ML20205T483
| ML20205T483 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 12/31/1998 |
| From: | CENTERIOR ENERGY |
| To: | |
| Shared Package | |
| ML20205T471 | List: |
| References | |
| NUDOCS 9904270263 | |
| Download: ML20205T483 (105) | |
Text
I i
ANNUAL ENVIRONMENTAL g
AM EFFLUENT RELEASE l
REPORT I
I FOR THE
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4 PERRY NUCLEAR POWER PLANT I
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JANUARY 01,1998, To DECEMBER 28,1998 l
l PREPARED BY:
RADWASTE, ENVIRONMENTAL, AND CHEMISTRY SECTION I
PERRY NUCLEAR POWER PLAhT FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY, OHIO March 1999 I
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l ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT TABLE OF CONTENTS
SUMMARY
AND CONCLUSIONS
_ -.2 ANNUAL Ern.UENT RELEASES-2 RA_rwOLOGicA1. ENVIRONMENTAL MONITORING PROGRAM 2
i LAND USE CENSUS -
3 CLAM / MUSSEL MON!TORING.
3 HERBICIDE USE 3
SPECIAL REPORTS 4
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PirRODUCTION 5
RADIATION FUNDAMENTALS 5
RADIADON AND RADIOACTIVITY 5
i UNITSOFMEASURE...-
6 LOWER LEIIT OF DETECTION 6
BACEGROUND RADIATION -
6 ANNUAL EFFLUENT RELEASES 8
INIRODUCTION 8
REGULATORY LIMrrS 8
[
METEORO1DGICAL DATA 14 W
DOSE ASSESSMENT 15 ABNORMAL RELEASES 17 PROGRAM Cl!ANGES ANDNON-COMPUANCES 18 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 19 INTRODUCTION -
19 SAMPUNG LOCATIONS.
_19 I
SAMPLE ANALYSIS -
24 1998 SAMPUNG PROGRAM 25 Iwrnt. LABORATORY CROSS-CHECK COMPARISON PROGRAM--
31 LAND USE CENSUS 35 DISCUSSIONS AND RESULTS 38 CLAM / MUSSEL MONITORING
.. 39 INTRODUCDON 39 j
CORB3CULA PROGRAM 39 DREISSENA PROGRAM
- 40 CONCLUSIONS 4I HERBICIDE USAGE 42 SPECIALREPORTS
. 43 NON-COMPUANCES 43 UNREVIEwm ENVIRONMENTAL QUESTIONS 43 NON. ROUTINE REPORTS -
43 APPENDIX A: 1998 REMP DATA
SUMMARY
44 APPENDIX B: 1998 REMP DATA
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.... 4 5 APPENDIX C: ABNORMAL RELEASE DOSE SUMMARIES & METEOROLOGICAL DATA
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ANNUAL ENVIRONMENTAL AND EITLUENT RELEASE REPORT gj g!
SUMMARY
AND CONCLUSIONS ne Annual Environmental and Effluent Release Report details the results of environmental and effluent monitoring pwgrams conducted at the Perry Nuclear Power Plant (PNPP) from-January 1 through December 28,1998. This report meets all of the requirements in PNPP Technical Specifications; Appendix g B, of the PNPP Operating License (the Environmental Protection Plan, or EPP); and Regulatory Guide g
1.21. Report topics include Annual Effluent Releases, Radiological Environmental Monitoring, Land Use Census, Clam / Mussel Monitoring, Herbicide Use, and Special Reports.
He Results of the Environmental and Effluent Program for 1998 indicate that the operations of the Peny Nuclear Power Plant did not result in any significant environmental impact.
ANNUAL EFFLUENT RELEASES During the normal operation of a nuclear power plant, small quantities of radioactivity may be released to the environment in liquid and gaseous effluents. Radioactive material may also be released as solid waste.
PNPP maintains a comprehensive program to control and monitor the release of all radioactive materials from the site. The Nuclear Regulatory Commission (NRC) strictly regulates all releases.
There were no liquid effluent discharges during 1998. The radioactivity released in the plant's gaseous E1 effluents during 1998 was well below applicable federal regulatory limits. The dose to the general public 5i from plant's gaseous effluents was also below the applicable regulatory limits. The hypothetical maximum i
individual dose potentially received by an individual resulting from PNPP gaseous effluents was 0.644 mrad (6.4% of the applicable limit). The summation of the hypothetical maximum individual dose from effluents in 1998 is equivalent to less than one percent of the total dose an individual living in the PNPP area receives from all sources of radiation.
Shipments of solid ~ waste consisted of waste generated during water treatment, radioactive material generated during normal daily operations and maintenance, and irradiated components. PNPP complied with all regulations governing radioactive shipments in 1998, making shipments of solid radioactive waste to a licensed burial site.
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM The Radiological Environmental Monitoring Program (REMP) was established in 1981 to monitor the radiological conditions in the environment around PNPP. The REMP is conducted in accordance with PNPP Technical Specifications and the Offsite Dose Calculation Manual (ODCM). This program includes the collection and analysis of environmental samples and evaluation of results.
The REMP was established at PNPP six (6) years before the plant became operational. This pre-operational program was designed to provide data on background radiation and radioactivity normally present in the area. PNPP has continued to monitor the environment during plant operation by collecting and analyzing samples of air, precipitation, milk, fish, produce, soil, grass, water and sediment as well as by measuring radiation directly.
Over 1267 radiological environmental samples were collected in 1998 and over 2500 analyses for radioactivity were performed. The results of the REMP indicate the adequacy of the control of the release of radioactivity in the effluents from PNPP. These results also demonstrate that PNPP complies with all applicable federal regulations. The REMP results are divided into four sections: atmospheric monitoring, terrestrial monitoring, aquatic monitoring, and direct radiation monitoring:
- Samples of air are collected to monitor the radioactivity in the atmosphere. The 1998 results are similar g
to those observed in both pre-operational and operational programs from prior years. Only background 3
environmental radioactivity was detected.
]Ii Summary and Conclusions Page 2
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ANNUAL ENVIRONMENTAL AND EFTLUENT RELEASE REPORT
- Terrestrial monitoring includes analysis of milk, produce, vegetation, and soil samples. The results of j
the sample analyses in 1998 indicate concentrations of radioactivity similar to that found in previous l
years. For example, the average concentration of cesium-137 in soil was 252.61 pCi/kg in 1998, which is at the low end of the range of 208.5 to 1104.05 pCi/kg observed during the past twelve (12) years.
Analyses of other terrestrial samples also detected concentrations of radioactivity similar to those observed in previous years, and indicated no build-up of radioactivity attributable to the operation of PNPP.
- Aquatic monitoring includes the collection and analysis of water, fish, and shoreline sediments. The I
1998 analytical results for water and firh sample showed normal background radionuclide concenantions. The results of sediment sample analyses indicated concentrations ofradioactivity similar to previous years. The average concentration of cesium-137 in the sediment was 457.81 pCi/kg, j
which is well within the range of up to 864 pCi/kg established since 1981.
- Direct radiation measurements showed no change from previous years. The indicator locations
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averaged 60.50 mrem / year and contml locations averaged 59.11 mrem / year. This shows that, in 1998, I
radiation in the area of PNPP was the same as radiation at locations greater than ten (10) miles away from the Plant.
Based on these results, PNPP operated in 1998 with no significant increase in the radionuclide concentrations observed in the environment.
LAND USE CENSUS In order to estimate radiation dose attributable to the operation of PNPP, the potential pathways through which public exposure can occur must be known. To identify these exposure pathways, an Annual land Use Census is performed as part of the REMP. During the census, PNPP personnel travel every public
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road within a five (5) mile radius of the plant to locate key radiological exposure pathways. These key pathways include the nearest resident, garden, and milk animal in each of the sixteen meteorological sectors. The information obtained from the census is entered into a computer program, which is used to assess the hypothetical dose to members of the public.
CLAM / MUSSEL MONITORING Clam and mussel shells can clog plant piping and components that use water from Lake Erie. For this I
reason, sampling for clams and mussels has been conducted in Lake Erie in the vicinity of PNPP since 1971, specifically for Corbicula (Asiatic clams) since their introduction into the Great Lakes in 1981, and for Dreissena (zebra mussels) since their discovery in Lake Eric in 1989. Since no Corbicula have ever been found at PNPP, routine Corbicula monitoring provides data to determine when, and if this pest species will arrive in the vicinity of PNPP. The breissena program includes both monitoring and control and is directed at minimizing the mussel's impact on plant operation. As in past years, this program has successfully prevented Dreissena from causing any operational problems at PNPP in 1998.
HERBICIDE USE The use of herbicides on the PNPP site is monitored. This ensures compliance with Ohio Environmental Protection Agency (OEPA) requirements and protects the site's natural areas. Based on the results of herbicide applications on site and weekly general site inspections, herbicide use has not had a negative impact on the environment around the plant.
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Summary and Conclusions Page 3 Y
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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT SPECIAL REPORTS Significant environmental events (for example, spills, releases), noncompliance with environmental regulations (for example, OEPA discharge limits), and changes in plant design or operation that affect the environment are reported to regulatory agencies as they occur. These special reports are also summarized annually in this report. Two (2) special reports were submitted in 1998:
Tri-chloro-ethylene release on January 23,1998; and
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High Oil & Grease in the sanitary sewage on October 08,1998.
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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT INTRODUCTION RADIATION FUNDAMENTALS Atoms are the basic building blocks of all matter. Simply described, atoms are made up of positively and negatively charged particles, and particles which are neutral. These particles are called protons, electrons, and neutrons, respectively. The relatively large protons and neutrons are packed together in the center of the atom called the nucleus. Orbiting around the nucleus are one or more smaller electrons: one electron for each proton in the nucleus. Due to their dissimilar charges, the protons and electrons have a strong attraction for each other, which helps hold the atom together.
Atoms with the same number of protons in their nuclei make up an element. He number of neutrons in the nuclei of an element may vary. Atoms with the same number of protons but different numbers of neutrons are called isotopes. All isotopes of the same element have the same chemical properties and many are stable or non-radioactive. An unstable or radioactive isotope of an element is called a radioisotope, or radionuclide. Radionuclides contain an excess amount of energy in the nucleus, which is usually due to an excess number of neutrons.
Radioactive atoms attempt to reach a stable, non-radioactive state through a process known as radioactive decay. Radioactive decay is the release of energy from an atom's nucleus through the emission of radiation.
Radionuclides vary greatly in the frequency with which their atoms release radiation. The length of time an atom remams radioactive is defined in terms ofits half-life. Half life is defined as the time required for a radioactive substance to lose halfits activity through the process of radioactive decay. Half-lives vary from millionths of a second to millions of years. The typical half-life for radionuclides released from the plant is approximately five years.
i RADIATION AND RADIOACTIVITY Radioactive decay is a process in which the nucleus of an unstable atom becomes more stable by spontaneously emitting energy. Radiation refers to the energy that is released when radioactive decay occurs within the nucleus. This section includes a discussion on the three (3) primary forms of radiation produced by radioactive decay.
Alpha Particles Alpha particles consist of two protons and two neutrons and have a positive charge. Because of their charge and large size, alpha particles do not travel very far when released (one to eight centimeters, in air).
They are unable to penetrate any solid material, such as paper or skin, to any significant depth. However, if alpha particles are released inside the body, they can damage the soft internal tissues because they deposit all their energy in a smallarea.
Beta Particles Beta particles are essentially free electrons, which usually carry a negative electrical charge. They are much smaller than alpha particles and travel at nearly the speed oflight, thus they can travel for longer distances than alpha particles. Beta particles have a similar ionizing effect as alpha particles, but since they are smaller, faster and have less charge, they cause less concentrated damage when interacting with tissue.
External beta radiation primarily affects the skin. Because of their electrical charge, paper, plastic or thin metals can stop beta particles.
Gamma Rays Gamma rays are bundles of electromagnetic energy, called photons, which behave as though they were particles. They are similar to visible light, but of a much higher energy. Gamma rays can travel long distances in air and are often released during radioactive decay, along with alpha and beta particles.
Introduction Page5 o
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Il ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Potassium-40 is an example of a naturally occurring radionuclide found in all humans that decays by emitting a gamma ray.
Interaction With Matter When radiation interacts with other materials, it affects the atoms of those materials principally by knocking the negatively charged electrons out of orbit. This causes an atom to lose its electrical neutrality and become positively charged. An atom that is charged, either positively or negatively, is called an ion and the radiation is called ionizing radiation.
UNITS OF MEASURE Some of the units of measure used in this report require explanation.
Activity Activity is the number of atoms in a material that decay per unit of time. Each time an atom decays, radiation is emitted. The curie (Ci) is the unit used to describe the activity of a material and indicates the h
rate at which the atoms are decaying. One curie of activity indicates the decay of 37 billion atoms per g'
second. Smaller units of the curie are often used in this repon. Two common units are the microcurie (pCi), one millionth of a curie, and the picoeurie (pCi), one trillionth of a curie. The mass, or weight, of radioactive material, which would result in one (1) curie of activity, depends on the disintegration rate. For example, one gram of radium-226 is equivalent to one (1) curie of activity. It would require about 1.5 million grams of natural uranium, however, to equal one (1) curie, since radium-226 decays more energetically than natural uranium.
Dose Biological damage due to alpha, beta, and gamma radiation may result from the ionization caused by these gj types of radiation. Some types of radiation, especially alpha panicles, which can cause dense local y
ionization, can result in much more biological damage for the same energy impaned than does gamma or beta radiation. Therefore, a quality factor must be applied to account for the different ionizing capabilities g
of various types ofionizing radiation. When the quality factor is multiplied by the absorbed dose, the result g is the dose equivalent, which is an estimate of the possible biological damage resulting from exposure to any type ofionizing radiation. The dose equivalent is measured in terms of the Roentgen Equivalent Man (rem). When discussing environmental radiation effects, the rem is a large unit. Therefore, a smaller unit, j
the millirem (mrem) is often used. One mrem is equal to 1/1000 of a rem.
LOWER LIMIT OF DETECTION Sample results are often reponed as below the Lower Limit of Detection (LLD). The LLD is the smsliest amount of radioactive material that will show a positive result for which there can be a 95% confidence that radioactivity is present. This statistical parameter is used as a measure of the sensitivity of a sample g
analysis. When a measurement is reported as less than the LLD (< LLD), it means that no radioactivity a
was detected. Had radioactivity been present at (or above) the stated LLD value, it statistically would have been detected. 'Ihe NRC has established LLD values for environmental and effluent sample analyses.
