ML20206Q068
| ML20206Q068 | |
| Person / Time | |
|---|---|
| Site: | Pilgrim |
| Issue date: | 12/31/1998 |
| From: | Landahl S, Sejkora K, Smalley P BOSTON EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| 31, BECO-2.99.036, NUDOCS 9905190054 | |
| Download: ML20206Q068 (100) | |
Text
{{#Wiki_filter:. _ _ _ _ ___ _ __ _ _ _ _ _-_ ___ m Technical Specification 5.6.2 l L 3 Boston Edison h EjV A BEC ENERGY COMPANY J.F. Alexander Nuclear Assessment Group Manager May 10, 1999 BECo Ltr. 2.99.036 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Ucense No. DPR-35 Docket No. 50-293 in accordance with the Pilgrim Nur.'aar Power Station Technical Specification S.6.2, Boston Edison Company submits the annual " Radiological Environmental Monitoring Program Report" for 1998 (Report #31). J. exan er RLC/cis 299036 Attachment cc: Mr. Hubert Miller Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Alan B. Wang, Project Manager Project Directorate 1-3 / Office of Nuclear Reactor Regulation Mail Stop: OWFN 8F2 U. S. Nuclear Regulatory Commissicn 1 White Flint North 11555 Rockville Pike Rockville, MD 20852 Senior Resident inspector 9951}00 [ 3 3 R Pilgrim Nuclear Power Station, Rocky Hill Road, Plymouth, Massachusetts 02360
PILGRIM NUCLEAR POWER STATION Radiological Environmental Monitoring Program Report No. 31 January 1 through December 31,1998
& Boston Edison
1 I
& Boston Edison PILGRIM NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT NO. 31 1
JANUARY 01 THROUGH DECEMBER 31,1998 i l l Prepared by: M ' a?#c N99 K.Wei f Senior ironmental Radiochemis]t Reviewed by: I -
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P.O. Smalley Chemistry Department Manager Approved by: k2/ d ' fh S.R. Landahl nsdiation Protection Manager Page 1
Pilgrim Nuclear Power Station Radiological Environmental Monitoring Program Report January-December 1998 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 Radiological Impact on Humans 17 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 22 2.1 Pre-Operational Monitoring Results 22 2.2 Environmental Monitoring Locations 23 2.3 Interpretation of Radioactivity Analyses Results 24 2.4 Ambient Radiation Measurements 26 2.5 Air Particulate Filter Radioactivity Analyses 28 l 2.6 Charcoal Cartridge Radioactivity Analyses 29 l 2.7 Milk Radioactivity Analyses 29 2.8 Forage Radioactivity Analyses 30 l l 2.9 Vegetab, / Vegetation Radioactivity Analyses 30 2.10 Cranberry Radioactivity Analyses 31 2.11 Soil Radioactivity Analyses 31 2.12 Surface Water Radioactivity Analyses 31 2.13 Irish Moss Radioactivity Analyses 31 2.14 Shellfish Radioactivity Analyses 32 2.15 Lobster Radioactivity Analyses 32 2.16 Fish Radioactivity Analyses 32 2.17 Sediment Radioactivity Analyses 33 3.0
SUMMARY
OF RADIOLOGICAL IMPACT ON HUMANS 72
4.0 REFERENCES
74 APPENDIX A Special Studies 75 APPENDIX B Effluent Release Information 76 APPENDIX C Land Use Census 89 APPENDIX D Environmental Monitoring Program Discrepancies 90 APPENDIX E Quality Assurance Program Results 92 Page 2
Pilgrim Nuclear Power Station
- Radiological Environmental Monitoring Program Report l January-December 1998 LIST OF TABLES TABLE TABLE TITLE PAGE 1.2 1 Radiation Sources and Corresponding Doses 8 1.3-1 PNPS Operating Capacity Factor During 1998 9 2.2-1 Routine Radiological Environmental Sampling Locations 34 2.4-1 Offsite Environmental TLD Results 36 2.4-2 Onsite Environmental TLD Results 38 2.4-3 Average TLD Exposures By Distance Zone During 1998 39 2.4-4 Beach Survey Exposure Rate Measurements 40 2.5-1 Air Particulate Filter Radioactivity Analyses 41 2.6-1 Charcoal Cartridge Radioactivity Analyses 42 2.7-1 Milk Radioactivity Analyses 43 2.8-1 Forage Radioactivity Analyses 44 2.9-1 VegetableNegetation Radioactivity Analyses 45 2.10-1 Cranberry Radioactivity Analyses 46 1
2.11-1 Soil Radioactivity Analyses 47 l 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 Radicactivity Analyses 51 2.16-1 Fish Radioactivi'v Analyses 52 2.17-1 Sedirr,ent Radioactivity Analyses 53 l 2.17-2 Sediment Plutonium Analyses 54 3.0-1 Radiation Doses From 1998 Pilgrim Station Ope" rations 73 1
1 l Page 3 J
Pilgrim Nuclear Power Station Radiological Environmental Monitoring Program Report January-December 1998 LIST OF FIGURES FIGURE FIGURE TITLE PAGE 1.3 1 Radioactive Fission Product Formation 11 1.3-2 Radioactive Activation Product Formation 12 1.3-3 Barriers to Confine Radioactive Materials 13 1.5-1 Radiation Exposure Pathways 19 2.2 1 Environmental TLD Locations Within the PNPS Protected Area 55 2.2-2 TLD and Air / Soil Sampling Locations: Within 1 Kilometer 57 2.2-3 TLD and Air / Soil Sampling Locations: 1 to 5 Kilometers 59 2.2-4 TLD and Air / Soil Sampling Locations: 5 to 25 Kilometers 61 2.2-5 Terrestrial and Aquatic Sampling Locations 63 2.2-6 Environmental Sampling and Measurement Control Locations 65 2.4 1 - Historical Beech Survey Exposure Rate Measurements 67 2.5-1 Airborne Gross Beta Radioactivity Levels: Near Station 68 2.5 2 Airborne Gross Beta Radioactivity Levels: Property Line 69 2.5-3 Airbome Gross Beta Radioactivity Levels: Offsite 70 2.7 1 Levels of Strontium-90 in Milk Samples 71 Page 4
EXECUTIVE
SUMMARY
BOSTON EDISON COMPANY PILGRIM NUCLEAR POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM REPORT JANUARY 01 THROUGH DECEMBER 31,1998 INTRODUCTION This report summarizes the results of the Boston Edison Company's Radiological Environmental Monitoring Program (REMP) conducted in the vicinity of Pilgrim Nuclear Power Station (PNPS) during the period from January 1 to December 31,1998. This document has been prepared in accordance with the requirements of PNPS Technical Specifications section 5.6.2. The REMP has been established to monitor the radiation and radioactivity released to the environment as a result of Pilgrim Station's operation. This program, initiated in August 1968, includes the collection, analysis, and evaluation of radiological data in order to assess the impact of Pilgrim Station on the environment and on the general public. SAMPLING AND ANALYSIS The environmental sampling media collected in the vicinity of PNPS and at distant locations included air particulate filters, charcoal cartridges, seawater, shellfish, Irish moss, American lobster, fishes, sediment, milk, cranberries, vegetation, and animal forage. During 1998, there were 1,399 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. A small number of inadvertent issues were encountered during 1998 in the collection of environmental samples in accordance with the PNPS Offsite Dose Calculation Manual (ODCM). 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 results being observed. A full description of any discrepancies encountered with the environmental monitoring program is presented in Appendix D of this report. There were 1,576 analyses performed on the environmental media samples. Analyses were performed by the Duke Engineering and Services Environmental Laboratory in Westborough, Massachusetts. Samples were analyzed as required by the PNPS ODCM. Page 5 i t J
LAND USE CENSUS The annualland use census in the vicinity of Pilgrim Station was conducted as required by the PNPS ODCM between October 19 and 23,1998. A total of 27 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 27 garden locations identified, samples were collected at or near five of the gardens as part of the environmental monitoring program. 1 i RADIOLOGICAL IMPACT TO THE ENVIRONMENT I During 1998, samples (except charcoal cartridges) collected as part of the REMP at Pilgrim Station continued to contain detectable amounts of naturally-occurring and man-made radioactive materials. The only samples collected in 1998 which showed detectable activity poNntially attributable to PNPS operations were blue mussel collected from the discharge canal l owall during the second quarter. The calculated dose to a maximum-exposed individual from l this radioactivity is estimated as being about 0.0001 mrem. Offsite ambient radiation measurements using environmental TLDs and a high pressure ion chamber ranged between 44 l and 99 milliRoentgens per year. The range of ambient radiation levels observed with the TLDs is consistent with natural background radiation levels for Massachusetts as determined by the Environmental Protection Agency (EPA). RADIOLOGICAL IMPACT TO THE GENERAL PUBLIC During 1998, radiation doses to the general public as a result of Pilgrim Station's operation continued to be well below the federal limits and much less than the dose due to other sources of man-made (e.g., X-rays, medical, fallout) and naturally-occurring (e.g., cosmic, radon) radiation. The calculated total body dose to the maximally-exposed member of the general public from radioactive effluents and ambient radiation resulting from PNPS operations for 1998 was about 2.9 mrem for the year. This conservative estimate is well below the EPA's annual dose limit to any member of the general public and is a fraction of a percent of the typical dose received from natural and man-made radiation. CONCLUSIONS 1 The 1998 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. Page 6
1 i l l
1.0 INTRODUCTION
The Radiological Environmental Monitoring Program for 1998 performed by Boston Edison , Company for Pilgrim Nuclear Power Station (PNPS) is discussed in this report. Since the l operation of a nuclear power plant results in the release of small amounts of radioactivity and l low levels of radiation, the Nuclear Regulatory Commission (NRC) requires a program to be l established to monitor radiation and radioactivity in the environment (Reference 1). This report, l which is required to be published annually by Pilgrim Station's Technical Specifications section 5.6.2, summarizes the results of measurements of radiation and radioactivity in the environment in the vicinity of the Pilgrim Station and at distant locations during the period January 1 to December 31,1998. The Radiological Environmental Monitoring Program consists of taking radiation measurements and collecting samples from the environment, analyzing them for radioactivity content, and interpreting the results. With emphasis on the critical radiation exposure pathways to humans, samples from the aquatic, atmospheric, and terrestrial environments are collected. These samples include, but are not limited to: air, soil, seawater, shellfish, lobster, fishes, milk, l cranberries, vegetables, and forage. Thermoluminescent dosimeters (TLDs) are placed in the l environment to measure gamma radiation levels. The TLDs are procesced and the environmental samples are analyzed to measure the very low levels of radiation and l radioactivity present in the environment as a result of PNPS operation and other natural and I l man-made sources. These results are reviewed by BECo's radiomgical staff and have been l reported semiannually or annually to the Nuclear Regulatory Corraission 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 irnpact on humans is provided. It is believed that this information will assist the reader in understanding the radiological impact on the environrnent and humans from the operation of Pilgrim Station. l l 1.1 Radiation and Radioactivity 1 All matter is made of atoms. An atom is the smallest part into which matter can be broken , j down and still maintain all its chemical properties. Nuclear radiation is energy, in the form of l l 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 j earth's crust, for example, contains radioactive uranium, radium, thorium, and potassium. l Some radioactivity is a result of nuclear weapons testing. Examples of radioactive fallout which is normally present in environmental samples are cesium-137 and strontium-90. Some examples of radioactive materials released from a nuclear power plant are cesium-137, iodine-131, strontium 90, and cobalt-60. i Page 7 k
Radiation is measured in units of millirem, much like temperature is measured in degrees. A millirem is a measure of the biological effect of the energy deposited in tissue. The natural and man-made radiation dose received in one year by the average American is 300 to 400 mrem (References 2,3,4). Radioactivity is measured in curies. A curie is that amount of radioactive material needed to produce 37,000,000,000 nuclear disintegrations per second. This is an extremely large amount of radioactivity in comparison to environmental radioactivity. That is why radioactivity in the environment is measured in picocuries. One picocurie is equal to one trillionth of a curie. 1.2 Sources of Radiation As mentioned previously, naturally occurring radioactivity has always been a part of our environment. Table 1.2-1 shows the sources and doses of radiation from natural and man-made sources. Table 1.2-1 Radiation Sources and Correspondjnp Doses NATURAL MAN-MADE Radiation Dose Radiation Dose Source (millirem / year) Source (millirem / year) Cosmic /cosmogenic 30 Medical / Dental X-Rays 39 Internal 40 Nuclear Medicine 14 Torrestrial 30 Consumer Products 10 Radon / Thoron 200 Weapons Fallout 1 Nuclear Power Plants 1 Approximate Total 300 Approximate Total 60 Cosmic radiation from the sun and outer space penetrates the earth's atmosphere and continuously bombards us with rays and charged particles. Some of this cosmic radiation interacts with gases and particles in the atmosphere, making them radioactive in turn. These radioactive byproducts from cosmic ray bombardment are referred to as cosmogenic radionuclides. Isotopes such as beryllium-7 and carbon-14 are formed in this way. Exposure to cosmic and cosmogenic sources of radioactivity results in about 30 mrem of radiation dose per year. Additionally, natural radioactivity is in our body and in the food we eat (about 40 millirem /yr), the ground we walk on (about 30 millirem /yr) and the air we breathe (about 200 millirem /yr). The majority of a person's annual dose results from exposure to radon and thoron in the air we breathe. These gases and their radioactive decay products arise from the decay of naturally occurring uranium, thorium and radium in the soil and building products such as brick, stone, and concrete. Radon and thoron levels vary greatly with location, primarily due to changes in the concentration of uranium and thorium in the soil. Residents at some locations in Colorado, New York, Pennsylvania, and New Jersey have a higher annual dose as a result of higher Page 8
levels of radon / thoron gases in these areas. In total, these various sources of naturally- ) occurring radiation and radioactivity contribute to a total dose of about 300 mrem per year. l In addition to natural radiation, we are normally exposed to radiation from a number of man-made sources. Tho single largest doses from man-made sources result from therapeutic and diagnostic applications of x rays and radiopharmaceuiicals. The annual dose to an individual in { the U.S. from medical and dental exposure is about 50 mrem. Consumer products, such as j televisions and smoke detectors, contribute about 10 mrem /yr. Much smaller doses result from i weapons fallout (less than 1 mrem) and nuclear power plants (less than 1 mrem /yr). Typically, the average person in the United States receives about 60 mrem per year from man-made sources. 1.3 Nuclear Reactor Operations l
~
Pilgrim Station generates about 670 megawatts of electricity at full power, which is enough electricity to supply the entire city of Boston, Massachusetts. Pilgrim Station is a boiling water reactor whose nuclear steam supply system was provided by General Electric Co. The nuclear station is located on a 1600 acre site about eight kilometers (five miles) east-southeast of Plymouth Center. Commercial operation began in December,1972. Pilgrim Station did not experience any major outages during 1998, although some power i reductions took place during May, August, and September to perform some minor equipment - maintenance and inspections. Monthly capacity factors are presented in Table 1.3-1. j l TABLE 1.3-1 l PNPS OPERATING CAPACITY FACTOR DURING 1998 (Based on 670 megawatts electric)
)
Month Percent Capacity January 98.4 February 99.5 March 99.5 April 97.2 l May 92.5 June 99.4 l July 95.5 l August 93.0 September 93.3 October 99.4 November 99.6 December 98.2 Average 97.1 Page 9
Nuclear-generated electricity is produced at Pilgrim Station by many of the same techniques used for conventional oil and coal-generated electricity. Bo" systems use heat to boil water to produce steam. The steam turns a turbine which turns a gunerator, 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 convent:onal power is the source of heat used to boil the water. Conventional plants burn fossil fuels in a boiler, while nuclear plants make use of uranium in a nuclear reactor. Inside the reactor, a nuclear reaction called fission takes place. Particles, called neutrons, strike the nucleus of a uranium-235 atom, causing it to split into fragments called radioactive fission products. The splitting of the atoms releases both heat and more neutrons. The newly-released neutrons then collide with and split other uranium atoms, thus making more heat and releasing even more neutrons, and on and on until the uranium fuel is depleted or spent. This process is called a chain reaction. The operation of a nuclear reactor results in the release of small amounts of radioactivity and Icw 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 f,ssioning of the nuclear fuel. These fission products get into the reactor coolant from their rehase by minute amounts of uranium on the outside surfaces of the fuel cladding, by diffusion through the fuel pellets and cladding and, on occasion, through defects or failures in the fuel cladding. These fission products circulate along with the reactor coolant water and will deposit on the internal surfaces of pipes and equipment. The radioactive fission products on the pipes and equipment emit radiation. F.xamples 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). Page 10
Nuclear Fission Fission is the splitting of the uranium-235 atom by a neutron to release heat and more neutrons, creating a chain reaction. Radiation and fission products are by-products of the process. uranium 8
^
N ,g, 9,' Radiation k Radiation h@ uranium
@4 e Neutrons y
Fission Products 9.,l N s uranium T Fission Products Figure 1.3-1 Radioactive Fission Product Formation l l t Pago 11
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 othe' 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 cc : tant corrosion from the reactor cooling water. These minute metallic particles (for example: nickel, iron, cobalt, or magnesium) are transported through the reactor core into the fuel region, where neutrons may react with the nuclei of these particles, producing radioactive products. So, activation products are nothing more than ordinary naturally-occurring atoms that are made unstab!e 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).
- - O 4
Vni I Co-59 Co Neutron Stable Radioactive 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) fuelpellets;
- 2) fuelcladding;
- 3) reactor vessel and piping:
- 4) primary containment (drywell and torus); and,
- 5) secondary containment (reactor building).
Page 12
1 SIMPLIFIED DIAGRAM OF A BOILING WATER REACTOR l
- 4. PRMARY CONTANMENT
- 3. REACTOR VESSEL
- 1. FUEL PELLETS
- 2. N E CMD M
- 5. SECONDARY CONTANMENT
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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 steel lined enclosure that is shaped like an inverted light bulb. The drywell's steel piescure vessel is enclosed by an approximately five foot thick concreto 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, centrol systems exist to collect and purify the radioactive effluents in order to reduce release.s 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. j L Page 14
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; e liquid radwaste treatment system; e sampling and analysis of the liquid radwaste tanks; and, e liquid waste effluent discharge header radioactivity monitor.
