul-Sep 1997 Oct-Dec 1997 Total Error A. FISSION AND ACTIVATION PRODUCTS Total Release (not including H 3, noble gas, or alpha): Cl 3.05E-03 6.97E-03 i12%

l j

Average Diluted Concentration During Period: pCUmL 3.61E-09 4.25E-09 Percent of Effluent Concentration Limit

• 4.92E-02%

4.64E-02%

B. TRITIUM i

Total Release: Cl 4.84E-02 5.73E+00 i9.4 %

l Avera0e Diluted Concentration During Period: pCi/mL 5.72E-08 3.50E-06 Percent of Effluent Concentration Limit

• 5.72E-03%

3.50E-01%

~C. DISSOLVED AND ENTRAINED GASES Total Release: Ci NDA NDA i16 %

l Average Diluted Concentration During Period: Ci/mL NDA NDA Percent of Effluen* Concentration Limit

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

NDA

.l NDA l

i34 %

l E. VOLUME OF WASTE RELEASED PRIOR TO DlLUTION l Waste Volume: Liters l

1.02E+05 l

6.04E+05 l

i5.7%

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

8.46E+08 l

1.64E+09 l

i10 %

l Notes for Table 2A:

• Additional percent of Technical Specification limit values based on dose assessments will be provided

. in the annual supplemental dose assessment report to be issued prior to April 1,1998.

1. NDA stands for No Detectable Activity.

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

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

Page 83

Table 28 i

Pilgrim Nuclear Power Statioa.

Effluent and Waste Disposal Report Liquid Effluents July-December 1997 Continuous Mode Batch Mode Nuclide Released Jul Sep 1997 l Oct-Dec 1997 Jul-Sep 1997 l Oct-Dec 1997

{

1. FISSION AND ACTIVATION PRODUCTS -Ci Cr-51 N/A N/A 6.80E 06 NDA j

Mn-54 N/A N/A 5.12E-04 8.68E-04 Fe-55 N/A N/A 1.68E-03 4.55E-03 Fe-59 N/A N/A 3.17E-05 5.30E-06 Co-58 N/A N/A 8.92E-06 1.63E-06 1

Co-60 N/A N/A 6.42E-04 1.38E-03 I

Zn-65 N/A N/A 3.26E-06 3.20E-06 Sr-89 N/A N/A 9.31 E-07 NDA Sr-90 N/A N/A 1.72E-06 7.23E-05

= Zr/Nb-95 N/A N/A NDA NDA Mo-99/Tc-99m N/A-N/A NDA NDA Ru-103 N/A N/A NDA NDA y

A0-110m N/A N/A 2.96E-06 1.16E-05 Sb-124 N/A N/A 1.29E-06 NDA l-131 N/A N/A NDA 5.89E-06 l-133 N/A N/A NDA NDA Cs-134 N/A N/A NDA NDA Cs-137 N/A N/A 1.60E-04 7.32E-05 Ba/La 140 N/A N/A NDA NDA Ce 141 N/A N/A NDA NDA Total for period N/A N/A 3.05E-03 6.97E-03

2. DISSOLVED AND ENTRAINED GASES -Ci Xe-133 N/A N/A NDA NDA Xe-135 N/A N/A NDA NDA Total for period N/A N/A N D.*

NDA Notes for Table 28:

3

1. N/A stands for not applicable.

2. NDA stands for No Detectable Activity.

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

Strontium:

SE-08 Cl/mL lodines:

1E-06 Ci/mL Noble Gases: 1E-05 Ci/mL All Others:

SE-07 Ci/mL Page 89 i

s

APPENDIX C -

LAND USE CENSUS RESULTS -

The annual land use census for gardens and milk and meat animals in the vicinity of Pilgrim.