BACKGROUND RADIATION Background radiation includes the decay of radioactive elements in the earth's crust, a steady stream of g,
his,h-energy panicles f.um space, called cosmic radiation, naturally occurring radioactive isotopes in the g
human body like potassium-40, the decay of radioisotopes used in medical procedures, man-made phosphate fenilizers (phosphates and uranium are often found together in nature), fallout from nuclear weapons testing, and even household items like smoke detectors. In the United States, a person's average annual exposure from background radiation is 360 mrem, and is from sources shown in the Table 1 (Source: National Council on Radiation Protection and Measurements}.
I, Introduction Page 6 K
ANNUAL ENVIRONMEffrAL AND EFFLUENT RELEASE REPORT Table 1: Background Radiation Chart NATURAL Souncts MAN-MADE SouncEs Radon 55 %
Medical /X-rays 11 %
Cosmic 8%
Nuclear Medicine 4%
Terrestnal 8%
Consumer Products 3%
Internal 11 %
Other ' "
<t%
(1)- Oaker mctaunts 0.3%)hme sscapatsonalsources, <0.3%pomfallout, <0.1%from ake nuclear JimIcyle, and 0.1%f.mr n atscellmerous sources.
Many radionuclides are present in the environment due to sources such as cosmic radiation and fallout from nuclear weapons testing. These radionuclides are expected to be present in many of the environmental samples collected in the vicinity of PNPP. Some of the radionuclides nonnally present include:
Beryllium-7, present as a result of the interaction of cosmic radiation with the upper atmosphere, e
Potassium-40, a naturally occurring radionuclide normally found in humans and throughout the e
environment,and Fallout radionuclides from nuclear weapons testing, including tritium and cesium-137. These radionuclides may also be released in minute amounts from nuclear facilities.
Beryllium-7 and potassium-40 are especially common in REMP samples. Since they are naturally occurring and are expected to be present, positive results for these radionuclides are not discussed in the section on the 1998 Sampling Program Results. The radionuclide data is included, however, in Appendix D, REMP Data.
a introduction Page 7 s
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ANNUAL ENVIRONMENTAL AND EFFLUENT PILEASE REPORT ANNUAL EFFLUENT RELEASES INTRODUCTION ne source of radioactive material in a nuclear power plant is the generation of fission products (e.g.: noble gas, iodine, and particulates) or mutron activation of water and corrosion products (e.g.: tritium and cobalt). The majority of the fisu mducts generated remain within the nuclear fuel pellet and fuel cladding. Of those fission products tnat do escape from the fuel cladding, as well as the majority of the activated corrosion products, are removed by plant processing equipment.
During the normal operation of a nuclear power plant, small amounts of radioactive material are released in the form of solids, liquids, and gases. PNPP was designed, and is operated in such a manner as to control and monitor these emuent releases. Emuents are controlled to ensure any radioactivity released to the h
environment is minimal does not exceed any regulatory limits. Effluent release programs include the 5
operation of monitoring systems, in-plant sampling and analysis, quality assurance, and detailed procedures covering all aspects of effluent monitoring.
The main objective of controlling effluent releases is to ensure that all doses are kept As Low As Reasonably Achievable (ALARA). The ALARA principal applies to reducing radiation dose both to the individuals working at PNPP and to the general public. The term " reasonably achievable" means that exposure reduction is based upon engineering, sound operating practices and economic decisions. By practicing the ALARA concept, PNPP minimizes the health risks and possible environmentalimpact, which ensures that all doses are maintained well below the regulatory limits.
The liquid and gaseous radioactive waste treatment systems at PNPP are designed to collect and process these wastes in order to remove most of the radioactivity. Emuent monitoring systems are used to provide continuous indication of the radioactivity present and are sensitive enough to measure several orders of magnitude lower than the applicable release limits. This monitoring equipment is equipped with alarms and indicators in the plant control room. The alarms are set to provide wamings to alert plant operators when radioactivity levels reach a small fraction of actual limits. In addition, the waste streams are sampled l and analyzed to identify and quantify the radionuclides being released. The analytical results are used with E flow measurements to calculate the composition and concentrations of radionuclides in effluents.
Gaseous effluent release data is coupled with on-site meteorological data in order to calculate the dose to the general public. In areas surrounding the plant, devices maintained for REMP constantly sample the air in the surrounding environment. Frequent samples of other environmental media are also taken to determine if any radioactive material deposition has occurred. This program is described in detail in the next section.
Generation of solid waste is carefully monitored to identify opportunities for minimization. Limiting the amount of material taken into the plant, sorting material as radioactive or non-radioactive, shredding and compacting, or incinerating waste once it is identified help to lower the volume of radioactive solid waste generated. Solid waste is shipped to a licensed burial site.
REGULATORY LIMITS The Nuclear Regulatory Commission has established limits for liquid and gaseous emuents that comply with Title 10 of the Code of Federal Regulations (10CFR) Part 20 (Standards for Protection Against g
Radiation) Appendix B, and Part 50 (Domestic Licensing of Production and Utilization Facilities) 3 Appendix 1 and Title 40 of the Code of Federal Regulations (40CFR) Part 190 (Environmental Radiation Protection Standards for Nuclear Power Plants). These limits were incorporated into the PNPP Technical u
Specifications, and subsequently into the ODCM. He ODCM prescribe the maximum doses and dose g
rates due to radioactive effluents resulting from the operation of PNPP. These limits are defined in several ways to limit the over-all impact on persons living near the plant. Since there are no other nearby fuel Annual Emuent Releases Page 8
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT cycle sources,40CFR190 limits. These regulatory limits, which are described below, were not exceeded in 1998.
Liquid Emments The concentration of radioactive material released in liquid emuents to unrestricted areas shall be limited to the concentrations specified in 10CFR20, Appendix B, Table 2, Column 2 for radionuclides other than dissolved or entrained noble gases, as required by the ODCM. For dissolved or entrained noble gases, the concentration shall be limited to 2.0E-04 pCi/mL of total activity. These values are the maximum emuent concentrations.
The dose or dose commitment to a member of the public from radioactive materials in liquid emuents released to unrestricted areas shall be limited to the following:
During any calendarquarter:
Less than or equal to 1.5 mrem to the total body, and Less than or equal to 5 mrem to any organ.
During any calendaryear:
Less than or equal to 3 mrem to the total body, and Less than or equal to 10 mrem to any organ.
Gaseous Emments Dose rate due to radioactive materials released in gaseous emuents from the site to areas at and beyond the site boundary shall be limited to the following:
Noble gases:
Less than or equal to 500 mrem per year to the total body, and Less than or equal to 3000 mrem per year to any organ.
Iodine-131, iodine-133, tritium, and all radionuclides in particulate form with halflives greater than eight days:
i ess than or equal to 1500 mrem per year to any organ Air dose due to noble gases to areas at, and beyond the site boundary, shall be limited to the following:
During any calendar quarter:
Less than or equal to 5 mrad for gamma radiation, and Less than or equal to 10 mrad for beta radiation.
Durmg any calendaryear:
Less than or equal to 10 mrad for gamma radiation, and Less than or equal to 20 mrad for beta radiation.
Dose to a member of the public from iodine-131, iodine-133, tritium, and all radionuclides in particulate form with halflives greater than eight days in gaseous effluents released to areas at and beyond the site boundary shall be limited to the following:
Less than or equal to 7.5 mrem to any organ per any calendar quarter, and Less than or equal to 15 mrem to any organ per any calendar year.
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'Ihe PNPP ODCM does not contain a concentration reference for gaseous emuents. For this reason, maximum permissible concentrations are not used to calculate maximum release rates for gaseous emuents.
Annual Emuent Releases Page 9
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i ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Emuents are sampled and analyzed to identify both the type and quantity of radionuclides present. This g
information is combined with emuent path flow measurements to determine the radioactive composition g
and concentration of emuents.
Liquid Emments The PNPP liquid radioactive waste system is designed to collect and treat all radioactive liquid waste produced in the plant. The treatment process used for radioactive liquid waste depends on its physical and chemical properties. It is designed to reduce the concentration of radioactive material in the liquid by filtration to remove suspended solids and demineralization to remove dissolved solids. Normally, the i
effluent from the liquid radioactive waste system is returned to plant systems. The processed liquid emuent, however, may be required to be released from the plant to reduce the volume of water stored in plant systems. In this case, dose calculations are performed prior to, and after discharging this processed water to Lake Eric to ensure regulatory compliance and ALARA principals are maintained.
Error is inherent in any analytical process. Error may be due to differences in analysis results of split samples, or may be attributable to the precision limitations of instrumentation. An estimate of total error J
associated with different parameters is shown in Table 2.
Table 2: Liquid Effluent Process Errors PARAMETER
% ERROR Gamma spectral analysis 10 Tritium analysis 8
Strontium-89/90 analysis 10 g
1ron-55 analysis 10 Gross alpha analysis 10 5
Dilution volu:ne 31 Discharge volume 25 g
Liquid waste volume I
g Liquid radioactive waste system effluents may be intermittently released, which are considered to be
" batch" releases. Table 3 provides information on the number and duration of these releases for 1998.
Table 3: Liquid Batch Releases ITEM VALUE Number of batch releases (1)
Total time period for batch releases (min)
Maximum time for a batch release (min)
Average time period for a batch release (min)
Minimum time for a batch release (min)
Average stream flow during periods of effluent release into a flowing stream (L/ min)
{ i j - No laquut rodsoactne epuent releases durms 1998 Table 4 provides information on the nuclide composition for the liquid radioactive waste system effluent releases. If a radionuclide was not present at a level " greater than or equal to the LLD"(2LLD), then the value is expressed as "less than the LLD"(<LLD). In each case, LLDs were met or were below the levels required by the Technical Specifications /ODCM.
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Annual Effluent Releases Page 10
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 4: Summation of All Liquid Effluent Releases QUARTER QUARTER QUARTER QUARTER EST. TOTAL UNIT 1
2 3
4 ERROR,%
A.
Fission and Activation Products
- 1. TotalReleases Ci (I)
N/A (excluding tritium, gases, alpha)
- 2. Average diluted concentration pCUmL
- 3. Percent of applicable limit B.
Tritium 1.
Total Release C1 (1) 2.
Average Diluted Concentration pCUmL 3.
Percent of Applicable Limit C.
Dissolved and Entramed Gases 1.
Tctal Release Ci 2.
Aveage Diluted Concentration pCi/mL (I) 3.
Percent of Applicable Limit D.
Gross Alpha Radioactivity 1.
Total Release Ci l (1) l l
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2.
Volume E.
Waste Released (prior to dilution)
Liters (I)
F.
Volume of Dilution Water Used Liters (1)
(i ) ~ No laquad radnoacttw efuent releases durmg 1998 N/A - Not Apphcable the ODCMdoes not lam a hmitferfis. tion andacttuation products The total number of curies (Ci) of each radionuclide present in liquid effluent releases for each quarter are shown in Table S.
Table Si Radioactive Liquid Effluent Nuclide Composition t
Nuclides Released Unit Quarter I Quarter 2 Quarter 3 Quarter 4 Tritium Ci (I)
Chromium-51 Ci Manganese-54 Ci Iron-55 Ci Cobalt-58 Ci Iron-59 Ci Cobalt-60 Ci Zinc-65 Ci
_ Strontium-89 Ci Strontium-90 Ci Strontium-92 Ci Molybdenum-99 Ci Technetium-99m Ci Iodine-131 Ci lodine-133 Ci Xenon-133 Ci Xenon-133m Ci Cesium-134 Ci Xenon-135 Ci Cesium 137 Ci Lanthanum 140 C
l Cerium-141 Ci Cerium-144 Ci Total for Period Ci
( I) - No hquad radsoacttw efuent releases durmg } 998 Annual Effluent Releases Page11 A
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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Gaseous effluents are made up of noble gas, iodine and particulates. The noble gas releases are primarily a l
result of containment purge operations, small steam leaks, and off-gassing during plant start up and shut down operations. The iodine and particulate releases are primarily a result of small steam leaks. Gaseous effluents from PNPP exit the plant from one of four effluent vents. Each of these four effluent vents contains radiation detectors that continuously monitor the air to ensure that radioactivity release levels are well below regulatory limits. Samples are also collected and analyzed on a routine basis to ensure regulatory compliance, and that ALARA principals are maintained. All gaseous effluent released from PNPP are considered continuous and at ground level.
A small amount of error is inherent in any analytical process. Error may be due to differences in analysis results of split samples, or may be attributable to the precision limitations ofinstrumentation. An estimate of total error associated with different parameters is shown in Table 6.
l Table 6: Gaseous Effluent Process Errors PARAMETER
- /e ERROR Noble gas analysis
!I 5W Particulate analysis 9
lodine analysis 12 Tritium analysis 8
Strontium-89/90 analysis 10 Gross alpha analysis 10 Sample flow rate 4
EfDuent flow rate 4
If a radionuclide was not present at a level " greater than or equal to the LLD"(2LLD), then the value is expressed'as "less than the LLD" (<LLD). In each case, LLDs were met or were below the levels required by the Technical Specifications /ODCM. A summation of all gaseous radioactive effluent releases is given in Table 7.
Table 7: Summation of All Gaseous Effluents QUARTER QUARTER QUARTER QUARTER Err. TOTA 1.
UNrr 1
2 3
4 ERROR, */.
A. Fission and activation gases
- 1. Total Release Ci 1.13E 01 6.44E-01 2.99E+00 7.71E-02 1.00E+0!