The purpose of the reactor water cleanup system is to continuously purify the reactor cooling water by removing radioactive atoms and non-radioactive impurities 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 lon exchange resins where radioactive elements, dissolved and suspended in the water, are removed through chemical processes. The net effect is a substantial reduction of the radioactive material that is present in the primary coolant water and consequently the amount of radioactive material that might escape from the system. Reactor cooling water that might escape the primary cooling system and other radioactive water sources are collected in floor and equipment drains. These drains direct this radioactive liquid waste to large holdup tanks. The liquid waste collected in the tanks is purified again using the liquid radwaste treatment system, which consists of a filter and ion exchange resins. Processing of liquid radioactive waste results in large reductions of radioactive liquids discharged into Cape Cod Bay. Of all wastes processed through liquid radwaste treatment,90 to 95 percent of all wastes are purified and the processed liquid is re-used in plant systems. Prior to release, the radioactivity in the liquid radwaste tank is sampled and analyzed to determine if the level of radioactivity is below the release limits and to quantify the total amount of radioactive liquid effluent that would be released. If the levels are below the federal release limits, the tank is drained to the liquid effluent discharge header. This liquid waste effluent discharge header is provided with a shielded radioactivity monitor. This detector is connected to a radiation level meter and a strip chart recorder in the Control Room. The radiation alarm is set so that the detector will alarm before radioactivity levels exceed the release limits. The liquid effluent discharge header has an isolation valve. If an alarm is received, the liquid effluent discharge valve will automatically close, thereby terminating the release to the Cape Cod Bay and preventing any liquid radioactivity from being released that may exceed the release limits. An audible alarm notifies the Control Room operator that this has occurred. Some liquid waste sources which have a low potential for containing radioactivity, and/or may contain very low levels of contamination, may be discharged directly to the discharge canal without passing through the liquid radwaste discharge header. One such source of liquids is the neutralizing sump. However, prior to discharging such liquid wastes, the tank is thoroughly mixed and a representative sample is collected for analysis of radioactivity content prior to being discharged. I 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 limited, controlled, and monitored by a variety of systems and procedures which include:
. reactor building ventilation system;
. reactor building vent effluent radioactivity monitor; ,
e sampling and analysis of reactor building vent effluents; j
. standby gas treatment system; e main stack effluent radioactivity monitor and sampling;
. 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. ' 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 I strip chart recorder for the reactor building vent effluent radioactivity monitor is located in the i 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% procedure, will isolate the reactor building ventilation system and initiate the standby gas treatment system to remove airborne particulates and gaseous halogen radioactivity from the reactor building exhaust. This filtration assembly consists of high-efficiency particulate air filters and charcoal adsorber beds. The purified air is then directed to the main stack. The main stack has dilution flow which further reduces concentration levels of gaseous releases to the environment to as far below the I release limits as is reasonably achievable. The approximately 330 foot tall main stack has a special probe inside it which withdraws a portion of the air and passes it through a radioactivity monitoring system. This main stack effluent radioactivity monitoring system continuously samples radioactive particulates, lodines, and noble gases. Grab samples for a tritium analysis are also collected at this location. The system also contains radioactivity detectors that monitor the levels of radioactive noble gases in the stack flow and display the result on radiation level meters and strip chart recorders located in the Control Room. To supplement the information continuously provided by the detectors, the particulate, iodine, tritium, and gas samples are analyzed periodically to quantify the total amount of radioactive gaseous effluent being released. The purpose of the augmented off-gas system is to reduce the radioactivity from the gases that are removed from the condenser. This purification system consists of two 30-minute holdup lines to reduce the radioactive gases with short half-lives, several charcoal adsorbers to remove radioactive iodines and further retard the short half-life gases, and offgas filters to remove Page 16
radioactive particulates. The recombiner collects free hydrogen and oxygen gas and recombines them into water. This helps reduce the gaseous releases of short-lived isotopes of oxygen which have been made radioactive by neutron activation. . I The radioactive off-gas from the condenser is then directed into a ventilation pipe to which the off-gas radiation monitors are attached. The radiation level meters and strip chart recorders for this detector are also located in the Control Room. If a radiation alarm setpoint is exceeded, an audible alarm will sound to alert the Control Room operators in addition, the off-gas bypass and charcoal adsorber inlet valve will automatically re-direct the off-gas into the charcoal adsorbers if they are temporarily being bypassed. If the radioactivity levels are not returned to below the alarm setpoint within 13 minutes, the off-gas releases will be automatically isolated, thereby preventing any gaseous radioactivity from being released that may exceed the release limits. ; Therefore, for both liquid and gaseous releases, radioactive effluent control systems exist to collect and purify the radioactive effluents in order to reduce releases to the environment to as low as is reasonably achievable. The effluents are always monitored, sampled and analyzed prior to release to make sure that radioactivity levels are below the release limits. If the release limits are being approached, isolation valves in some of the waste effluent lines will automatically shut to stop the release, or Control Room operators will implement procedures to ensure that federal regulatory limits are always met. 1.5 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 is to measure the quantities of radioactivity being released to determine compliance with the radioactivity release limite. 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 1998 were reported to the Nuclear Regulatory Commission annually. The 1998 Radioactive Effluents are provided in Appendix B and will be discussed in more detail in Section 3 of this report. These liquid and gaseous effluents were well below the federal release limits and were a small percentage of the PNPS ODCM effluent control limits. These measurements of the physical and chemical nature of the effluents are used to ) determine how the radionuclides will interact with the environment and how they can result in radiation exposure to humans. The environmental interaction mechanisms depend upon factors such as the hydrological (water) and meteorological (atmospheric) characteristics in the area. Information on the water flow, wind speed, wind direction, and atmospheric mixing characteristics are used to estimate how radioactivity will distribute and disperse in the ocean and the atmosphere. Page 17
r l 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) external radiation frcm liquid effluents that deposit and accumulate on the shoreline;
]
- 2) extemal radiation from immersion in ocean water containing radioactive liquids; and,
- 3) internel radiation from consumption of fish and shellfish containing radioactivity absorbed from the liquid effluents.
There are six major ways in which gaseous effluents affect humans:
- 1) external radiation from an airbome plume of radioactivity;
- 2) internal radiation from inhalation of airborne radioactivity;
- 3) external radiation from deposition of radioactive effluents on soil;
- 4) ambient (direct) radiation from contained sources at the power plant;
- 5) internal radiation from consumption of vegetation containing radioactivity absorbed l from the soil due to ground deposition of radioactive effluents; and,
- 6) internal radiation from consumption of milk and meat containing radioactivity i 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 l exposure immediately adjacent to the plant. Smaller amount of ambient radiation result from low-level radioactive waste stored at the site prior to shipping and disposal. To the extent possible, the radiological dose impact on humans is based on direct measurements of radiation and radioactivity in the environment. When PNPS-related activity is detected in samples which represent a plausible exposure pathway, the resulting dose from such exposure is assessed (see Appendix A). However, the operetion 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 aust sensitive radioactivity measurement and analysis i 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 in Regulatory Guide 1.109 (Reference 6). The dose calculations are documented and described in detail in the Pilgrim . luclear Power Station's Offsite Dose Calculation Manual (Reference 7) which has been reviewed by the NRC. j i Page 18
EXAMPLES OF PILGRIM STATION'S RADIATION EXPOSURE PATHWAYS
- GASEOUS;
(\
$ .hEFFLUENTS:
-"" 1 LIQUID Itt g
[F q:- EFFLUENTS f Psea . )
; wn f 3. DIRECT RADIATION (STATI N) 2. AIR INHALATION
- 4. DIRECT RADIATION (SOIL DEPOSITION) 1. DIRECT RADIATION (AIR SUBMERSION)
T
, x . I
- 1. SHORELINE DIRECT RADIATION (FISHING, PICNICING) 5. CONSUMPTION i d
(VEGETATION) j DEPOSITION
- 2. DIRECT RADIATION (IMMERSION IN OCEAN, BOATING, SWIMMING)
D
! [ @ G dB3P G GIIP \
\
gewaelo ( 6. CONSUMPTION l 1 DEPOSITION (MILK AND MEAT)
- 3. CONSUMPTION (FISH, SHELLFISH) A DINGESTION
,A M &
v.dh::y?'.N.S .'<4'%::::'" ' h ' - - 1 Figure 1.5-1 Radiation Exposure Pathways Page 19 l I
Monthly dose calculations are performed by Boston Edison Co. personnel. Semlannual dose , l 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 real individual. After dose calculations are performed, the results are compared to the federal dose limits for the public. The two federal agencies that are charged with the responsibility of protecting the public from radiation and radioactivity are the Nuclear Regulatory Commission (NRC) and The Environmental Protection Agency (EPA). The NRC, in 10CFR 20.1301 (Reference 8) limits the levels of radiation to unrestricted areas resulting from the possession or use of radioactive materials such that they limit any individual to a dose of:
. less than or equal to 100 mrem per year to the total body.
In addition to this dose limit, the NRC has established design objectives for nuclear plant licensees. Conformance to these guidelines ensures that nuclear power reactor effluents are maintained as far below the legal limits as is reasonably achievable. The NRC, in 10CFR 50 Appendix 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.
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, a less than or equal to 20 mrad per year for beta radiation.
The dose to a member of the general pubGc from iodine-131, tritium, and all particulate radionuclides with half-lives greater than 8 days in gaseous effluents is limited to:
. less than or equal to 15 mrem per year to any organ.
Page 20
p - 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:
e, - 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, ! .* less than or equal to 25 mrem per year to any other organ. The summary of the 1998 radiologicalimpact 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 l Monitoring Program (REMP). The description and.results of the REMP at Pilgrim Nuclear l Power Station during 1998 is discussed in Section 2 of this report. l l l l l l 1 l l Page 21 t-
y 2.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 2.1 Pre-Operational Monitorina Results l l The Radiological Environmental Monitoring Program (REMP) at Boston Edison Company 1 l Pilgrim Nuclear Power Station was first initiated in August 1968, in the fo.m of a pre-operationa5 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 ano radioactivity in the environment.
The pre-operational program (Reference 12) continued for approximately three and a :aif i years, from August 1968 to June 1972. Examples of background radiation and radioact'.4y levels measured during this time period are as follows:
. Airborne Radioactivity Particulate Concentration (gross beta): 0.02 - 1.11 pCi/m';
e Ambient Radiation (TLDs'): 4.2 - 22 micro-R/hr (37 - 190 mR/yr); e Seawater Radioactivity Concentrations (gross beta): 12 - 31 pCi/ liter; e Fish Radioactivity Concentrations (gross beta): 2,200 - 11,300 pCi/kg; e Milk Radioactive Cesium-137 Concentrations: 9.3 - 32 pCi/ liter; I l
. Milk Radioactive Strontium-90 Concentrations: 4.7 - 17.6 pC!/ilter;
]
. Cranberries Radioactive Cesium-137 Concentrations: 140 - 450 pCi/kg; l e Forage Radioactive Cesium-137 Concentrations: 100 - 290 pCl/kg. !
This information from the pre-operational phase is used as a basis for evaluating changes in i 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
l
- 1) demonstrating that doses to the general public and levels of radioactivity in the l
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-
)
- 4) assessing the dose equivak:at to t% general public and the behavior of radioactivity released during the unlikely event of an accidental release; and,
- 5) determining whether or not the radiological impact on the environment and humans is significant.
The Nuclear Regulatory Commission requires that Boston Edison Company provide monitoring of the plant environs for radioactivity that wi!I 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 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 pravisions of an ) agreement made with the Massachusetts Wildlife Federation (Reference 16). The program ) was supplemented by inc!uding improved ardysis of shellfish and sediment at substantially higher sensitivity levels to verify the adequscy of el fluent controls at Pilgrim Stat!an. 2.2 Environmental Monitorina Locations ! l Sampling locations have been established by considering meteorology, population distribution, I hydrology, and land use characteristics of the Plymouth area. The sampling locations are ! divided into two classes, indicator and co1 trol. Indicator i0 cations are those which are expected to show effects from PNPS operations, if any exist. Thesa 'ocations were primarily selected on the basis of whue the highest predicteo environmental contentrations would occur. While the indicator locations are typically within a few kilometers of the plant, the control stations a:e generally located so as to be outside the influence of Pilgrin Station. They provide a basis on v'hich to evaluate fluctuations at indicator locations relative b natural background radiation and i natural radioactivity and fallout from prior nuclear weapons tosts. The environmental sampling media collected in the vicinity of Pilgrim Station during 1998 included eir particulate filters, charcoal cartridges, seawater, shellfish, Irish moss, American l lobster, ficnes, sediment, milk, cranberries, vegetation, and forage. The sampliri; medium, i station description, station number, distance, and direction for indicator and control s imples are listed in Table 2.2-1. These sampling locations are also displayed on the map , shown in , Figures 2.2-1 through 2.2-6. ) 4 The radiation monitoring locations for the environmental TLDs are shown in ' igures 2.2-1 ) through 2.2-4. The frequency of collection and types of radioactivity analys!s are described in Pilgrim Station's ODCM, Sections 3/4.5. The land-based (tenestrial) samples and monitoring devices are collected by Boston Edison personnel from the Electrical Engineering and Staaon Opera'.lon Department's Environmental Laboratory. The aquatic samples are collected by the Div;sion of Marine Fisheries - Pilgrim Station Project personnel. The direct radiation rr.easurements and soil radioactivity measuremer.ts are conducted by Duke Enginoering and Services Radiological Engineering ; Group and Environmental Laboratory personrel. respectively. The radioactivity analysis of samples and the processing of the environmr.;al TLDs is performed by Duke Engineering and Services Environmental Laborator,merennnel. The frequency, types, minimum number o' samples, and maximum lower limits of detection , (LLD) for the analytical measurements, are specified in the PNPS ODCM. Upon receipt of the analysis results from Due e Engineering and Services, the Boston Edison staff reviews the results. If the radioactivity ccqcentrations 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 Pilgrim Station's operation, calculations are performed to determine the cumulative dose contribution for the current year. Depending upon the circumstances, a special study may also be completed (see Appendix A for 1998 special studies). Most importantly, if radioactivity levels , in the environment become elevated as a result of the station's operation, an investigation is . performed and corrective actions are recommended to reduce the amount of radioactivity to as j far below tne legal limits as is reasonably achievable. l The radiclogical environmental sampling locations are reviewed annually, and modified if l necessary. A garden and milk animal census is performed every year to identify changes in the I use of the environment in the vicinity of the station to permit modification of the monitoring and : sampling locations. The results of the 1998 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 (QA) program. BECo's OA program has been established to ensuro confidence in the measurements and results of the radiological monitoring program through:
. Regular surveillances of the sampling and monitoring program; e An annual audit of the analytical laboratory by the sponsor companies;
. Participation in the United States Environmental Protection Agency and other cross-check programs;
. Use of blind duplicates for comparing separate analyses of the same sample; and,
. Spiked sample analyses by the analytical laboratory.
OA audits and inspections of the Radiological Environmental Monitoring Program are performed by the NRC, American Nuclear Insurers, and by Boston Edison Company's Quality i 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 1998 results of this OA program are summarized in Appendix E. ; These results indicate that the analyses and measurements performed during 1998 exhibited l acceptable precision and accuracy. 2.3 Interpretation of Radioactivity Analyses Results The following pages summarize the analytical results of the environmental samples collected during 1998. 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 ; i 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 ODCM. Those sampling stations within the range of influence of Pilgrim Station and which could conceivably be affected by its operation are called " indicator" stations. Distant stations, which Page 24
l 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: i
. The mean value of all concentrations, including negative values and values below i LLD; e The standard deviation of the measurements; ;
1
. 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. 1 l
Each single radioactivity measurement datum is based on a single measurement and is i 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 I pCi/ liter would be considered " positive" (detectable Sr-90), whereas another sample with a l concentration of 2.1 i 0.9 pCi/ liter would be considered " negative", indicating no detectable J strontium-90. The latter sample may actually contain strontium-90, but the levels counted during its analysis were not significantly different than background levels. The Duke Engineering and Services Environmental Laboratory uses background-subtract I corrections when analyzing samples for radioactivity content. This method involves analyzing a representative " clean" sample of the given material under similar conditions as a true sample, l and storing the results of this analysis. When a true sample is analyzed, the results of the i " clean" background sample are subtracted from the results to correct for any naturally-occurring l l radioactivity that may be present in the sample. If the true sample undergoing analysis has ) radioactivity count data which is lower than the " clean' background sample, the method can l result in a arithmetically-negative value, yielding a concentration value less than zero. As an example of how to interpret data presented in the results tables, refer to the first entry on the table for air particulate filters (page 41). Gross beta (GR-B) analyses were performed on 572 routine samples (11 stations /wk
- 52 weeks). None of the samples exceeded ten times the average concentration at the control location. The lower limit of detection (LLD) required by the ODCM is 0.01 pCl/m'.
For samples collected from the ten indicator stations, 515 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 0.02210.0103 (2.2 i 1.0 E-2) pCi/m'. Individual values ranged from -0.0011 to 0.0673 (-1.1 - 67.3 E-3) pCi/m The monitoring station which yielded the highest mean concentration was station number 10 l (Cleft Rock), which yielded a mean concentration of 0.023 i 0.012 pCi/m , based on 52 observations. Individual values ranged from 0.0056 to 0.0673 pCi/m . Fifty-two of the fifty-two samples showed detectable activity at the three-sigma level. j Page 25
w At the control location, 52 out of 52 samples yielded detectable gross beta activity, for an average concentration of 0.023 i 0.010 pCi/m . Individual samples at the control location ranged from 0.0079 to 0.0442 pCl/m . Referring to the third entry in the table, analyses for potassium-40 (K-40) were performed 44 i times (quarterly composites for 11 stations
- 4 quarters). No samples exceeded ten times the mean control station concentration. There is no LLD value listed for K-40 in the PNPS ODCM. !
l At the indicator stations, individual concentrations of K-40 ran I 0.0214 pCi/m , for a mean concentration of 0.0029 i 0.0074However, pCi/m3.ged none offrom the -0.0083 to' 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 n_o detectable activity. The station which yielded the highest mean concentration of K-40 was station 15. Again, the mean valv? of 0.0069 0.0118 pCi/m is based on four observations, none of which yielded any detectable activity. Therefore, no potassium-40 was detected in any of the samples collected from the sampling stations. The prt*us paragraphs illustrates an important point about apply,ag the three-sigma criterion j to detemnoe if radioactivity is detected. While such a screening criterion can be applied to a ; sinale measurement, it is inappropriate to apply it to a mean value calculated from multiple l 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 raWion exposure received over the period. Although TLDs can be used to monitor radiation exposure for short time periods, environmental TLDs are typically posted for periods of one to three months. Such TLD monitoring yields averaae exposure rate measurements over a relatively long time period. The PNPS environmental TLD monitoring program is based on a quarterly (three month) posting period, and a total of 110 locations are monitored using this technique. In addition,27 of the 110 TLDs are located onsite, within the PNPS protected / restricted area. Out of the 440 TLDs (110 locations
- 4 quarters) posted during 1998,434 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 offsite, beyond the PNPS protected / restricted area fence, are presented in Table 2.4-1.
Results from onsite TLDs posted within the restricted area presented in Table 2A-2. In addition to TLD results for individual locations, results from offsite TLDs were grouped according to geographic zone to determine average exposure rates as a function of distance. These results are summarized in Table 2.4-3. All of the listed exposure vaims represent continuous occupancy (2190 hr/qtr or 8760 hr/yr). Annual exposure rates measured at offsite locations ranged from 44 to 606 mR/yr. The averw exposure rate at controllocations greater than 15 km from Pilgrim Station (i.e., Zone 4) was 61.8 i 6.7 mR/yr. When the 3-sigma confidence interval is calculated based on these Page 26
control measurements,99% of all measurements of backaround ambient exposure would be expected to be between 42 and 82 mR/yr. Inspection of onsite TLD results listed in Table 2.4-2 indicates that all of those TLDs located within the PNPS protected / restricted area yield exposure measurements higher than the expected background. These increases are due to the close proximity of these locations to radiation sources onsite. The radionuclide nitrogen-16 (N-16) contained in steam flowing through the turbine accounts for most of the exposure onsite. Although this radioactivity is contained within the turbine and is not released to the atmosphere, the " sky shine" which occurs from the turbine increases the ambient radiation levels in areas near the turbine building. Such onsite TLD locations which experienced appreciable increases due to N-16 skyshine since 1997 are P02, PO4, P12, P13, P14, P15, P16, P17, P18, P19, P20, P22, and P24. Some increases in exposure also occur from the transit and temporary storage of radioactive wastes onsite. Such TLD locations which experienced appreciable increases since 1997 due to the temporary storage and movement of radioactive waste onsite are P08, P09, and P26. These TLDs are located along the transit route to the trash compaction facility, where materials are processed and staged for final shipping. 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 offsite TLD locations in close proximity to the protected / restricted area indicated ambient radiation exposure above expected background levels. All of these locations are on Boston Edison controlled property, and experience exposure increases due to turbine sky shine (e.g., locations OA, TC, P01, and WS) and/or transit and storage of radwaste onsite d (e.g., location BLW). 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 2.5 mrem /yr above their average ambient background dose of 62 mrem /yr. The TLD monitoring location at Manomet Point (MP) experienced a 22% increase from 59 mR in 1997 to 72 mR in 1998. However, TLD readings at this location during the first and third quarters of 1998 were more variable than usual, and corresponded to times when there was visible moisture in the TLD packets. Although efforts are made to seal the TLDs in air-tight plastic bags, the bags can leak and allow moisture into the bag. Such moisture can result in abnormal readings when the TLD is analyzed. None of the other TLDs in the southeast compass sector (e.g., EP, TT, TP, ME, or BW) indicated elevated readings. Had there been an actual increase in radiation levels at this location resulting from PNPS operations, other TLDs in that direction would have also indicated an increase in exposure levels. In addition, there were no increases in effluent releases from Pilgrim Station during these two quarters, nor were there any significant differences in meteorological conditions that could account for such increases in exposure levels. The increase observed at MP is attributed to anomalous readings rerutting from moisture on the TLDs. 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 B2 ton 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 97.6 i 89.8 mR/yr to 63.7 i 7.5 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 offsite resident Page 27
(location HB,0.6 km SE) was 65.3 i 6.0 mR/yr, which compares quite well with the average control location exposure of 61.8 i 6.7 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 expusure around Pilgrim Station do not indicate any significant increase in exposure levels. Although some increases in ambisnt radiation exposure level were apparent on Boston Edison property very close to Pilgrim Station, there were no measurable increases at areas beyond Boston Edison's control. 2.5 Air Particulate Filter Radioactivity Analyses Airborne particulate radioactivity is sampled by drawing a stream of air through a glass fiber filter which has a very high efficiency for collecting airborne particulates. These samplers are operated continuously, and the resulting filters are collected weekly for analysis. Weekly filter samples are analyzed for gross beta radioactivity, and the filters are then composited on a quarterly basis for each location for gamma spectroscopy analysis. Boston Edison uses this technique to monitor 10 locations in the Plymouth area, along with the control location in East Weymouth. Out of 572 filters (11 locations
- 52 weeks),572 samples were collected and analyzed during 1998. 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. Three such events occurred during 1998, resulting in the required LLDs not being met on 3 of the 572 filters collected during 1998.