Station was performed between October 27 and 31,1997..The census was conducted by driving along each improved road / street in the Plymouth area within 5 kilometers (3 miles) of Pilgrim Station to survey for visible _ gardens with an area of greater than 500 square feet. In compass sectors where no gardens were identified within 5 km (SSW and NNW sectors), the survey was extended to 8 km (5 mi). A_ total of 30 gardens were identified in the vicinity of Pilgrim Station. In addition, the Town ~ of Plymouth Animal Inspector was contacted for information regarding milk and meat animals.

Atmospheric deposition (D/Q values) at the locations of the identified gardens were compared to those for the existing sampling program locations. These comparisons enabled Boston Edison' Company personnel to ascertain the best locations for monitoring fnr releases of airbome 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 !he 1997 land use census, samples of garden-grown vegetables or naturally-growing vegetation (e.g. grass, leaves from bushes or -

trees, etc.) were collected at or near the closest gardens in.each of the following !andward compass sectors. These locations, and their distance and direction relative to the PNPS Reactor Building, are as follows:

Rocky Hill Road 0.9 km SE Brook Road - _..

2.9 km OSE Beaverdam Road 3.4 km S Clay Hill Road 1.6 km W in addition to these special sampling locations identified and sampled in conjunction with the 1997 land use census, samples were also collected at or near the Plymouth County Farm (5.6 km W), Whipple Farm (2.9 km SW), and from a control location at Bridgewater Farm (31 km W).

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

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

Highest Main Stack D/Q:

1.5 km SSW Highest Reactor Building Vent D/Q:

0.5 km ESE 2nd highest D/Q, Main Stack:

1.1 km S 2nd highest D/Q, Reactor Building Vent:

0.8 km SE

' Control sample of naturalty-growing vegetation were collected at the DMF shop in Sandwich (21 km SSE) and in Norton, MA (50 km W).

No new milk or meat animals were identified during the land use census, in addition, the Town 1-of Plymouth Animal inspector stated that their office is not aware of any animals at locations otherinan 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 1997 sampling program.

1 I

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N APPENDIX D l:

ENVIRONMENTAL MON;TORING PROGRAM DISCREPANCIES i.-

There were a number of instances during 1997 in which inadvertent issues were encountered q

in the collection of environmental samples. All of these issues were minor in nature and did not have en adverse affect on the results or integrity of the' monitoring program. Details of these various problems are given below, i:

In 1997, six thermoluminescent dosimeters (TLDs) were not recovered from their assigned locations during the quarterly retrieval process. During the first quarter, the TLDs were not

' recovered at Right of Way (RW), Cedarville Substation (CS), and Main & Meadow (MM). - In j

' these cases, the TLDs missing from their. posted locations were presumably lost to storm damage or vandaEsm. - During the second quarter retrieval, TLDs were missing at Manomet I

l Elementary (ME) and Hyannis Road (HR). In each of these cases, the plastic straps, plastic cages, and TLDs were missing and presumably lost due to vandalism. The TLD at Emerson Road.(EM) was missing during the ' fourth quarter-retrieval, and was presumably lost to vandalism. In all cases of TLD losses, the TLDs were re-located in the immediate vicinity, but L

steps were taken whenever possible to post the TLD cages in a less conspicuous manner.

[

The 434 TLDs which were collected (98.6%) allowed for adequate assessment of the ambient radiation levels in the vicinity of Pilgrim Station.

-l Within the air sampling program, there were a few instances in which continuous sampling was interrupted at the eleven airborne sampling locations during 1997. 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 L

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.

l l

When sampling interruptions resulted from power losses, steps were taken to restore power as L

soon as possible. Power was. interrupted ai the Pedestrian Bridge when the ground fault L

interrupt circuit tripped during the period of 09-Apr-96 through 17-Apr-96 (18 hour2.083333e-4 days <br />0.005 hours <br />2.97619e-5 weeks <br />6.849e-6 months <br /> run time).

This breaker trip was due to salt spray entering the sampler enclosure during high winds. Due j

to the low run time and sample volumes, the required LLDs were not met on the particulate g

filter and charcoal cartridge collected during this week, and the results were not included in the values presented in Tables 2.5-1 and 2.6-1.