- 2. Average Release Rate pCi/sec 1.45E 02 8.19E-02 3.76E-01 1.00E-02
- 3. Percent of Tech Specification Limit N/A N/A N/A N/A B. Iodine
- 1. Totallodine-131 Release Ci 1.28E 04 4.12E-04 6.35E-04 5.94E-04 1.00E+01 gi
- 2. Average Release Rate pCi/sec 1.64 E-05 5.24E-05 7.99E-05 7.72E-05
- 3. Percent of Tech Specification Limit 0.00E+00 0.00E+00 0.00E+00 0.00E+00 g
C. Particulates
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- 1. Paniculates with Half-lives >8 days Ci 8.99E-04 6.85E-03 1.58E-03 9.13E-04 1.00E+01
- 2. Average Release Rate pCi/sec 1.16E-04 8.72E-04 1.99E-04 1.19E-04
- 3. Percent of Tech Specification Limit 0.00E+00 0.00E+00 0.00E+00 0.00E+00
- 4. Gross alpha radioactivity Ci
<LLD
<LLD
<LLD
<LLD D. Tritium
- 1. TotalRelease Ci 1.32E+00 1.23E-01
<LLD
<LLD 1.00E+0!
- 2. Average Release Rate Ci/sec 1.69E-01 1.57L-02
<LLD
<LLD
- 3. Percent of Tech Specification Limit 84 0.00E+00 0.00E+00 0.00E+00 0.00E+00
<LLD - Less shan the lowr hmes qfdetectson N/A - Not Apphcable the ODCMdoes not hm a hmstforfossion andacttvarson products.
I' Annual Efiluent Releases Page 12 i e
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT The radionuclide composition of all gaseous radioactive effluents for a continuous mode, ground-level release is given in Table 8.
Table 8: Radioactive Gaseous Effluent Nuclide Coniposition NUCLIDE RELEASED UNIT l QUARTER 1 l QUARTER 2 l QUARTER 3 l QUARTER 4 A. Fission and Activation Gases Tritium Ci 1.32E+00 1.23E-01
<LLD
<LLD Argon-14 Ci
<LLD
<LLD
<LLD
<LLD Krypton-85 Ci
<LLD
<LLD
<LLD
<LLD Krypton-85m Ci
<LLD
<LLD
<LLD
<LLD Krypton-87 Ci
<LLD
<LLD
<LLD
<LLD krypton-88 Ci
<LLD
<LLD
<LLD
<LLD Xenon-131m Ci
<LLD
<LLD
<LLD
<LLD Xenon-133 Ci 8.44E-02 5.16E-01 4.0GE-01 3.63E-02 Xenon-133m Ci
<LLD
<LLD
<LLD 7.89E-03 Xenon-135 Ci 2.82E-02 1.28E-01 1.51E+00 3.29E-02 Xenon-135m Ci
<LLD
<LLD 1.08E+00
<LLD f
Xenon-137 Ci
<LLD
<LLD
<LLD
<LLD
\\
Xenon-138 Ci
<LLD
<LLD
<LLD
<LLD Total for Period Ci iyE+00 7.67E-01 2.99E+00 7.71E-02 B. lodine lodine-131 Ci 1.28E-04 4.12E-04 6.35E-04 5.94E-04 lodine-132 Ci
<LLD 5.46E-05 2.99E-05 2.81E-05 1
lodme-133 Ci 2.31E-04 1.04E-03 7.57E-04 7.79E-04 lodme-134 Ci
<LLD
<LLD
<LLD 1.02E-06 lodine-135 Ci
<LLD 2.04E-04
<LLD 5.66E-05 Total for Period Ci 3.59E-04 1.71E-03 1.42E-03 1.46E-03 C. Particulates Manganese-56 Ci
<LLD
<LLD
<LLD
<LLD Cobalt-56 Ci
<LLD
<LLD
<LLD
<LLD Cobalt-60 Ci
<LLD 1.56E-06 8.47E-06 5.52E-06 Rubidium-88 Ci
<LLD
<LLD
<LLD
<LLD
(
Rubidium-89 Ci
<LLD
<LLD
<LLD
<LLD
/
Strontium-89 Ci 2.04E-05 9.88E-05 2.18E-05 3.06E-05 Strontium-90 Ci
<LLD 3.92E-07
<LLD 3.94E-07 Strontium-91 Ca
<LLD 1.02E-04 9.l lE-06 1.25E-05 Yttrium-91m Ci
<LLD
<LLD
<LLD
<LLD Strontium-92 Ci
<LLD
<LLD
<tLD
<LLD Molybdenum-99 Ci
<LLD
<LLD
<LLD
<LLD Technetium-99m Ci
<LLD
<LLD
<LLD
<LLD Technetium-104 Ci
<LLD
<LLD
<LLD
<LLD Cesium-138 Ci 2.10E-04 1.84E-03 3.4 t E-04 9.82E-05 Barium 139 Ci 6.69E-04 4.74E-03 1.17E-03 7.65E-04 j
i Barium-140 Ci
<LLD 7.64E-05 2.74E-05
<LLD Lanthanum-140 Ci
<LLD
<LLD
<LLD
<LLD Total for Period Cl 8.99E-04 6.85E-03 1.58E-03 9.13E-04
<LLD - Less than the lower hast ofdesecnon Solid Waste Three (3) shipments of PNPP radioactive solid waste were transported by truck for disposal in 1998. These shipments were delivered to the Barnwell, South Carolina,. PNPP waste was also combined with radioactive solid waste from several other utilities. SEG/GTS Duratek, ATG, and MSC in Oak RidgeTN, Annual Effluent Releases Pr.ge 13
I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT sent this waste to the Barnwell and Clive, Utah, disposal facilities. The waste total in Table 9 below includes these shipments. No irradiated fuel was transported from PNPP in 1998.
g Table 9: Solid Waste Shipped Offsite for Burial or Disposal 3
A. Type of Solid Waste Shipped 5
- VOLUME, ActivrTY, EST. TOTAL 8
m Ci ERaon,%
3 Spent resin, filter sludge, evaporator bottoms, 3.0 40.3 1 25 etc.
Dry compressible waste, contammated 31.7 2.8 1 25 equipment, etc.
Irradiated components, control rods, etc.
9.1 9.9 1 25 Other(describe)
None 0
1 25 B.
Estimate of Major
- Nuclide Composition (by type of waste)
ABUNDANCE, EST. TOTAL RADIONUCLID ERROR,%
E Spent Resin, Filter Sludge, Evaporator Bottoms, H-3 1.5 1 25 etc.
Mn-54 3.1 Fe-55 25.3 Co40 37.4 Ni43 1.2 Zn45 28.4 gi Cs-137 2.2 Dry Compressible Waste, Contaminated Mn-54 2.2 1 25 g f Equipment, etc.
Fe-55 37.2 Co-58 1.2 l
Co40 38.1 Zn45 20.4 5 i Cs-137 1.0 Irradiated Components, Control Rods, etc.
Cr-51 30.3 1 25 Mn-54 4.6 Fe-55 35.8 Co-58 7.3 Co40 20.2 Ni43 1.1 Other(describe)
None C.
Disposition Number of Mode of Shipments Transportation Destination Solid Waste 3m Truck Bamwell. SC trradiated Fuel Shipments 0
N/A N/A N/A -Not Apphcable (1) " Mayor"is defmedas any individualradionucMe identfiedas >l% of the misse type abundance.
(2)- Additionalshipments were combined with mastefrom other utilitws to the Bamwell and Clive, Utah, disposal facilities hy SEG/GTS Duratek, ATG, and MSC in Oak Ridge, TN.
METEOROLOGICAL DATA The Meteorological Monitoring System at PNPP consists of a 60-meter tower equipped with two independent systems for measuring wind speed, wind direction, and temperature at both 10-meter and 60-h meter heights. The tower also has instrumentation to measure dew point and barometric pressure. Data is W
logged from the tower instrumentation into the Meteorological Data Processing System. This system compiles the data and calculates a variety of atmospheric parameters, communicates with the g
MeteorologicalInformation Dose Assessment System (MIDAS), and sends data over communication links 5
to the plant Control Room.
All meteorological data is maintained at PNPP and is available upon request.
Annual Effluent Releases Page 14 I e
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT DOSE ASSESSMENT The maximum concentration for any radioactive release is controlled by the limits set forth in the Code of Federal Regulations, Title 10, Part 20 (10CFR20). Sampling, analyzing, processing, and monitoring the effluent stream ensures compliance with these concentration limits. Dose limit compliance is verified through periodic dose assessment calculations. Some dose calculations are conservatively performed for a hypothetical individual who is assumed to reside on the site boundary at the highest potential dose location all year. His person, called the " maximum individual", would incur the maximum potential dose from dirwt exposure (air plus ground plus water), inhalation, and ingestion of water, milk, vegetation, and fish.
Because no one actually meets these criteria, the actual dose received by a real member of the public is significantly less than what is calculated for this hypothetical individual.
Dose calculations for this maximum individual at the site boundary are performed for two cases. First, they are performed using data for a 360* radius around the plant site (land and water based meteorological sectors), even though some of this area is over Lake Erie, which has no permanent residents. He second calculation is performed considering only those sectors around the plant in which people reside (land-based meteorological sectors). The calculated hypothetical maximum site boundary dose values to either the total body or worst-case, organ, considering all meteorological sectors, is provided in Table 10 and Table 11.
Table 10: Maximum Individual Site Boundary Dose, Considering All Sectors ErnurTro Dost,
% or Tvrt or Dost ORGAN Mrem LIMIT LIMIT Liquid Emuent Total body (I) 3.0E+00 Liquid Emuent Liver (I) 1.0E+01 Noble Gas - gamma N/A 7.56E-02 1.0E+01 7.6E 01 Noble Gas beta N/A 5.09E-02 2.0E+01 2.5E-0i Noble Gas Total body 3.73E-02 5.0E+00 7.5E-01 Noble Gas Skin 7.93E-02 1.5E+01 5.3E-01 Particulates & lodme Thyroid 1.15E-01 1.5E+01 7.7E-01 (I) ~ No imund radioactive efluent rwieases durmg 1998
<LLD - Less than the lowr hmit ofdesection Table 11: Population Dose, Considering All Sectors ESTIMATED Porut.ATioN ORGAN Dost, person-Rem Liquid Emuent Total body (1)
Thyroid (I)
Gaseous Emuent Total body 2.5E-03 Thyroid 6.5E-02
( I) - No hqusdrodsoaettve efluent releases durmg 1998
< LED -Isss than the lowr hmtt ofdetection Annual Effluent Releases Page 15 i
f I
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 12 provides the calculated hypothetical maximum site boundary dose values considering only the land-based sectors. If any radionuclide was not present at a level greater than the LLD, it was not used in the dose calculations.
Table 12: Maximum Individual Site Boundary Dose, Considering Sectors on Land f
ErnMATED Dose
% oF OncAN Mrem LIMIT LIMrr j
Liquid Eftluent Total body (1) 3.0E+00 Liver (I) 1.0E+01 Noble Gas - gamma NA 9.68E-03 1.0E+01 9.7E 02 Noble Gas - beta NA 6.52E-03 2.0E+01 3.3E-02 Noble Gas Total body 3.14E-03 5.0E+00 6.3E-02 Noble Gas Sitin 7.56E-03 1.5E+01 5.0E-02 Paniculates & lodine Thyroid 2.27E-02 1.5E+01 1.5E-01 (I ) - No Isquad radscacttw efluent releases durrng I998
<LLD - Less than the lowr limit ofdearction Other dose calculations are performed for a hypothetical individual who is assumed to be mside the site boundary for some specified amount of time. This person would receive the maximum dose during the i
tirr.e spent inside site boundary. Because no one actually meets the criteria established for these conservative calculations, the actual dose received by a real member of the public is significantly less than what is calculated for this hypothetical individual. This dose is assessed relative to the offsite dose, and considers dilution, dispersion, and occupancy factors.
The highest hypothetical dose from liquid effluents to a member of the public inside the site boundary is to a person who is fishing on Lake Erie from the shore on PNPP property. The calculations assume that this person spends 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year fishing, and the dilution factor is 10. The ration of the exposure pathway to the doses calculated for offsite locations yields the dose values shown in Table 13, below.
Table 13: Maximum Site Dose from Liquid Effluents TOTA 1. BODY Dose, ORGAN Dost, Mrem Mrem First Quaner (1)
Second Quaner Third Quaner
=
Fourth Quarter Annual (I ) - No Isquad radscactsw efluent releases dursng I998 Although several cases were evaluated to determine the highest hypothetical dose from gaseous efTluents to W
q members of the public inside site boundary (including traversing a public road within the site boundary, shoreline fishing, non-plant related training, car-pooling, and job interviews), the activity inside the site g]
boundary with the highest dose potential is also shoreline fishing (assuming 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year fishing).
3j The maximum on site dose values generated are shown in Table 14.
Table 14: Maximum Site Dose from Gaseous Effluents TOTAL BODY Dose, ORGAN Dost, j
mrem mrem First Quaner 1.67E-04 7.40E-05 i
Second Quaner 2.77E-05 8.05E-04 WI Third Quaner 3.54E-04 2.07E-03 J
Founh Quarter 2.21E-05 6.10E-04 Annual 3.92E-4 3.25E-03 An average total body dose to individual members of the public is t'aen determined by combining the dose from gaseous and liquid radiological effluents. The dose from gaseous radiological effluents is based upon the population that lives within 50 miles of PNPP (2,420,000 people). The dose from liquid Annual Efiluent Releases Page 16 I
ANNUAL ENVIRONMENTAL AND EFFL,UENT RELEASE REPORT radiological effluents is determined for the population that receives drinking water from intakes within 50 miles of PNPP (1,820,000 people). The results of this calculation are provided in Table 15.
Table 15: Average Individual Total Body Dose LIQUID EnWENTs gaseous ErrLorxrs First Quaner (1) 3.6E-10 Sccond Quaner I.4E-10 Third Quarter 8.2E-10 Founh Quaner 5.3E-11 Annual 1.4E-9 (1) - No hquad radioactin gfhnent relea.ses durmg I998 ABNORMAL RELEASES Loss of Negative Pressure Envelope for the Hester Bay,620-ft Elevation On 6/16/98 it was discovered that degraded flow conditions on the turbine building / heater bay (TB/HB) ventilation stack had caused a loss of the negative pressure envelope in the 620-ft elevation of the heater bay (HB). The problem was attributed to fouling of the flow-straighteners in the stack, which could not be cleaned without a complete shutdown of that system. To assess the dose impact of this condition, noble gas I
grab samples were obtained from the affected area once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. These samples were analyzed with no detectable activity. A low-volume air sampler was also set up to continuously composite samples of the atmosphere in this area. These composite samples were analyzed for particulates and iodine activity. The average measured activity for 1-131 and 1-133 was 1.53E-13 pCi/cc and 2.45E-13 pCi/ce, respectively.