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 567 of the filter samples collected, including 52 of the 52 control location samples. This gross beta activity arises from naturally- , occurring radionuclides such as radon decay daughter products. Beryllium-7 was the only gamma emitting nudide 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 i the airborne particulate samples collected. There was one anomalous measurement of airborne gross beta radioactivity made during 1998. During Week #10 (03-10 Mar 1998), the sample collected from Cleft Rock (station #10) indicated a gross beta concentration of 0.067 pCi/m , compared to a control station concentration of 0.011 pCl/m for the same period. None of the filters (air particulate or charcoal cartridge) collected from the other monitoring stations during this period indicated unusual values. Weekly effluent monitoring results of the Pilgrim Station main stack and reactor building vent were reviewed for the period, and there was no indication of increased or abnormal gaseous effluent releases. Page 28
Heanalysis of this filter for gross beta activity confirmed the originally-observed level of activity. A gamma spectroscopy analysis was performed on this sample, and no PNPS-related activity was identified. Qualitative gamma spectroscopy results on this sample indicated higher than normallevels of low-energy, naturally-occurring radon daughter activity. 2.6 ' - Charcoal Cartridae Radioactivity Analvses Airborne radioactive iodine is sampled by drawing a stream of air through a charcoal cartridge after it has passed through the high efficiency glass fiber filter. As is the case with the air particulate filters, these samplers are operated continuously, and the resulting cartridges are collected weekly for analysis. Weekly cartridge samples are analyzed for radioactive iodine.
.The same eleven locations mc.:itored for airborne particulate radioactivity are also sampled for airbome radioiodine.
Out of 572 cartridges (11 locations
- 52 weeks),572 samples were collected and analyzed during 1998. 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. Three such events occurred during 1998, resulting in the required LLDs were not being met on 3 of the 572 filters collected during 1998.
The results of the analyses performed on these 572 charcoal cartridges are summarized in Table 2.6-1. No airborne radioactive iodine was detected in any of the charcoal cartridges collected. 2.7 Milk Radioactivity Analyses Samples of unprocessed milk are collected from the Plymouth County Farm and from the control location in Whitman. The Annual Land Use Census conducted within five kilometers of Pilgrim Station did not identify any additional milk animals requiring sampling. Results of this census are summarized in Appendix C. Milk samples are collected monthly from November through April, and once every two weeks when animals are assumed to be on pasture during the period May thrcugh October. These milk samples are analyzed by gamma spectroscopy, low-level analysia fs. 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 1998. 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 mdioactive ;odine was
~ detected in any of the samples. Strontium-90 was detected in 9 of the 20 samples from Plymouth County Farm, and in 5 of the 20 samples collecteti from the control location in Whitman. Cesium-137 was not detected ;3 any of the sampes collected during the year. - Concentrations of Sr-90 as a function of time are shown in Figure 2.7-1.
The highest concentration of Sr-90,4.8 pCi/ liter, was observed in a sample collected'from the control location at Whitman Farm. The highest concentration of Sr-90 in samples collected from Plymouth County Farm was 3.1 pCi/ liter. The Sr-90 detected in the samples resulted from radioactivity in the environment which was deposited from nuclear weapons testing conducted in the 1950s and 60s. Strontium-90 was routinely detected in the preoperational sampling program conducted prior to Pilgrim Startup in 1972, at concentrations ranging from 5 to 18 pCi/ liter. When the average preoperational Sr-90 concentration of 9 pCi/ liter is corrected for radioactive decay which occurred between 1972 and 1998, the expected concentration would i be about 5 pCi/ liter. The concentrations of 3 tc 5 pCi/ liter observed in 1998 samples are well Page 29
below the expected Sr-90 concentrations resulting from weapons testing. It is clear that the Sr-90 observed did not arise from Pilgrim Station operations. 2.8 Foraae Radioactivity Analyses Samples of animal forage (hay) are collected from the Plymouth County Farm and from the control location in Whitman. Samples of corn to be used for silage at Plymouth County Farm were also collected from the Whipple Farm (2.9 km SW). Samples are collected annually and analyzed by gamma spectroscopy.
' All samples of forage were collected and analyzed as required during 1998. 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 beryllium-7 potassium-40. No radionuclides attributable to Pilgrim Station operations were detected in any of the samples.
2.9 Veaetable/Veaetation Radioactivity Analvses Samples of vegetables are routinely collected from the Plymouth County Farm and from the control location in Bridgewater. Due to a loss of state funding at the Bridgewater Correctional Facility, garden semples were not available from this source. An alternate sampling location (Hanson Farm) was identified in the general vicinity in Bridgewater, and was used as a source of control vegetable samples. In addition, samples of vegetables or leafy vegetation were collected at or near a number of gardens ioentified during the Annual Land Use Census. Results of this census are discussed in Appendix C. Samples were also collected from four locations corresponding to the highest atmospheric deposition factors from the two PNPS release points. Samples of vegetables are collected annually and analyzed by gamma spectroscopy. All samples of vegetables / vegetation were collected and analyzed as required during 1998. Results of the gamma analyses of these samples are summarized in Table 2.9-1. Naturally-occurring beryllium-7, potassium-40, and thorium-232 were identified in most of the samples collected. Cesium-137 was also detected in five of the samples collected. The highest level of cesium-137 (200 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 I for all samples of naturally-growing vegetation, these samples were collected and analyzed "as is", without processing the material to remove soil and dust on the surface of the plants. As documented in the previous REMP reports, Cs-137 was detected in nearly all of the soil surveys conducted in previous years indicating that Cs-137 is widespread in soil throughout New England. In addition to Cs-137, the vegetation samples in question also contained detectable thorium-232 decay-chain nuclides, indicating appreciable levels of soil and dust were incorporated with the vegetation comprising the sample. Cesium-137 is a ' product of nuclear weapons testing, and was routinely detected in the preoperational monitoring program at levels of 150 to 290 pCi/kg. When corrected for radioactive decay, the expected concentration in samples of naturally-growing vegetation collected during 1998 would be between 90 and 170 pCi/kg. The average Os-137 concentration of 37 pCi/kg observed in the samples collected is indicative of radioactivity arising from weapons fallout, and not Pilgrim Station operations. Page 30 ,
)
T 2.10 Cranberry Radioactivity Analyses Samples of cranberries are routinely collected from two bogs in the Plymouth area and from the l 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 1998. Results of the gamma analyses of cranberry samples are summarized in Table 2.10-1. The only radionuclide detected in any of the samples was naturally-occurring potassium-40. No radionuclides attributable to Pilgrim Station operations were detected in any of the samples. 2.11 Soil Radioactivity Analyses A survey of radioactivity in soil is conducted once every three years at the 10 air sampling stations in the Plymouth area and the control location in East Weymouth. These locations serve as fixed survey locations at which repeated measurements can be made to determine any buildup of radioactivity from deposition of airborne radionuclides. At each of these locations, in situ (in-field) rneasurements 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 I radionuclides in the soil. The soil survey was performed as required in 1997. Therefore, a soil survey was not performed during 1998, and the next survey is scheduled for the year 2000. 1 2.12 Surface Water Radioactivity Analyses ' Samples of surface water are routinely collected from the discharge canal, Bartlett Pond in Manomet and from the control location at Powder Point Bridge in Duxbury. The discharge canal is sampled continuously by a composite sampler. Grab samples are collected weekly from the Bartlett Pond and Powder Point Bridge locations. Samples of surface water are composited every four weeks and analyzed by gamma spectroscopy and low-level iodine analysis. These monthly composites are further composited on a quarterly basis and tritium analysis is performed on this quarterly sample. i A total of 36 samples (3 locations
- 12 sampling periods) of surface water were collected and analyzed as required during 1998. Results of the analyses of water samples are summarized in i Table 2.12-1. Naturally-occurring potassium-40 was detected in samples composed primarily of i seawater. No radionuclides attributable to Pilgrim Station operations were detected in any of the samples.
2.13 Irish Moss Radioactivity Analyses I Samples of Irish moss are collected from the discharge canal outfall and two other locations in the Plymouth area (Manomet Point, Ellisville), and from a control location in Marshfield (Green Harbor). All samples are collected on a quarterly basis, and processed in the laboratory for gamma spectroscopy analysis. All 16 samples of Irish moss scheduled for collection during 1998 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. Page 31
-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 coilected on a quarterly basis, and processed in the laboratory for gamma spectroscopy analysis. In addition to analyzing the edible portion (meat) from each of the samples, the shells from samples collected from the discharge canal outfall and from all control location samples are also analyzed.
All 48 samples of shellfish meat and shells scheduled for collection during 1998 were obtained and analyzed, as well as an additional sample of mussel shell. Results of the gamma analyses of these ' samples are summarized in_ Table 2.14-1. Naturally-occurring . beryllium-7, potassium-40, and thorium-232 were detected in a number of the samples. Low levels of - cobalt-60 were detected in blue mussel shells and meat collected from the discharge canal. Since the shells are not edible, such low-level contamination does not represent a normal exposure pathway, and no dose assessment was performed. The edible portions of mussel meat collected during the same period contained an average Co-60 concentration of 2.3 pCi/kg. This concentration was used to assess the resulting dose impact, as presented in Appendix A.- This small amount of Co-60 is estimated to have resulted in a dose of about 0.0001 mrem to the maximum-exposed individual. 2.15 Lobster Radioactivity Analyses Samples of lobsters are routinely collected from the outfall area of the discharge canal and from the control location in Duxbury. Samples are collected monthly from the discharge canal outfall from June through September and annually from the control location. All lobster samples are !' analyzed by gamma spectroscopy. i l All five samples of lobsters were collected and analyzed as required during 1998. Results of l the gamma analyses of lobster samples are sumrnarized 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. I 2.16 Fish Radioactivity Analyses Samples of fish are routinely collected from the area at the outfall of the discharge canal and from the control locations in Cape Cod Bay and Buzzard's Bay. Fish species are grouped into four major categories according to their biological requirements and mode of life. These major categories and the representative species are as follows: Group I - Bottom Oriented: Winter Flounder, Yellowtail Flounder Group 11 - Near-Bottom Distribution: Tautog, Cunner, Pollock, Atlantic Cod, Hake Group lll- Anadromous: Alewife, Smelt, Striped Bass Group IV - Coastal Migratory: Bluefish, Herring, Menhaden, Mackerel i Two subsamples of each category of fish are typically collected during each collection period. Group I and ll fishes are sampled on a quarterly basis from the outfall area of the discharge canal, and on an annual basis from a control location. Group ill and IV fishes are sampled annually from the discharge canal outfall and control location. All samples of fish are analyzed by gamma spectroscopy. Page 32
)
. Thirty-one samples of fish were collected during 1998. 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 I Station operations were detected in any of the samples. 2.17 Sediment Radioactivity Analyses Samples of sediment are routinely collected from the outfall area of the discharge canal and from three other locations in the Plymouth area (Manomet Point, Plymouth Harbor and Plymouth Beach), and from control locations in Duxbury and Marshfield. Samples are collected twice per year and are analyzed by gamma spectroscopy. Sediment cores are subdivided into > depth increments for analysis of radionuclide distribution by depth. During the first half of the year, samples are divided into 2 cm increments, whereas samples for the second half of the year are divided into 5 cm increments. In addition to the gamma analyses, plutonium analyses are performed on the surface layer samples collected during the first half of the year from the ; discharge canal outfall, Plymouth Harbor, Manomet Point and Duxbury. Plutonium analyses are also performed on a mid-depth section from the discharge canal sample and Duxbury sample. All 56 samples of sediment were collected as required during 1998. All of the required gamma analyses were performed on these samples. However, due to an error in paperwork submitted to the Duke Engineering Environmental Laboratory, plutonium analyses were initially missed on . three of the six required samples.- By the time the error was identified, the original samples had been disposed of. Backup samples were obtained for 2 of the 3 samples omitted from the first set of analyses, and plutonium analyses were performed on these backup samples. Additional details regarding this event are discussed in Appendix D of this report. 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 5 of 39 indicator station samples and in 10 of 17 control station samples. Plutonium-239/240 was detected in four of the indicator station samples, as well as in the control station samples. Cesium-137 levels in indicator samples ranged from non-detectable to a maximum concentration of 28 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 28 pCi/kg. The comparability of the results from indicator and control stations indicates that the source of this activity is not Pilgrim Station. The levels detected are also comparable to concentrations observed in the past few years and are indicative of Cs-137 resulting from nuclear weapons testing.
Plutonium-239/240 levels in indicator samples ranged from 2.2 to 7.9 pCi/kg. The concentration of Pu-239/240 in the single sample collected from the control locations beyond the influence of Pilgrim Station was 12.4 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. Page 33 1
\
f. Table 2.2-1 Routine Radioloalcal Environmental Samplina Locations Pilarim Nuclear Power Station. Plymouth. MA Description ' No Code Distance Direction Air Particula'e Filters. Charcoal Cartridaes. 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 Substaibn 17 MS 3.6 km SSE East Weymouth Contcol 21 EW 40 km NW M_i[h Plymouth County Farm 11 CF 5.6 km W Whitman Farm Control 21 WF 34 km WNW Foraae Plymouth County Farm 11 CF 5.6 km W
'Nhitman Farm Control 12 WF 34 km WNW Whipple Farm 43 WH 2.9 km SW Veoetation Plymouth County Farm 11 CF 5.6 km W Bridgewater Farm Control 27 BF 31 km W Cranberries .
Manomet Point Bog 13 MR 3.9 km SE Bartlett Road Bog 14 BR 4.3 km SSE Pine Street Bog Control - 23 PS 26 km WNW Page 34
Table 2.2-1 (continued) Routine Radioloaical Environmental Samolina Locations Pilarim Nuclear Power Station. Plymouth. MA Description No Code Distance Direction Surface Water Discharge Canal 11 DlS 0.2 km N , Bartlett Pond 17 BP 2.7 km SE Powder Point Control 23 PP 13 km NNW Irish Moss Discharge Canal Outfall 11 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 Hart >or 12 Ply-H 4.1 km W Duxbury Bay Control 13 Dux-Bay 13 km NNW l 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 l Plymouth Harbor 15 Ply-H 6.4 km WNW Duxt,ury Bay Control 13 Dux-Bay 11 km NNW ! Fishes Discharge Canal Outfall 11 DIS 0.5 km N Priest Cove Control 29 PC 48 km SW Jones River Control 30 JR 13 km WNW Vineyard Sound Control 92 MV 64 km SSW Buzzard's Bay Control 90 BB 40 km SSW l Cape Cod Bay Control 98 CC-Bay 24 km ESE Sediment Discharge Canal Outfall 11 DlS 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 i Green Harbor Control 24 GH 16 km NNW Page 35
Table 2.4-1 OffSite Environmental TLD ReSultS TLD Station TLD Location
- Exposure Rate - mR/ quarter (Value
- Std.Dev.)
1998 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 63.7
- 7.1 60.0
- 2.5 61.9 3.2 68.6
- 3.3 254.1
- 17.1
,OA OVERLOOK AREA 0.15km W 154.2
- 7.4 150.9
- 5.5 147.1
- 7.0 153.6
- 7.3 605.9
- 18.9 y HEALTH CLUB 0.15 km WSW 48.6
- 2.1 49.2
- 1.9 47.9
- 2.1 50.4
- 3.1 196.1
- 6.2 BLL BOAT LAUNCH EAST 0.16 km ESE 55.7
- 2.5 55.9
- 4.3 57.0
- 3.6 62.4 t 2.4 230.9
- 14.2 PB Pi )ESTRIAN BRIDGE 0.21 km N 35.8
- 1.7 34.1
- 2.4 Missing 36 9
- 3.2 142.5
- 8.0 P01 SHOREFRONT SECURITY 0.22 km NNW 313
- 2.6 34.7 + 1.2 35.7
- 2.0 36.4
- 2.7 146.0
- 9.0 WS MEDICAL BUILDING 0.23 km SSE ?,4 0
- 2.4 34.222.0 36.1
- 3.9 37.1
- 3.7 141.4
- 8.6 CT PARKING LOT 0.31 km SE 27.7
- 1.2 28 8
- 1.7 29.2
- 2.3 29.8 t 1.6 115.5
- 4.9 PA SHOREFRONT PARKING 0.35 km NNW 20.5
- 1.0 20.1
- 0.9 21.421.1 21.9
- 1.4 83.9
- 3.9 i A STATION A 0.37 km WSW 18 1
- 0.8 19.1
- 1.3 22.3
- 2.3 21.3
- 1.6 80.9
- 8.4 )
F STATION F 0.43 km NW 17.9
- 1.2 18.4
- 0.9 20.7
- 1.2 19.9
- 1.4 76 9
- 5.7 '
B STATION B 0.44 km S 21.2 1.0 21.6
- 1.3 22.9
- 1.r' 22.0
- 1.1 87.7 3.7 l EB EAST BREAKWATER 0.44 km ESE 22.4
- 1.2 22.6
- 1.0 24.5
- 1.3 23.3
- 1.3 92.8
- 4.5 PMT PNPS MET TOWER O.44 km WNW 17.2 t 0.9 17.3
- 1.0 18.9
- 0.7 18 5
- 1.3 71.8
- 4.0 H STATION H 0 47 km SW 21.4
- 0.9 20.5
- 1.3 22.6
- 1.1 22.2
- 1.0 86.8
- 4.2 1 STATION I 0.48 km WNW 18.4
- 1.0 17.8
- 0.8 19.9 t 0.9 19.3
- 1.6 75.4
- 4.4 )
I L STATION L 0.50 km ESE 19.2
- 0.9 18.6
- 0.7 20.2 e 1.0 20.0
- 1 0 78.1
- 3.4 G STATION G 0.53 km W Missing 16.1
- 0.6 17.5
- 0.8 18.4
- 1.7 69.4
- 5.4 D STATION D 0.54 km NW 18.1
- 0.7 17.5
- O.9 Missing 19.3
- 1.4 73.1
- 4.3 PL PROPERTY LINE 0.54 km NNW 16.4
- 0.9 16.7
- 1.0 Missing 17.2
- 1.1 67.1
- 2.9 C STATION C 0.57 km ESE 16.5 0.7 16.0 1.1 17.7
- 1.0 17.7
- O 8 67.9
- 3.8 HB HALL'S BOG 0.63 km SE 14.8
- O 6 15 3
- 1.0 17.6
- O.9 17.5*08 65.3
- 6.0 GH GREENWOOD HOUSE 0.65 km ESE 18.2
- 0.8 20.1
- 1.2 20.7
- 0.9 19.4
- 1.4 78.4 4.8 WR W ROCKY HILL ROAD 0 83 km WNW 19.0 t 0.9 18.6
- 0.8 19.8
- 0.8 20.5
- 1.7 77.9
- 4.0 ER E ROCKY HILL ROAD 0.89 km SE 13.7
- 0.7 13.3
- 0.8 14.7
- 0.9 14 9
- 0.7 56.5
- 3.5 MT MICROWAVE TOWER 1.03 km SSW 16.8
- 0.9 16.4 t 0.9 17.5
- 0 9 17.0
- 2.9 67.7
- 3.8 CR CLEFT ROCK 1.27 km SSW 15.2
- 0.6 14.3
- 0.7 15.6
- 0 8 15.9
- 1.2 60 9
- 3.2 BD BAYSHORE/ GATE RD 1.34 km WNW 16.5
- 0.8 14.9
- 0.6 17.9
- 1.0 16.5
- 1.3 66.0
- 5.2 MR MANOMET ROAD 1.38 km S 12.9
- 0.6 15.2
- 1.1 13.5
- O 8 14.1
- 1.0 55.7
- 4.3 l DR DIRT ROAD 148 km SW 13.4
- O.5 16.8
- 1.6 14.3
- 0.7 15.0
- 1.0 59.4
- 6.1 EM EMERSON ROAD 1. 53 km SSE Missing 15.1
- 1.3 17.7
- 1.2 16.3
- 0.7 65 4
- 5.7 EP EMERSON /PRISCILLA 1.55 km SE 14.9
- 0.7 14.8
- 0.5 17.0
- 1.0 16.7
- 0.5 63.4
- 4 8 l l AR EDISON ACCESS ROAD 1.59 km SSE 15.6
- 0.8 12 9
- 0.7 16.3
- 1.2 15.1
- O 6 59.9
- 6.1 '
l l BS BAYSHORE 1.76 km W 16.7 0.8 17.0
- 1.5 18 3
- 1.1 18.2
- 1.1 70.2
- 4.0 E STATION E 1.86 km S 14.7
- O 8 18.0
- 0.9 16.4
- O O 16.7
- 1.1 65.9
- 5.7 i JG JOHN GAULEY 1.99 km W 16.2
- 1.0 16.0 0.6 17.3
- 0 8 17.6
- 0.9 67.223.6 l
J STATION J 2.04 km SSE 164*08 13.5
- O 8 17.1
- 1 0 15.5
- 1.0 62.6
- 6.4 WH WHITEHORSE ROAD 2 09 km SSE 15.4
- 0.7 14.5
- 0.9 17.2
- 1.0 16.0
- 1.0 63.1 t 4.9 RC PLYMOUTH YMCA 2.09 km WSW 14.7
- 0.7 17.6
- 1.3 15.6
- U.8 16.1
- 0.9 64.1 5.3 K STATION K 2.17 km S 16.4
- 0.7 13 5
- 0.7 16.5
- 0.7 15.6
- 1.7 62.0
- 6.0 TT TAYLOR / THOMAS 2.26 km SE 15 8
- 0.7 14.9
- 0.8 16.9
- 0.9 16.120.5 63.7
- 3.6 YV YANKEE VILLAGE 2.28 km WSW 14.4
- 0.6 18.0
- 0.8 15.0
- 0.8 16.4
- 0 8 63.726.6 GN GOODWIN PROPERTY 2.38 km SW 108*05 13.6
- 0.6 12.0
- 0.6 12.5
- 0.5 48.8
- 4.7 RW RIGHT OF WAY 2.83 km S 15 4
- 0.8 14.3
- 0.5 14.520.9 16.0 0.7 60.1
- 3.4 TP TAYLOR / PEARL 2.98 km SE 18.7 e 1.5 13 5
- 0.7 15.3
- 0.7 14.7
- O 8 62.1
- 9.1 Distance and direction are measured from centerline of Reactor Building to the monitoring location.