. An interruption to power service was experienced at Overlook Area (OA) during the week of l

25-Feb through 03-Mar-997. This coincided with the refueling outage at PNPS, when load l

- shifting was being performed and interrupted power to this location. The sampler ran 122.7 l

hour out of the possible 168-hour sampling period. Load shifting was also suspccted as being i

related to an interruption in power at the Pedestrian Bridge (PB) air sampler during the week of 04-Mar to 11-Mar-1997, when the ground fault interrupt breaker was tripped. The sampler ran 21.2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.s out of the required 168_ hour period. Despite the low sample volumes, lower limits of detection were met on all samples.

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l A major snow storm hit southem New England on 01-April, which caused damage to niectrical' service at some locations. Power was interrupted at Pedestrian Bridge (PB) and Cleft Rock (CR), which ran 170.9 and 162.4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />si respectively, out of a 192-hour sampling period during the week of 25-Mar through 02-Apr-1997.

' Pump failures occurred Plymouth Center (PC) during the week of 14-Jan to 21-Jan-1997, and 1

L Cleft Rock (CR) during the week of 04-Mar to 11-Mar-1997. In each of these cases, the defective pump was replaced with an operating unit, and did not impact the monitoring program.

During the fourth quarter, several pumps experienced partial failure of the diaphragm during

- the sampling week. - When the sample was exchanged at the end of the week, the measured flow volume was much greater than indicated by the in-line flow indicator. Although the units continued to sample'at a diminished rate, corrections needed to be applied to the sampled volumes ' collected through the filters.- These diaphragm failures occurred at Warehouse (WS) during the period 07-Oct to 14-Oct-1997; and at Overlook Area (OA) and East Rocky Hill Road (ER) during the period 04-Nov to 12-Nov-1997, in each case, the sampler continued to

{

operate, and volumes in excess of 300 cubic meters were collected by each unit, yielding l

sufficient sample volume to achieve required LLrs.

i l-Despite the lower-than-normal _ sampling volumes in the various instances involving power l

interruptions and equipment failures, required LLDs were met on all 572 of the 572 particulate filters and 572 iodine cartridges collected during 1997. None of the 1188 sample analyses performed indicated any questionable or ano~malous results. When viewed collectively during the entire year of 1997, the following sampling recoveries were achieved in the airbome t

sampling program:

Location Recovery Location Recovery Location Recovery WS 100.0 %

PB 97.7 %

PC 99.9 %

i I

ER 99.7 %

OA 99.2 %

MS 99.9%

I WR 99.9 %

EB 100.0 %

EW 100.0 %

PL 99.9%

CR 99.6 %

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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 j

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 l

calculated deposition coefficients (D/Q) for airbome releases from PNPS. Such samples l_

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.

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1 A second sub-sample of Group 11 (near-bottorn distribution) fish was not collected in the vicinity of the discharge canal outfall during the first quarter of 1997. This situation also occurred for Group I (bottom-distribution) fish during the fourth quarter. Fish species in these categories j

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 second sub-samples.

In summary, the various problems encountered in collecting environmentai samples during i

1997 were relatively minor whan viewed in the context of the entire monitoring program.

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 j

1

' ntroduction i

n J

The accuracy of the data obtained through Boston Edison Company's Radiological Environmental Monitoring Program (REMP). is ensured through a comprehensive Quality i

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 Duke Engineering and Services Environmental Laboratory (DESEL). Much of the information contained herein has been summarized from the DESEL " Semi-Annual Quality Assurance Status Report: January -

June 1997," and the DESEL " Semi-Annual Quality Assurance Status Report: July - December 1997."