This activity was consistently less than the activity observed for the TB/HB vent release path, g
An estimate of the maximum possible release flow rate out the ventilation louvers in this area was g
determined to be the difference between the actual and the design flow rates for the TB/HB ventilation stack (7.5E+04 cfm). The estimated flow rate was used with the activity from the particulates and iodine analyses in assessing the impact from this release. Particulates and iodine dose during this period of time was calculated to be 8.86E-2 mrem, which is 0.59% of the 10CFR50, Appendix 1, limit. The dose rate was 0.247 mrem /yr which is 0.016% of the 10CFR50, Appendix 1, limit. This release did not result in an increase to plant effluents, since the air-volume released from the HB 620-ft elevation would have been i
vented out the TB/HB ventilation stack had a negative envelope existed. The negative envelope was re-established at 19:29 on 10/25/99, when the system operation was established in the reduced-flow, summer mode. Refer to Appendix C for dose summaries and meteorological data.
Intermediate Building Stairwell Vent to Environment On 9/21/98 the intermediate building (IB) stairwell was isolated frum the plant by shutting the individual 3
floor access doors. Outside air was then supplied to the lower stairwell levels via a Coppus blower,
[
resulting in flow up and out the stairwell's roof access door. This action was undertaken to ventilate paint fumes to the atmosphere, instead of challenging the effluent treatment system's charcoal filter banks. To assess the dose impact of this condition, a noble gas grab sample was obtained from the ventilation exhaust during the discharge. This sampics was analyzed with no detectable activity. A low-volume air sampler was also set up to obtain a compcaite particulate filter and iodine cartridge sample of the ventilation exhaust. When the composite sample was analyzed, Co-60 was detected (7.36E-13 pCi /cc). The source of this activity was attributed to surface preparation activities that had occurred in the stairwell. The discharge flow rate for this event was 250 cfm, based on the design capacity of the blower. The duration of the event was 39.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The calculated organ dose for this period was 168E-3 mrem, which is 0.01% of the 10CFR50, Appendix I, limit. The highest dose rate wa: calev.ated to be 0.353 mrem /yr, or 0.02% of the 10CFR50, Appendix 1, limit. Refer to Appendix C for dose summaries and meteorological data.
Annual Effluent Releases Page 17
__]
[
I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT PROGRAM CHANGES AND NON-COMPLIANCES Program Changes l
There were three (3) changes made to the Offsite Dose Calculation Manual or the Process Control Program I
in 1998.
One change became effective on January 5,1998. This change: (a) revised the Unit 2 vent flow methodology to accurately reflect the system flow by adding an additional 12,000 cfm for the service building hot shop ventilation; (b) revised Table 3.3.7.10-1 to provide added guidance on system g
applicability for flow monitors;(c) revised Action Statements 122 and 123 to clarify the applicability B
requirements for flow monitors; (d) removed sample location 62 (no longer growing produce); and (e) added sample location 37 to the ENE Sector.
g The second program change became effective on January 22,1998. Table 4.3.7.9-1, Notation (4) was T
revised to read "- during periods of flow." This change allows a CHANNEL CHECK to be performed by recirculating flow back to Radwaste, therefore, eliminating the need to perform a discharge in order to ljl declare the monitor operable.
5I The effective date for the last change was September 2,1998. This change: (a) corrected discrepancies in the skin dose factors incorporated in Table 3.1-1 and Regulatory Guide 1.109;(b) adopted a uniform title for the X/Q (Chi-over-Q) factor throughout the body of the ODCM; (c) added notations to clarify the unrestricted area boundaries for liquid and gaseous efiluents into Figure 3.2.1; and (d) added a note to Figure A-2 to clarify which part of USAR Table 2.3-27 was used to obtain the ODCM X/Q values.
Non-Compliances On January 23,1998, PNPP declared an unusual event as a result of a reportable hazardous chemical spill.
E A HAZMAT team was mobilized to clean up 275 gallons of tri-chloro-ethylene spilled. Immediate and 3
follow-up notifications were made in accordance with all regulatory requirements. There was no apparent adverse impact upon the environmem.
The Unit 2 ventilation exhaust stack radiation monitor,2D17-K786, was out-of service from December 12, 1997, until February 05,1998, which was a total of 53 days. The root cause of the event was the failure of j
the noble gas channel on the monitor. A contributing factor was the inability to obtain replacement parts in gl a timely manner. During this period of time, compensatory sampling was performed to assure radiological 5
effluents out this discharge path remained a very small fraction of the regulatory limits.
I I
I I
I Annual Effluent Refer.ses Page 18
1 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT 1
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM INTRODUCFION The Radiological Environmental Monitoring Program (REMP) was established at PNPP for several I
reasons. First, it verifies the adequacy of plant design and operation to control radioactive materials and limit effluent releases. Second, it assesses the radiological impact, if any, that the plant has had on the su:munding environment. Third, it ensures compliance with regulatory guidelines. Tht; REMP is conducted in accordance with the PNPP Operating License, Appendix B, Technical Specifications and the I
ODCM. He Nuclear Regulatory Commission (NRC) established the REMP requirements.
A wide variety of samples is collected as part of the PNPP REMP. He selection of sample types, sampling l
locations, and sample collection frequency are based on many things. Potential pathways for the transfer of p
radionuclides through the environment to humans, sample availability, local meteorology, population characteristics, land use and NRC requirements are all considered.
To ensure that the REMP data are meaningful and useful, detailed sampling methods and procedures are followed. This ensures that samples are collected in the same manner and from the same locations each f
time. Ah samples are packaged on site, then shipped to an independent vendor laboratory for analysis. The I
vendor laboratory analyzes the samples and reports results to the PNPP Environmental Unit staff, the Lake County General Health District, and the State of Ohio Department of Health.
The REMP began in 1981 with 24 direct radiation monitoring locations, four sediment locations, and two fish sampling locations. In 1982, collections of air, water, milk, food products, and feed / silage were added.
Precipitation and soil were added in 1985. Although the NRC did not require these last two media, they were incorporated into the program to establish baseline data. In 1993, feed / silage sampling was dropped from the program based on the past ten years of data. For the san.c reason, strontium analyses were deleted from the program in 1994, gross beta and tritium were deleted from precipitation analyses in 1995, and precipitation sampling was deleted entirely in 1996. The precipitation sample sites remain available if I
future samples are desired. Also in 1995, the frequency for collecting soil samples was changed from quarterly to binnnually.
SAMPUNG LOCATIONS REMP samples are cellected at numerous locations, both on site and up to 22 miles away from the jant.
Sampling locations are divided into two general categories: indicator and control. Indicator locations are those which would be most likely to display effects caused by plant operation. They are relatively close to the plant. Control locations are those which are considered to be unaffected by plant operation. Typically, they are a greater distance from the plant, in the least prevalent wind directions. Data obtained from the indicator locations are compared with data from the control locations. This comparison allows naturally l
occurring background radiation to be taken into account when evaluating any radiological impact PNPP s
may have had on the environment. Table 16 and Figures 1,2 and 3 identify the PNPP REMP sampling locations.
Many REMP samples are collected in addition to those required by the PNPP ODCM. In some cases (soil, for example), the sample type is not required to be collected at all. In other cases (air sampling and direct radiation monitoring, for example), the PNPP REMP includes more locations than are required. The Technical Specifications /ODCM requirements for each sample type are discussed in more detail below.
Sample types and locations required by the ODCM are shown in BOLD in Table 16.
Radiological Environmental Monitoring Page 19
_____A
f I
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 16: REMP Sampling Locations EnrAnON #
DEscuarnON M H.ES DIRECnON MEDtA( I )
1 Chapel Road 3.4 ENE TLD, AIP g
2 Kanda Garden 1.9 ENE Food Products 3
3 Meteorological Tower 1.0 SE TLD, AIP, Soil 4
Site Boundary 0.7 S
TLD, AIP, Soil 5
Quincy Substation 0.6 SW TLD, Air 6
Concord Service Center 11.0 SSW TLD, AIP, Soil, Veg 7
Site Boundary 0.6 NE TLD, AIP, Soil, Veg l
8 Site Boundary 0.8 E
TLD 9
Site Boundary 0.7 ESE TLD, Soil M
10 Parmly Rd.
0.6 SSW TLD 12 Site Boundary 0.6 WSW TLD, Soil 13 Madison-on-the-Lake 4.7 ENE TLD 14 Hubbard Rd.
4.9 E
TLD 15 Eagle Substation 5.1 ESE TLD 16 Eubank Garden.
0.8 S
Food Products 17 Peny Schools Garden 2.0 S
FW Products l
21 Hardy Rd.
5.1 WSW TLD 23 High St.
7.9 WSW TLD E
24 St. Clair Ave.
15.1 SW TLD 15 Offshore - PNPP discbarge 0.6 NNW
!iediment Fish 26 Offshore Redbird 4.2 ENE Sediment 27 Offshore - Fairport Harbor 7.9 WSW Sediment 28 CEI Ashtabula Plant latake 22.0 ENE Water 29 River Rd.
4.8 SSW TLD 31 Wood and River Rd.
32 Offshore - Mentor 15.8 WSW Sediment Fish 33 River Rd.
4.5 S
TLD E
34 PNPP latake 0.7 NW Water 35 Site Boundary 0.6 E
TLD, AIP, Soil.Veg 36 Lake County Water Plant 3.9 WSW TLD, Water 37 Gerlica Farm 1.5 ENE Food Products 42 Pannly Rd.
0.8 S
TLD, Veg 51 Rettger Milk Fann 9.6 S
Milk 53 Neff Perkins 0.5 WSW TLD 54 Hale Rd. School 4.6 SW TLD 55 Center Rd.
2.5 S
TLD 56 Madison High School 4.0 ESE TLD g
58 Antioch Rd.
0.8 ENE TLD 59 Lake Shoreline at Green Rd.
4.0 ENE Water 60 Lake Shoreline at Peny Park 1.0 WSW Water 61 Keller Milk Farm 7.4 SE Milk 63 Minor Stream Mouth 0.08 NNE Sediment 64 Northwest Drain Mouth 0.09 NW Sediment 65 Major Stream Mouth 0.18 W
Sediment M
70 H&H Farm Stand 16.2 SSW Food Products g
71 Mosley Farm 7.9 SE Milk 77 Orosz Farm 1.2 E
Food Products g
(1) AIP = Atr,lodneandParnculaw Veg = Vrgrtation TID = Thermoluminescent Dosimesers Radiological Environmental Monitoring Page 20 I e
I 1998 ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT I
Figure 1: REMP Sampling Locations within Two Miles of Plant Site j
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Radiological Environmental Monitoring Page 21
l 1998 ANNUAL ENVIRONMENTAL AND EFFLUENT REl. EASE REPORT Figurr 2. REMP Sampling Imcations between Two and Eight Miles of Plant Site, j
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I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT SAMPLE ANALYSIS When environmental samples are analyzed for radioactivity, several types of measurements are performed to provide information about the types of radiation and radionuclides present. The major analyses that are performed are discussed below.
I Gross beta analysis measures the total amount of beta emitting radioactivity present in a sample. Beta radiation may be released by many different radionuclides. Since beta decay results in a continuous energy I
spectrum rather than the discrete energy levels, or " peaks", associated with gamma radiation, identification of specific beta emitting nuclides is much more difficult. Therefore, gross beta analysis only indicates whether the sample contains normal or abnormal concentrations of beta emitting radioactivity; it does not identify specific radionuclides. Gross beta analysis primarily acts as a tool to identify samples that may I
require further analysis.
Gamma spectral analysis provides more specific information than does gross beta analysis. Gamma I
spectral analysis identifies each radionuclide present in the sample that emits gamma radiation, and the amount of radioactivity associated with it. Each radionuclide has a very specific " fingerprint" that allows for accurate identification.
I lodine analysis measures the amount of radioactive iodine present in a sample. Some media (for example, air sample charcoal cartridges) are analyzed directly. With other media (for example, milk), iodine is extracted by chemical seperation.
Tritium analysis measures the amount of the radionuclide tritium (H-3) present in a s. ample. Tritium is an isotope of hydrogen that emits low energy beta particles. Tritium occurs naturally and is also man-made.
I Gamma doses received by Thermoluminescent Dosimeters (TLD) while in the field are determined by a special laboratory procedure. Thermoluminescence is a process by which ionizing radiation interacts with the sensitive phosphor material in the TLD. Energy is trapped in the TLD material and can be stored for months or years. This provides an excellent method to measure the dose received over long periods of I
time. The amount of energy that was stored in the TLD as a result ofinteraction with radiation is released by a controlled heating process and measured in a calibrated reading system. As the TLD is heated, the phosphor releases the stored energy as light. The amount oflight is directly proportional to the amount of radiation to which the TLD was exposed. The reading process also zeroes the TLD and prepares it for reuse. Table 17 provides a list of the analyses performed on environmental samples collected for the PNPP REMP in 1998.
Table 17: REMP Sample Analyses Tyre SAurLE FREQUENCY ANALYSIS Atmospheric Monitoring Airborne Weekly Gross Beta I
Particulates Quarterly Gamma Spectral Analysis Airborne Weekly lodine-131 Radioiodine I
Terrestrial Monitoring Milk Bi-Monthly Gamma Spectral Analysis Iodine-131 Food Products Monthly Gamma Spectral Vegetation Monthly Gamma Spectral I
Soil Biannually Gamma Spectral Aquatic Monitoring Water Monthly Gross Beta.
Gamma Spectral Analysis I
Quarterly Tritium Fish Biannually Gamma Spectral Sediment Biannually Gamma Spectral Direct Radiation Monitoring TLD Quarterly Gamma Dose Annually Gamma Dose Radiological Environmental Monitoring Page 24 2
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Sample results are often reported as less than the Lower Limit of Detection (< LLD), which is defined as the smallest amount of radioactive material that will show a positive result for which there can be confidence that radioactivity is present. This statistical parameter is used as a measure of the sensitivity of a sampic analysis. When a measurement is reported as less than the LLD, it means that no radioactivity was detected at a value above or equal to the appropriate ODCM table values. The NRC has established LLD values for REMP sample analyses. He vendor laboratory for REMP sample analyses was able to comply with those valuesin 1998.