" Annual value is based on arithmetic mean of the observed quarterly values multiplied by four quarters / year.
Page 36
Table 2.4-1 (continued) ' Offsite Environmental TLD ResultS TLD Station TLD Location
- Exposure Rate - mR/ quarter (Value i Std.Dev.)
1998 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 14.7
- 0.6 13.6
- 0.6 14.1
- 1.1 14.5
- 0.6 56.9
- 2.6 ME MANOMET ELEM 3.29 km SE 16.5
- 0.8 12.7
- 0.8 17.0 0.9 15.8 t 1.1 62.1
- 7.9 WC WARREN /CLIFFORD 3.31 km W 13.1
- 0.6 15.8
- 0.8 14.6
- 0.9 14.8
- 0.6 58.2
- 4.7 BB RT.3A/ BARTLETT RD 3.33 km SSE 15.7 t 0.8 13.4
- 0.5 16.1
- 0.9 15.7
- O.7 60.9
- 5.1 MP MANOMET POINT 3.57 km SE 20.0
- 1.9 14.0
- 1.1 22.5
- 1.3 15.8
- 1.1 72.3
- 15.7 MS MANOMET SUBSTATION 3.60 km SSE 17.720.8 17.1
- 0.9 18.7
- 1.2 18.6
- 1.3 72.2
- 3.8 BW BEACHWOOD ROAD 3.93 km SE 16.7 1.3 13.2
- 0.8 16.9
- 1.0 15.9
- 1.2 62 6
- 7.1 PT F:NES ESTATE 4.44 km SSW 14.5
- 0.6 13.7
- 0.6 15.0 t 1.5 14.0
- 0.9 57.2
- 3.1 EA EARL ROAD 4.60 km SSE 14.6
- 0.9 11.7
- 0.9 14.4
- 0.8 13.8
- 0.7 54.5
- 5.6 SP S PLYMOUTH SUBST 4.62 km W 16.0
- 0.8 15.1 s 0 7 15.6
- 0.9 15.820.7 62.4
- 2.1 RP ROUTE 3 OVERPASS 4.81 km SW 14.8*0.7 *3* 14.6
- 0.7 14.9
- 0.9 58.1
- 2.5 RM RUSSELL MILLS RD 4.85 km WSW 14.0 t 0.7 -
13.2
- O.7 13.4
- 0.9 53.2
- 2.5 HD HILLDALE ROAD 5.18 km W 14.2
- 0.6 '
.9 15.4
- 0.8 15.7 t 0.9 62.1
- 4.6 MB MANOMET BEACH 5.43 km SSE 16.0
- 0.7 0.7 15.3
- 0.7 14.3
- 0.5 57.8
- 6.6 BR BEAVERDAM ROAD 5.52 km S 14.2
- 0.7 0.0 13.7
- 0.6 13.8
- 0.7 54.3
- 2.9 PC PLYMOUTH CENTER 6.69 km W 12.6
- 3.7 l
,c 0.6 10.8
- 0.8 10.5
- 0.4 43.6
- 6.1 LD LONG POND / DREW RD 6.97 km WSW 12.5
- 0.5 1
- 1.1 13.5
- 0.8 14.3
- 0.6 55.4
- 4.8 HR HYANNIS ROAD 7.33 km SSE 15.5
- 0,7 c.8
- 0.5 15.4
- 0.9 15.1
- 0.7 58.8 t 5.4 MH MEMORIAL HALL 7.58 km WNW 24.0
- 1.0 24.0
- 0.9 25.5
- 1.2 25.1
- 1.1 98.6
- 3.7 SN SAOUISH NECK 7.58 km NNW 11.6 0.6 10.9
- 0.5 12.5
- 0.7 12.5
- O.6 47.5
- 3.3 CP COLLEGE POND 7.59 km SW 16.6
- 1.1 13.9
- 0.9 14.3
- 1.0 14.3 e 0.8 59.1 t 5.2 Zone 3 TLDs: 8-15 km DW DEEP WATER POND 8.59 km W 17.1
- 0.8 16.2 0.7 17.3
- 0.8 17.7
- 0.5 68.3
- 2.9 LP LONG POND ROAD 8.88 km SSW 13.2
- 0.6 12.2
- 0.5 13.0
- 0.9 13.8
- 1.1 52.223.1 NP NORTH PLYMOUTH 9.38 km WNW 17.2
- 0.8 18.3
- 0.9 18.2
- 0.8 18.1
- 0.8 71.8
- 2.6 SS STANDISH SHORES 10.39 km NW 13.7
- 0.6 13.0
- 0.7 14.7
- 0.9 14.2
- 1.0 55.5
- 3.3 EL ELLISVILLE ROAD 11.52 km SSE 15.8
- 0.7 12.6
- 0.5 15.9
- 0.9 15.3
- 0.6 59.6
- 6.4 UC UP COLLEGE POND RD 11.78 km SW 14.4
- 0.6 12.6
- 0.6 13.1
- 0.8 13.7
- 0.5 53.8
- 3.2 SH SACRED HEART 12.92 km W 15.2
- 0.6 13 4
- 0.9 14.7
- 0.7 15.4
- 0.7 58.6
- 4.0 RKtNG CAESAR ROAD 13.11 km NNW 14.4
- 0.6 Missing 16.0
- 1.1 15.6
- 0.7 61.4
- 4.0
_BE BOURNF__ ROAD 13.37 km S 13.9
- 0.8 12.7
- 0.7 13.2
- 0.7 14.0
- 0.5 53 8 e 2.8 SA SHERMAN AIRPORT 13.43 km WSW 18.1
- 0.9 13.3
- 0.5 14.5
- 0.6 14.4
- 0.9 60.2
- 8.5 Zone 4 TLDs: >15 km CS CEDARVILLE SUBST 15.93 km S 17.0
- 0.8 13.4
- O 8 18.1
- 1.0 15.4 0.9 63.9
- 8.3 KS KINGSTON SUBST 16.15 km WNW 15.4
- 0.7 13.3
- 0 5 14.0
- 0.8 14.1*0 8 56.9
- 3.9 LR LANDING ROAD 16.46 km NNW 15.7
- 1.3 14 5
- 0.7 16.0 1.0 15.2
- 0.5 61.3
- 3.2 CW CHURCH / WEST 16.56 km NW 12.7
- 0.6 12.4
- 0.6 14.2
- 0.7 13 9
- 0.6 53.1
- 3.8 MM MAIN / MEADOW 17.02 km WSW 15.3
- 0.7 14.5
- 1.0 14.8
- 0.7 15.7
- 0.5 60.3
- 2.7 DMF DIV MARINE FISH 20.97 km SSE 17.7
- O 8 14.9
- 0.8 18.1 1.0 17 5
- 1.0 68.1
- 6.0 EW E.WEYMOUTH SUBST 39.69 km NW 16.7
- 0.8 16.6
- 0.6 18.2
- 1.3 17.2
- 1.3 68.7
- 3.6 Distance and direction are measured from centerline of Reactor Building to the monitoring location.
" Annual value is based on arithmetic mean of the observed quarterly values multiplied by four quarters / year.
Page 37
Table 2,4-2 Onsite Environments TLD ReSults TLD Station TLD Location
- Exposure Rate - mR/ quarter (Value i Std.Dev.}
1998 Annual" ID Description Distance / Direction Jan-Mar Apr Jun Jul-Sep Oct-Dec Exposure mR/ year Onsite TLDs P21 O&M/RXB. BREEZEWAY 50 m SE 27.5
- 1.3 26.9
- 0.9 26.5
- 1.3 28.5
- 0.9 109 4
- 4.2 P24 EXEC. BUILDING 57m W 60.8
- 3.3 62.9 2.8 61.9
- 3.3 65.023.1 250.6
- 9.6 PO4 FENCE-R SCREENHOUSE 66 m N 110.7
- 4.5 113.7
- 6.3 104.0
- 5.5 110.1
- 7.4 438.4
- 20.3 P20 O&M 2ND W WALL 67 m SE 75.9
- 6.0 78.8
- 3.4 76.3
- 3.2 78.6 e 3.8 309.7
- 10.5 P25 EXEC. BUILDING LAWN 76 m WNW 125.4
- 5.7 139.6 9.1 125.1
- 6.9 141.0 e 8.2 531.2
- 38.0 POS FENCE WATER TANK 81 m NNE 36.9
- 2.7 41.2
- 2.5 33.7
- 2.0 38.6
- 3.1 150.3
- 13.5 P06 FENCE-OIL STORAGE 85 m NE 51.5
- 2.9 49.2
- 1.9 58.6
- 4.7 63.9
- 3.0 223.2 27.7 P190&M - 2ND SW CORNER 86 m S 100.5
- 6.8 85.0
- 3.6 109.7 8.1 107.8
- 5.7 403.0
- 46.6 P180&M 1ST SW CORNER 90 m S 65.4
- 2.9 61.0
- 3.2 69.8
- 6.5 68.5
- 2.7 264.7
- 17.7 P08 COMPRESSED GAS STOR 92 m E 58.0
- 3.1 61.9
- 4.7 68.2
- 5.6 71.9
- 7.6 260.0
- 27.3 P03 FENCE-L SCREENHOUSE 100 m NW 98.624.9 102.5
- 5.6 97.5
- 4.0 101.4 t 5.1 400.0
- 13.6 P17 FENCE-EXEC. BUILDING 107 m W 180.8
- 11.5 172.2
- 6.0 178.7
- 7.1 188.5
- 6.7 720.3
- 31.4 P23 CLM - 2ND S WALL 121 m ENE 55.2
- 2.2 i 58.0
- 1.8 59.6
- 5.2 60.7
- 5.2 233.5
- 12.3 P07 FENCti-INTAKE BAY 121 m SSE 55.9
- 2.8 57.6
- 3.0 55.6
- 2.1 59.8
- 3.1 228.9
- 9.4 j P26 FENCE-WAREHOUSE 134 m ESE 53.9
- 2.3 57.2
- 4.8 55.2
- 1.9 64.0
- 4.3 230.4
- 19.4 l P02 FENCE-SHOREFRONT 135 m NW 64.7
- 3.2 65.7
- 4.6 62.1
- 2.7 66.4
- 4.4 258.9 2 10.7 P09 FENCE-W BOAT RAMP 136 m E 49 6 3.7 48.4 t 3.4 49.8
- 3.2 51.9
- 5.3 199.6
- 9.9 P22 O&M 2ND N WALL 137 m SE 45.7 e 2.3 45.223.4 46.9
- 3.4 48 8
- 2.7 186.7
- 8.7 P16 FENCE-W SWITCHYARD 172 m SW 140.7
- 5.4 139.0
- 4.4 137.7
- 6.7 150.9 7.5 568.4
- 27.0 P11 FENCE-TCF GATE 183 m ESE 55.5
- 3.0 61.2
- 3.5 76.5
- 4.5 81.6
- 3.9 274.7
- 50.0 P27 FENCE-TCF/ BOAT RAMP 185 m ESE 62.0 e 3.4 56.0
- 2.3 59.0
- 3.2 61.7
- 2.5 238.6
- 12.6 P12 FENCE-ACCESS GATE 202 m SE 37.1
- 2.3 37.4
- 3.7 36.8
- 2.0 39.5
- 2.1 150.8
- 7.1 P15 FENCE E SWITCHYARD 220 m S 48.6
- 2.3 50.5
- 1.9 47.9
- 2.4 54.0
- 3.5 201.0
- 12.1 P10 FENCE-TCF/ INTAKE BAY 223 m E 48.8
- 2.2 47.5
- 10.3 51.2
- 2.9 56.1
- 3.3 203.5
- 19.0 P13 FENCE-MEDICAL BLDG. 224 m SSE 38.1
- 2.4 35.4
- 1.2 36.0
- 1.6 38.3
- 1.3 147.7
- 6.7__
P14 FENCE-BUTLER BLDG 228 m S 35.5
- 1.7 34.7
- 1.3 35.2
- 1.5 37.8
- 1.5 143.2
- 6.2 P28 FENCE TCF/PRKNG LOT 259 m ESE 98.3
- 7.7 91.9
- 8.6 96.3 e 3.7 l 79.5
- 7.1 366.0
- 36.5
- Distance and direction are measured from centerlirse 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 i 1 i Page 38
Table 2.4-3 Average TLD Exposures By Distance Zone During 1998 Average Exposure i Standard Deviation: mR/ period Exposure Zone 1* Zone 2 Zone 3 Zone 4 Period 0-3 km 3-8 km 815 km >15 km Jan-Mar 24.3 i 23.3 15.5 i 2.7 15.3 1.7 15.8 i 1.7 Apr-Jun 23.6 i 22.2 14.1 i 2.9 13.8 i 2.1 14.2 i 1.4 Jul-Sep 24.7 i 22.2 15.7 i 3.3 15.1 i 1.8 16.212.0 Oct-Dec 25.0123.0 15.2 i 2.8 15.2 i 1.6 15.6 1.4 l Jan-Dec 97.6 i 89.8" 60.4 i 11.8 59.5 i 7.2 61.8 i 6.7
- 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 63.7 i 7.5 mR/yr.
l Page 39
I-Table 2.4-4 l l Beach Survey Exposure Rate Measurements Ambient Radiation Survey Results Exposure Rate i 1 std. dev. Location R/hr mR/yr Beach Terrain White Horse Beach l (Near Hilltop Ave) 8.4 i 0.1 7410.9 Sandy. Few granite boulders 2.62 km SE within thirty feet. Priscilla Beach (In Back of Full Sail Bar) 10.2 i 0.1 89 i 0.9 Sandy with small amounts of 1.89 km SE g. ravel. Plymouth Beach (Outer Beach) 6.5 i 0.1 57 i 0.9 Sandy. 7.21 km WNW _ Plymouth Beach (Inner Beach) 6.8 i 0.1 60 i 0.9 Sandy. 6.07 km WNW Plymouth Beach l (Behind Bert's Restaurant) 9.8 i 0.1 8610.9 Sandy with gravel. Breakwater 3.66 km W _ and seawall nearby. Duxbury Beach (Control) 9.2 1 0.1 81 i 0.9 Sandy with coarse gravel and 10.94 km NNW exposed cobble. l I l ! l l l Page 40
II l- ! Table 2.5 l Air Particulate Filter Radioactivity Analyses l l Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January December 1998) MEDIUM: Air Particulates (AP) UNITS: oCl/ cubic meter ) l l !"d'.?.' '.8.*?..
.S'*?.
- a. *lf.h,Highnt,,Mean
, , , , , g,ontrq,,S,tations i Radionuclides Mean Sta. Mean Mean' I (No. Analyses) - Required Range Range Range f (NonRoutine*) LLD (No. Detected") (No. Detected **) (No. Detected")
l [ GR-B (572) 0.01 ( 2.2 1.0)E 2 10 ( 2.3 a 1.2)E -2 ( 2.3 e 1.0)E -2 (0) ( 1.1 67.3)E -3 ( 5.6 67.3)E 3 ( 7.9 - 442)E -3 (515/520) (52/52) (52/ 52) Be-7 (44) ( 8.3 t 1.6)E -2 09 ( 9.0 a 1.9)E -2 ( 8.2 s 1.0)E -2 (0) ' ( 5.2 - 11.5;.' -2 ( 6.8 10.7)E -2 ( 7.3 - 8.9)E -2 (40/40) (4/ 4) (4/ 4) ! K-40 (44) ( 2.9 s 7.4)E -3 15 ( 6.9 11.8)E -3 ( 2.8
- 6.2)E -3
( (0) (-8.3 21.4)E -3 (-3.1 21.4)E -3 ( -4.5 - 8.6)E -3 (0/ 40) (0/ 4) (0/ 4)
' Cs-134 (44) 0.01 (-2.4
- 29.0)E -5 17 ( 2.7 2 4.9)E -4 (-1.3
- 30.4)E -5 (0) ( -5.7 - 9.5)E -4 (-4.4 95.4)E -5 ( -2.6 2.6)E -4 l (0/ 40) (0/ 4) (0/ 4) l l Cs-137 (44) 0.01 ( 1.8 s 24.2)E -5 07 ( 1.7 a 2.1)E 4 ( 1.5 s 3.6)E -4 l (0) ( -6.9 - 4.1)E -4 (-2.1 38.1)E -5 ( -1.8 5.9)E -4
- i. (0/ 40) (0/ 4) (0/ 4)
- Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.
" The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.
i l I l I Page 41
i 1 Table 2.6-1 i Charcoal Cartridge Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA l (January - December 1998) MEDIUM CharcoalCartridae (CF) UNITS: DCi/ cubic meg Indicator Stati Station With Highest Mean Control Stations
. .ons ............................. ......................
Radionuclides Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (NonRoutine*) LLD (No. Detected **) (No. Detected") (No. Detected") 1-131 (572) 0.07 ( 5.8 s 102.4)E -4 07 ( 1.4 a 10.8)E -3 (1.0 10.8)E -3 (0) ( -7.4 - 2.6)E -2 (-2.2 2.6)E 2 ( -2.3 - 2.4)E -2 (0/520) (0/ 52) (0/ 52) j
- Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.
" The fraction of sample analyses yiekling detectable measurements (i.e. >3 standard deviations) is shown in parentheses.
l i 1 l I l l l l ! I l 1 Page 42
Table 2.7-1 Milk Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station Plymouth, MA (January - December 1998) MEDIUM: Milk (TM) UNITS: oCi/ Liter
!".dyator Stat
, . . , Stat {ogs ,, ,,, yn {, ,, j,,h H ghest..My,an
,, g,ogtlp,1, ,Stations Radionuclides Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (NonRoutine') LLD (No. Detected") (No. Detected **) (No. Detected")
K-40 (40) ( 1.4 2 0.1)E 3 11 ( 1.4
- 0.1)E 3 ( 1.4 2 0.1)E 3 (0) ( 1.3 - 1.6)E 3 ( 1.3 - 1.6)E 3 ( 1.3 - 1.6)E 3 (20/20) (20/20) (20/20)
Sr-89 (40) ( -5.7 18.1)E -1 21 (-4.2
- 21.3)E -1 ( -4.2 21.3)E 1
(0) ( -2.7 - 4.5)E O (-3.5 3.9)E O (-3.5 - 3.9)E O (0/ 20) (0/ 20) (0/ 20) Sr-90 (40) (1.3 0.7)E O 11 ( 1.3 s 0.7)E O ( 9.2
- 12.4)E -1 (0) ( 2.7 30.5)E -1 ( 2.7 - 30.5)E -1 ( -7.6 - 47.7)E -1 (9/ 20) (9/ 20) (5/ 20) 1131 (40) 1 . ( 3.2 7.1)E -2 21 ( 4.5
- 10.0)E -2 ( 4.5 210.0)E -2 (0) ( -6.0 - 22.6)E 2 ( -4.5 - 33.2)E -2 ( -4.5 - 33.2)E -2 (0/ 20) (0/ 20) (0/ 20)
Cs 134 (40) 15 ( -2.3 10.6)E 1 11 ( -2.3 10.6)E -1 ( -2.9 14.7)E -1 (0) (-2.6 - 1.2)E O (-2.6 1.2)E O (-4.4 - 2.9)E O (0/ 20) (0/ 20) (0/ 20) i Cs-137 (40) 15 ( 1.8 21.3)E O 11 ( 1.8
- 1.3)E O ( 3.7 21.5)E -1 (0) ( 2.6 - 42.3)E -1 ( 2.6 42.3)E -1 (-3.3 4.2)E O (0/ 20) (0/ 20) (0/ 20)
Da-140 (40) 15 ( -6.2 20.7)E -1 21 (-2.9 218.0)E 1 (-2.9
- 18.0)E 1 (0) ( -4.4 - 2.6)E O ( -4.3 - 2.3)E O ( -4.3 - 2.3)E O 1 (0/ 20) (0/ 20) (0/ 20) j l
- Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.