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Laboratory Analyses The quality control programs that were performed during 1997 to demonstrate the validity of laboratory analyses by DESEL in the media types of air filter, charcoal (iodine) cartridges, milk, soil / sediment, vegetation,-and water. These quality control assessments are performed within the following intercomparison programs:

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

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DESEL participation in a cross-check program with Analytics, Inc. for environmental air j

filter, water, and milk samples.

j DESEL participation in a cross-check program with the National Institute of Standards e

and Technology (NIST), formerly the National Bureau of Standards. This comparison program evaluates the E-Lab's performance relative to standard measurement techniques certified by the NiST.

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

DESEL participation in cross-check programs with the Department of Energy's Quality q

Assessment Program (QAP) and Mixed Analyte Performance Evaluation Program (MAPEP). Sample of air filters, soil,' water, and vegetation are analyzed in this program for comparison to DOE's quality standards.

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'In addition to the intercomparison programs mentioned previously, 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 in environmental media typically collected and analyzed for the sponsor companies.

The results of these studies are discussed below.

DESEL intralaboratory aad independent Interlabcratory Results Results of the Quality Assurance Program are reported in two separate categories based upon y

DESEL acceptance criteria. The first criterion concems accuracy, which is defined as the deviation of any one result from the assumed known value. The second criterion concerns precision, which deals with the ability of the measurement to be. faithfully replicated Dy a comparison of an individual result to the mean of all results for a given sample set.

The Quality Assurance Program implemented at the analytical laboratory indicated good I

precision and accuracy in reported values. Table 1 shows the cumulative results of accuracy and precision for laboratory analyses in 1997 for DESEL intralaboratory analyses, as'well as

~ Analytics and NIST interlaboratory cross-check analyses. A total.of 526 analyses were -

performed for accuracy cross-comparisons, while 363 cross-check analyses were performed to assess precision. For accuracy,67% and 89% of the results were within 5 and 10 percent of the known values, respectively, with 98% of all results falling within the laboratory criterion of

~15 percent. For precision,84% and 97% of the results were within 5 and 10 percent of the mean, respectively, with 100% of all results meeting the laboratory criterion of 15 percent.

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DESEL Intercomparison results with the EPA and DOE programs are evaluated based on criteria specified by these two agencies. Within the EPA intercomparison program for drinking water samples, the DESEL mean for multiple measurements is compared to the EPA grand L

mean and acceptable control limits established for each performance evaluation (PE) sample set. During 1997,49 PE sample sets were analyzed by DESEL,47 of which (96%) met the EPA's acceptance criteria. Two sample sets analyzed for radium-228 in drinking water did not i

fall within the EPA's acceptance range.

Since this radionuclide is not analyzed for in l

environmental monitoring programs at nuclear power plants, this adverse result has no impact l

on the REMP monitoring results.

.Witnin the DOE arena, intercornparisons are performed under two separate programs. During 1997, DEGEL performed intercomparison analyses for 10 radionuclides under the DOE's Mixed Analyte Performance Evaluation Program (MAPEP). All ten (100%) of these analyses met the MAPEP acceptance criteria. In the other DOE program, various environmental media are analyzed under the DOE's Quality Assurance Program (QAP). During 1997, DESEL analyzed a combination of 18 radionuclide in four media type; for a total of 81 intercuoparison analyses. Of these,80 (99%) met the DOE's acceptance criteria. Only one sample, and air filter analyzed for antimony-125, was in non-agreement with DOE results. As was the case with the' Ra-228 in the EPA sample, this radionuclide would not be expected to occur in an environmental samp:e.

The results of the numerous intercomparisons performed during 1997 validate the quality of the analyses performed by DESEL. Even though some of the analyses may not be directly applicable to samples and analyses encountered in a REMP program, they high degree of compliance reflects the overall quality of laboratory controls in place at DESEL.