1998 SAMPUNG PRocRAM De contribution of radionuclides to the environment resulting from PNPP operation is assessed by comparing results from the 1998 program with pre-operational data (i.e., data from before 1986),
operational data from previous years, and control location data, ne results for each sample type are discussed below and compared to historical data to determine if there are any observable trends. All results are expressed as concentrations. Refer to Appendix A,1998 REMP Data Summary, and Appendix B,1998 REMP Data, for detailed results. He NRC requires special reporting whenever sample analysis results exceed set limits. No values exceeded these reporting levels in 1998.
Program Changes I
As a result of the increasing unavailability of produce in recent years, a concerted effort was made to acquire new sampling locations. Sample location #1 was physically moved as a result of housing development. The location description was changed from Haynes Road to Chapel Road. Four (4) new garden locations were acquired in 1998. In the ENE sector, Location #2 was changed from the Site I
Boundary to the Kanda Garden. Location #37 (Gerlica Farm) was added to replace location #62 (Shreve Garden) lost in 1997, when the farmer discontinued growing produce. Location #16 was relocated from Dayton Road, in the SE sector, to the Eubank garden, in the S sector. Location # 17 was relocated from i
Chadwick Road in the SSE sector to the Perry Schools garden in th : S sector.
Missed Samples i
On occasion, samples cannot be collected. This can be due to a variety of events, including equipment malfunction, animal husbandry practices, or lost shipments. Events may also occur which prevent a sample from being collected in the normal way, or prevent a complete sample from being collected. The drying I
period for goats is an annual occurrence, since unlike cows, goats cannot produce milk year-round.
Missing TLDs may be the result of vandalism. When vandalism has been identified as a recurring problem, the TLD is relocated, if the loss of a TLD is determined to be a single or unusual event, it is not normally relocated. Table 18 provides information on samples missed during 1998.
I Table 18: Missed REMP Samples in 1998 MEDIA lACAno DATE Rt.AsoN I
N Food Products All April. June Vegetables not ready for harvest 70W July Retail stand not yet open Grass 35 April Insufficient growth Milk 61 January, February, March, Drying period for goats April. November. December 51 April Owner failed to fill containers after repeated attempts TLD 5
Annual. Fourth Quarter Lost in field W (1)- A ctatrollocatu.n that sells locally grownproducw.
(2)- The loss oftwo 71.Ds at location 3 was clauttledas a single event, since ? hey were located together andlost at the same same.
Atmospherie Monitoring I
Air Air sampling is conducted to detect any increase in the concentration of airborne radionuclides. Five locations (four indicator and one control), are required by the PNPP Technical Specifications /ODCM. Air Radiological Environmental Monitoring Page 25 d
Il ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT sampling pumps are used to draw continuous samples at a rate of approximately one cubic foot per minute.
The air is drawn through glass fiber filters, to collect particulates, and charcoal cartridges, to adsorb iodine.
The samples are collected on a weekly basis,52 weeks a year, from each of seven air sampling stations.
5 Six of the locations are within four miles of the plant site; the seventh is used as a control location and is B
eleven miles from PNPP.
Air samples are analyzed weekly for gross beta, iodine, and by gamma spectral analysis (quarterly). A total of 363 of each type of air sample (particulate and iodine) were collected in 1998.
Gross beta activity was detected in all air samples and ranged up to 0.05 pCi/m'. The annual average i
concentration of gross beta at both indicator and control locations was 0.02 pCi/m'. Historically, the
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concentration of gross beta in air has been essentially identical at indicator and control locations, as shown in Figure 4.
Except for naturally occurring beryllium-7, no radionuclide was identified in the gamma s etral analysis l
above the LLD. Iodine-131 was not detected in any sample above the LLD of 0.05 pCi/m Figure 4: Annual Average Gross Beta Concentration in 1998 q
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Year TerrestrialMonitoring Collecting and analyzing samples of milk, food products and vegetation provides data to assess the build-g up of radionuclides that may be ingested by humans. The data from soil samples provides information on W
the deposition of radionuclides from the atmosphere. The PNPP Technical Specifications /ODCM requires neither vegetation nor soil samples.
g Milk n
Samples of milk are collected once each month from November through March, and twice each month from April through October. Sampling is increased during the summer because animals usually feed outside on pasture and not on stored feed. The PNPP REMP includes three (3) milk locations (two within five miles of the plant, and one control). Since the milk sampling locations did not meet the requirements of the Technical Specifications /ODCM, fcod product sampling (discussed below) was performed. Milk was collected from the available locations even though they did not meet the Technical Specifications /ODCM requirements. If new locations that meet the Technical Specifications / ODCM requirements are identified in the future, they will be added to the program.
q Milk samples are analyzed for iodine and by gamma spectral analysis. A total of 49 milk samples were collected in 1998. Iodine was not detected above the LLD of 0.75 pCi/l in any of the samples. The concentrations of all radionuclides except naturally occurring potassium-40 were below LLDs in all Radiological Environmental Monitoring Page 26 I
o
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT samples collected. He results for potassium-40 were similar at indicator and control locations, as expected.
Food Products Food products can provide a direct pathway to humans by ingestion. They can absorb radionuclides from I
atmospheric deposition on soil or from irrigation water drawn from a lake or pond receiving airborne or liquid effluents. Also, radionuclides in the soil may be absorbed by the roots of the plants and become incorporated into the edible portions. Because there is not a sufficient number of milk sampling locations, g
the PNPP REMP is required to include two food product indicator locations and one control location. Food
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products are collected monthly during the growing season from three farms in the vicinity of PNPP. He control location for food products is 16.2 miles from PNPP.
l A total of forty-two (42) food product samples were collected and analyzed by gamma spectral analysis in B
1998. Seven (7) food products were collected which included: cabbage, broccoli, cauliflower, dill, beet greens, turnip greens, collared greens and kale. Beryllium-7 and potassium-40, naturally-occurring radionuclides, were found in several samples, as expected. No other radionuclides were detected above the I
LLDs.
Vegetation Vegetation (grass) was collected monthly during the growing season from four locations (three indicator and one control)in 1998. Grass is clipped from open areas using standard lawn trimming equipment. He controllocation for vegetation is eleven miles away. A total of twenty-seven (27) grass samples were collected and analyzed by gamma spectral analysis in 1998. Two naturally occurring radionuclides were detected: beryllium-7 and potassium-40. No other radionuclides were detected above the LLDs.
Soil Soil samples are collected biannually from seven (7) locations. One (1) of these is a control location that is eleven (11) miles from the plant. Only the top inch of soil is sampled in an effort to identify possible trends in the local environmental radionuclide concentrations.
I Fourteen (14) soil samples were collected and analyzed by gamma spectral analysis in 1998. As expected, one naturally-occurring radionuclide, potassium-40 was detected in the samples. Cesium-137 activity was
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detected in all samples and ranged from 130.77 - 471.88 pCi/kg. The annual average cesium-137 p
concentration was 276.12 pCi/kg at the indicator locations and 135.05 pCi/kg at the control location. For all sample sites, the annual average concentrations were similar to those measured in previous years (Figure g
5). The downward trend apparent in the figure represents the decrease in cesium-137 deposition from l
atmospheric weapons testing in the 1960's and '70's.
I I
Radiological Environmental Monitoring Page 27
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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 5: Average Annual Cesium-137 Concentration in Soil
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radionuclides in soil is so dependent on site-specific factors such as soil type and drainage. These factors 3
detemnine the ability of the soil to attract ions. For example, differences in soil types at the six indicator locations in 1998 resulted in cesium-137 concentrations ranging from 157.0 pCi/kg to 471.9 pCi/kg.
g Aquatic Monitoring B
Radionuclides may be present in Lake Erie from many sources (other than PNPP) including atmospheric deposition, run-oft / soil erosion, and releases of radioactivity in liquid effluents from hospitals, universities or other industrial facilities. Rese sources provide two forms of potential radiation exposure, external and internal. External exposure can occur from contact with water or shoreline sediments. Internal exposure can occur from ingestion of radionuclides, either directly from drinking the water, or as a result of the transfer of radionuclides through the aquatic food chain to the eventual consumption of aquatic organisms, such as fish. To monitor these pathways, PNPP samples water, shoreline sediments, and fish.
Water Water is sampled from five locations along Lake Eric in the vicinity of the PNPP as required by the PNPP Technical Specifications /ODCM. Samples from three locations are collected using composite sample a
pumps. The pumps are designed to collect water at regular intervals and composite it in a sample g
container. The containers are emptied monthly and the samples shipped to the laboratory for analysis.
Samples from two locations are collected weekly and combined. Each month the combined sample is shipped for analysis.
One hundred twenty (120) water samples were collected and analyzed for gross beta activity and gamma spectral analysis in 1998. From these monthly samples, a quarterly composite sample was obtained and B
analyzed for tritium. Gross beta activity was detected in nine (9) of the sixty (60) sample locations and g
none of twelve (12) controllocations sampled. The concentration range for samples with detectable activity (i.e., above the ODCM LLD) ranged from 3.16 - 12.4 pCi/L. The annual average gross beta concentration was 4.48 pCi/L at the indicator locations and < LLD at the control location usicg the mean of values > LLD. The mean value, using the LLD value for samples with activity less than the LL.D, resulted in the annual average gross beta concentration of 2.6 pCi/L at the indicator location and 2.1 pCi/L at the controllocation. Refer to Figure 6.
I Radiological Environmental Monitoring Page 28 I L
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT The significant difference between pre-1988 data and post-1988 data has been attributed to a change in vendor laboratoriesin 1987/1988. A comprehensive explanation is provided in the 1988 Annual EnvironmentalOperating Repon.
Figure 6: Annual Average Gross Beta Concentration in Water y pr;7 3
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No radionuclides were detected by gamma spectral analysis above the LLD. Tritium was not detected in any of the twenty (20) samples above the LLD. These results are well within the range of those measured in previous years, which have ranged from below the lower limit of detection to 2,200 pCi/L.
Sediment Sampling lake bottom sediments can provide an indication of the accumulation of undissolved radionuclides which may lead to internal exposure to humans through the ingestion of fish, through re-suspension into drinking water, or as an external radiation source from shoreline exposure to fishermen and swimmers. Although the PNPP Technical Specification /ODCM requires only one location, sediment is sampled twice each year from seven (7) locations, two (2) of which are also fish sampling locations.
Sediment samples from offshore are collected using a hand dredge. Near shore samples are collected using a scoop. Fourteen (14) sediment samples were collected in 1998 and analyzed by gamma spectrometry.
The predominant radionuclide detected by gamma spectral analysis was potassium-40, which is naturally occurring. Potassium-40 has been detected in all samples since the program began in 1981. Cesium-137 was detected in eight (8) samples and ranged from 148.6 - 839.4 pCi/kg. The annual average concentration was 334.0 pCi/kg at the indicator locations and 829.3 pCi/kg at the control location. These are within the range of concentrations measured in previous years (refer to Figure 7).
The changes in cesium-137 concentration from year to year may be related to the movement of sediment on the lake bottom. Wave action and currents can cause significant sediment movement between sample collections. For this reason, it is unlikely the same bed of sediment is sampled at each collection. This would contribute to inconsistent data demonstrated Figure 7.
Radiological Environmental Monitoring Page 29
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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 7: Annual Average Cesium-137 Concentration in Sediment n.
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Fish are analyzed primarily to quantify the dietary radionuclide intake by humans, and secondarily to serve as indicators of radioactivity in the aquatic ecosystem. Fish are collected from two locations, twice each year as required by the Technical Specifications /ODCM. Importa it sport and commercial species are targeted, and only the fillets are sent to the laboratory for analysis. A scientific collecting permit is obtained annually from the Ohio Department of Natural Resources for fish sampling.
Twenty-three (23) fish samples were collected and analyzed by gamma spectral analysis in 1998. Eight (8) species of fish were represented, including walleye, drum, smallmouth bass, carp, white sucker, yellow perch, mdhorse sucker, and catfish. As expected, naturally occurring potassium-40 was found in all samples. No other radionuclides were detected above the LLD.
Direct Radiation Monitoring Thermoluminscent Dosimeter (TLD)
Environmental radiation is measured directly at twenty-eight locations around the PNPP site, two of which are control locations. The locations are positioned in two rings around the plant as well as at the site boundary. The inner ring is within a one-mile radius of the plant site; the outer ring is four to five miles from the plant. Control locations are over ten miles from the plant in the two least prevalent wind directions. Each location is equipped with three TLDs. Two are changed quarterly and one is changed g
annually.
W A total of 250 TLDs were collected and analyzed in 1998. This included 223 collected on a quarterly basis, and twenty-eight (28) collected annually. In 1998, the annual average dose for all indicator locations was 60.5 mmm, and 59.1 mrem for all control locations. Prior to 1988, the TLD results were higher due to a change in vendor laboratory services. A comprehensive explanation of this difference was provided in the 1988 Annual EnvironmentalOperating Report.
I I
Radiological Environmental Monitoring Page 30 I L
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 8: Average Dose per Quarter 2-m;V, m :
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~' r fe s st W :ge INTER-LABORATORY CROSS-CHECK COMPARISON PROGRAM Introduction The purpose of the Inter-laboratory Cross-Check Comparison Program (iCCCP) is to provide an independent check on the vendor laboratory's analytical procedures. Samples with a known concentration I
of specific radionuclides are provided to the vendor laboratory. The vendor laboratory measures and reports the concentration of specified radionuclides. The known values (EPA values) are then compared to the vendor irsults. Results consistently outside established acceptance criteria indicate a need to check I
instruments or procedures.
In 1998, the vendor laboratory analyzed 42 samples of water for this program. All results were within the I
acceptable range. The results of this program are shown in Table 19. Results are expressed in pCi/L.
In addition to their participation in the EPA Inter laboratory Comparison Program, the vendor laboratory periodically conducts an internal cross-check program for dosimeters. The Eleventh International Inter-I Comparison of Environmental Dosimeters was conducted in 1997 and was organized by the Department of Energy's Environmental Measurements Laboratory in collaboration with Brookhaven National Laboratory and the National Institute of Standards and Technology. No dosimeters were submitted for cross-check in 1998.