" The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses. Page 43
Table 2.8-1 Forage Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 1998) MEDIUM: Foraae UC) UNITS: oCi/ka wet Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (NonRoutine') LLD (No. Detected") (No. Detected") (No. Detected **) Be-7 (3) ( 1.5
- 0.2)E 3 21 ( 4.1
- 0.2)E 3 ( 4.1
- 0.2)E 3 (0) ( 1.4 - 1.5)E 3 (2/ 2) (1/1) (1/1)
K-40 (3) ( 5.2 e 2.8)E 3 21 ( 8.8 0.4)E 3 ( 8.8 s 0.4)E 3 (0) ( 3.2 7.2)E 3 (2/ 2) (1/1) (1/1) 1-131 (3) ( 3.1 18.7)E O 33 ( 8.6 s 21.6)E O (-1.4
- 3.8)E 1 (0) (-2.3 8.6)E O (0/ 2) (0/1) (0/1)
Cs-134 (3) 130 ( 7.6 216.5)E O 11 ( 1.7
- 1.6)E 1 ( -3.4 13.1)E O (0) (-1.8 - 17.0)E O (0/ 2) (0/1) (0/1)
Cs-137 (3) 130 ( 6.3 33.1)E O 11 ( 2.9
- 1.7)E 1 ( 4.1212.6)E O (0) (-1.6 - 2.9)E 1 (0/ 2) (0/1) (0/1)
Th-232 (3) ( 5.4 6.6)E 1 11 ( 8.3 2 9.4)E 1 ( 8.12 64.3)E O (0) ( 2.4 - 8.3)E 1 (0/ 2) (0/1) (0/1)
- Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.
" The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses. Page 44 1
m 1 l
)
l Table 2.9-1 J VegetableNegetation Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 1998) MEDIUM: Vecetation (TF) UNITS: oCi/ko wet indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (NonRoutine*) LLD (No. Detected") (No. Detected") (No. Detected") ! Be-7 (16) ( 2.0
- 1.5)E 3 01 (4.6 0.1)E 3 ( 1.0
- 1.2)E 3 j (0) (-6.9 457.5)E 1 ( -8.7 - 239.3)E 1 i (8/10) (1/1) (3/ 6)
K-40 (16) ( 3.3 s 1.2)E 3 31 ( 4.5 0.2)E 3 ( 3.5 z 1.0)E 3 (0) ( 1.2 4.8)E 3 ( 2.2 - 4.4)E 3 (10/10) (1/1) (6/ 6) 1-131 (16) 60 ( -2.0 16.1)E O 35 ( 1.5 s 0.9)E 1 (-6.1
- 21.9)E O (0) ( -4.3 - 1.5)E 1 (-3.1 - 2.3)E 1 (0/10) (0/1) (0/ 6)
Cs 134 (16) 60 ( -4.8 119.8)E -1 31 ( 2.7
- 1.5)E 1 (-3.7 7.3)E O (0) (-1.4 - 2.7)E 1 ( -1.2 - 0.7)E 1 i (0/10) (0/1) (0/ 6)
Cs-137 (16) 60 ( 3.7 2 7.1)E 1 01 ( 2.0
- 0.1)E 2 ( 6.7
- 17.5)E O (0) ( -2.2 - 20.1)E 1 ( -1.2 - 3.6)E 1 (4/10) (1/1) (1/ 6) ,
i Th-232 (16) ( 6.2 9.1)E 1 01 (1.9 0.2)E 2 ( 5.3 s 5.8)E 1 I (0) ( -1.3 - 1.9)E 2 ( 7.7 - 141.4)E O (4/10) (el1) (2/ 6)
- Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.
" The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.
l ! Page 45 l l
r t Table 2.10-1 Cranberry Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January December 1998) l M,,jDIUM: Cranberries (CB) UNITS: DCi/ka wet S*" .".'."2.".iS. hest Mqan
..'. g,on1rg,,StaUons
!".dic*'.5.St'.'!
. . ".t.. . , , , , , ,,,, ,,, ,,,,
Radionuclides Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (NonRoutine*) LLD (No. Detected **) (No. Detected") (No. Detected **) Be-7 (3) ( 1.2
- 7.3)E 1 13 (4.3 10.5)E 1 ( 1.5 t 0.8)E 2 I (0) ( 1.9 - 4.3)E 1 (0/ 2) (0/1) (0/1)
K 40 (3) ( 8.6
- 4.4)E 2 13 ( 1.1 a 0.3)E 3 (7.3 2.1)E 2 (0) ( 5.7 - 11.5)E 2 (2/ 2) (1/1) (1/1) i 1-131 (3) ( 8.2 + 24.7)E O 13 ( 6.7 2 21.9)E O ( -2.4 3.0)E 1 '
(0) (-2.3 0.7)E 1 (0/ 2) (0/1) (0/1) Cs-134 (3) 60 ( 1.1 2.3)E 1 13 ( 2.7 21.2)E 1 ( 8.0
- 11.6)E O (0) ( -4.0 - 26.7)E O (0/ 2) (0/1) (0/1)
Cs 137 (3) 60 ( 3.3 s 11.1)E O 13 ( 8.2
- 16.1)E O ( 1.9 2 9.7)E O (0) (-1.6 8.2)E O )
(0/ 2) (0/1) (0/1) l Th-232 (3) ( 1.3 e 2.8)E 1 23 ( 7.7 2 5.1)E 1 ( 7.7 z 5.1)E 1 (0) ( 8.8 16.7)E O (0/ 2) (0/1) (0/1)
- Non-Reutine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.
" The fraction of sample analyses yielding detectable measurements (i e. >3 standard deviations) is shown in parentheses. j i
l Page 46
Table 2.11-1 Soil Radicactivity Analyses i Routine soil surveys and analyses are required only once every three years. The survey was performed as scheduled in 1997, and is not due to be performed again until the year 2000. 1 l l Page 47
r Table 2.12-1 Surface Water Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA i panuary December 1998) MEDIUM: Surface Water (WE) UNITS: oC6/ka S
!ada*M.Sfa'.. .
..'*?. a.*!!".Highes{,y,ean
, , , , , g,g,ntgStag,ons,,,,
t Radionuclides Mean Sta. Mean Mean l (No. Analyses) Required Range Range Range (NonRoutine') LLD (No. Detected **) (No. Detected **) (No. Detected **) H-3 (12) 3000 (-5.4 218.7)E 1 11 (-2.4 a 13.5)E 1 (-3.3 212.7)E 1 (0) (-42 1.4)E 2 (-1.0 0.6)E 2 ( 8.1 4.0)E 1 (0/ 8) (0/ 4) (0/ 4) K-40 (36) ( 1.5
- 1.5)E 2 11 (3.0 0.4)E 2 (2.9 0.4)E 2 ;
(-3.6 35.5)E 1 ( 2.5 3.6)E 2 (0) ( 2.3 - 3.8)E 2 (12/24) (12/12) (12/12) Mn-54 (36) 15 (-2.8
- 10.5)E -1 17 ( -2.3
- 10.0)E -1 (-3.9 e 12.9)E -1 l (0) ( 1.9 2.2)E O ( 1.9 1.2)E O (-2.4 - 1.4)E O (0/ 24) (0/12) (0/12)
- i. Co-58 (36) 15 ( 2.0 e 102.0)E -2 17 ( 1.4 e 103.3)E -2 ( 1.1 s 1.3)E O l (0) (-2.2 2.2)E O ( 2.2 1.3)E O ( -2.7 - 1.4)E O
- l. (0/ 24) (0/12) (0/12)
Fe-59 (36) 30 ( 3.6
- 26.5)E 1 17 ( 5.5
- 22.4)E 1 (-7.4 2 38.1)E 1 (0) ( 4.3 - 5.2)E O ( -4.3 - 4.0)E O ( -5.7 - 6.7)E O (0/ 24) (0/12) (0/12)
Co-60 (36) 15 ( 2.0
- 16.4)E -1 11 ( 8.8
- 12.4)E 1 ( 7.1
- 14.7)E -1 i
(0) . ( 5.2 3.0)E O (-8.3 29.9)E 1 (-2.1 - 2.7)E O l (0/ 24) (0/12) (0/12) 1 l Zn-65 30 (36) ( 9.7 s 35.3)E 1 17 ( 8.12 29.8)E -1 ( 7.2
- 32.3)E 1 (0). ( -6.9 - 4.4)E O (-4.0 4.4)E O (-5.0 4.6)E O (0/ 24) (0/12) (0/12) l Zr-95 (36) 15 (-3.2
- 20.8)E 1 17 (1.7 19.3)E -1 ( 3.6 2 22.1)E -1 l (0) ( -4.3 - 3.8)E O (-3.6 3.8)E O (-3.4 4.1)E O l (0/ 24) (0/12) (0/12) 1-131 (36) 1 ( 1.5 211.1)E -2 17 (-5.5 e 72.9)E -3 ( -2.3 s 6.2)E -2 (0) (-3.8 1.6)E -1 ( -9.8 - 15.9)E -2 (-1.2 - 1.1)E -1 (0/ 24) (0/12) (0/12)
Cs-134 (36) 15 ( -4.3 10.7)E -1 23 ( -3.6
- 16.5)E -1 ( 3.6 216.5)E 1 (0) (-2.4 2.3)E O (-2.4 2.9)E O ( 2.4 - 2.9)E O (0/ 24) (0/12) (0/12)
Cs-137 (36) 18 ( 2.6 212.9)E 1 23 (-1.1
- 13.8)E 1 (-1.1 e 13.8)E -1 (0) (-3.5 1.6)E O ( 2.2 - 1.6)E O ( 1.6)E O j (0/ 24) (0/12) (0/12) j Ba-140 (36) 15 ( 1.9 s 19.6)E -1 17 ( 6.0 s 22.7)E 1 (-5.6 s 18.9)E -1 1 (0) (-3.1 - 3.2)E O ( 3.1 - 3.2)E O (-3.0 2.5)E O (0/ 24) (0/12) (0/12) ;
i l
- Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.
** The fracton of sample analyses yielding detectable measurements (i.e. >3 standard deviations)is shown in parentheses.
Page 48 L
Table 2.13-1 Irish Moss Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January December 1998) MEDIUM: Insh Moss (AL) UNITS: oCi/ka wet Indicator Stations Station With Highest Mean Control Stations Radionuclides Mean Sta. Mean Mean l (No. Analyses) Required Range Range Range (NonRoutine*) LLD (No. Detected **) (No. Detected **) (No. Detected") Be-7 (16) ( 2.2 1.4)E 2 22 ( 3.6 2 0.9)E 2 ( 1.4 a 0.8)E 2 (0) ( 6.5 - 41.1)E 1 ( 2.5 - 4.1)E 2 ( 4.8 21.9)E 1 (2/12) (2/ 4) (1/ 4) K-40 (16) ( 6.3 e 1.2)E 3 11 ( 7.0 21.3)E 3 ( 6.8 s 1.0)E 3 (0) ( 4.9 - 8.3)E 3 ( 5.7 8.3)E 3 ( 5.8 - 8.0)E 3 (12/12) (4/ 4) (4/ 4) l Mn-54 (16) ( -6.0 56.0)E 1 34 ( 4.4
- 7.1)E O (4.4 7.1)E O (0) (-9.2 - 7.7)E O (-9.7 - 123.0)E -1 (-9.7 - 123.0)E 1 (0/12) (0/ 4) (0/ 4)
Co-58 (16) (-1.7
- 8.6)E O 22 ( 6.4 2 70.8)E 1 (-1.1 s 7.2)E O (0) (-1.4 - 1.4)E 1 (-4.9 9.0)E O (-9.3 - 6.2)E O (0/12) (0/ 4) (0/ 4)
Fe-59 (16) ( 1.8 s 25.2)E O 15 ( 7.5
- 27.1)E O (-2.5 a 1.6)E 1 l (0) ( 3.2 - 4.5)E 1 ( 1.2 4.5)E 1 (-3.0 --2.0)E 1 (0/12) (0/ 4) (0/ 4)
I Co-60 (16) (-1.118.5)E O 11 ( 2.2 13.1)E O (-2.3 2 5 0)E O ( (0) ( -1.4 - 1.4)E 1 (-1.4 - 1.4)E 1 ( -4.7 - 3.5)E O (0/12) (0/ 4) (0/ 4) Zn-65 (16) ( 4.3
- 22.2)E O 11 ( 1.9 t 2.3)E 1 ( 5.3
- 27.5)E O i
(0) (-3.4 - 3.5)E 1 ( 2.4 35.0)E O ( -1.0 - 4.3)E 1 (0/12) (0/ 4) (0/ 4) Cs-134 (16) (-3.1 z 7.0)E O 34 ( 8.1
- 8.7)E O ( 8.1
- 8.7)E O (0) (-1.5 1.1)E 1 ( 0.0 1.9)E 1 ( 0.0 - 1.9)E 1 (0/12) (0/ 4) (0/ 4)
Cs-137 (16) (-1.8
- 7.6)E O 34 (7.0 5.1)E O ( 7.0 e 5.1)E O (0) ( -1.3 - 1.1)E 1 ( 1.4 9.9)E O ( 1.4 9.9)E O (0/12) (0/ 4) (0/ 4)
Th-232 (16) ( 3.8 z 2.3)E 1 22 ( 4.6 s 2.7)E 1 ( 2.12 3.6)E 1 (0) ( 2.4 72.4)E O ( 2.2 7.2)E 1 (-5.3 68.3)E 0 (0/12) (0/ 4) (0/ 4)
- Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.54. i
** 1 he fraction of sample analyses yielding detectable measurements (l.a. >3 standard deviations) is shown in parentheses.
Page 49
l l Table 2.14-1 I Shellfish Radioactivity Analyses ) l Radiological Environmental Program Summary l Pilgrim Nuclear Power Station, Plymouth, MA j (January December 1998) MEDIUM: Shellfish (SF) UNITS: oCi/ka wet S*i
!"dic*to'f*.'!?.a$
. . . . . ..'. '...".1"2.".'.9"*t'..Y.**.a
. . S .a'.'.?.St*!'..a*
. .... 1 Radionuclides Mean Sta. Mean Mean !
l (No. Analyses) Required Range Range Range (NonRoutine*) LLD (No. Detected **) (No. Detected") (No. Detected **) Be-7 (49) ( 6.0 t 5.8)E 1 12 ( 8.2
- 7.8)E 1 ( 1.9 4.7)E 1 (0) ( -2.3 - 21.0)E 1 ( -2.3 - 21.0)E 1 ( -4.3 - 13.7)E 1 (8/ 25) (2/12) (3/ 24)
K-40 (49) ( 9.1
- 4.9)E 2 15 ( 1.0
- 0.3)E 3 ( 8.1
- 6.6)E 2 (0) ( 6.2 - 159.4)E 1 ( 4.1 12.7)E 2 ( 9.7 - 244.5)E 1 (21/ 25) (5/ 5) (20/24)
Mn-54 (49) 130 ( 3.6 2 57.6)E -1 13 ( 1.1 t 4.1)E O ( 8.3
- 33.3)E -1 i (0) ( -1.0 - 2.1)E 1 ( -6.3 6.8)E O (-6.3 6.8)E O l (0/ 25) (0/16) (0/ 24) l Co-58 (49) 130 ( 1.3
- 4.1)E O 24 ( 3.0
- 14.0)E -1 (-9.4
- 55.5)E -1 4
l (0) ( -1.5 - 0.6)E 1 ( -1.5 - 2.9)E O ( -1.6 - 1.1)E 1 (0/ 25) (0/ 8) (0/ 24) Fe-59 (49) 260 (9.7 126.9)E 1 12 ( 2.1
- 18.6)E O ( 5.0 e 257.9)C 1 (0) (-2.8 - 3.8)E 1 ( -2.8 - 3.8)E 1 (-7.2 4.7)E 1 (0/ 25) (0/12) (0/ 24) {
l I Co 60 (49) 5 (1.7 5.2)E O 11 ( 2.8 s 2.6)E O (-1.7
- 6.5)E O (0) (-9.2 - 15.0)E O ( 6.8 - 80.6)E -1 ( -1.7 - 0.5)E 1 (3/ 25) (3/ 8) (0/ 24 )
1 Zn-65 (49) 5 ( -2.8 17.9)E O 24 ( 1.6
- 3.6)E O (-2.3
- 10.7)E O (0) (-5.7 - 2.8)E 1 (-4.5 7.0)E O ( 2.5 - 2.5)E 1 (0/ 25) (0/ 8) (0/ 24)
Zr-95 (49) 5 (-1.1
- 76.6)E -1 13 ( 5.9
- 20.0)E O (4.0 16.3)E O (0) ( 2.6 - 1.6)E 1 ( -3.0 - 5.8)E 1 ( -3.0 - 5.8)E 1 (0/ 25) (0/16) (0/ 24)
Cs-134 (49) 5 ( 1.4 6.2)E O 12 ( 2.3
- 8.8)E O (-2.2
- 6.5)E O (0) (-1.3 1.8)E 1 ( -1.3 - 1.8)E 1 ( -2.3 - 0.6)E 1 (0/ 25) (0/12) (0/ 24)
Cs-137 (49) 5 (-1.2
- 2.9)E O 15 ( 2.5
- 7.7)E 1 (-4.1 z 69.1)E -1 (0) ( -9.2 - 3.2)E O (-3.8 - 13.2)E -1 ( -1.2 - 2.3)E 1 (0/ 25) (0/ 5) (0/ 24)
Ce 144 (49) 15 ( 2.3 15.5)E O 13 ( 9.7 2 38.7)E O ( 6.1
- 31.4)E O (0) (-4.7 4.5)E 1 (-5.2 - 11.2)E 1 (-5.2 - 11.2)E 1 (0/ 25) (0/16) (0/ 24)
Th-232 (49) (1.2 2.0)E 1 13 (4.3 5.0)E 1 ( 3.4 4.3)E 1 (0) ( 2.7 - 5.0)E 1 (-2.1 - 15.7)E 1 (-2.1 15.7)E 1 l (5/ 25) (5/16) (9/ 24)
- Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.
" The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.
Page 50
Table 2.15-1 Lobster Radioactivity Analyses Radiological Environmental Program Summary Pilgdm Nuclear Power Station, Plymouth, MA (January - December 1998) MEDIUM: American Lobster (HA) UNITS: oCl/ka wet
!"d?.*'.5.S!*.'!o".t..
St*!'.."."".H[gpst,,Mean
. , , , , g,ontrol Stations Radionuclides Mean Sta. Mean Mean I (No. Analyses) Required Range Range Range l (NonRoutine*) LLD (No. Detected") (No. Detected") (No. Detected")
Be-7 (5) ( 3.4 e 6.5)E 1 11 ( 3.4 6.5)E 1 (-5.2 t 6.3)E 1 (0) (-2.7- 8.4)E 1 ( -2.7 - 8.4)E 1 (0/ 4) (0/ 4) (0/1) K-40 (5) ( 22 0.4)E 3 89 ( 2.2
- 0.3)E 3 ( 2.2 0.3)E 3 (0) ( 1.7 - 2.6)E 3 (4/ 4' (1/1) (1/1)
Mn-54 (5) 130 ( 1.2
- 0.9)E 1 11 ( 1.2
- 0.9)E 1 ( 6.5 2 8.0)E O (0) ( 1.4 - 18.9)E O ( 1.4 - 18.9)E O (0/ 4) (0/ 4) (0/1)
Co-58 (5) 130 ( 7.0 a 7.8)E O 89 (-5.4 7.4)E O (-5.4 s 7.4)E O (0) (-1.2 --0.1)E 1 (0/ 4) (0/1) (0/1) l Fe-59 (5) 260 ( 2.0
- 6.9)E 1 11 ( 2.0 a 6.9)E 1 (1.3 19.7)E O (0) ( -4.9 - 9.3)E 1 (-4.9 9.3)E 1 (0/ 4) (0/ 4) (0/1)
Co-60 (5) 130 ( 6.6 8.9)E O 11 ( 6.6
- 8.9)E O ( 4.12 6.3)E O (0) (-2.1 - 11.8)E O (-2.1 11.8)E O (0/ 4) (0/ 4) (0/1) j Zn-65 (5) 260 ( 1.8
- 2.8)E 1 69 (2.3 1.9)E 1 ( 2.3 21.9)E 1 (0) ( -1.9 - 3I)E 1 (0/ 4) (0/1) (0/1)
Cs-134 (5) 130 (-6.6
- 15.1)E O 89 ( 1.3 z 0.8)E 1 ( 1.3 0.8)E 1 (0) ( 2.8 - 0.2)E 1 (0/ 4) (0/1) (0/1)
Cs-137 (5) 130 ( 2.3
- 9.4)E O 89 ( 3.6
- 9.9)E O ( 3.6 9.9)E O (0) ( -8.0 - 10.2)E O (0/ 4) (0/1) (0/1)
Th-232 (5) ( 3.3
- 2.8)E 1 89 ( 3.5 2 3.0)E 1 ( 3.5
- 3.0)E 1 (0) ( 4.1 - 52.5)E 0 (0/ 4) (0/1) (0/1)
- Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.