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TABLE 1

.1 INTRALABORATORY AND INTERLABORATORY RESULTS - 1997 i

i l

Fraction of Measurements Total Number of

'within deviation range Category Measurements t5%

i10%

i15%*

]

DESEL~lNTRALABORATORY ANALYSES l

Accuracy -

208 77.9 %

89.9 %

98.1 %

o Precision 45 53.3 %

84.4 %

100.0 %

L ANALYTICS INTERLABORATORY ANALYSES -

Accuracy 288 58.3 %

88.2 %

98.3 %

Precision 288 87.8 %

98.6 %

100.0 %

i l-NIST INTERLABORATORY ANALYSES-Accuracy 30

~ 70.0% -

93.3 %

' 93.3%.

}

100.0%'

Precision 30 96.7 %

100.0 %

TOTAL COMBINED ANALYSES 1

.-Accuracy 526 66.7 %

89.2% -

97.9%.

Precision 363 84.3 %

97.0 %

100.0 %

l e

(

• 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, i

Blind Duolicate Proaram L

'A total of 55 paired samples were submitted by the five sponsor companies for analysis during 1997.. The database used for the duplicate analysis consisted of paired measurements of 25 gamma-emitting nuclides,- H-3, Sr-89, Sr-90, low-level 1-131, and gross beta. The sample media included milk, groundwater, sea / river water, food crops, marine algae, and mussel meat.

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' A dual-level criteria for agreement has been established. If the paired measurements fall L

within 15% of their average value, then agreement between the measurements has been met. If the value falls outside of the i 15% criteria, then a two standard deviation range (95 i-I percent confidence level) is establi61 for each of the analyses. If the confidence intervals

for the two analyses overlap, agreemp at is obtained.

From the 55 paired samples,1435 paired duplicate measurements were analyzed during 1997.'.Out of these measurements, 1426 (99.4%) fell within the established criteria discussed above. No trend was evident with respect to repeated failings of measurements for the listed radionuclides and media.

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' Environmental TLD Measurements Quality control testing was performed during 1997 to demonstrate,the performance of the routine environmental TLDl processing by DESEL. The quality of the dosimetric results is evaluated relative to independent third party testing and intemal performance testing. These tests were performed independent of the processing of environmental TLDs at DESEL. In all of these tests, dosimeters were irradiated to known doses and submitted to DESEL for.

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

DESEL began performance te. sting of the Panasonic environmental TLDs in July 1987. The testing included intemal performance testing and testing by an independent third party.

A i 30% accuracy acceptance standard under field conditions is recommended by ANSI 545-1975, "American Nation.sl Standard Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry (Environmental Applications)." Acceptance criteria for accuracy and precision to be used in 1997 was adopted by the Laboratory Quality Control Audit '

Committee (LOCAC) on November 13,1987. Recognizing the inherent variability associated with each dosimeter type, control limits for both accuracy and precision of i 3 sigma plus 5%

(for bias) were set by the LOCAC. The actual magnitude of the 3 sigma plus 5% control limits depends on the histcrical performance of each type of dosimeter, with each response being indicative of random and systematic uncertainties, combined with any deviation attributable to TLD operation.

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

The quality control program implemented for dosimetry processing indicated good precision and accuracy in the reported values. In 1997, there were 95 quality control tests. All 48 environmental TLDs tested during January - June 1997 were within the control limits for both accuracy and precision.

The comparisons yielded a mean securacy of +3.5%

The comparisons exhibited a precision value with an overall standard deviation of 1.4% The 47 TLDs tested in July - December 1997 showed a mean accuracy of +1.5% TLDs measured during the second semiannual period exhibited a precision value with a standard deviation of 1.7%, well within the acceptance criteria. In total, all G5 environmenta' TLDs tested during 1997 were within the controllimits for both accuracy (* 20.1%) and precision (i 12.8%).

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

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

deviation in more than 97% of all cases.

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

Therefore, the quality assurance programs for the Boston Edison Company's Radiological Environmental Monitoring Program indicated that the analyses and measurements performed by Duke Engineering and Services Environmental Laboratory during 1997 exhibited acceptable accuracy and precision.

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