I 1I InternationalIntercomparison Date lab Code 11.D Type Measurement Teledyne Results Known Value Average! 2 sigma April ll5-II A LiF-100 Field 13.211.0 19.0 17.8184 1997 Chips I
April ll5-II A LIF-100 Lab,Cs 32.112.0 58.1 55.219.9 1997 Chips April 115-11B CaSO4:Dy Field 19.111.4 19.1 18.918.7 1997 Cards April 115-11B CaSO4:Dy Lab,Cs 55.714.1 58.3 55.2 + 14.9 1997 Cards Radiological Environmental Monitoring Page 31
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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 19: EPA Inter-Laboratory Cross-Check Comparison Program Results DATE SAMrLE ANALYSIS VENDOR REsULTs, EPA VALUE, ACCErrABLE RANCE Tyre pCi/L pCi/L pCi/L January Water Sr-89 6.0 i 1.0 8.0 i 5.0 2.2 13.8 St-90 273 t 1.2 32.0 i 5.0 26.2 -37.8 l
Gross Alpha 31.2123 30.5 i 7.6 21.7-393 Gross Beta 6.610.6 3.9 i 5.0 0.09.7 E
February Water 1 131 111.110.9 104.9 i 10.5 86.7 123.1 g
Ra-226 14.9 i 1.3 16.012.4 11.8 47.7 Ra-228 30.9 i 1.9 333 i 8.3 18.9 -47.7 5
Uranium 25.8 i 1.1
- 32.0 i 3.0 26.8-37.2 March Water H-3 2151.0 1 1.1 2153 1 348.0 1551.2 2758.8 April Water Gross Alpha 483i1.5 54.4 i 13.6 30.8 70.8 Ra-226 153 i 0.9 15.0 i 2 3 11.0 - 19.0 Ra-228 7.8 i 1.0 9.3123 53-133 Uranium 5.1 i 0.1 5.013.0 0.0 10.2 Co-60 50.0 i 1.7 50.0 i 5.0 413 - 58.7 Cs 134 20.7 i 1.2 22.0 i 5.0 133 -30.7 Cs 137 9.0 i 1.0 10.0 i 5.0 1.3 - 18.7 Gross Beta 92.123.2 94.7 i 10.0 77.4 112.0 Sr-89
$ 3 i 1.5 6.015.0 0.0 14.7 l
Sr-90 173 i 1.5 18.0 i 5.0 93 26.7 June Ba-133 36.0 i 1.0 40.015.0 31.3 48.7 E
Co-60 14.0 i 1.0 12.015.0 33 20.7 g
Cs l34 26.7 t 1.2 31.015.0 22.3 - 39.7 Cs-137 32.7 i 3.8 35.015.0 263 -43.7 m
Zn-65 99.0 i l 1.8 104.0 i 10.0 86.7 1213 E.
Ra-226 4.7 i 0.4 4.9 i 0.7 3.7 - 6. I Ra-228 2.610.7 2.1 i 0.5 1.2 - 3.0 g
Uranium 3.0 i 0.1 3.013.0 0.0 - 8.2 Sr-89 19.013.0 21.015.0 123 -29.7 Sr-90 7.010.0 7.0 i 5.0 0.0 - 15.7 Gross Alpha 5.8 i 0.4 7.2 i 5.0 0.0 15.9 Gross Beta 12.410.4 12.8 i 5.0 4.1 - 21.5 Aug.
Water H-3 17,732.0 1 31.0 17,996.0 1 1800.0 14,873.0 - 21.119.0 Sept.
Water 1 131 5.9 i 0.1 6.112.0 2.69.6 Ra-226 1.7 i 0.1 1.7 i 0.3 1.2 - 2.2 Ra-228 6.1 i 0.6 5.7 i 1.4 33 8.1 Uranium 8.2 i 0.5 9.1 i 3.0 3.9 - 14 3 (1)- Presence of U-232 m sample marrjered wuh the recmery calculatsort Result of recalculatum uas 28211.2 pCstL.
The vendor laboratory routinely monitors the quality of their analyses by analyzing " spiked" samples (samples with a specific quantity of radioactive material present in them. The sample analyst does not know the quantity). Table 20 shows the results of this program for 1998. No samples were outside the acceptable range. All results are expressed in pCi/L except air filter results, which are in pCi/ filter.
I I
Radiological Environmental Monitoring Page 32 k
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 20: Vendor Spiked Sample Results
- REsULTs, KNowN AcctFTABLE RANCE DATE SAMPLE Tvrt ANALY5is pCi/L ACTivrTY. pCi/L pCi/L January Water Cs-137 78.64 i 7.76 77.23 67.23. 87.23 Am-241 16.% i1.24 20.64 12.38 - 28.90 Ra-226 9.39 i 0. I4 1035 7.25 - 13.46 Ra-228 12.74 1 3.05 14.03 9.82 -18.24 Co-60 443817.85 36.92 26.92 46.92 l
Cs134 34.97 1 7.78 32.52 22.52 -42.52 I
Cs-137 39.15 i 10.40 38.56 28.56 - 48.56 H3 45,125.00 i 568.00 45,598.00 36,478.40 54,717.60 l
Milk Co-60 41.40 i 3.61 36.92 26.92 - 46.92
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Cs-I34 31.78 i 3.15 32.52 22.52 - 42.52 Cs-137 37.03 1 4.57 38.56 28.56-48.56 Air Filter Cs-137 1.6810.02 1.90 1.14 - 2.66 I
February Water U-234 2.63 i 0.40 3.00 1.80 - 4.20 1-131 13635 i 133 137.03 109.62 - 164.44 Gross Alpha 43.73 i 7.61 41.27 20.64 - 6I.91 62.60 1 5.10 53.88 26.94 - 80.82 Gross Beta 59.45 1 2.90 61.70 51.70 - 71.70 Ra-226 I4.4410.50 13.80 9.66 - I7.94 i
Ra-228 I8.79 i 1.58 I8.29 12.80- 23.78 Milk U-238 3.26 i 0.49 3.00 0.00 - 15.00 l 131 132.63 i 1.63 137.03 109.62 - l64.44 Charcoal Canister I 13I (g) 1.7310.06 2.03 1.22 - 2.84 Vegetation 1-13I (g) 6.16 i 0.14 5.43 0.00 - 15.43 Air Filter Gross Beta 1.7210.02 1.66 0.00 - 11.66 l
March Water Ra-226 14.16 1 0.29 13.80 9.66 - 17.94 i
Ra-228 I8.06 i 1.70 18.29 12.80 23.78 Sr-89 65.40 1 2.70 75.94 60.75 91.13 Sr-90 28.04 i 1.22 32.65 26.12 -39.18 Air Filter Gross Bets 8.15 - 0.03 7.98 0.00- 17.98 April Water Ra-226 13.70 1 0.33 13.80 9.66 - 17.94 Ra-228 14.65i138 I8.20 12.74 - 23.66 Th-230 18.62 i 2.85 1739 10.43 - 24.35 H-3 41,641.00 1552.00 43,287.00 34.629.60-51,944.40 Gross Alpha 41.09 1 1.83 41.26 20.63-61.89 Gross Beta 32.01 i 1.10 30.72 20.72 -40.72 Co.60 48.50 1 3.74 44.65 34.65 - 54.65 Cs-137 42311432 3834 2834-48.34 Milk Cs-l37 80.78 1 6.60 76.68 66.68 86.68 May Water Ra-226 11.91 1 0.27 13.80 9.66 17.94 Ra-228 16.26 1 1.67 18.00 12.60- 23.40 Gross Alpha 40.49 1 2.57 41.25 20.63 - 61.88 Gross Beta 35.79 1 1.52 30.66 20.66 - 61.88 Air Filter Cs-137 2.0010.02 1.89 1.13 - 2.65 Soil Cs-134 0.1110.01 0.10 0.06 - 0.14 Cs-137 0.4810.02 0.43 0.26 - 0.61 Fish C5-134 03610.03 0.33 0.23 - 0.53 Cs-137 0.2910.03 0.31 0.18 0.43 Radiological Environmental Monitoring Page 33 o
I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT g
I RIsotTs.
KNOWN AccErTABLE RANGE 3
DATE SAMPt.E TYPE ANALYSTS pCi/L Actnm pCi/L pC1/L June Water Ra-226 12.98 i 0.18 13.80 9.66 - 17.94 Ra-228 16.73 i 1.62 17.80 12.46 - 23.14 Gross Alpha 41.38 1.87 41.25 20.62 - 61.87 Gross Beta 61.92 i 1.51 64.92 54.92 - 74.92 July Milk Cs-137 83.87 1 9.09 76.36 66.36 86.36 I.I31 63.98 1 0.77 61.03 48.82 - 73.24 1-131 (g) 62.05 1 11.00 61.03 36.62-71.03 Sr-89 52.66 i 2.13 62.0'5 49.64 - 74.46 Sr-90 29.78 i 1.39 32.41 25.93 -38.89
=
Water H-3 20.918.00 i 3 %.00 21666.00 17.332.80 - 25.999.20 l
- 44. % i 4.00 43.56 33.56 - 53.56 Cs-137 72.05 1 5.48 76.36 66.36 - 86.36 m
I-131 52.07 i 0.69 61.03 48.82 - 73.24 E
1-13I (g) 58.78 1 7.69 61.03 36.62 - 71.03 Gross Alpha 50.02 1 2.28 41.24 20.62 - 61.86 g
Gross Beta 70.19 i 1.88 64.80 54.80 - 74.80 Air Filter Cs-137 1.6810.02 1.86 1.12 - 2.60 g
Air Filter
- 1. % 1 0.02 1.86 1.12 - 2.60 g
Fish Cs-137 0.3310.03 0.31 0.18 - 0.43 August Water Gross Alpha 30.59 1 1.69 41.23 20.62 - 61.85 Gross Beta 30.28 i 1.71 30.48 20.48-40.48 Ra-226 6.29 i 0.19 6.90 4.83 - 8.97 Ra-228 7.85 i 1.28 8.72 6.10 - 11.34 September Water Ra-226 12.31 1 0.48 13.79 9.65 - 17.93 Ra-228 15.70 t 1.68 17.25 12.08-22.43 Gross Alpha 35.48 i 1.65 33.97 16.99 50.%
l Gross Beta 33.06 i 1.11 30.41 20.41-40.41 Co-60 46.15 i 8.78 42.34 32.34-52.34 5
1-131 77.97 1 0.81 82.07 65.66-98.48 g
1-131 (g) 80.62 i 13.90 82.07 49.24 - 92.07 Milk 1-131 58.15 1 0.90 61.55 49.24 - 73.86 g
Vegetation 1-131 (g) 2.6110.80 2.46 1.48 - 3.44 Charcoal Canister 1-131 (g) 1.4110.06 1.28 0.77 - 1.79 October Fish Cs 137 0.5610.04 0.61 0.37 - 0.85 Water Gross Alpha 25.22 i 1.90 33.%
16.98-50.94 Gross Beta 30.20 i 1.31 30.36 20.36-40.36 r
Ra-226 11.12 1 0.16 13.80 9.66 - 17.94 Ra-228 17.83 i 1.87 17.09 11.96 22.22 Air Filter Cs-137 1.78 i 0.02 1.84 1.10 - 2.58 Gross Beta 6.5410.10 6.47 0.00 - 16.47 Soil Cs-134 0.0810.01 0.09 0.05 - 0.12 Cs-137 0.4510.01 0.43 0.26 0.60 l
November Water Ra-226 14.73 1 0.47 13.80 9.66 - 17.94 Ra-228 15.67 1 1.59 16.95 11.87 - 22.04 W
Gross Alpha 27.49 1 2.38 33.97 16.99 - 50.%
g Gross Beta 36.04 1 2.14 30.31 20.31-40.31 Sr-90 4.3011.10 3.20 0.00 - 13.20 g
H-3 38.980.00 i 548.00 38.848 00 31,078.40 -46,617.60 I
Radiological Environmental Monitoring Page 34 '
L
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT
- REsuLTs, KNOWN ACCEPTABLE RANct DATE SAMPLE TYPE ANALYSTS pCi/L ActnTry, pCi/L pCi/L December Water Ra-226 6.7310.25 6.89 4.82 - 8.%
Ra-228 7.44 i 1.77 8.40 5.88 - 10.92 Gross Alpha 49.30 1 3.35 33.97 16.99-50.%
Gross Beta 33.63 i 1.70 30.25 20.25 40.25 Uranium 4.1010.25 4.17 2.50 - 5.84 Uranium 4.29 i 0.25 4.17 2.50 - 5.84 Conclusion No unusual radionuclide concentrations or exposure levels were detected during 1998. Atmospheric monitoring results were consistent with past results. He prevalent radionuclide in air was beryllium-7 which is naturally occurring. Naturally occurring potassium-40 was detected in all terrestrial samples, as r
expected. Cesium-137 was detected in soil and is the result of fallout from weapons testing. He l
concentrations were similar to those measured in previous years and are not related to plant operation.
There was no significant change in radionuclide concentrations at indicator locations for aquatic samples in 1998. Cesium-137 was detected in sediment. Results were within the range of past data.
Finally, direct radiation measurements are consistent with past data.
LAND UsE CENSUS Introduction Each year a land use census is conducted to identify the locations of the nearest milk animal, garden (of f
greater than 500 square feet), and residence in each of the meteorological sectors that is over land. The Land Use Census is required by the PNPP ODCM, Section 3/4.12.2. Information gathered during the Land Use Census is used for off-site dose assessment and to update sampling locations for the Radiological f
Environmental Monitoring Program. The Land Use Census is conducted by traveling all roads within a five-mile radius of the plant site, and recording and mapping the location of the nearest resident, milk animal, and vegetable garden in each of the meteorological sectors that is over land.
He 1998 Census was conducted September 9-10. He information has been tabulated below for the garden, residence and milk animal locations depicted on I
I Radiological Environmental Monitoring Page 35 A
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I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Figure 9. Note that the W, WNW, NNW, NW N, and NNE sectors extend over Lake Erie, and therefore, were not included in the survey.