** The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses.
l l i Page 51
p Table 2.16-1 Fish Radioactivity Analyses Radiological Environmental Prograrn Summary Pilgrim Nuclear Power Station, Plymouth, MA (January December 1998) MEDIUM: Fish (FH) UNITS: oCi/ko wet l- Indicator Stations Station With Highe Control Stations l
...................... . ..... ................st..Mean I Radionuclides Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (NonRoutine*) -LLD (No. Detected **) (No. Detected **) (No. Detected **)
l Be (31) (-2.6 e 7.4)E 1 97 ( 6.8 e 10.7)E 1 (-2.2
- 9.5)E 1 l (0) (-1.6 - 1.0)E 2 (-1.6 - 15.3)E 1 (-1.0 1.5)E 2 i
(0/23) (0/ 3) (0/ 8) - K 40 (31) ( 2.7
- 0.5)E 3 97 ( 3.2 s 0.9)E 3 ( 2.8 s 0.8)E 3 (0) ( 1.9 3.8)E 3 ( 2.2 3.8)E 3 ( 1.9 3.8)E 3 (23/23) (3/ 3) (8/ 8)
Mn-54 (31), 130 . (-2.8 e 99.6)E 1 97 ( 1.0 s 6.6)E O ( -5.8 10.2)E O (0) ( 1.7 1.4)E 1 (-8.1 39.0)E -1 ( -2.0 - 0.5)E 1 (0/23) . (0/ 3) (0/ 8) Co 58 (31) 130 ( 2.2
- 9.6)E O - 97 ( 7.4 t 17.9)E O (-2.1 a 17.1)E O (0) ( 1.6 1.2)E 1 ( -9.4 - 23.5)E O ( -2.9 - 2.4)E 1 (W23) (0/ 3) (0/ 8) l Fe 59 (31) 260 (-1.2 s 3.7)E 1 94 ( 1.5 3.3)E 1 ( 1.1 e 3.0)E 1 (0) (-8.8 6.6)E 1 ( -1.3 - 5.8)E 1 ( 2.3 5.8)E 1 (0/ 23) (0/ 5) (0/ 8)
Co-60 (31) 130 ( 6.2 e 1303.9)E -2 97 ( 2.3 a 11.6)E O (-4.6 e 11.1)E O l (0) ( 2.6 - 2.6)E 1 . ( -3.5 - 12.1)E O (-1.9 1.2)E 1 (0/ 23) (0/ 3) (0/ 8) ( Zn-65 (31) 260 ( 1.0 2.2)E 1 97 ( 7.0 27.8)E O (-4.3
- 29.4)E O
(-5.2 4.7)E 1 (0) ( .1.7 2.5)E 1 ( -5.2 - 2.5)E 1 (0/ 23) (0/ 3) (0/ 8) Cs-134 (31) 130 (-4.9
- 8.8)E O 97 ( 8.5 e 13.7)E O ( 3.1 s 13.5)E O (0) (-1.8
- 1.6)E 1 (-4.8 - 17.0)E O ( -1.3 - 2.2)E 1 (0/ 23) (0/ 3) (0/ 8) i Cs-137 (31) 130 ( 6.1
- 12.6)E O ' 11 ( 6.1
- 12.6)E O ( 1.1210,5)E O I (0) (-1.6 3.0)E 1 (-1.6 3.0)E 1 (-1.2 1.6)E 1 (0/ 23) (0/ 23) (0/ 8)
( .Th-232 (31) ( 7.9 31.4)E O 11 ( 7.9
- 31.4)E O ( -1.4 6.2)E 1 l (0) (-8.4 4.0)E 1 (-8.4 4.0)E 1 ( 1.2 - 0.8)E 2 (0/ 23) (0/ 23) (0/ 8)
- Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4.
l ! " The fraction of sample analyses yielding detectable rneasurements (i.e. >3 standard deviations)is shown in parentheses. [ .. Page 52 l
F i l Table 2.17-1 Sediment Radioactivity Analyses Radiological Environmental Program Summary Pilgrim Nuclear Power Station, Plymouth, MA (January - December 1998) MEDIUM: Sediment (SE) UNITS: oCi/ka dry l Indicator Stations Station With Highest Mean Control Stations l Radionuclides Mean Sta. Mean Mean (No. Analyses) Required Range Range Range (Non-Routine *) LLD (No. Detected **) (No. Detected **) (No. Detected **) Be-7 (56) ( 2.9 e 6.6)E 1 13 ( 8.5 14.9)E 1 ( 7.2 12.1)E 1 (0) ( -5.0 - 25.3)E 1 ( 1.1 - 48.3)E 1 (-1.1 48.3)E 1 (6/ 39) (2/11) (4/17) K 40 (56) ( 1.0 2 0.2)E 4 13 ( 1.2
- 0.1)E 4 ( 1.1 0.2)E 4 (0) ( 7.6 - 14.9)E 3 ( 1.1 - 1.4)E 4 ( 9.1 - 13.8)E 3 (39/39) (til11) (17/17)
Co-58 (56) 50 (-2.2 e 2.5)E O 15 ( 1.3 2.0)E O (-3.2
- 2.9)E O (0) (-7,1 - 2.2)E O ( 3.9- 0.6)E O (-8.9 - 1.3)E O (0/ 39) (0/11) (0/17)
Co-60 (56) 50 ( 8.3 2 27.7)E -1 14 ( 2.3 21.6)E O (-2.1
- 24.5)E -1 (0) (-7.7 7.7)E O ( 1.1 - 4.1)E O (-3.8 - 3.8)E O (0/ 39) (0/ 6) (0/17)
Zn-65 (56) 50 ( 5.7
- 9.7)E O 11 (7.6 7.5)E O ( 5.0
- 12.0)E O (0) (-1.1 - 3.5)E 1 ( -5.8 - 19.1)E O (-1.2 - 3.4)E 1 (0/ 39) (0/11) (0/17)
Zr-95 (56) 50 ( 6.1
- 4.8)E O 13 ( 8.4
- 8.9)E O ( 7.8 s 7.3)E O (0) (-3.9 - 17.2)E O (-8.6 - 23.2)E O (-8.6 23.2)E O >
(0/ 39) (0/11) (0/17) l Cs-134 (56) 50 ( -2.4 472.5)E -2 24 ( 1.4 8.4)E O ( -1.7 : 7.3)E O l (0) (-5.4 - 19.3)E O (-6.7 - 16.1)E O ( -1.8 - 1.6)E 1 l (0/ 39) (0/ 6) (0/17) j I Cs 137 (56) 50 ( 4.3
- 7.0)E O 13 ( 2.0 0.5)E 1 ( 1.5 2 0.9)E 1 (0) ( 5.6 - 27.3)E O ( 1.1 - 2.8)E 1 ( -1.8 - 27.7)E O (5/ 39) (10/11) (10/17)
Ce-144 (56) 150 ( -5.9 13.9)E O 15 (-4.0
- 18.7)E O ( -7.7 17.6)E O (0) (-4.4 - 1.8)E 1 (-4.4 - 1.8)E 1 (-4.4 - 2.4)E 1 (0/ 39) (0/11) (0/17)
Th-232 (56) ( 3.2 21.0)E 2 13 ( 4.9 2 0.5)E 2 (4.5 0.7)E 2 (0) ( 1.5 5.8)E 2 ( 4.2 - 5.8)E 2 ( 3.4 - 5.8)E 2 (39/39) (11/11) (17/17) Pu-238 (5) 25 ( 7.1 a 9.7)E 1 12 (1.7 2.1)E O ( 1.5 e 2.9)E O (0) ( 1.3 - 17.0)E -1 , (0/ 4) (0/1) (0/1) i Pu-239 (5) 25 ( 3.7
- 2.6)E O 13 ( 1.2
- 0.3)E 1 ( l.2 2 0.3)E 1 (0) ( 2.2 - 7.5)E O (4/ 4) (1/1) (1/1)
Non-Routine refers to those radionuclides that exceeded the Reporting Levels in ODCM Table 3.5-4. l ** The fraction of sample analyses yielding detectable measurements (i.e. >3 standard deviations) is shown in parentheses. l l Page 53 t
Table 2.17-2 Sediment Plutonium Analyses Environmental Radiological Program Summary i Pilgrim Nuclear Power Station, Plymouth, MA (January - December 1998) I pCl/kg (dry)i1 S.D. Location Core Depth (cm) Plutonium-238 Plutonium-239/240 Discharge Canal Outfall 0-2 NDA 2.3 i 0.4 Discharge Canal Outfall 12-14 NDA 2.2 i O.4 Plymouth Harbor 14 -16 NDA 7.5 i 2.2 Manomet Point 0-2 NDA 2.9 i 0.5 Duxbury Bay - Control 0-2 Missing" Missing" ) Duxbury Bay - Control 10-12 NDA 12.4 i 2.9
- NDA indicates no detectable activity. l l
" Analyses were not performed on this samples due to a sample coding error. See discussion of sediment results for an explanation and analysis of implications. l
)
l l Page 54 i
Figure 2.2-1 Environmental TLD Locations Within the PNPS Protected Area TLD Station Locaton* Desenption 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 O&M 2ND SW CORNER P19 86 m S O&M 1ST SW CORNER P18 90 m S COMPRESSED GAS STOR P08 92 m E FENCE-L SCREENHOUSE P03 100 m NW FENCE-EXEC. BUILDING P17 107 m W O&M 2ND S WALL P23 121 m ENE FENCE-INTAKE BAY P07 121 m SSE FENCE-WAREHOUSE P26 134 m ESE
' FENCE-SHOREFRONT P02 135 m NW FENCE W BOAT RAMP P09 136 m E O&M - 2ND N WALL P22 137 m SE FENCE W SWITCHYARD P16 172 m SW FENCE-TCF GATE P11 183 m ESE FENCE-TCF/ BOAT RAMP P27 185 m ESE FENCE-ACCESS GATE P12 202 m SE FENCE-E SWITCHYARD P15 220 m S FENCE-TCFANTAKE BAY P10 223 m E FENCE-MEDICAL BLDG, P13 224 m SSE FENCE-BUTLER BLDG P14 228 m S .
FENCE-TCF/PRKNG LOT P28 259 m ESE Distance and direction are measured from centerline of Reactor Building to the monitoring location. l l Page 55
Figure 2.2-1 (coritinued) EnvironmentalTLD Locations Within the PNPS Protected Area g 4* . :q ;; J , ' %gg (, 4 e , ., a ,. - :,n u: . Cape Cod Bay l7 ' R
~
=~~
loo meters , b 4 s, SCALE 1
$N"',.
qni !,, y up y i s
+
[ 1 ,h , d a, - , ...p.. m 7 g , m wa g , p>
. w ; i, m
, ., ! ., 'UU ll ,
i r : in "-, i P a-Intake Channel Q '
- t. +
g,o, , 9
- i POS (X) .. :
j.l P07 .
~ ~ ~ ~ ~ '
f.f3fr tur
./ ,_ _ _
. _-C 7 Trash
~" Compaction P04 <
/
Main Stack g ;
,[ / , _ . / Facility iI e
( l I [ Reactor h Ii
~~ ' '-
P2:) l P02 {_ Dldg Executive
--- Turbine a _8 0p: 2t'):4.., -j lh_
1 ft Building g -{ Building A Met Tower He Ith p q ,- ' ] g
~k 4 8 ( s O
,8 \
Switchyard ' - -- 'l 8 P16 l (P14) li
# , il li- ~_ _- _ , _ _r . =
l -A
\ Protected Fn!e Rocky Hill R
{ Page 56
r Figure 2.2-2 l l l TLD and Air / Soil Sampling Locations: Within 1 Kilometer TLD Station Locaton" Air / Soil Sampi:ng, Station Location
- I)esengon T Code Distance / Direction , , , Description T Code Distance /Directon Zone 1 TLDs: 0-3 km l BOAT LAUNCH WEST BLW 0.11 km E OVERLOOK AREA I OA 0.15 km W OVERLOOK AREA OA 0.15 km W PEDESTRIAN BRIDGE PB 0.21 km N I HEALTH CLUB TC 0.15 km WSW MEDICAL BUILDING WS 0.23 km SSE )
l BOAT LAUNCH EAST BLE 0.16 km ESE EAST BREAKWATER EB 0.44 km ESE PEDESTRIAN BRIDGE PB 0.21 km N PROPERTY LINE PL 0.54 km NNW l SHOREFRONT SECURITY P01 0.22 km NNW W ROCKY HILL ROAD WR 0.83 km WNW l MEDICAL BUILDING WS 0.23 km S3E E ROCKY HILL ROAD ER 0.89 km SE PARKING LOT CT 0.31 km SE SHOREFRONT PARKING PA 0.35 km NNW STATION A A 0.37 km WSW STATION F F 0.43 km NW STATION B B 0.44 km S l EAST BREAKWATER EB 0.44 km ESE l l PNPS MET TOWER PMT 0.44 km WNW ! STATION H H 0.47 km SW ; STATION I I 0.48 km WNW ) STATION L L 0.50 km ESE 1 STATION G G 0.53 km W l STATION D D 0.54 km NW PROPERTY LINE PL 0.54 km NNW STATION C C 0.57 km ESE HALL'S BOG HB 0.63 km SE GREENWOOD HOUSE GH 0.65 km ESE W ROCKY HILL ROAD WR 0.83 km WNW E ROCKY HILL ROAD ER 0.89 km SE l l l l l Page 57 L
Figure 2.2-2 (continued) , i TLD and Air / Soil Sampling Locations: Within 1 Kilometer N j hM 3 d hg$a$N!!N[p{@*idhN(ijf}@'[jgjcf9E!kO2fihyskkIM7NidPNNk' ngi M y l m' gjg*1hhMjpgl wpp ' EE . ;w g { W i g, jg a
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Figure 2.2-3 TLD and Air / Soil Sampling Locations: 1 to 5 Kilometers TLD Station, Locaton' Air / Soil Sampi,ing Station _ Location
- Descr6ption Code Distance /birection _ Description Code Distance / Direction Zgng i TLDs: 0-3 km MICROWAVE TOWER MT 1.03 km SSW CLEFT ROCK CR 1.27 km SSW CLEFT ROCK CR 1.27 km SSW MANOMET SUBSTATION MS 3.60 km SSE BAYSHORE/ GATE RD BD 1.34 km WNW MANOMET ROAD MR 1.38 km S DIRT ROAD DH 1.48 km SW EMERSON ROAD EM 1.53 km SSE EMERSON /PRISCtLLA 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 S3E PLYMOUTH YMCA RC 2.09 km W3W STATION K K 2.17 km S TAYLOR / THOMAS TT 2.26 km SE YANKEE VILLAGE YV 2.28 km WSW GOODWIN PROPERTY GN 2.38 km SW RIGHT OF WAY RW 2.83 km S TAYLOR / PEARL TP 2.98 km SE Zone 2 TLDs: 3-8 km VALLEY ROAD VR 3.26 km SSW 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.
I i i Page 59
Figure 2.2-3 (continued) TLD and Air / Soil Sampling Locations: 1 to 5 Kilometers WiQMMi ~45%Welk M'(Alpkk&Sdaty4:M
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Page 60
I ' I 1 i 1 Figure 2.2-4 TLD and Air / Soil Sampling Locations: 5 to 25 Kilomefers l TLD Station Location- ...,, Air / Soil Sampling,, Station Location *
" Description I Code Distance / direction Description I. Code Distance / Direction Zone 2 TLDs: 3-8 km l HILLDALE ROAD HD 5.18 km W PLYMOUTH CENTER ' PC 6.69 km W MANOMET BEACH MD 5.43 km SSE BEAVERDAM ROAD BR 5.52 km S PLYMOUTH CENTER PC 6.69 km W '
LONG POND / DREW RD LD 6.97 km WSW HYANNIS ROAD HR 7.33 km SSE MEMORIAL HALL MH 7.58 km WNW i SAOUISH NECK SN 7.58 km NNW I COLLEGE POND CP 7.59 km SW Zone 3 TLDs: 8-15 km DEEP WATER POND DW 8.59 km W LONG POND ROAD LP 8.88 km SSW j NORTH PLYMOUTH NP 9.38 km WNW J STANDISH SHORES SS 10.39 km NW ELLISVILLE ROAD EL 11.52 km SSE f z UP COLLEGE POND RD UC 11.78 km SW I SACRED HEART SH 12.92 km W KING CAESAR ROAD KC 13.11 km NNW BOURNE ROAD BE 13.37 km S SHERMAN AIRPORT SA 13.43 km WSW Zone 4 TLDs: >15 km CEDARVILLE SUBST CS 15.93 km S KINGSTON SUBST KS 16.15 km WNW LANDING ROAD LR 16.46 km NNW CHURCH / WEST CW 16.56 km NW MAIN / MEADOW MM 17.02 km WSW DIV MARINE FISH DMF 20.97 km SSE Distance and direction are measured from centerline of Reactor Building to the monitoring location. ) J l l I Page 61
)
l I Figure 2.2-4 (continued) TLD and Air / Soil Sampling Locations: 5 to 25 Kilometers 3 ! (
, :s km "N 4. _ . >w4 c
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Figure 2.2-5
]
Terrestrial and Aquatic Sampling Locations Description Code Distance / Direction
- Description Code Distance / Direction
- M!U$ SURFACE WATER I Plymouth County Farm CF 5.6 km W Discharge Canal DIS 0.2 km N Whitman Farm Control WF 34 km WNW Bartlett Pond BP 2.7 km SE Powder Point Control PP 13 km NNW FORAGE Whipple Farm WH 2.9 km SW IRISH MOSS Plymouth County Farm CF 5.6 km W Discharge Canal Outfall DIS 0.7 km NNE Whitman Farm Control WF 34 km WNW Manomet Point MP 4.0 km ESE j Ellisville EL 12 km SSE VEGETABLES /VEGETATI.QN 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 DIS 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 l Cape Cod Bay Control CC-BAY 24 km ESE I N River-Hanover Control NR 24 km NNW Cataumet Control CA 32 km SSW Provincetown Control PT 32 km NE Bunards Bay Control BB 40 km SSW Priest Cove Control PC 48 km SW Nantucket Sound Control NS 48 km SSE Atlantic Ocean Contrat AO 48 km E Vineyard Sound Control MV 64 km SSW SEDIMENT Discharge Canat Outfall DIS 0.8 km Nti Plymouth Beach PLB 4.0 km W 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 centerkne of the reactor to the ,ampling/ monitoring location.
Page 63
r Figure 2.2-5 (continued) Terrestrial and Aquatic Sampling Locations UMWm
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Page 64
p Figure 2.2-6 Environmental Sampling And Measureme.,t Control Locations Description Code Distance / Direction
- Description Code Distance / Direction
- TLQ SURFACE WATER Cedarville Substation CS 16 km S Powder Point Control PP 13 km NNW Kingston Substation KS 16 km WNW Landing Road LR 16 km NNW IRISH MOSS Church & West Street CW 17 km NW Brant Rock Control BK 18 km NNW Main & Meadow Street MM 17 km WSW Div. Marine Fisheries DMF 21 km SSE SHELLFISH East Weymouth EW 40 km NW Duxbury Bay Control DUX-BAY 13 km NNW Substation Powder Point Control PP 13 km NNW AIR SAMPLER Green Harbor Control GH 16 km NNW East Weymouth EW 40 km NW Substation LOBSTER M!LK Duxbury Bay Control DUX-BAY 11 km NNW Whitman Farm Control WF 34 km WNW FISHES FORAGE Jones River Control JR 13 km WNW Whitman Farm Control WF 34 km WNW Cape Cod Bay Control CC-BAY 24 km ESE N River-Hanover Control NR 24 km NNW VEGETABLES / 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 50 km W Priest Cove Control FC 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 SQ!L Duxbury Bay Control DUX-BAY 14 km NNW East Weymouth EW 40 km NW Green Harbor Control GH 16 km NNW Substation
- Distance and direction are measured from the centerline of the reactor to the sampling / monitoring location.