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ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE RSPORT DISCUSSIONS AND RESULTS In general, the predominant land use within the census area continues to be rural / agricultural. l There was no change in nearest residences within five miles of the plant in 1998. Table 21 lists the nearest h residence by sector. There were no changes to the nearest milk animal location in 1998. Information on 5 the milk animal is shown in Table 22. There were three (3) changes in the nearest gardens recorded during this year's census. Table 23 lists the nearest gardens that occupy at least 500 square feet. Table 21: Nearest Residence, By Sector IhCATION MILES MtOM X/Q VALUE, MAP LOCATOR SECTOR ADDRESS PNPP sec/m NUMBER 3 I NE 4385 Lockwood 02 2.17E-6 I ENE 435 Lockwood 1.0 1.13 E-6 2 E 2654 Antioch 1.1 6.77E-7 3 1 ESE 2774 Antioch 1.2 4.44 E-7 4 SE 4495 N. Ridge 1.2 3.89E-7 5 SSE 3119 Parmly 0.9 1.89E-6 6 S 3121 Center 0.9 2.25E-6 7 SSW 3850 Clark 0.9 1.11E-6 8 SW 3440 Clark 1.2 4.98E-7 9 WSW 2815 Perry Park I.0 1.72E-6 10 I Table 22: Nearest Milk Animal, By Sector thCATION MILES FROM MAP LOCATOR I SECTOR ADDRESS PNPP NUMBER S 3588 River 4.8 I Table 23: Nearest Garden, By Sector i LOCATION MILES FRoM D/Q VALUE, MAP LOCATOR SECTOR ADDRESS PNPP m'8 NUMsER NE 4398 Lockwood 0.8 1.09E-8 11 1 ENE 4602 Lockwood I.I 4.llE-9 12 E 2656 Antioch 1.2 4.56E-9 13 ESE 2774 Antioch 1.2 3.41E-9 4 SE 5021 Middle Ridge 2.1 1.31E-9 14 SSE 33139 Call Road 1.5 2.30E-9 15 S 3121 Center 0.9 1.31E-8 7 SSW 3515 N. Ridge 1.7 1.19E-9 16 i SW 3440 Clark 1.2 2.24E-9 9 WSW 2975 Perry Park I.2 2.31 E-9 17 l 1 l l 't Radiological Environmental Monitoring Page 38
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT CLAM / MUSSEL MONITORING INTRODUCTION Sampling for benthic macro-invertebrates (clams and mussels) has been conducted in Lake Eric in the vicinity of PNPP since 1971. The clam / mussel program currently focuses on two species: Corbicula fluminea (Asiatic clam) and Dreissenapolymorpha (zebra mussel). CORBICULA PROGRAM N Monitoring specifically for Corbicula was initiated in response to a NRC bulletin and concerns of the Atomic Safety and Licensing Board. The current monitoring is part of the Environmental Protection Plan (Operating License, Appendix B). The program consists of periodic sampling of areas at both the PNPP I and Eastlake Power Plants. Its purpose is to detect Corbicula, should it appear in the study area. No Corbicula have ever been found in any sample collected from PNPP or from Lake Erie in the vicinity of I PNPP. Two Corbicula were found in a sample collected from the Eastlake plant in June,1987. No Corbicula have been found in any other sample collected since that time. A more detailed program history can be found in the 1986 and 1987 PNPP Annual Environmental Operating Reports. Monitoring Samples were collected quarterly in 1998 from the service water and emergency service water pump houses at PNPP, and semiannually from Lake Eric in the vicinity of the Eastlake Power Plant. Sample collection I dates are listed in Table 24. Table 24: 1998 Corbicula Sampling Dates and Locations i DATE SAMPLE 1DCA110N January 13 Service Water (SW) and Emergency Service Water (ESW) Forebays and trash baskets April 22 SW and ESW Forebays and trash baskets June 10 Lake Ene in the vicinity of the Eastlake Plant i August 11 SW and ESW Forebays and trash baskets September 14 Lake Eric in the vicinity of the Eastlake Plant October 27 SW and ESW Forebays and trash baskets Weekly inspections of PNPP property shoreline, weather permitung All samples were collected by Ponar hand dredge, hand scoop, or scraper. They were examined for bivalve shells and fragments, which were then identified to the lowest possible species. In addition to sample collections, plant components that use raw water are inspected whencver opened for maintenance or repair. Intemet environmental sites have been utilized specifically for the purpose of obtaining information on bivalves. Results No Corbicula were found in any sample collected during the 1998 monitoring program. All bivalves collected are listed in Table 25. I I I Clam /MusselMonitoring Page 39 A
I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Table 25: Bivalves Collected During 1998 Corbicula Monitoring Program SrtcEs/ LOCATION PNPP EAsTLAKE Ancylidoe X X Dreissena polymorpha X X E Dreissena bugensis X X l Gastropod X Limpets X g Pelecypoda X Physa sp. X X Pisidium amnicum X Pisidium sp. X Pisidsum casertanum X X Pisidium equilaterale X X Pisidsumferrugmeum X m Pisidium tilljeborgi X Pisidium subtruncatum X X Fisidsum vanabile X Sphaeridae X X Sphaerium corneum X X Sphaerium nitidium X Sphaerium striatinum X Sphaerium transversum X X Valvatacea X Conclusions The collection in June 1987 was the only indication of Corbicula in the vicinity of PNPP. However, it has E not been demonstrated that the presence of these clams is creating any operational problems at the Eastlake g Power Plant or at PNPP. DREISSENA PROGRAM Zebra mussels were first discovered at PNDP in September 1988. The initial collection of 19 mussels was made as part of the Corbicula monitoring p agram. The Dreissena program began in 1989 with monitoring and testing. The current control program was designed and implemented in 1990. Monitoring in addition to visually inspecting plant raw water systems when they are opened for maintenance or repair, monitoring methods include the use of commercial divers, side-stream monitors, and plankton nets. Commercial divers monitor mussel infestation during the inspection of forebays, basins, and the intake and discharge stmetures. Divers have also been used to take underwater videotapes of the water basins and g intake tunnel. Sidestream monitors are flow-through containers that receive water diverted from plant 3 systems, and are normally used in three in-plant locations during the mussel season. The sidestream monitors are fitted with slides and inspected weekly for veliger settlement. A plankton net was used on a limited basis in 1998. Treatment Chemicals used for mussel control in 1998 included chlorine and a commercial molluscicide. The system provides chlorine to plant service water, emergency service water, and circulating water systems. Sodium sulfite is added to plant discharge water to dechlorinate it before discharge to Lake Erie. The use of commercial molluscicides requires approval of the Ohio Environmental Protection Agency (OEPA). The chemical selected for use at the PNPP in 1998 was Didecyl-dimethyl-ammonium chloride. One treatment was applied in October,1998. The active ingredients were detoxified by adsorption onto bentonite clay prior to discharge into Lake Erie. Clam / Mussel Monitoring Page 40 I e
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT Results I ne effectiveness of the intermittent chlorination treatment has been determined in several ways. First, visual inspections of raw water system components are conducted when systems are open during maintenance or repair. In addition, settlement monitors were inspected weekly for new settlement. No live settlement has been found in any plant component to date. The effectiveness of the application of the commercial molluscicide was measured by observing mortality of mussels placed in a flow-through container placed in plant service water and subjected to the chemical treatment. Mortality observed in the flow-through container was 100%. To date, PNPP has had no problems related to zebra mussels. CONCLUSIONS Perry Nuclear Power Plant has taken the approach that the best method for avoiding problems with zebra mussels is preventive treatment of plant water systems. He current program of monitoring and chemical treatment will be continued to minimize the possibility that PNPP will experience future problems due to zebra mussels. However, the monitoring for Corbicula at the Eastlake facility is being re-evaluated to determine the extent of value, since the introduction of Zebra mussels at PNPP. I I I I I I I J Clam / Mussel Monitori'ig Page 41
l I ANNUAL ENVIRONMDfTAL AND EFFLUENT RELEASE REPORT HERBICIDE USAGE Herbicides are used snaringly on the PNPP site. An application must be made to the PNPP Chemistry Unit prior to spraying to ensure that only approved chemicals are used, and only in approved areas. In 1998, there were nine (9) herbicide applications initiated for spraying purposes. All usage was in g compliance with Ohio Environmental Protection Agency regulations. No adverse environmental impacts 3 as a result of this usage were noted during weekly site environmentalinspections. Surflan AS and Round Up were used in equal portions at 2% concentration for all locations, except the E field perimeter, where Prameml was used at a maximum of 20% concentration. Oust and Karnex were also used at a 0.015% concentration. The data available is provided below. 'Ihe volume used represents quantity of chemical prior to dilution, except for the October 17 application when premixed solution was purchased and used. Table 26: Documented Herbicide Usage Date Area. Chemical Cone. s Applied Location ft Volume 05/18 Parameter fence gravel areas 120,000 20 gal 2 05/26 Unit I and 2 transformer yards 85,000 20 gal 2 05/27 Unit 2 uart-up transformer yard; 39,900 5 gal 2 06/23 Transmission yard 484.000 28.7 lbs 0.015 10/05 Miscellaneous owner-controlled areas 215,000 150 gal 2 10/17 Gravel areas inside the protected area 4.000 4 gal 2 I I I I I I I I I Herbicide Usage Page 42 I
ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT SPECIAL REPORTS NON-COMPLIANCES NPDES Permit I ne National Pollutant Discharge Elimination System (NPDES) permit, is issued by the Ohio Environmental Protection Agency (OEPA). It establishes monitoring requirements and limits for discharges from the plant. It also specifies the locations from which the plant is allowed to discharge. I Here were no notification made to the OEPA in 1998. Environmental Protection Plan The Environmental Protection Plan (EPP), a part of the PNPP Operating License, requires a non-radiological environmental monitoring and reporting program be established at PNPP. There were no instances of EPP non-compliance identified in 1998. UNREVIEWED ENVIRONMENTAL QUESTIONS All proposed changes in plant design or operation, as well as tests or experiments conducted during 1998, were reviewed for potential environmental impact in accordance with the EPP and administrative quality assurance procedures. These reviews ensured that no changes to the facility or programs were performed whicF wuld cause an adverse environmentalimpact. Therefore, there were no potentially significant unreviewed environmental questions in 1998. I NON-ROUTINE REPORTS There was cne (1) non-routine report submitted in 1998. His report was initiated on 10/08/1998, as r. I result of an industrial wastewater sample oil & grease analysis of I 80 mg/L. The NPDES Permit limit for this analysis is 50 mg/L. Since the source of this wastewater was kitchen and bathroom wastes, the root cause was determined to be human error. Corrective actions were implemented. A follow-up sample was I obtained and analyzed, with the results being within the Permit limit. The Lake County Department of Utilities was notified in accordance with the PNPP Industrial Wastewater Permit. l I I l Special Reports Page 43 A
I ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX A: 1998 REMP DATA
SUMMARY
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d l .Ill!llllllll M M M M E E 1 44-0 E 5/a a40m ta ig DNS $2 lia: E t eDr/ n+ 8mte3 9rak m c/ 9goi oD p C 1 r N tP r n og i 1 pn s 3 i er t 1 l o Rt ou I is linhe i oOR atMy DDDDD DDDDDDDDDDDDDDDDDDDDDDDDDDDDDDDDDDDDDDDDDDDDD e LLLLL LLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLL t Dl ny LLLLL LLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLLL at ul erok e in-.Ce d .eW o .k E ma: l s rv L,i i int y AEncan ll e aPu c irq gee owrr lo o e iPe t l a d rp 88888 888888888888888888888888888888888888888888888 Ream D S9999 a 999966//S6/S6S97889S///6/699999S9999999999999 99 9 999 9 / / / / / / / / / /// / //////////// // // a n 29629 7418418541851751 96307307418529529529630741 84I lcS 122/ 2/ 1123/ 22/ 2// 23! 22/ 122/ 112// 122 / 22/ 11 I 1 1 1 1 1 1 N io // u 22/// I 22223 4 5 / / / /// / / // /// / //6///77///8/// 99///0/// / I 5$5 666 777 888 999 000 222 I11 3333 444 t 11 1 1 c 111 111 I r le y r l e o P C M E. e p yT ~ e lp r rrrr r rrr r r r rrr r rr rr r r rr r r r rr r r r r r r r r r r r r r r r r r r r r r m iiiiiAAAAA AAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAAA iiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiiii a S E ~ nio ta 66666 777777777777777777777777777777777777777777777 co L U l' 1'll
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J ANNUAL ENVIRONMENTAL AND EFFLUENT RELEASE REPORT APPENDIX C: ABNORMAL RELEASE DOSE SUMMARIES & METEOROLOGICAL DATA ) ( l I Special Reports Page 46 A
i i SITE: PERRY UNIT: UNIT 1 9902251647 l USER: MED
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES LAST ACCUMULATIONS FOR PERIODS: g 1 LIQUID 981228 1-99 21424 gi GASEOUS 98 61716-981026 2 l AIR 98 61716-981026 2 APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT l EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE g i (MREM) (M) (TOWARD) LIMIT (MREM) 3 LIQUID TOTAL BODY 0.00E+00 ADULT RECEPTOR 1 0.0E+00 3.0E+00 LIQUID BONE 0.00E+00 ADULT RECEPTOR 1 0.0E+00 1.0E+01 i NOBLE GAS AIR DOSE 7.55E-02 283. WNW 7.6E-01 1.0E+01 (GAMMA-MRAD) g NOBLE GAS AIR DOSE 5.08E-02 283. WNW 2.5E-01 2.0E+01 5 (BETA-MRAD) NOBLE GAS T. BODY 3.73E-02 ALL 283. WNW 7.5E-01 5.0E+00 NOBLE GAS SKIN 7.92E-02 ALL 283. WNW 5.3E-01 1.5E+01 IODINE & THYROID 8.86E-02 CHILD 283. WNW 5.9E-01 1.5E+01 PARTICULATES
SUMMARY
OF POPULATION DOSES l LAST ACCUMULATIONS FOR PERIODS: LIQUID 99 2 8 7-99 2 8 7 m 4 GASEOUS 97 1 1 1-97123124 EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE LIQUID TOTAL BODY 1.5E-01 LIQUID THYROID 1.1E-01 GASEOUS TOTAL BODY 1.3E-02 GASEOUS THYROID 1.BE-01 ee******************************************************************** I. I' I l l, K
SITE: PERRY UNIT: UNIT 1 9903090628 USER: MED
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES l LAST ACCUMULATIONS FOR PERIODS: I LIQUID 99 3 812-99 3 815 J GASEOUS 98 921 8-98 92116 AIR 98 921 8-98 92116 APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT l EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE B (MREM) (M) (TOWARD) LIMIT (MREM) LIQUID TOTAL BODY 4.02E-04 TEEN RECEPTOR 1 1.3E-02 3.0E+00 LIQUID GI-TRACT 6.05E-04 TEEN RECEPTOR 1 6.0E-03 1.0E+01 NOBLE GAS AIR DOSE 0.00E+00 273. N 0.0E+00 1.0E+01 l (GAMMA-MRAD) l NOBLE GAS AIR DOSE 0.00E+00 273. N 0.0E+00 2.0E+01 (BETA-MRAD) NOBLE GAS T. BODY 0.00E+00 ALL 0. 0.0E+00 5.0E+00 NOBLE GAS SKIN 0.00E+00 ALL 0. 0.0E+00 1.5E+01 IODINE & THYROID 1.61E-04 CHILD 678. NE 1.1E-03 1.5E+01 PARTICULATES
SUMMARY
OF POPULATION DOSES l LAST ACCUMULATIONS FOR PERIODS: P LIQUID 98 4 1 1-98 63024 GASEOUS 98 4 1 1-98 63024 EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE I______.......____________________________(PERSON-REM) LIQUID TOTAL BODY 0.0E+00 LIQUID THYROID 0.0E+00 GASEOUS TOTAL BODY 2.6E-04 l GASEOUP THYROID 2.1E-02 t @@W@@***************************************************************** l o
1 SITE: PERRY UNIT: UNIT 1 9903090630 USER: MED
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES LAST ACCUMULATIONS FOR PERIODS: LIQUID 99 3 812-99 3 815 i GASEOUS 98 922 8-98 92316 AIR 98 922 8-98 92316 APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE g (MREM) (M) (TOWARD) LIMIT (MREM) E LIQUID TOTAL BODY 4.02E-04 TEEN RECEPTOR 1 1.3E-02 3.0E+00 LIQUID GI-TRACT 6.05E-04 TEEN RECEPTOR 1 6.0E-03 1.0E+01 NOBLE GAS AIR DOSE 0.00E+00 273. N 0.0E+00 1.0E+01 (GAMMA-MRAD) NOBLE GAS AIR DOSE 0.00E+00 273. N 0.0E+00 2.0E+01 (BETA-MRAD) NOBLE GAS T. BODY 0.00E+00 ALL 0. 0.0E+00 5.0E+00 NOBLE GAS SKIN 0.00E+00 ALL 0. 0.0E+00 1.5E+01 IODINE & THYROID 1.27E-03 CHILD 230. NNW 8.5E-03 1.5E+01 PARTICULATES
SUMMARY
OF POPULATION DOSES LAST ACCUMULATIONS FOR PERIODS: LIQUID 98 4 1 1-98 63024 5 GASEOUS 98 4 1 1-98 63024 EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE j (PERSON-REM) i LIQUID TOTAL BODY 0.0E+00 LIQUID THYROID 0.0E+00 GASEOUS TOTAL BODY 2.6E-04 GASEOUS THYROID 2.1E-02 I co********************************* I I I I v
SITE: PERRY UNIT: UNIT 1 9903090651 USER: MED
SUMMARY
OF MAXIMUM INDIVIDUAL DOSES LAST ACCUMULATIONS FOR PERIODS: LIQUID 99 3 812-99 3 815 GASEOUS 98 924 8-98 92416 AIR 98 924 8-98 92416 APPLICABLE ESTIMATED AGE LOCATION % OF LIMIT EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE (MREM) (M) (TOWARD) LIMIT (MREM) LIQUID TOTAL BODY 4.02E-04 TEEN RECEPTOR 1 1.3E-02 3.0E+00 LIQUID GI-TRACT 6.05E-04 TEEN RECEPTOR 1 6.0E-03 1.0E+01 NOBLE GAS AIR DOSE 0.00E+00 273. N 0.0E+00 1.0E+01 (GAMMA-MRAD) NOBLE GAS AIR DOSE 0.00E+00 273. N 0.0E+00 2.0E+01 (BETA-MRAD) NOBLE GAS T. BODY 0.00E+00 ALL 0. 0.0E+00 5.0E+00 NOBLE GAS SKIN 0.00E+00 ALL 0. 0.0E+00 1.5E+01 IODINE & THYROID 2.46E-04 INEANT 294. N 1.6E-03 1.5E+01 PARTICULATES
SUMMARY
OF POPULATION DOSES LAST ACCUMULATIONS FOR PERIODS: LIQUID 98 4 1 1-98 63024 GASEOUS 98 4 1 1-98 63024 EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE (PERSON-REM) LIQUID TOTAL BODY 0.0E+00 LIQUID THYROID 0.0E+00 GASEOUS TOTAL BODY 2.6E-04 GASEOUS THYROID 2.1E-02 oooooo****************************************************************
f SIT".: PERRY UNIT: UNIT 1 02/25/99 16:50 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 98061716-98101901 STABILITY CLASS: A DT/DZ l ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH) EE WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL g N 0 7 1 0 0 0 8 g NNE O 3 15 0 0 0 18 NE 2 3 17 0 0 0 22 ENE O 1 1 0 0 0 2 E 1 3 0 0 0 0 4 ESE 1 5 0 0 0 0 6 SE 1 1 2 0 0 0 4 g SSE 1 1 2 0 0 0 4 3 S 0 0 0 0 0 0 0 SSW 0 0 0 0 0 0 0 SW 0 1 0 0 0 0 1 J WSW 0 0 1 1 0 0 2 W 0 6 1 1 0 0 8 MM 0 6 5 0 0 0 11 { NW 0 4 2 0 0 0 6 NNW 0 5 0 1 0 0 6 TOTAL 6 46 47 3 0 0 102 g PERIODS OF CALM (HOUP.S): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 89 I I I! I I' I I I' I v
SITE: PERRY UNIT: UNIT 1 02/25/99 1 51 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 98061716-98101901 STABILITY CLASS: B DT/DZ ' ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL NNE O 12 11 0 0 0 23 NE O 1 27 0 0 0 28 ENE O 1 1 0 0 0 2 E O 8 0 0 0 0 8 ESE O O 1 0 0 0 1 SE O 2 3 0 0 0 5 SSE O 4 1 0 0 0 5 S 0 2 0 0 0 0 2 SSW 1 1 0 0 0 0 2 SW 0 1 0 0 0 0 1 WSW 0 2 1 0 0 0 3 W 0 3 9 0 0 0 12 WNW 0 16 10 0 0 0 26 NW 1 4 6 0 0 0 11 NNW 1 12 1 1 0 0 15 TOTAL 3 79 76 2 0 0 160 PERIODS OF CALM (HOURS) : 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 89 g w
SITE: PERRY UNIT: UNIT 1 02/25/99 16:51 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 98061716-98101901 STABILITY CLASS: C DT/DZ 3 i . ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH) E WIND W; DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N O 13 8 1 0 0 22 NNE O 14 9 0 0 0 23 j NE O 10 9 0 0 0 19 ENE O 3 0 0 0 0 3 E O 4 0 0 0 0 4 ESE O 1 0 0 0 0 1 SE O 2 0 0 0 0 2 3 SSE O 2 1 0 0 0 3 g S 1 2 1 0 0 0 4 SSW 0 3 0 0 0 0 3 SW 0 1 0 0 1 0 2 WSW 0 1 3 5 0 0 9 W 0 3 30 2 0 0 35 WNW 1 22 24 0 0 0 47 NW 0 12 11 0 0 0 23 E NNW 0 6 7 3 0 0 16 q TOTAL 2 99 103 11 1 0 216 ) f PERIODS OF CALM (HOURS) : 0 VARIABLE DIRECTION 0 HOURS OF MISSING DATA: 89 I I I I I I I I, I v
SITE: PERRY UNIT: UNIT 1 02/25/99 16:51 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 98061716-98101901 STABILITY CLASS: D DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M j WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL g.. ___... y N 5 27 32 2 0 0 66 NNE 3 20 5 0 0 0 28 NE 4 46 14 0 0 0 64 i ENE 3 12 4 0 0 0 19 E 11 10 0 0 0 0 21 ESE 4 21 1 0 0 0 26 SE 2 6 6 0 0 0 14 SSE 2 23 6 0 0 0 31 S-4 32 18 0 0 0 54 g SSW 4 25 19 5 0 0 53 l SW 6 30 32 4 0 0 72 WSW 5 20 44 22 0 0 91 W 4 42 62 6 0 0 114 IWNW 4 41 25 1 0 1 72 NW 3 47 28 10 0 0 88 NNW 2 32 31 11 0 0 76 g._......__.......____._____._____......__.___..__...________ y TOTAL 66 434 327 61 0 1 889 PERIODS OF CALM (HOURS): 0 lVARIABLEDIRECTION O HOURS OF MISSING DATA: 89 I I l l l l J
SITE: PERRY UNIT: UNIT 1 02/25/99 16:51 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 98061716-98101901 STABILITY CLASS: E DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 9 16 20 0 0 0 45 NNE 5 11 5 0 0 0 21 NE 4 13 3 0 0 0 20 ENE 24 14 0 0 0 0 38 E 26 20 0 0 0 0 46 ESE 12 14 2 0 0 0 28 SE 8 18 7 0 0 0 33 3 SSE 14 48 3 0 0 0 65 g S 15 63 24 0 0 0 102 SSW 15 77 36 2 0 0 130 SW 9 63 40 6 0 0 118 WSW 13 32 30 7 0 0 82 W 6 16 5 1 0 0 28 WNW 6 11 8 0 0 0 25 NW 6 6 8 1 0 0 21 NNW 6 9 11 0 0 0 26 g TOTAL 178 431 202 17 0 0 828 g PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O HOURS OF MISSING DATA: 89 I I I I I I I I I t
r SITE: PERRY UNIT: UNIT 1 02/25/99 16:52 HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 98061716-98101901-STABILITY CLASS: F DT/DZ ELEVATION: SPEED:SPD10P DIRECTION.DIR10P LAPSE:DT50M j WIND SPEED (MPH) J WIND DIRECTION-1-3 4-7 8-12 13-18 19-24 >24 TOTAL N 2 0 0 0 0 0 2 NNE 2 0 0 0 0 0 2 NE 4 1 0 0 0 0 5 ENE 7 0 0 0 0 0 7 E 19 1 0 0 0 0 20 ESE 19 6 0 0 0 0 25 j SE 19 21 0 0 0 0 40 SSE 16 14 0 0 0 0 30 I S 15 31 0 0 0 0 46 8 SSW 10 15 0 0 0 0 25 SW 8 6 0 0 0 0 14 WSW 8 0 0 0 0 0 8 W 4 1 1 0 0 0 6 WNW 3 0 0 0 0 0 3 j NW 3 0 0 0 0 0 3 i NNW 2 0 0 0 0 0 2 TOTAL 141 96 1 0 0 0 238 PERIODS OF CALM (HOURS): 0 VARIABLE DIRECTION O j HOURS OF MISSING DATA: 89 ) i i J
SITE: PERRY UNIT: UNIT 1 02/25/99 16:52 ~ HOURS AT EACH WIND SPEED AND DIRECTION PERIOD OF RECORD = 98061716-98101901 STABILITY CLASS: G DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M l l WIND SPEED (MPH) WIND DIRECTION 1-3 4-7 3-12 13-18 19-24 >24 TOTAL g N O O O O O O O g NNE 2 0 0 0 0 0 2 NE 6 0 0 0 0 0 7 l ENE 17 0 0 0 0 0 17 E 37 0 0 0 0 0 37 ESE 98 8 0 0 0 0 106 SE 85 8 0 0 0 0 93 SSE 74 18 0 0 0 0 92 W S 38 2 0 0 0 0 40 SSW 22 2 0 0 0 0 24 3 SW 10 1 0 0 0 0 11 g WSW 6 0 0 0 0 0 6 W 1 0 0 0 0 0 1 l WNW 0 0 0 0 0 0 0 NW 2 0 0 0 0 0 2 = NNW 1 1 0 0 0 0 2 gl TOTAL 399 40 0 0 0 0 440 g PERIODS OF CALM (HOURS): 0 hRIABLE DIRECTION O HOURS OF MISSING DATA: 89 I, I I I I I I I I w
SITE: PERRY UNIT: UNIT 1 02/35/99 16:52 HOURS AT EACH WIND SPEED AND DIRECTION 3 PERIOD OF RECORD = 98061716-F9101901 $ STABILITY CLASS: ALL DT/DZ ELEVATION: SPEED:SPD10P DIRECTION:DIR10P LAPSE:DT50M WIND DIRECTION 1-3 4-7 8-12 13-18 19-24 >24 TOTAL 8.......-- N 16 73 66 4 0 0 159 i NNE 12 60 45 0 0 0 117 20 74 70 0 0 0 165 i I NE ENE 51 31 6 0 0 0 88 i E 94 46 0 0 0 0 140 ESE 134 55 4 0 0 0 193 SE 115 58 18 0 0 0 191 SSE 107 110 13 0 0 0 230 S 73 132 43 0 0 0 248 52 123 55 7 0 0 237 i I SSW SW 33 103 72 10 1 0 219 WSW 32 55 79 35 0 0 201 W 15 71 108 10 0 0 204 I WNW 14 96 72 1 0 1 184 NW 15 73 55 11 0 0 354 NNW 12 65 50 16 0 0 143 i I...............................--...---...--...............-- TOTAL 795 1225 756 94 1 1 2873 PERIODS OF CALM (HOURS): 0 E VARIABLE DIRECTION O HOURS OF MISSING DATA: 89 R E I I I I I I I
f I I I PHPPD +_.~4 axy- "'cy Lu u1 I s 1 i For more information, write or call: I Perry Nuclear Power Plant Radwaste, Environmental and Chemistry Section 10 North Center Road P.O Box 97 Perry OH 44081 (440) 280-5599 i
I I I PNPPD " "y +.a. w g . /kjl.} JL k ' 'vf o;gtjii Diy r3, g f& 'f '!P; y :lRb! c i -? - l a m. jI Formon information, write or caH: I Perry Nuclear Power Plant Radwaste, Environmental and Chemistry Section l 10 North Center Road P.O Box 97 l Perry OH 44081 I (440) 280-5599 I !I e}}