Page 65
1 l Figure 2.2-6 (continued) Environmental Sampling And Measurement Control Locations 1 i SYMBOL KEY O SHELLFISH (M BLUEMUSSEL) (S SOFT-SHELL CLAM) (H HARD-SHELLCLAM) Q IEISHMOSS
, ( E 2 LOBSTER j MAZACHU2TT5 aAY I O StWACEWATER BOSTON HARBOR -
1 a j o C,metor VEGETATION / FORAGE O= o B [ o m) o m Suata 6 0 MILES 10 y n m SCALE I .rU ' i BL GH G J
" An
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Historical Beach Survey Exposure Rate Measurements 14 l 12 a. 10 B - - = n - 1 ' N/ v'z , _ 1
'y \\/
sj' ~ ~~ p == W-- - V e 4 2 0 , , , , , , , , , , 77 79 81 83 85 87 89 91 93 95 97 Year l l
-*- Whitehorse Beach at Hilltop Avenue =- Priscilla Beach at Full Sail Bar
-- Plymouth Beach Outer -*- Plymouth Beach - Inner
- = -- Plymouth Beach at Berts - *- DuburyBeach Control Figure 2.4-1 Historical Beach Survey Exposure Rate Measurements Page 67
\
\
Airborne Gross-Beta Radioactiety Lewis Near-Station Monitors 0.07 0.00 - I 0.05 I [ 5 F f 0.04 - 0.03 - 8 i -
$ l, '
.{ / 54, g .. $
0.02 ** *I l -
^
- r t er 0.01 -
l' l 0 , , , , , , , , , , , Jan- Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month - 1998
--+- AP-00 Warehouse - s - AP-07 Pedestrian Bridge I - AP-08 Owrlook Area -*- AP-09 East Breakwater
--=-- /P-21 East Weyrnouth Control
/
Figure 2.5-1 Airborne Gross-Beta Radioactivity Levels: Near Station Monitors Page 68
h l Airborne Gross-Beta Radioactisty Lewis ! Propeny Line Monitors 0.07 i 0.06 0.05
+
t [ I 0.04 - l 1
.9 Ps 0.03
- f 3 -
\ f
,[ k [
0.02 b ' IA -
- I $
0 01
- 7yy.,
0 , , , , , , , , , , , ; Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month - 1998
-+ -- AP-01 E. Rocky Hill Road - =- AP-03 W. Rocky Hill Road
- - AP-06 Property Line - - AP-21 East Weymouth Control Figure 2.5-2 l Airborne Gross-Beta Radioactivity Levels: Property Line Monitors l
l Page 69
Airborne Gross-Beta Radioactivity Lewis Offsite Monitors 0.07 o 0.06 0.05 5 $ 0.04 1. f 0.03 ' f i .
# y'o,qs 12 .
,* S-0.02 - l m
^
0.01 -
,,,I 0 , , , , , , , , , , ,
Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month 1998
- +- AP-10 Cleft Rock -=- AP-15 Plymouth Center
-- AP-17 ManometSubstation -+- AP-21 East Weymouth Control Figure 2.5-3 Airborne Gross-Beta Radioactivity Levels: Offsite Monitors Page 70
i Lewis of Strontium-90 in Milk Samples 5 , o 4 f i 3 1 S 9 1 2 -
/\ " E T
1 . . . 1 0 - Jan Feb Mar Apr May Jun Jul Aug Sep Oct Nov Dec Month - 1998
-+- Plymouth County Farm - a- Whitman Farm 1
Figure 2.7-1 Levels of Strontium-90 in Milk Samples l 1 Page 71
- 3.0 -
SUMMARY
OF RADIOLOGICAL IMPACT ON HUMANS q The radiological impact to humans from the Pilgrim Station's radioactive liquid and gaseous releases has been estimated using two methods:
- 1) calculations based on measurements of plant effluents; and I
- 2) calculations based on measurements of environmental samples.
The first method utilizes data from the radioactive' effluents (measured at the point of release)' together with conservative models that calculate the dispersion and transport of radioactivity through the environment to humans (Reference 7). The second method is based on actual ' measurements of radioactivity in the environmental samples and on dose conversion factors recommended by the Nuclear Regulatory Commission. The measured types and quantities of radioactive liquid and gaseous effluents released from Pilgrim Station during 1998 were reported to the Nuclear Regulatory Commission, copies of which are provided in Appendix B. The measured levels of radioactivity in the environmental samples .that required dose calculations are listed in Appendix A. The maximum individual dose from liquid effluents was calculated using the following radiation i exposure pathways: 1)' shoreline external radiation during fishing and recreation at the Pilgrim Station Shorefront;. 'l l
- 2) external radiation from the ocean during boating and swimming; and
- 3) ingestion of fish and shellfish.
i For gaseous effluents, the maximum individual dose was calculated using the following radiation exposure pathways:
- 1) external radiation from cloud shine and submersion in gaseous effluents; i 2) inhalation of airborne radioactivity;
- 3) external radiation from soil deposition;
- 4) consumption of vegetables; and
- 5) consumption of milk and meat.
The results from the dose calculations based on PNPS operations are presented in Table 3.0-1. The dose assessment data presented was taken from the " Annual Dose Assessment to the General Public from Radioactive Effluents" report for the period of January 1 through December 31,1998.- l Page 72
1 Table 3.0-1 ' Radiation Doses from 1998 Pilgrim Station Operations Maximum Individual Dose From Exposure Pathway - mrem /yr Gaseous Liquid Ambient Receptor Effluents
- Effluents Radiation" Total Total Body 0.42 0.0002 2.5 2.9 Thyroid 0.69 0.00008 2.5 3.2 l
Max. Organ 0.69 0.0009 2.5 3.2
- Gaseous effluent exposure pathway includes combined dose from particulates, iodines and tritium in addition to noble gases.
" Ambient radiation dose for the hypothetical maximum-exposed individual at a location on 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 tc 400 mrem /yr from such sources. 1 As can be seen from the doses resulting from Pilgrim Station Operations during 1998, 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 1998, the only sample media that indicated detectable radioactivity attributable to PNPS was blue mussels collected during the second quarter, which contained low levels of Co-60. The dose resulting from this pathway is estimated at 0.0001 mrem, and would be included as part of the 0.0002 mrem total body dose from liquid effluents listed in the table above. A more detailed calculation of the dose from this specific pathway can be found in Appendix A. 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. l Page 73
p
4.0 REFERENCES
- 1) United States of America, Code of Federal Regulations, Title 10, Part 50, Appendix A Criteria 64.
- 2) Donald T. Oakley, " Natural Radiation Exposure in the United States." U. S. Environmental Protection Agency, ORP/SID 72-1, June 1972.
- 3) National Council on Radiation Protection and Measurements, Report No. 93, "lonizing Radiation Exposures of the Population of the United States," Septernber 1987.
- 4) United States Nuclear Regulatory Commission, Regulatory Guide 8.29, " Instructions Concerning Risks fiom 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 Offsite Dose Calculation Manual, Revision 8, August 1998.
- 8) United States of America, Code of Federal Regulations, Title 10, Part 20.1301.
- 9) United States of America, Code of Federal Regulations, Title 10, Part 50, Appendix 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 of the Population," May 1984.
- 14) United States Nuclear Regulatory Commission, NUREG-0473, " Standard Radiological Effluent Technical Specifications for Boiling Water Reactors," Revision 3, September 1982.
- 15) United States Nuclear Regulatory Commission, Branch Technical Position, "An Acceptable Radiological Environmental Monitoring Program," Revision 1, November 1979.
- 16) Settlement Agreement Between Massachusetts Wildlife Federation and Boston Edison Company Relating to Offsite Radiological Monitoring - June 9,1977.
- 17) E. Vossahlik, Yankee Atomic Electric Company, Computer Program "ERMAP," Version 3.1
- January 9,1979.
- 18) J. Pelczar, Duke Engineering and Services, " Summary of the Results of the 1998 BECO Beach Survey," REG 98-165, December 8,1998.
Page 74
[. APPENDIX A. SPECIAL STUDIES SHELLFISH RADIOACTIVITY DOSE IMPACT During 1998, cobalt-60 was detected in edible portions of blue mussels collected from the
- discharge canal outfall during the second quarter, at a concentration of 5.0 pCi/kg. Samples collected during the first, third, and fourth quarter yielded no detectable Co-60 activity (less than 4.5 pCi/kg), although samples of non-edible mussel shells contained detectable Co-60 during the first and second quarters ( 8.1 and 2.6 pCi/kg, respectively).
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
- dose values presented in Section 3 of this report. - However, since Co-60 was detected in blue mussels, an assessment of the dose resulting specifically from the ingestion of this medium - was performed. Based on the four measurements made during the year, an average concentration of 2.3 pCi/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 kg/yr, child = 3 kg/yr) to determine the amount of Co-60 ingested via this pathway. The resulting dose was estimated by multiplying the ingestion intake (pCi) of cobalt-60 by the total body dose conversion factor (mrem /pCi ingested) as listed in Regulatory Guide 1.109. Results of these calculations are listed below, pCl Co-60 Total Body DCF Total Body Dose Age Class ingested mrem /pCi mrem Adult 21 4.72E-06 9.91 E-05 Teen 14 6.33E-06 8.86E-05 Child 7 1.56E-05 1.09E-04 Based on the above calculations, the maximum total body dose received from the ingestion of shellfish containing cobalt-60 is about 0.0001 mrem. This additional dose would be considered negligible in comparison to the 300-400 mrem received by the average individual each year from other sources of radiation exposure.
i l I l l Page 75 l
APPENDIX B Effluent Release Information TABLE TITLE ,. PAGE Supplement'.:Information: January-June 1998 77 1A Gaseour, Effluents Summation of All Releases 78 January, June 1998
~
1B Gasio'u~E Effluents - Elevated Releases 79 January-June 1998
~
1C Gaseous Effluents - Ground Level Releases 80 January-June 1998 2A Liquid Effluents Summation of All Releases 81 January-June 1998: 2B Liquid Effluents: January June 1998 82 Supplementalinformation: July-December 1998 83 i 1A Gaseous Effluents Summation of All Releases 84 July-December 1998 1B Gaseous Effluents - Elevated Releases 85 July-December 1998 ~ 1C Gaseous Effluents - Ground Level Releases 86 July-December 1998 2A Liquid Effluents Summation of All Releases 87 2B Liquid Effluents: July-December 1998 88 Page 76
Pilgrim Nuclear Power Station Effluent and Waste Disposal Report SupplementalInformation January-June 1998 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 e' 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 11
- d. Liquid effluents: 2E-04 pCi/mL for entrained noble gases; 10CFR20 Appendix B Table il values for all other radionuclides
- 3. AVERAGE ENERGY Not Applicable
- 4. MEASUREMENTS AND APPROXIMATIONS OFTOTAL 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 Jan-Mar 1998 Apr-Jun 1998
,Ns. 3
; .o, '
- a. Liquid Effluents !- JW 4
- 1. Total number of releases: 1.20E+01 1.70E+01
- 2. Total time period (minutes): 6.13E+02 1.29E+03
- 3. Maximum time period (minutes): 1.95E+02 1.80E+02
- 4. Average time period (minutes): 5.11 E+01 7.59E+01
- 5. Minimum time period (minutes): 2.00E+01 2.50E+01
- 6. Average stream flow (Liters / min): 1.17E+06 1.20E+06 during periods of release of effluents . >. y ,;_
into a flowing stream b g'W r
- o , , w
, :q
- b. Gaseous Effluents None None
- 6. ABNORMAL RELEASES M rp N 4 r
. ,a + , w
- a. Liquid Effluents None None
- b. Gaseous Effluents None None Page 77
l l l Table 1 A Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Summation of All Releases January-June 1998 Period: Period: Estimated Jan-Mar 1998 Apr-Jun 1998 Total Error A. FISSION AND ACTIVATION GASES TotalRelease: Ci 1.07E+02 1.32E+02 122 % l Average Release Rate During Period: pCi/sec 1.36E+01 1.67E+01 Percent of Effluent Control Limit *
- B. lODINES Totallodine-131 Release: Ci 3.04E-04 6.11 E-04 f20% l Average Release Rate During Period: Ci/sec 3.86E-05 7.74E-05 Percent of Effluent Control Limit
- C. PARTICULATES Total Release: Ci 3.49E-04 5.54E-04 i21 % l Average Release Rate During Period: pCi/sec 4.42E-05 7.02E-05 Percent of Eftluent Control Limit Gross Alpha Radioactivity: Ci NDA NDA D. TRITIUM Total Relesse: Ci 9.92E+00 9.04E+00 i20% l Average Release Rate During Period: pCi/sec 1.26E+00 1.15E+00 Percent of Effluent Control Limit
- Notes for Table 1 A:
l
- Percent of Effluent Control Llimit values in above sections are based on dose assessments not performed as part of this report. These will be provided in the annual effluent release report to be issued prior to May 15,1999.
- 1. NDA stands for No Detectable Activity.
- 2. LLD for airborne gross alpha activity listed as NDA is 1E-11 pCi/cc.
l l l l Page 78
)
Table 1B Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Elevated Release January-June 1998 Continuous Mode Batch Mode Nuclide Released Jan-Mar 1998 l Apr-Jun 1998 Jan-Mar 1998 l Apr-Jun 1998
- 1. FISSION AND ACTIVATION GASES-Cl Kr-85m 2.56E+01 2.90E+01 N/A N/A Kr-87 9.48E+00 1.41 E+01 N/A N/A Kr-88 4.79E+01 5.65E+01 N/A N/A Xe-131 m NDA NDA N/A N/A Xe-133 2.20E+01 2.41 E+01 N/A N/A Xe-135 2.48E+00 8.55E+00 N/A N/A Xe-135m NDA NDA N/A N/A Xe-138 NDA NDA N/A N/A Total for period 1.07E+02 1.32E+02 N/A N/A
- 2. IODINES - Cl 1-131 2.44 E-04 4.16E-04 N/A N/A l-133 1.15E-03 2.08t -03 N/A N/A Total for period 1.39E-03 2.50E-03 ~
N/A N/A l I
- 3. PARTICULATES - Cl Co-60 1.31 E-06 NDA N/A N/A Sr-89 4.56E-05 1.43E-04 N/A N/A Sr-90 NDA ,
1.75E-06 N/A N/A Cs-134 NDA NDA N/A N/A Cs-137 NDA 5.80E-06 N/A N/A Ba/La-140 1.83E-04 2.71 E-04 N/A N/A I Total for period 2.30E-04 4.22E-04 N/A N/A
- 4. TRITIUM - Cl l H-3 l 5.84E-01 l 6.90E-01 l N/A l N/A l Notes for Table 1B:
- 1. N/A stands for not applicable.
- 2. NDA stands for No Detectable Activity.
- 3. LLD for airborne radionuclides listed as NDA are as follows: ;
Fission Gases: 1E-04 pCi/cc lodines: 1E-12 pCi/cc Particulates: 1E-11 pCi/cc l Page 79 I
r Table 1C Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Ground Level Release January-June 1998 Continuous Mode Batch Mode Nuclide Released Jan-Mar 1998 l Apr-Jun 1998 Jan-Mar 1998 l Apr-Jun 1998
- 1. FISSION 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 j I-131 6.02E-05 1.95E-04 N/A N/A l l-133 8.01 E-04 1.51 E-03 N/A N/A I Total for period 8.61 E-04 1.71 E-03 N/A N/A
- 3. PARTICULATES - Cl Co-60 9.74E-06 1.04E-05 N/A N/A Sr-89 1.09E-04 1.22E-04 N/A N/A Sr-90 NDA NDA N/A N/A Cs-134 NDA NDA N/A N/A Cs-137 NDA NDA N/A N/A
_B 3/La 140 NDA NDA N/A N/A Total for period 1.19E-04 1.32E-04 N/A N/A
- 4. TRITIUM - Cl l H-3 l 9.34E+00 l 8.35E+00 l 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 aitorne radionuclides listed as NDA are as follows:
Fission Gases: 1E-04 pCi/cc lodines: 1E-12 pCi/cc Particulates: 1E-11 pCi/cc Page 80
i Table 2A Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents - Summation of All Releases January-June 1998 ) l , 1 Period: Period: Estimated Jan-Mar 1998 Apr-Jun 1998 Total Error j ( i A. FISSION AND ACTIVATION PRODUCTS l Total Release (not including H-3, noble gas, or alpha): Ci 1.51 E-03 4.29E-03 112 % l l Average Diluted Concentration During Period: pCi/mL 2.10E-09 2.79E-09 l Percent of Effluent Concentration Limit
- 2.81 E-02% 1.13E-01%
i B. TRITlUM j TotalRelease: Ci 4.17E-02 2.20E+00 19.4 % l l Average Diluted Concentration During Period: Ci/mL 5.79E-08 1.43E-06 l Percent of Effluent Concentration Limit
- 5.79E-03% 1.43E-01%
C. DISSOLVED AND ENTRAINED GASES Total Release: Ci NDA NDA 116 % l Average Diluted Concentration During Period: pCi/mL NDA NDA Percent of Effluent Concentration Limit
- NDA NDA D. GROSS ALPHA RADIOACTIVITY l Total Release: Ci l NDA l NDA l 134 % l E. VOLUME OF WASTE RELEASED PRIOR TO DILUTION l Waste Volume: Liters l 9.83E+04 l 3.30E+05 l i5.7% l F. VOLUME OF DILUTION WATER USED DURING PERIOD l Dilution Volume: Liters l 7.20E+08 l 1.54E+09 l 110 % l Notes for Table 2A:
- Additional percent of Effluent Control Limit values based on dose assessments will be provided in the annual effluent release report to be issued prior to May 15,1999.
- 1. NDA stands for No Detectable Activity.
- 2. LLD for dissolved and entrained gases listed as NDA is 1E-05 pCi/mL.
- 3. LLD for liquid gross alpha activity listed as NDA is 1E-07 pCi/mL.
Page 81
Table 2B Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents January-June 1998 Continuous Mode Batch Mode Nuclide Paleased Jan-Mar 1998 l Apr-Jun 1998 Jan-Mar 1998 l Apr-Jun 1998
- 1. FISSION AND ACTIVATION PRODUCTS-Cl Cr-51 N/A N/A NDA NDA Mn-54 N/A N/A 1.13E-04 5.95E-04 Fe-55 N/A N/A 1.04E-03 1.47E-03 Fe-59 N/A N/A NDA 2.10E-05 Co-58 N/A N/A NDA NDA Co-60 N/A N/A 2.57E-04 7.71 E-04 Zn-65 N/A N/A NDA NDA Sr-89 N/A N/A 7.75E-07 1.76E-05 St-90 N/A N/A 3.08E-06 2.68E-05 Zr/Nb-95 N/A N/A NDA NDA Mo-99/Tc-99m N/A N/A NDA NDA Ag-110m N/A N/A NDA NDA Sb-124 N/A N/A NDA NDA l-131 N/A N/A NDA NDA l-133 N/A N/A NDA NDA l Cs-134 N/A N/A NDA NDA Cs-137 N/A N/A 9.62E-05 1.39E-03 Ba/La-140 N/A N/A NDA NDA Ce-141 N/A N/A NDA NDA Total for period N/A N/A 1.51 E-03 4.29E-03
- 2. DISSOLVED AND ENTRAINED GASES - Cl l Xe-133 N/A N/A NDA NDA Xe-135 N/A N/A NDA NDA Total for period l N/A N/A NDA NDA I 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 pCi/mL lodines: 1E-06 pCi/mL Noble Gases: 1E-05 pCi/mL All Others: SE-07 pCi/mL Page 82
Pilgrim Nuclear Power Station Effluent and Waste Disposal Report { Supplemental Information July-December 1998 FACILITY: PlLGRIM 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 11
- b. lodines: 10CFR20 Appendix B Table il
- c. Particulates with half-life > 8 days: 10CFR20 Appendix B Table ll
- d. Liquid effluents: 2E-04 pCi/mL for entrained noble gases; 10CFR20 Appendix B Table 11 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 1998 Oct-Dec 1998
- a. Liquid Effluents
- 1. Total number of releases: 1.30E+01 7.00E+00
- 2. Totaltime period (minutes): 6.99E+02 2.90E+02
- 3. Maximum time period (minutes): 1.60E+02 1.30E+02
- 4. Average time period (minutes): 5.38E+01 4.14 E+01
- 5. Minimum time period (minutes): 2.50E+01 2.50E+01
- 6. Average stream flow (Liters / min): 1.17E+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
- b. Gaseous Effluents None None Page 83
l i Table 1 A Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Summation of All Releases July-December 1998 Period: Period: Estimated Jul-Sep 1998 Oct-Dec 1998 Total Error A. FISalON AND ACTIVATION GASES TotalRelease: Ci 2.14E+02 2.07E+02 122 % l Average Release Rate During Period: pCi/sec 2.71 E+01 2.62E+01 Percent of Effluent Control Limit *
- B. IODINES Totallodine-131 Release: Ci 6.86E-04 6.28E-04 120 % l Average Release Rate During Period: Ci/sec 8.70E-05 7.96E-05 ~
Percent of Effluent Control Limit *
- C. PARTICULATES TotalRelease: Ci 5.79E-04 3.42E-04 f21%_j Average Release Rate During Period: pCi/sec 7.34E-05 4.34E-05 Percent of Effluent Control Limit *
- Gross Alpha Radioactivity: Ci NDA NDA D. TRITIUM TotalRelease: Ci 1.01 E+01 1.13E+0* f20% l Average Release Rate During Period: pCi/sec 1.28E+00 1.43E+00 Percent of Effluent Control Limit *
- Notes for Table 1 A:
- Percent of Effluent Control Limit values in above sections are based on dose assessments not performed as part of this report. These will be provided in the annual effluent release report to be issued prior to May 15,1999.
- 1. NDA stands for No Detectable Activity.
- 2. LLD for airbome gross alpha activity listed as NDA is 1E 11 pCi/cc.
Page 84
Table 1B Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Gaseous Effluents - Elevated Reiease July-December 1998 Continuous Mode Batch Mode Nuclide Released Jul-Sep 1998 l Oct-Dec 1998 Jul Sep 1998 l Oct-Dec 1998
- 1. FISSION AND ACTIVATION GASES-Cl Kr-85m 3.91 E+01 4.24E+01 N/A N/A Kr-87 2.13E+01 1.90E+01 N/A N/A Kr-88 7.77E+01 7.81 E+01 N/A N/A I Xe-131m NDA NDA N/A N/A Xe-133 3.50E+01 4.01 E+01 N/A N/A Xe-135 2.78E+01 2.69E+01 N/A N/A Xe-135m NDA NDA N/A N/A Xe-138 NDA NDA N/A N/A Total for period 2.01 E+02 2.07E+02 N/A N/A
- 2. lODINES - Cl 1-131 3.86E-04 2.73E-04 N/A N/A l-133 2.02E-03 1.55E-03 N/A N/A Total for period 2.41 E-03 1.82E-03 N/A N/A
- 3. PARTICULATES - CI Co-60 NDA NDA N/A N/A )
Sr-89 8.02E-05 3.80E-05 N/A N/A Sr-90 5.39E-07 6.95E-07 N/A N/A Cs-134 NDA NDA N/A N/A Cs-137 NDA 1.24E-06 N/A N/A ! Ba/La-140 2.96E-04 1.47E-04 N/A N/A Total for period 3.77E-04 1.87'E-04 N/A N/A
- 4. TRITIUM - Cl l H-3 l 1.04E+00 l 1.33E+00 l N/A l N/A l Notes for Table 1B:
- 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 pCi/cc lodines: 1 E-12 pCi/cc Particulates: 1E-11 pCi/cc Page 85
Table 1C Pilgrim Nuclear Power Station { j Effluent and Waste Disposal Report Gaseous Effluents - Ground Level Release July-December 1998 Continuous Mode Batch Mode Nuclide Released Jul-Sep 1998 l Oct-Dec 1998 Jul-Sep 1998 l Oct-Dec 1998
- 1. FISSION 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 1.34E+01 NDA N/A N/A j Xe-135 NDA NDA N/A N/A Xe-135m NDA NDA N/A N/A Xe-138 NDA NDA N/A N/t.
Total for period 1.34E+01 NDA N/A N/A I
- 2. IODINES - Cl 1-131 3.00E-04 3.55E-04 N/A N/A 4 l-133 1.90E-03 3.46E-03 N/A N/A l Total for period 2.20E-03 3.82E-03 N/A N/A
- 3. PARTICULAitS - Cl Co-60 3.14E-06 4.82E-06 N/A N/A Sr-89 1.63E-04 1.50E-04 N/A N/A Sr-90 NDA NDA N/A N/A
]
Cs-134 NDA NDA N/A N/A Cs-137 NDA NDA N/A N/A Ba/La-140 3.59E-05 NDA N/A N/A Total for period 2.02E-04 1.55E-04 N/A N/A
- 4. TRITIUM - Ci l H-3 l 9.09E+00 l 9.96E+00 l 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 airborne radionuclides listed as NDA are as follows:
Fission Gases: 1E-04 pCi/cc lodines: 1E-12 pCi/cc Particulates: 1E-11 pCi/cc i i Page 86 j
Table 2A Pilgnm Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents - Summation of All Releases July-December 1998 Period: Period: Estimated Jul-Sep 1998 Oct-Dec 1998 Total Error A. FISSION AND ACTIVATION PRODUCTS Total Release (not including H-3, noble gas, or alpha): Ci 5.10E-04 2.31 E-04 i12% l Average Diluted Concentration During Period: pCi/mL 6.21 E-10 6.79E-10 Percent of Effluent Concentration Limit
- l 3.45E-02% 2.47E-02%
B. TRITIUM Total Release: Ci 1.69E-02 1.14E-02 19.4 % l Average Diluted Concentration During Period: pCi/mL 2.06E-08 3.35E-08 Percent of Effluent Concentration Limit
- 2.06E-03% 3.35E-03%
C. DISSOLVED AND ENTRAINED GASES Total Release: Ci NDA NDA 116 % l Average Diluted Concentration During Period: pCi/mL NDA NDA Percent of Effluent Concentration Limit
- NDA NDA D. GROSS ALPHA RADIOACTIVITY l Total Release: Ci l NDA l NDA l 134 % l E. VOLUME OF WASTE RELEASED PRIOR TO DlLUTION l Waste Volume: Liters l 8.87E+04 l 4.06E+04 l 5.7% l F. VOLUME OF DILUTION WATER USED DURING PERIOD l Dilution Volume: Liters l 8.21 E+08 l 3.40E+08 l i10% l Notes for Table 2A:
- Additional percent of Effluent Control Limit values based on dose assessments will be provided in the l' annual effluent release report to be issued prior to May 15,1999.
- 1. NDA stands for No Detectable Activity.
- 2. LLD for dissolved and entrained gases listed as NDA is 1E-05 pCi/mL.
- 3. LLD for liquid gross alpha activity listed as NDA is 1E-07 pCi/mL.
1 Page 87
Table 2B Pilgrim Nuclear Power Station Effluent and Waste Disposal Report Liquid Effluents July December 1998 Continuous Mode Batch Mode Nuclide Released Jul-Sep 1998 l Oct-Dec 1998 Jul-Sep 1998 l Oct-Dec 1998
- 1. FlSSION AND ACTIVATION PRODUCTS-Cl Cr-51 N/A N/A NDA NDA
_Mn-54 N/A N/A 2.84E-05 7.26E-06 Fe-55 N/A N/A 1.23E-04 1.22E-04 Fe-59 N/A N/A NDA NDA Co-58 N/A N/A NDA NDA Co-60 N/A N/A 1.28E-04 3.10E-05 Zn-65 N/A N/A NDA NDA Sr-89 N/A N/A NDA NDA Sr-90 N/A N/A 8.32E-06 1.83E-06 Zr/Nb-95 N/A N/A NDA NDA Mo-99/Tc-99m N/A N/A NDA NDA Ag-110m N/A N/A NDA NDA Sb-124 N/A N/A NDA NDA l-131 N/A N/A NDA NDA l-133 N/A N/A NDA NDA Cs-134 N/A N/A NDA NDA Cs-137 N/A N/A 2.22E-04 6.87E-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 5.10E-04 2.31 E-04
- 2. DISSOLVED AND ENTRAINED GASES - Cl 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 2B:
- 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 pCi/mL lodines: 1E-06 pCi/mL Noble Gases: 1 E-05 pCi/mL All Others: SE-07 Ci/mL Page 88
APPENDIX C LAND USE CENSUS RESULTS The annual land use census for gardens and milk and meat animals in the vicinity of Pilgrim Station was performed between October 19 and 23,1998. 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 27 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/O values) at the locations of the identified gardens were compared to those for the existing sampling program locations. These comparisons enabled Boston Edison Company personnel to ascertain the best locations for monitoring for releases of airborne radionuclides. Gardens yielding higher D/O values than those currently in the sampling program were also sampled as part of the radiological environmental monitoring program. Based on assessment of the gardens identified during the 1998 land use census, samples of garden-grown vegetables or naturally-growing vegetation (e.g. grass, leaves from bushes or trees, etc.) were collected at or near the closest gardens in each of the following landward compass sectors. These locations, and their distance and direction relative to the PNPS Reactor Building, are as follows: Rocky Hill Road 0.9 km SE Brook Road 2.9 km SSE Beaverdam Road 3.4 km S Clay Hill Road 1.6 km W in addition to these special sampling locations identified and sampled in conjunction with the j 1998 land use census, samples were also collected at or near the Plymouth County Farm (5.6 km W), Whipple Farm (2.9 km SW), and from a control location in Bridgewater (31 km W). Samples of naturally-growing vegetation were also collected from the site boundary locations yielding the highest deposition (D/Q) factors for each of the two release points. These locations, and their distance and direction relative to the PNPS Reactor Building were: Highest Main Stack D/Q: 1.5 km SSW Highest Reactor Building Vent D/Q: 0.5 km ESE 2nd highest D/O, Main Stack: 1.1 km S 1 2nd highest D/O, Reactor Building Vent: 0.8 km SE Control sample of naturally-growing vegetation were collected at the DMF shop in Sandwich (21 km SSE) and in Norton, MA (50 km W). No new milk or meat animals were identified during the land use census. In addition, the Town of Plymouth Animal Inspector stated that their office is not aware of any animals at locations other than the Plimoth Plantation and the Plymouth County Farm. Samples of milk and forage have historically been collected from the Plymouth County Farm and were part of the 1998 sampling program. Page 89
APPENDIX D ENVIRONMENTAL MONITORING PROGRAM DISCREPANCIES There were a number of instances during 1998 in which inadvertent issues were encountered in the collection of environmental samples. All of these issues were minor in nature and did not have an adverse affect on the results or integrity of the monitoring program. Details of these various problems are given below, in 1998, six thermoluminescen; dosimeters (TLDs) were not recovered from their assigned locations during the quarterly retrieval process. During the first quarter, the TLDs were not recovered at Station G (G) and Emerson Road (EM)). In these cases, the TLDs missing from their posted locations were presumably lost to storm damage or vandalism. During the second quarter retrieval, the TLD was missing at King Caesar Road (KC). In this case, the plastic straps, plastic cages, and TLD was missing and presumably lost due to vandalism. The TLDs at Property Line (PL), Pedestrian Bridge (PB), and Station D (D) were not recovered during the fourth quarter retrieval, and was presumably lost to weather-related degradation of the plastic housings holding the TLDs. In all cases of TLD losses, the TLDs were re-located in the immediate vicinity, but steps were taken whenever possible to post the TLD cages in a less conspicuous manner. The 434 TLDs which were ccliected (98.6%) allowed for adequate assessment of the ambient radiation levels in the vicinity of Pilgrim Station. Within the air sampling program, there were a few instances in which continuous sampling was interrupted at the eleven airborne sampling locations during 1998. Most of these interruptions were due to short-term power losses and were sporadic and of limited duration (less than 24 hours out of the weekly sampling period). Such events did not have any significant impact on the scope and purpose of the sampling program, and all lower limits of detection (LLDs) were met for both particulates and iodine-131 on the filters. When sampling interruptions resulted from power losses, steps were taken to restore power as soon as possible. Power was interrupted at the Overlook Area following a lightening strike during the week of 17-24 Feb 1999 (20 hour run tirne). Power was restored during the following week. Due to the low run time and samplo volumes, the required LLDs were not met on the particulate filter and charcoal cartridge collected during this week A pump failure occurred at the Medical Building (WS) air sampler during the week of 02-09 Jun. The sampler ran 9 hours out of the possible 168-hour sampling period. The required LLDs j were not met on the particulate and charcoal samples collected due to the low sample volume. l A pump failure also occurred at the Overlook Area (OA) air sampler during the week of 17-24 Nov 1998. In this case, the sampler ran 51 hours out of the possible 168-hour sampling period. Again, the required LLDs were not met on the particulate end charcoal samples collected due to the low sample volume. Despite the lower-than-normal sampling volumes in the various instances involving power interruptions and equipment failures, required LLDs were met on 569 of the 572 particulate i filters and 569 of the 572 iodine cartridges collected during 1998. None of the 1188 sample Page 90
F analyses performed indicated any questionable or anomalous results. When viewed collectively during the entire year of 1998, the following sampling recoveries were achieved in the airborne sampling program: Location Recovery Location Recovery Location Recovery WS 98.2 % PB 100.0 % PC 100.0 % ER 100.0 % OA 96.9 % MS 100.0 % WR 100.0 % EB 100.0 % EW 100.0 % PL 100.0 % CR 100.0 % An attemate location had to be found for sampling control vegetable samples in the Bridgewater area. In past yeac, samples had been collected at the Bridgewater County Farm, associated with the Bridgewater Correctional Facility. Due to loss of state funding for garden projects during 1998, no garden was grown. An alternate location was found at the Hanson Farm in Bridgewater, located in the same compass sector, and at approximately the same distance as the Bridgewater County Farm. As expected for control samples, vegetables collected at this location only contained naturally-occurring radioactivity (K-40). Samples of naturally-growing vegetation (grass, leaves from trees and bushes, etc.) were collected near some gardens identified during the annual land use census. Due to the unavailability of crops grown in these gardens, these substitute samples were collected as near as practicable to the gardens of interest. In addition to these substitute samples, samples of naturally-growing vegetation were also collected in the three locations yielding the highest calculated deposition coefficients (D/O) for airborne releases from PNPS. Such samples represent " worst case" samples for comparison, as the deposition and resulting ground-level concentrations of radionuc!! des 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. Problems were encountered with performing plutonium analyses on three of six sediment samples collected during the first half of 1998. Samples were collected from Plymouth Harbor and Duxbury Bay on 21-Apr-1998. However, when the samples were delivered to the Duke Engineering Environmental Lab, the sample submission forms detailing the required analyses were not included with the samples. Although the forms were submitted on the following day, the samples were received and logged by the Environmental Lab on the day of delivery, without capturing the requirement for plutonium analyses. When this oversight was finally discovered, the original samples had been disposed of, and were not available for analyses. Alternate mid-depth samples were used in-lieu of the surface samples for the missing analyses. Results of the analyses on these mid-depth samples were comparable with those observed over the past few years. Steps were taken to stress the importance of ensuring proper submittal of sampie forms when delivering samples to the analytical lab. These discussions took place both with Boston Edison and Duke Engineering personnel. In summary, the various problems encountered in collecting and analyzing environmental samples during 1998 were relatively minor when viewed in the context of the entire monitoring program. None of the discrepancies resulted in an adverse impact on the overall monitoring program. l Page 91
m 5 APPENDIX E
- QUALITY ASSURANCE PROGRAM RESULTS Introduction The accuracy of the data obta!ned through Boston Edison Company's Radiological Environmental Monitoring Program (REMP) is ensured through a comprehensive Quality Assurance Program. This appendix addresses those aspects of quality assurance that deal with the accuracy and precision of the analytical sample results and the environmental TLD measurement results that are obtained by Boston Edison from the 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 1998," snd the DESEL
- Semi-Annual Quality Assurance Status Report: July - December 1998."
Laboratory Analyses The quality control programs that were performed during 1998 to demonstrate the validity of laboratory analyses by DESEL in the media types of air filter, charcoal (iodine) cartridges, milk, soil / sediment, vegetation, and water. These quality control assessments are performed within the following intercomparison programs:
. DESEL intralaboratory quality control program to assure the validity and reliability of the data. This program includes quality control of laboratory equipment, use of reference standards for calibration, and analysis of blank and spiked samples. The records of the quality control program are reviewed by the responsible cognizant individual, and corrective measures are taken, as appropriate.
- DESEL participation in a cross-check program with Analytics, Inc. for environmental air filter, water, and milk samples.
- DESEL participation in a cross-checli program with the National institute of Standards and Technology (NIST), formerly the National Bureau of Standards. This comparison program evaluates the E-Lab's performance relative to standard measurement techniques certified by the NIST.
. 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 Assessment Program (OAP) 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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w 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 and Independent Interlaboratory Results - Results of the Quality Assurance Program are reported in two separate categories based upon 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 by 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 precision and accuracy in reported values. Table E-1 shows the cumulative results of accuracy and precision for laboratory analyses in 1998 for DESEL intralaboratory analyses, as well as Analytics and NIST interlaboratory cross-check analyses. A total of 503 analyses were performed for accuracy cross-comparisons, while 436 cross-check analyses were performed to assess precision. For accuracy,75% and 94% of the results were within 5 and 10 percent of the known values, respectively, with 99% of all results falling within the laboratory criterion of 15 percent. For precision,81% and 947% of the results were within 5 and 10 percent of the mean, respectively, with 99% of all results meeting the laboratory criterion of 15 percent. 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 mean and acceptable control limits established for each pedormance evaluation (PE) sample set. During 1998,33 PE sample sets were analyzed by DESEL,32 of which (97%) met the EPA's acceptance criteria. One sample sets analyzed for gross alpha in drinking water did not fall within the EPA's acceptance range. Since this radionuclide-category is not analyzed for in environmental monitoring programs at nuclear power plants, this adverse result has no impact on the REMP monitoring results.
Within the DOE arena, intercomparisons are performed under two separate programs. During 1998, DESEL performed intercomparison analyses for 13 radionuclides in soil under the DOE's Mixed Analyte Pedormance Evaluation Program (MAPEP). Eleven of 13 ( 85%) 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 (OAP). During 1998, DESEL analyzed a combination of 20 radionuclide in four media type, for a total of 80 intercomparison analyses. Of these, 78 (98%) met the DOE's acceptance criteria. Two samples, a water sample analyzed for strontium-90 and an air filter analyzed for antimony-125, was in non-agreement with DOE results. 'As was the case with the gross alpha in the EPA sample, these radionuclide analyses would normally not be performed on these types of environmental samples. The results of the numerous intercomparisons performed during 1998 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. Page 93
r - TABLE E-1 INTRALABORATORY AND INTERLABORATORY RESULTS - 1998 Fraction of Measurements Total Number of within deviation range Category Measurements i5% i 10 % 15%* DESEL INTRALABORATORY ANALYSES Accuracy 227 84.6 % 95.6 % 98.7 % Precision 160 61.3 % 87.5 % 98.8 % ANALYTICS INTERLABORATORY ANALYSES Accuracy 249 65.5 % 93.2 % 98.4 % Precision 249 92.4 % 98.0 % 99.2 % NIST INTERLABORATORY ANALYSES Accuracy 27 74.1 % 96.3 % 100.0 % Precision 27 100.0 % 100.0 % 100.0 % TOTAL COMBINED ANALYSES Accuracy 503 74.6 % 94.4 % 98.6 % Precision 436 81.4 % 94.3 % l 99.1 %
*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 Duplicate Proaram A total of 57 paired samples were submitted by the five sponsor companies for analysis during ! 1998. The database used for the duplicate analysis consisted of paired measurements of 25 gamma-emitting nuclides, H-3, Sr-89, Sr-90, low-level 1-131, and gross beta. The sample , media included milk, groundwater, sea / river water, food crops. marine algae, and mussel meat. A dual-level criteria for agreement has been established. If the paired measurements fall within i 15% of their average value, then agreement between the measurements has been met. If the value falis outside of the 15% criteria, then a two standard deviation range (95 percent confidence level)is established for each of the analyses. If the confidence intervals for the two analyses overlap, agreement is obtained. l l From the 57 paired samples,1492 paired duplicate measurements were analyzed during 1998. Out of these measurements, 1486 (99.6%) fell within the established criteria discussed above. No trend was evident with respect to repeated failings of measurements for the listed radionuclides and media. All of the ' failures' involved gamma spectroscopy pairings for l nuclides in which there was no detectable radioactivity in either of the paired measurements. i Page 94
r \ Environmental TLD Measurements Quality control testing was performed during 1998 to demonstrate the performance of the routine environmental TLD processing by DESEL. The quality of the dosimetric results is evaluated relative to independent third party testing and internal performance testing. These tests were performed independent of the processing of environmental TLDs at DESEL. In all of these tests, dosimeters were irradiated to known doses and submitted to DESEL for processing as unknowns. The quality control programs provide a statistical measure of accuracy, precision and consistency of the processing against a reliable standard, which in turn points out any trends or changes in performance. DESEL began performance testing of the Panasonic environmental TLDs in July 1987. The testing included internal performance testing and testing by an independent third party. A i 30% accuracy acceptance standard under field conditions is recommended by ANSI 545-1975, "American National Standard Performance, Testing and Procedural Specifications for Thermoluminescent Dosimetry (Environmental Applications)." Acceptance criteria for accuracy and precision to be used in 1998 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 LOf9. The actual magnitude of the 3 sigma plus 5% control limits depends on the historical pert; mance of each type of dosimeter, w:th each response being indicative of random and systeatic uncertainties, combined with any deviation attributable to TLD operation. The results of the TLD quality control programs are reported in the categories of accuracy and I precision. Accuracy was calculated by comparing each discrete reported dose to the known or delivered dose. The deviation of individual results relative to the mean reported dose is used as a measure of precision. The quality control program implemented for dosimetry processing indicated good precision and accuracy in the reported values. In 1998, there were 96 quality control tests. All 48 environmental TLDs tested during January - June 1998 wers within the control limits for both accuracy and precision. The comparisons yielded a mean accuracy of -1.9%. The comparisons exhibited a precision value with an overall standard deviation of 2.0%. The 48 TLDs tested in July - December 1998 showed a mean accuracy of -0.1%. TLDs measured during the second semiannud period exhibited a precision value with a standard deviation of 1.8%, well within the acceptance criteria. In total, all 95 environmental TLDs tested during 1998 were within the control limits for both accuracy (i 20.1%) and precision ( 12.8%). Conclusions i' 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 98% of all cases. The environmental TLD measurements for intralaboratory and independent third party comparisons resulted in both mean accuracy and precision within 5 percent deviation. j 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 1998 exhibited acceptable , accuracy and precision. l l Page 95 ; i s}}